ML13003A033
| ML13003A033 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/16/2012 |
| From: | Schlaseman C MPR Associates |
| To: | Office of Nuclear Reactor Regulation, Exelon Generation Co |
| References | |
| RS-12-173 MPR-3812, Rev 3 | |
| Download: ML13003A033 (158) | |
Text
U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 19, 2012 Page 6 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 3, Report Number: MPR-3812, Revision 3 (684 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 3 1848 Lay Road, Delta, PA 17314 Facility Operating License No. DPR-56 NRC Docket No. STN 50-278 Correspondence No.: RS-12-173 Exelon Exelon Generation Company, LLC (Exelon)
PO Box 809398 Chicago, IL 60680-5398 Prepared by:
MPR Associates, Inc.
320 King Street. Alexandria, VA 22314 Report Number. MPR-3812, Revision 3 Preparer.
SCarolina ftpaw' Schlaserman Reviewer:.
Benlarnin Frazier Approver.
John Simons Peer Review Team Leader.
Patrkck Butl"r 11116/2012 1111612012 14k/,
11116/2012
,11/16/2012 Lead Responsible En~.
Branch Manage.
Senior Mner Design Engineering:
Jesse Lucas jeffy* Ch vewr Michael Woedman Corporate Acceptance:
Jeffrey Clark
- MPR ASSOCIATES INC NTTF 2.3 Seismic Walkdown of Peach Bottom Atomic Power Station Unit 3 MPR-3812 Revision 3 November 2012 QUALITY ASSURANCE DOCUMENT This document has been prepared, reviewed, and approved in accordance with the Quality Assurance requirements of 1 OCFR50 Appendix B and/or ASME NQA-1, as specified in the MPR Nuclear Quality Assurance Program.
Prepared by:_______
Caroline S. Sch"aseman Reviewed by:
Benjfifmn M. Frazier Approved by:
J4, was,'
Jo,'FW. gimons Peer Review "L'I.
T Team Leader:_
Patrick J. Butler Principal Contributors Mojtaba Oghbaei Craig B. Swanner James N. Wiggin Kevin Gantz Prepared for Exelon Generation Company, LLC Exeton 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.
Deleted citation for Unit 2 work order in Table 7-1.
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173
Contents Tables.......................................................................................................................................
iii Executive Sum m ary.................................................................................................................
iv 1
Introduction...................................................................................................................
1-1
1.1 Background
.... 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 Composite 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 3 MPR-3812, 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 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 ii
Tables T able 3-1. Personnel R oles................................................................................................
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 3 and Common IPEEE Seismic Vulnerabilities Resolutions................ 7-2 Table 7-2. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis.7-6 T able B -I. S W E L for U nit 3...................................................................................................
B -98 Table B-2. SWEL for Unit 0 (common)............................................................................
B-102 Table B-3. Deferred to RFO or Electrical Bus Outage: Inaccessible or Electrical S afety C o nce rn.................................................................................................
B -104 Table C-1. Unit 3 Seismic Walkdown Checklists (SWCs)........................................................
C-2 Table C-2. Unit 0 Seismic Walkdown Checklists (SWCs)....................................................
C-301 Table D-I. Unit 3 Area Walk-By Checklists (AWCs)................................................................
D-2 Table D-2. Unit 0 Area Walk-By Checklists (AWCs)..............................................................
D-53 Table E-I. Summary of Inaccessible Equipment.................................................................
E-1 Table E-2. Assessment of Unit 3 Electrical Cabinet Internal Inspections.................................
E-3 Table E-3. Assessment of Unit 0 Electrical Cabinet Internal Inspections.................................
E-5 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 iii
Executive Summary PURPOSE This report documents the seismic walkdowns performed at Peach Bottom Atomic Power Station (PBAPS) Unit 3 in response to NRC 50.54(f) letter dated March 12, 2012,, 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 3, including the items selected that are common to both Units 2 and 3, e.g., emergency cooling tower equipment, is comprised of 122 items. Of this list, 109 equipment items were walked down during the 180-day window of completion of the initial scope of work required by the 50.54(f) letter. Walkdowns for the remaining 13 items were deferred to the Unit 3 Peach Bottom Atomic Power Station Unit 3 iv MPR-3812, Revision 3 Correspondence No.: RS-12-173
Refueling Outage (RFO) or future electrical bus outages due to accessibility issues, e.g.,
location inside primary containment or 4KV bus outage requirements. 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 55 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 3) 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 3 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 for a solenoid valve, were identified and entered into the plant's Corrective Action Program (CAP). A total of 12 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 3 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:
Thirteen (13) inaccessible equipment items will need to be walked down during the next Unit 3 RFO or future electrical bus outages.
Six (6) electrical cabinets will need to be opened for an internal inspection for "other adverse seismic conditions" in accordance with NRC expectations that were provided to industry after these walkdowns were completed. These inspections are scheduled for the next available electrical outages.
- 2.
None of the 109 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 twelve (12) anomalies or discrepant conditions identified during the equipment walkdowns or area walk-bys have been assessed in accordance with the plant Peach Bottom Atomic Power Station Unit 3 v
MPR-3812, Revision 3 Correspondence No.: RS-12-173
corrective action program (CAP), and their resolutions are being tracked for timely closure.
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 vi
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 3.
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 3 received its full-power license in July 1974 (Facility Operating License No. DPR-56 (Reference 9)).
1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference 1) is used for the PBAPS Unit 3 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 3 1-1 MPR-3812, 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 3 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 3 MPR-3812, 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 Seismic Licensing Equipment Plant Walkdown Bacesisg IEE Pe Name Selection Pln akon Basis 1EE Pe Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE)
B. Frazier X
X X
X C. Swanner X
X x(Note 2)
M. Oghbaei X
X J. Wiggin X
X K. Gantz X
X C. Schlaseman X(Note 1)
X P. Butler X(Note 3)
J. Hanley X
(Exelon)
Notes:
- 1. SWE team member for six seismic walkdowns and one area walk-by; therefore did not act as Peer Reviewer for this portion of the walkdowns.
- 2.
Peer Review Team Member for SWEL review.
- 3. Peer Review Team Leader.
A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Seismic Walkdown Guidance (Reference 1).
Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.
The SWEL preparer, 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 3 3-1 MPR-3812, 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 3 3-2 MPR-3812, 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 3.
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 #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 3 4-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173
4.2.3 Screen #3 - Support for the 5 Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions:
- 1.
Reactor Reactivity Control
- 2.
Reactor Coolant Pressure Control
- 3.
Reactor Coolant Inventory Control
- 4.
- 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 3) 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 3 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 3 4-2 MPR-3812, Revision 3 Correspondence No.: RS-12-173
as part of SQUG and IPEEE programs, PBAPS Unit 3 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." 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 3. 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 3 with the highest F-V risk ranking (0.0168 and above) and highest RAW risk ranking (9.0 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 3 4-3 MPR-3812, Revision 3 Correspondence No.: RS-12-173
4.3.1 Screen #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 3 (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 #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 #3-Sample Considerations Sample considerations do not apply because no Seismic Class I items meet the Screen #1 requirement.
4.3.4 Screen #4-Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly. Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the earthquake. Consistent with Reference 1, the scope of items included in this screen is limited to the hydraulic lines connected to the SFP and the equipment connected to those lines. For the purposes of this program, the SFP gates are considered to be installed and the SFP cooling system is in its normal alignment for power operations. The SFP gates are passive devices that are integral to the SFP. As such, they are considered capable of withstanding a design basis earthquake and do not allow for a rapid drain-down of the SFP.
Based on review of the PBAPS Unit 3 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 3 is the combined SWEL 1 and SWEL 2. For PBAPS Unit 3, there are Peach Bottom Atomic Power Station Unit 3 4-4 MPR-3812, 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 3 MPR-3812, 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 3 SWEL and Unit 0 (common equipment with Unit 2) 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 items identified at the end of the SWEL. Additionally, photos are included with each SWC to provide a visual record of the item and any significant comment noted on the SWC. Drawings and other plant design documents are cited in most of the SWCs, but they are not included with the SWCs because they are readily available in the plant's electronic document management system. Seismic Walkdowns were completed for 80 of the 92 items on the PBAPS Unit 3 SWEL, plus 29 of the 30 items on the Unit 0 (common) SWEL, for a total of 109 items, not including the 13 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 was 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 3 5-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173
Table 5-1. Anchorage Configuration Confirmation Unit 3 or Unit 0 No. of SWEL N/A Items Required to Items ItemsConfirm?
(Common)?
Items (B)
(A-B)/2 Confirmed (A)
AB/
3 80 11 35 38 0 (Common) 29 4
13 17 Unit3and 109 15 47 55 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 y/N(Notes 1, 2) 3DD003 (also Possible open S-hook noted on light IR 01413285 Yes AWC-U0-1) fixture.
SV-3-03-033 SV Mounting does not match print.
IR 01413655 No (also AWC-U3-13)
- 30C003, The MCR ceiling's restraint system is IR 01428651 No
- 30C004C, consistent with design documentation but 30C005A, L13-2 the design basis Calculation G-106-1 could 113, LI-9027, not be located from records management LRITR-9123B, or Iron Mountain. This issue is to P13-6-90A, re-constitute design analysis to PR/TR3-2-3-404B, supplement existing calculation 26-5/Z-12, PR/TR-5805 (also specifically at MCR ceiling perimeter, AWC-UO-7) during NTTF 2.1 seismic re-evaluation.
3AE56, 3AE57, Anchorage for ECCS room coolers does IR 01437853 No 3AE58, 3BE55, not match drawings.
(Note 3) 3BE57 (also AWC-U3-8) 30B338 A front panel screw is missing and another IR 01424719 Yes screw is loose.
Peach Bottom Atomic Power Station Unit 3 MPR-3812, 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 Y/N(Notes 1, 2) 30C722A The internal flow detector instrument has a IR 01424662 No loose mounting screw.
30C722B The two internal power supplies are IR 01424692 No missing mounting screws where they are mounted to the cabinet.
0AG12, 0BG12, Inconsistency between the observed IR 01438055 No 0CG12, 0DG12 OAG12, 0BG12, OCG12, and 0DG12 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 3 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 25 AWCs were completed for Unit 3, 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 3 MPR-3812, 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 YIN (Notes 1, 2)
AWC-U3-2 U-bolt identified as unattached on a non-Q IR Yes line.
01413652 AWC-U3-3 Severely corroded nut on 3A HPSW Plate.
IR No 01410116 AWC-U3-25 Ladder identified on floor of SW Screen IR Yes House.
01406272 AWC-U3-7 Loose cover plate bolt identified on 30C221 IR No judged acceptable. Bolt should be tightened.
01424737 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 3 MPR-3812, 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 3 MPR-3812, 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. A1056479 (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 each one was resolved, and identifies the specific items that were verified in the field during the walkdowns. Table 7-2 lists the PBAPS Unit 3 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 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 7-1
Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown
- A1056479 Resolution 00197 Interaction concerns.
Breaker hoist wilt be restrained or removed.
Work completed under work order C01 68074 on None 00B98 August 1, 2000.
00B99 30B10/11/12/13 Some cubicles missing plug welds Add missing plug welds.
Work completed for plug welds under work orders 30B010 and 306013 included in to embedded angle.
Breaker hoist will be restrained or removed.
C0186234 and C0186267 on August 1, 2000, and walkdown sample.
under work orders C0186428 and C0186429 on Breaker hoists are interaction Modification will replace with ventilated dry type October 16, 2000.
Confirmed issue resolved.
concern, not prevented from tipping, transformers that are properly anchored.
Work completed for breaker hoist under work order Adjacent oil filled transformers are C01f83131 on August 1, 2000.
unanchored.
A walkdown was performed on April 24, 1997 to verify that all of the new transformers were installed for MOD 5099.
00B94/95/96 Unanchored switchgear and Switchgear will be anchored.
Work completed for anchorage under work orders None transformers.
C01 89242 and C01f89243 on August 1, 2000, and Hoist will be restrained or removed.
C0189244 on October 16, 2000.
Interaction concern with breaker Work completed for breaker hoist under work hoist.
orders C01 88074 on August 1, 2000.
30A15/16/17/18 Door latching mechanisms are only Latches will be fastened and neoprene pads Work completed under work order C0177308 on None engaged at center of door. Latching may be provided.
August 1, 2000.
bolts at top and bottom are not engaged.
Spare breakers will be removed or secured.
Per Item 4, p. 17 of A1056479, as of August 1, 2000, spare breakers removed and will not be 30A15,16,17 have spare breakers stored in switchgear rooms per procedure SO which are not adequately secured.
54.7.C. No PIMS work recorded for removal of spare breakers.
30X133/150 30KVA transformer coils are missing Perform evaluation of coil anchorage and ECR PB 97-02258 has been completed. CALC 30X133 included in walkdown 2 of 4 holding bolts, modify if required.
PS-0947 reviewed the transformers and concluded sample.
that the outlier conditions are seismically acceptable (September 29, 1997).
No modification to confirm.
30X31/33 Oil filled transformers are Replace with ABB 1000KVA VPE ventilated dry A walkdown was performed on April 24, 1997 to 30X33 included in walkdown sample.
unanchored.
type transformer properly anchored, verify that all of the new transformers were installed for MOD 5099.
Confirmed issue resolved.
Peas Bottom Atomic Por Sation unt 3 MPR43812, Reoiion 3 Coweopondenc So.: RS-12r173 7-2
Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown
- A1056479 Resolution 00X103 Anchorage of transformer coils to Vendor drawings will be reviewed and ECR PB 97-02258 has been completed. CALC None 30X135 enclosure support surface evaluated and if necessary anchorage will be PS-0947 reviewed the transformers and concluded indeterminate, reworked to comply.
that the outlier conditions are seismically acceptable (September 29, 1997).
0AX26/0BX26/0CX26 Anchorage could not be verified.
Transformer will be anchored.
Work completed under work order C0189169 on None August 1, 2000.
3AP42/3BP42/3CP42/3DP42 Pump casing and shaft are greater Analytic evaluation proved pump casings and Analysis completed as of IPEEE submittal May 3CP042 and 0BP057 included in 0AP57/0BP57 than 20 ft.
shafts acceptable.
1996.
walkdown sample.
Non-tied down yard gantry crank Yard crane will be restrained when not in use.
Work completed under A/R Al188705 on August 1, Confirmed issue resolved.
could fall on pump house.
2000.
MO-33-0498 Valve has interaction concern with Support for radiation element outlet will be Work completed under work order C0182155 on MO-0-33-0498 included in walkdown radiation element outlet modified.
August 1, 2000.
sample.
Confirmed issue resolved.
A03-03-33 Distances from pipe centedine to Review documentation and perform analysis if ECR PB 97-02258 has been completed. CALC A03-03-33 included in walkdown top of valve operator is outside of required to demonstrate seismic capacity.
PS-0947 reviewed the air operated valve and sample.
experience database, concluded that the outlier conditions are seismically acceptable (September 29, 1997).
No modification to confirm.
M03-13-5487 Valve operator weights and/or Review documentation and perform analysis if ECR PB 97-02258 has been completed. CALC None centedine distances are outside of required to demonstrate seismic adequacy.
PS-0947 reviewed the MOV and concluded that the experience database.
the outlier conditions are seismically acceptable (September 29, 1997).
0AV035136 Overhead ducts need to be Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and OAV036, 0BV035, and OBV036 O0 reviewed as part of the I PEEE for required or develop suitable operator actions, complete) status on July 24, 1997. The required included in walkdown sample.
seismic adequacy.
physical (MOD) work in the plant was tracked by A1056479-12.
No issues identified with overhead ducting.
00F043 Overhead ducts are an interaction Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and None
- concern, required or develop suitable operator actions, complete) status on July 24, 1997. The required physical (MOD) work in the plant was tracked by A1056479-12.
Peacuh Beiom Atomic Powr station Un 3
-PRS-812, Revg~on 3
Correspodence No.: RS-12-7-n 7-3
Table 7-1. PSAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from A/R
- A1056479 Sample Component Walkdown Resolution 0AV034 Attached heating piping at upper Evaluate steam piping and modify if required.
ECR 97-00992 was taken to approved (and None nozzJes is poorly supported.
Evaluate overhead systems and modify as complete) status on July 24, 1997. The required required or develop suitable operator actions.
physical (MOD) work in the plant was tracked by Overhead ducts are an interaction A1056479-12.
concern.
30D22/23124 Depth of panels are less than that Top supports will be provided and existing floor Work completed under work order C0190338 on None which is included in earthquake anchorage will be evaluated and modified as December 14, 2000.
experience database, required.
Anchor bolts have 2 1/4" eccentricity and in addibion, comer plates are too flexible and do not provide an adequate load path.
3ADO1/3BD01/3CD01/3DD01 Batteries are more than 450 lbs.
Review of existing data showed that the Work completed under work order C0193773 on 3BC01, 3CD01, and 30001 included (actual weight 700 lbs.) which is batteries are qualified to IEEE-323 (1974) and August 1, 2000.
in walkdown sample.
outside experience database. Also, IEEE-344 (1975).
end rails are not snug with batteries.
Confirmed issue resolved for 38C01 Also overhead fluorescent lights are A snug fit will be provided at end rails and the and 3DD01.
suspended with chains having open S-hooks will be closed.
S-hooks.
0AG12/0BG12/0CG12/0DG12 Interaction concerns with overhead Overhead crane controller will be tied down Work completed under work orders C0181161, 0AG012 and 0DG012 included in crane controller. Local panel on when not in used.
C0181153, C0181159, and C0179951, and walkdown sample.
vibration isolators without lateral C0193768 on August 1, 2000.
capacity.
Vibration isolators will be modified to preclude Confirmed issue resolved.
dislodging in SSE.
TIC-30223 Cover on temperature controller is Cover will be secured.
Component was secured under ECR 99-00149 on None loose.
August 1, 2000.
OAG13/OBG13/OCG13/0DG13 Interaction concerns exist regarding Overhead crane controller will be tied down Work completed under work order C0193768 on 0AC097 included in walkdowo 0AC097/0tC097/000097 overhead crane controller, when not in use.
August 1, 2000.
sample.
0DC097 Confirmed issue resolved (documented for 0AGO12).
00C29A/B/C/D Interaction concerns with Items will be removed or restrained.
Work completed under work order C0183590 on 00C29B included in walkdown 30C124 housekeeping issues in the Control August 1, 2000.
sample.
Room.
Confirmed issue resolved.
Peach Bottom Atomic Powmr Station Uni 3 MPR-3812, Re-ion 3 Corpondence No.: RS-12-173 7-4
Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from A/R Sample Component Walkdown
- A1056479 Resolution 30C32/33 Cabinets are not bolted to the Adjacent cabinets will be tied together front and Work completed to resolve cabinet interactions 30C32. 30C33, and 30C722B 30C722B adjacent cabinet. Interaction back.
under work order C0190338 on December 14, included in walkdown sample.
concerns exist with adjacent non-2000.
safety cabinets and cable tray.
Table will be blocked and located so tipping will Confirmed issue resolved.
not cause impact Work completed to resolve cable tray interaction Cushioning will be provided between adjacent with 30C032 under work order C01 93837 on non-safety cabinet and impact loading will be August 1, 2000.
evaluated.
Pipe stanchion supports Lateral load criteria not met.
Install knee brace at top of stanchion at Work completed underwork orders C0189101, None - issue not applicable to this midspan of raceway and attach to floor or C0189160, and C0190050 on August 1, 2000.
walkdown.
Rx. Bldg. 195' install lateral supports.
RW Bldg. 165' U3 HCU's Top horizontal frame for HCU piping Horizontal bracing will be added.
Work completed under work orders C0187209 and HCU-06-47 and HCU-14-35 included does not have adequate lateral C0187392 on August 1, 2000.
in walkdown sample.
bracing.
Confirmed issue resolved.
El. 165' Mech. Equipment Various duct and interaction issues Perform evaluation of overhead systems and Work completed under work orders C01 90892, None Room HVAC ducting including aux. steam piping.
modify as required or develop suitable operator C0187741, C0191039, and C0182488 on August actions.
2, 2000, and under work order C0195436 on December 18, 2000.
Peach Bottom Atomic Po-r Station Unt 3 MPR-3812, Revision 3 Correspondence 5N.: RS-12-173 7-5
Table 7-2. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis Component ID Issue Planned Resolution Actual Resolution of Condition Resolution Date 30D11 Anchorage evaluation required.
Evaluate anchorage.
Anchorage evaluation completed and anchorage of 5/1997 00B53 MCCs are adequate.
00B54 00855 00856 A03-01-086A/B/C/D Distance from pipe centerline to top Evaluate centerline distance of valve operators. Calculations show valves have acceptable seismic 2/1996 A03-01-086A/B/C/D of valve operator is outside of capacities.
experience database.
M03-23-019 Valve operator weights and/or Evaluate weight and centerline distance of Existing documentation review indicates valves are 5/1996 M03-23-025 centerline distances are outside of valve operators, qualified to an acceptable seismic acceleration.
M03-10-016A5 /C/D the experience database.
M03-12-015 M03-10-025A/B M03-13-027 M03-13-131 M03-13-132 M03-30-3233A/B Cast iron yoke.
Evaluate suitability of cast iron yoke.
Existing documentation was reviewed and 5/1996 components were determined to be seismically adequate.
3AC65 Anchorage does not screen.
Evaluate anchorage.
Evaluation of anchorage was performed and was 5/1997 shown to be seismically adequate.
3AE24/3BE2413CE2413DE24 Heat exchanger anchorage Evaluate anchorage.
Review of RHR Heat Exchanger modification 112004 evaluation is unknown, calculations evaluated anchorage capacity for the RHR Heat Exchangers and found them to be seismically adequate.
POeh Bottom Aomic Power Satn unit 3 MPR-3812, Reision 3 Corresponden. No.: RS-12-173 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 26% 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 3 8-1 MPR-3812, 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 3 8-2 MPR-3812, 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 2, 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-56, NRC Docket No. 50-278, Amendment No. 284, Dated May 29, 2007.
- 10. PBAPS Action Request Al 056479, Last updated 12/20/2000.
Peach Bottom Atomic Power Station Unit 3 9-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173
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 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-1
WIMPR ASSOCIATES INC.
FN G IN EFR S Benjamin M. Frazier EXPERIENCE
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 3 MPR-3812, Revision 3 r.nrrA._,nnnrd*nr.A Nn ' RR-17-173 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 3 MPR-3812, Revision 3 r.nrrpqnnndPnrA. Nn " RR-1 '-17.
A-3
~i*PI ELECTRIC POWER spell 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-3812, Revision 3 Correspondence No.: RS-12-173 A-4
WMPR ASSOCIATES INC.
F N G I NE 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 3 MPR-3812, Revision 3 rnrrmqnnndArnr.A.Nn RR-1-17R A-5
I ELECTRIC POWER raUeU IRESEARCH INSTITUTE Certificate of Completion Kevin Gantz Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns July 3, 2012 Date
'~-,
~-
Caroline S. Schtaseman, P.E.
Instructor MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-6
UMPR ASSOCIATES INC.
F N GIN E 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 OCFR50 Appendix B and how it is applied at different utilities.
BWR In-Vessel Piping Repairs Designed first-of-a-kind repair clamps to structurally replace cracked welds in a BWR in-vessel feedwater sparger and a core spray line.
Designed and managed fabrication of the tooling to remotely install feedwater sparger repair clamps from refueling bridge above vessel.
Design Basis Information Review Provided management direction for a program to demonstrate the adequacy and availability of design basis information. Assisted preparation of the utility response to the NRC's 10 CFR 50.54(f)
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnmrr.nnnrdPnrA 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.
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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 seismictweak 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.
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,ELECTRIC POWER Ul I RESEARCH INSTITUTE Certificate Craig of Completion Swanner Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.
Instructor MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-9
RIMPR ASSOCIATES INC.
F N G IN F F R~ S 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.
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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.
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IlELECTRIC POWER meiU I
RESEARCH INSTITUTE Certificate of Completion Mojtaba Oghbaei Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns July 3, 2012 Date 00, Caroline S. Schlaseman, P.E.
Instructor MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-12
WMPR ASSOCIATES INC.
E N G INFERS 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 3 MPR-3812, Revision 3 rnrrA~nnndln-.- Nn " RR-1 -171 A-13
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.
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- ELECTRIC POWER RESEARCH INSTITUTE Certificate of Completion James Wiggin Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.
Instructor MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-1 5
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.
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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.
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F ECTftIC POWER IEII~ II IFSAIC H INSTIMTE.T Certificateof Completion Caroline Schlaseman Training on Near Term Task Force Recommendation 2.3
- Plant Seismic Walkdowns June 21, 2012 Date Robolt K -Kassawera EPRI Manage, Stnicurl Rafiabihty & Integrtty MPR-3812, Revision 3 Correspondence No.: RS-12-173 A-18
MMPR ASSOCIATES INC.
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 XI 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 3 MPR-3812, Revision 3 rnrrPqnnnrlPnr.P Nn
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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.
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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 3 MPR-3812, Revision 3 A-21 rnrrP.qnnnHA~nA.* Nn
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B Equipment Lists The following documents are included in this appendix:
Base List (95 pages)
SWEL Signature Page Table B-i: SWEL for Unit 3 Table B-2: SWEL for Unit 0 (common)
Note that there are no items in the SWEL 2 for Peach Bottom Unit 3.
Table B-3: Deferred to RFO or Electrical Bus Outage: Inaccessible or Electrical Safety Concern Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-1
DOCUMENT NO. 00674-0084-0001 REVISION 2 TRAIN SOUG CI Equip ID Uni Evel recfd?
PUS to PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE: 3128M PAGE I Norm date Motive power Suippo System Destred State Co power Supp Sys dwg system Notes EquRi Desoiption ROB 16011W Camp Orwfng No.
Loc Code Room Elev Lkn No Function Bun 3
0 IGA-23205A SV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT I ODW2-27 OPERABLE NIA 2
NIA RV-2-2-071A 154 2102 PASSIVE CHK-2-16A-23205A Dywll -U2 OPERABLE NIA 3
0 16A-232058 SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT I 0AN2-29 OPERABLE NWA 2
WA RV-2-2-018 164 2107 PASSIVE CHK-2-1&A-232058 Drywa -U2 OPERABLE N/A 3
0 1OA-23205C SRV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT I D0W2-27 OPERABLE NWA 2
N/A RV-2-2-071C 154 2112 PASSIVE CHK-2-16A-23206C ryweall -U2 OPERABLE WA 3
0 16A-23205G SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SPIT 2 D4AV2-W3 OPERABLE NWA 2
MIA RV-2-2-071G 154 2123 PASSIVE CHK-2-16A-23205G Drywae -U2 OPERABLE NIA 3
0 16A-23205K SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT 2 0IW2-34 OPERABLE NIA 2
NWA RV-2-2-071K 154 2132 PASSIVE CHK-2.16A-23205K D"Mil - U2 OPERABLE NIA 1
0 2-0696B RCIC FEEDWATER CHECK VALVE LOOP B M-351, SHT 2 R2-30 OPEN NWA 2
NWA OUTER 135 3134 PASSIVE CHK-2-06-M6B Reactor Bldg. U2 CLOSED NIA 1
0 2-10-177 RHR4B HIGH PRESSURE SERVICE WATER TO M-315, SHT I R2-6 CLOSED NWA 2
WA RHR CROSSTIE CHECK VALVE 091 4208 PASSIVE C,
.2-10-177 Reactor Bldg - U2 CLOSED NWA 2
0 2-i0-184A RHR-A RHR PRESSURING LINE INNER CHECK M-36i, SHT i R2-24 CLOSED WiiA 2
NWA VALVE TO RHR LOOP A 135 4116 PASSIVE CHK-2-10-184A Reactor Bldg - U2 CLOSED NWA 1
0 2-10-184B RHR-8 RHR PRESSURING UNE INNER CHECK M-361, SHT2 R2-26 CLOSED NWA 2
WA VALVE TO RHR LOOP B 135 4215 PASSIVE CHIC-2-10-184B Reactor Hdg - U2 CLOSED NIA 0
2-1048A RHR.C RHR PUMP 2AP035 DISCHARGE CHECK M-361., SHT I R2-5 CLOSED NWA 2
WA VALVE 091 4306 PASSIVE CHK-2-10-48A 3
Reactor Bldg - U2 OPERABLE NWA 1
0 2-10-488 RHR-D RHR PUMP 20P035 DISCHARGE CHECK M-361, SHIT 2 R2-6 CLOSED N/A 2
NWA VALVE 091 4407 PASSIVE CMK-2-10-488 3
Reactor Bdg -U2 OPERABLE WA 2
0 2-10.48C RHR-A RHR PUMP 2CP03S DISCHARGE CHECK "I381. SHT I R2.7 CLOSED NWA 2
NIA VALVE 091 4110 PASSIVE CHK-2-10.48C ReactoIdg-in OPERABLE WA 1
0 2-10-48D RHR-B RHR PUMP 2DP035 DISCHARGE CHECK M-381. SHT 2 R2-8 CLOSED MIA NWA PASSIVE CHK-2-10-48D VALVE 091 Reactor B ug
-2 OPERABLE N/A 4210 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C*nrrP.qnnd.n-P. Nn - RS-19-17.
B-2
DOCUMENT NO. 006740084-3001 REVISION 2 TRAIN SQUG CI Eqip U)
Unit Evas reqd?
PU1S ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power i Suppo System Desred State ConU power Supp Sys deg DATE: 3/2r196 PAGE 2 System Nan Equip Descripon ROB Morner Comp Drm"ng No.
Loc Code Room Elov Line No Function Budlding 3
0 2-16-257A SRV INSTR N2 CHECK VALVE TO RV-2.2-071A M-351, SHT 1 0N2-27 OPERABLE NIA 2
N/A 154 2103 PASSIVE CHK-2-16-257A Orywl -U2 CLOSED NIA 3
0 2-16-2578 SRV INSTR N2 CHECK VALVE TO RV-2-2-071S 1-351. aSIT 1
01*f2-29 OPERABLE N/A 2
N/A 154 2108 PASSIVE CHK-2.16-257B Oryweu -U2 CLOSED N/A 3
0 2-16-257C SRV INSTR N2 CHECK VALVE TO RV.2-2-071C M-351, SHT I DMW2-26 OPERABLE N/A 2
N/A 154 2113 PASSIVE CHK-2-16-257C Drywel. U2 CLOSED N/A 3
0 2-16-2570 SRV INSTR N2 CHECK VALVE TO RV-2-2-071G M-351. SHT 2 DO2-.35 OPERABLE N/A 2
N/A 154 2124 PASSIVE CHK-2-16-2570 Orywen -U2 OPERABLE N/A 3
0 2-16-257K SRV INSTR N2 CHECK VALVE TO RV-2-2-071K "I-35. SMlT 2 ON12-34 OPERABLE N/A 2
N/A 154 2133 OPERABLE CHK-2-16-257K IM
-U2 OPERABLE N/A 2
0 2-32-5M.A HPSW HPSW 2AP042 DISCHARGE CHECK W-315. SHlT 1 PH.6 OPERABLE N/A 2
N/A VALVE 111 5518 PASSIVE CHK-2-32-502A Pump House OPERABLE NWA 1
0 2-32-5028 HPSW HPSW2BPO42 DISCHARGE CHECK M-315, SHIT 1 PM.6 OPERABLE N/A 2
N/A VALVE 111 5520 PASSIVE CHK-2-32.502B Pump House OPERABLE N/A 2
0 2.32-'WC HPSW HPSW 2CP042 DISCHARGE CHECK M-315. SHT 1 PIH-6 OPERABLE N/A 2
N/A VALVE III 5522 PASSIVE CHK-2-32-502C PuFnp House OPERABLE N/A 1
0 2-32-6020 HPSW HPSW 2DP042 DISCHARGE CHECK M1315. SHT 1 P1146 OPERABLE N/A 2
N/A VALVE 111 5524 PASSIVE CHK-2-32-502D Pump House OPERABLE N/A 3
0 2-33-514 ESW SERVICE WATER TO ESW CROSS TIE W-315, SHT 5 T2-45 N/A N/A 2
NIA CHECK VALVE 116 5563 PASSIVE CHK-2-33-614 Turbine Bldg - U2 CLOSED N/A 3
0 2-3A-13 CRD HYDRAULIC CONTROL UNITS, TYPICAL M-357. SHlT I R2-24 OPERABLE N/A 2
S OF 185 135 1100 ACTIVE U2 HCU 02-19 1
Reactor Bmdg
. U2 OPERABLE N/A 1
0 2-6-96A HPCI FEEDWATER CHECK VALVE LOOP A M-351. SHlT 1 R2-30 OPEN N/A 2
N/A OUT135 3233 PASSIVE CHK-2-06-W9A Reactor Bldg -U2 CLOSED N/A 2
0 2AS769 RHR-2A RHR PP 2AP035 SUCTION STRAINER M-361. SHT I Torus OPERABLE N/A 2
S PASSIVE 1Il Tomus Proper - U2 2AS769 OPERABLE N/A U-361, M-4578.
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (lnrrpqnnndtpnn.c Nn
- RS-12-173 B-3
DATE: 312816 DOCUMENT NO. 0067400084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 3 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID System Equi Descrption Drawing No.
Loc Code N" m e
Motive power SuLport System unit Eval reqcd?
PIMS ID Notes ROB Moher Comp Room Elev Desied state Cowt power Supp Sys dwg Line No Funtion 1
0 28S769 RHR.2B RHR PP 2BP035 SUCTION STRAINER M-361, SHT 2 ToMs OPERABLE NIA 2
S 111 4200 PASSIVE 2US769 Torus Proper. U2 OPERABLE NIA M4-361.1M-4578.
2 0
2CS769 RHR-2C RHR PP 2CP035 SUCTION STRAINER M-361, SHT I Toan OPERABLE NIA 2
S 111 4300 PASSIVE 2CS769 3
Tows Proper - U2 OPERABLE NIA M4-361. M4-4578.
1 0
20S769 RHR.2D RHR PP 2DP035 SUCTION STRAINER M-361, SHT 2 ToMus OPERABLE NIA 2
S III 4400 PASSIVE 2DS769 3
Tonus Proper - U2 OPERABLE NIA M-361, M..4578, 2
0 A02-10-46A RHR-A RHR LOOP A CHECK VALVE M-361, SHT I O/W2-21 CLOSED MIA 2
S 134 411812211 PASSIVE AO-2-10-048A O"I
- U2 OPERABLE NWA M-144-21-7 1
0 A02-10-46B RHR-4 RHR LOOP B CHECK VALVE M-361. SHT 2 DNV2-16 CLOSED NIA 2
S 134 4217 PASSIVE AO-2-104-46B Drywel - U2 OPERABLE NWA M-144-21-7 3
0 A02-14-013A CS CORE SPRAY LOOP A CHECK VALVE M-352. SHT I OM2-21 CLOSED NIR 2
NWA 134 2214 PASSIVE AO-2-14-013A Drmll - U2 CLOSED N/R 3
0 A02-14-0138 CS CORE SPRAY LOOP B CHECK VALVE M-362. SHT 1 DIW2-16 CLOSED NIR 2
NWA 134 2215 PASSIVE AO-2-14-0138 Oyell -
U2 CLOSED NIR 1
0 A02-23-018 HPCI HPCI DISCHARGE CHECK VALVE M-365, SHT 1 R2-30 OPERABLE NIA 2
S 135 3232 PASSIVE AO-2-23-018 Reactor Bldg. U2 OPERABLE NFA Vendor 16097-02 3
0 M02-10020 RHR-A RHR LOOPS AB X-TIE M-361, SHT I R2-93 CLOSED NWA 2
NWA 116 4108.4207 PASSIVE MO-2-10-020 11 Reactor Bldg - U2 CLOSED NWA 2
0 M02-10-033 RHR-A HEAD SPRAY OUTBOARD ISOLATION M-361. SHT I R2-33 CLOSED NIR 2
NWA VALVE 165 4111 PASSIVE MO-2-10,033 11 Reactor Bldg - U2 CLOSED NIR 3
0 M02-48-2213 ESW UNIT 2 ESWPUMP SLUICE GATE M-330 SIK-4 OPEN NIR 2
R 116 5631 PASSIVE M0-2-33-2213 Scew House OPEN NIR 3
0 PCV-8917A BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT 1 R2-22 OPERABLE NWA 2
5 BACKUP SUPPLY TO ADS 135 6105 ACTIVE PCV-2-16A-891?A Reactor Bldg - U2 OPERABLE NWA 3
0 PCV-8917B BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-=333 SHT 1 R2-22 OPERABLE WA 2
S BACKUP SUPPLY TO ADS 135 6106 ACTIVE PCV-2-16A-8917B Reactor Bldg - U2 OPERABLE NWA Peach Bottom Atomic Power Station Unit 3 B-4 MPR-3812, Revision 3 C'nrriqnnrlnn.n. Nn
- R-2-1-73
DOCUMENT NO. 0674004-O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTOOWN EQUIPMENT LIST DATE: 3rA295 PAGE 4 NorM gate Motve power Su.pon System Des0kd Stae Cona power Supp Sys fwg TRAIN Unit SOUG CI Equip W Eval reqd?
PIM4510 Systes NOWe Equip De-saion ROB Mother Camp Loc Code Room Elew Line No Function Build 3
0 PCV-8917C BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-33, SHT I R2-22 OPERABLE N/A 2
S BACKUP SUPPLY TO ADS 135 6107 ACTIVE PCV.2-16A.8917C Reaclot Bldg. U2 OPERABLE N/A 1
0
- PSD2-23-006 HPCI HPCI TURBINE EXHAUST RUPTURE DISC M-3668 SHT I R2-13 OPERABLE N/A 2
N/A 088 3206 PASSIVE PSD-2-23-006 Reactor Bdg - U2 OPERABLE N/A 1
0 SUCTION HPCI HPCI SUCTION STRAINER M-365, SHlT I Tanas OPERABLE N/A 2
S STRAINER.2HPCI 111 3220 PASSIVE Reactor Bdg9
- U2 OPERABLE N/A 3
0 VRV2-2-8096A SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHlT I D0A2-26 OPERABLE N/A 2
S STEAM LINE RELIEF W A t 58 2104 ACTIVE VRV.2-02-8096A Oyell - U2 OPERABLE MIA M120-75-4 3
0 VRV2-2-80968 SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT I 0NW2-29 OPERABLE N/A 2
S STEAM LINE RELIEF W 158 I
2109 ACTIVE VRV-2-02-80968 DWO - U2 OPERABLE N/A M120-7.5-1 3
0 VRV2-2-8096C SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT I DN42-26 OPERABLE N/A 2
S STEAM LINE RELIEF W C 168 2114 ACTIVE VRV-2-02-8096C 2-
- U2 OPERABLE NA M120-75-1 3
0 VRV2-20960 SRV VACUUM RELIEF VALVE FOR MAIN M4-351, SHT 1 DM12-27 OPERABLE NIA 2
S STEAM LINE RELIEF W D Ise 2116 ACTIVE VRV-2-02-8096D Drywal. U2 OPERABLE N/A M120-75-1 3
0 VRV2-2406 SRV VACUUM RELIEF VALVE FOR M
4N351.
S STEAM LINE RELIEF W E 158 2118 ACTIVE VRV-2-02-8096E ryell - U2 OPERABLE N/A M120-75-1 3
0 VRV2-2-8096F SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT I DN2-29 OPERABLE N/A 2
S STEAM LINE RELIEF W F 158 2120 ACTIVE VRV-2-02-8096F Drywall - U2 OPERABLE N/A M120-76-1 3
0 VRV2-2-8096G SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 2 Dm2-35 OPERABLE N/A 2
S STEAM LINE RELIEF W G 158 2126 ACTIVE VRV-2-02-09G Orywell -U2 OPERABLE N/A M120-75-1 3
0 VRV2-2-3096H SRV VACUUM RELIEF VALVE FOR MAIN I-351, SHT 2 DMN2-34 OPERABLE N/A 2
S STEAM LINE RELIEF W H Ise 2127 ACTIVE VRV-2-02-8096H DryweI.- U2 OPERABLE N/A M120-75-1 3
0 VRV2-2.8096J SRV VACUUM REUEF VALVE FOR MAIN M-351. SIlT 2 DW2-32 OPERABLE N/A 2
S STEAM LINE RELIEF W J Ise 2129 ACTIVE VRV-2-02-8O96J Orywea - I2 OPERABLE N/A M120-75-1 3
0 VRV2-2-80s6K SRV VACUUM REUEF VALVE FOR MAIN I-351.
SHT 2 DMV2-34 OPERABLE N/A S
ACTIVE STEAM LINE RELIEF W K 158 Drywall - U2 VRV-2-0248096K OPERABLE N/A M120-75-1 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrmrqnnndr.nr.
Nn* RS-19-173 B-5
DATE: 3120396 PAGE 5 DOCUMENT NO. 00674-0841D001 REVISION 2 TRAIN SQUG CI Equip ID UnA Eval recd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System Notes RqOi DesMotempn ROB Mother Camp Drawing No.
Loc Code Room Elev Norm Stew Mote Powe Support Syst.
Desaed Stale Co owe Supp Sys dwg Line No Functin Buildig 3
0 VRV2-2.8096L SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 2 DN2-32 OPERABLE NIA 2
S STEAM UNE REUEFW L 15O 2136 ACTIVE VRV-2-02-806M Orywa. -U2 OPERABLE NIA M120-75-1 1
0 VRV2-23C-140A HPCI HPCI TURBINE EXHAUST TO. TORUS M-365. SHT 1 R2-92 OPERABLE NIA 2
WA VACUUM RELIEF VALVE 116 3215 PASSIVE VRV-2-23C-140A Reactor Bldg -U2 OPERABLE NIA 1
0 VRV2-23C-1408 HPCI HPCI TURBINE EXHAUST TO, TORUS M-365, SHT I R2-92 OPERABLE NIA 2
NIA VACUUM RELIEF VALVE 116 3216 PASSIVE VRV-2.23C-140B Reactor 81dg U2 OPERABLE WA 1
0 VRV2-23C-140C HPCI HPCI TURBINE EXHAUST TO, TORUS M-365. SHT I R2-92 OPERABLE WA 2
NIA VACUUM RELIEF VALVE 116 3217 PASSIVE VRV-2-23C-140C Reactor Bldg. U2 OPERABLE N/A 1
0 VRV2-23C-1400 tPCI HPCI TURBINE EXHAUST TO, TORUS M-365, SHT I R2-92 OPERABLE WA 2
NIA VACUUM REUEF VALVE 116 3218 PASSIVE VRV-2-23C-1400 Reacto Bldg - U2 OPERABLE NIA 1
0 VRV2-23C-499aA HPCI HPCI TURBINE EXHAUST VACUUM.
M-366, SHT 1 R2-13 CLOSED WNA 2
NWA RELIEF VALVE 08 3207 PASSIVE VRV-2.23C-4998A Reactor Bg - U2 CLOSED NWA I
0 VRV2-23C-49988 HPCI HPCI TURBINE EXHAUST VACUUM M-356. SHT 1 R2-13 CLOSED NIA 2
NWA REUEF VALVE 088 3208 PASSIVE VRV.2-23C-49988 Reactor Bldg -U2 CLOSED NWA 3
1 20838 EPS-2A 480 V REACTOR AREA EL 165 MCC E-1615 R2-41 ENERGIZED 2081013 2
S 20B36 (E124-R-C) 165 8000 ACTIVE E124-R-C (20836)
Reactor Bklg. U2 ENERGIZED 3
1 20837 EPS-2B 480V REACTOR AREA EL 165' MCC E-1615 R2-23 ENERGIZED 2081113 2
S 20837 (E224-R-.)
135 8000 ACTIVE E224-R-B (20837)
Reacto O
- U2 ENERGIZED 3
1 20838 EPS-2C 480V RADWASTE AREA EL 135' MCC E-t617 R2-29 ENERGIZED 2081213 2
S 20838 (E324R-8) 135 amo ACTIVE E324-R-B (20838)
Reactor Bldg - U2 ENERGIZED 3
1 20839 EPS-2D 480V RADWASTE AREAEL 116' MCC E-t617 T2-44 ENERGIZED 2081313 2
S 20839 (E424-W-A) 116 8000 ACTIVE E424-W-A (20839)
Turbine Bldg - U2 ENERGIZED 3
1 20859 EPS-2A 480V TURBINE AREA EL 135 MCC E-1615 T2.71 ENERGIZED 2081014 2
S 20859 (EI24-T-8) 135 8000 ACTIVE E124-T-B (20859)
Tubine Bldg -.2 ENERGIZED 3
1 20860 EPS-2B 480V TURBINE AREA EL 135 MCC E.1615 T2-71 ENERGIZED 2081114 S
ACTIVE 20860 (E224.T.B) 135 Tutine Bldg - U2 ENERGIZED 8000 E224-T-8 (20=80)
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrmrPnndp.ne.. Nn - RS-19-17.3 B-6
DATE: 312V86 PAGE 6 DOCUMENT NO. 0067-0084-0001 REVSION 2 TRAIN SOUG CI Equip ID Ung Eva[ rqo'?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System NOtell Equip Description ROB Moom Camp DOUwb No.
Loc Code Room Elov SUM" Norm state Desired State Moti power Cont power Support System SUpp Sys d" Line No Function 3
1 2011 EPS-28 (2001 1) RX BUILDING DC MOTOR E-26. SHT I R2-26 ENERGIZED 28018 T
28018 2
S CONTROL CENTER 135 N
8213 ACTIVE 2D0-R-8 Reactor Bldg - U2 ENERGIZED 3
2 20810 EPS-2A 480V BUS E124 E-1615 R2-41 ENERGIZED 20X30 2081012 2
S 165 8000 ACTIVE 208010 Reactor Bldg - U2
.ENERGIZED 3
2 2091012 EPS-2A BREAKER TO E124 48D V BUS (LC20810)
E-1615 R2-41 CLOSED 20810 2
OR 165 a000 PASSIVE E-73 (1012) 20810 Reactor Bidg - U2 CLOSED 3
2 2081013 EPS-2A BREAKER TO 480 V MCC 20836(EI24-R-C)
E-1615 R2.41 CLOSED 20810 2
BR 165 a000 PASSIVE E124(1013) 20810 Reactor Bldg - L2 CLOSED 3
2 2081014 EPS-2A BREAKER TO 480 V MCC 20859 E-1615 R2-41 CLOSED 20810 2
BR (EI24-T-8) 165 8000 PASSIVE E124(1014) 20810 Reactor Bid0 -U2 CLOSED 3
2 2081021 EPS.2A BREAKER TO MCC 00853 E-1615 R2-41 CLOSED 20810 2
BR 165 8000 PASSIVE E47 (1021) 20810 Reactor BidJ 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 Bidg - U2 CLOSED 3
2 20811 EPS-28 480 V BUS E224 E-1615 R2-116 ENERGIZED 20X31 2081112 2
S 165 8000 ACTIVE 208011 Reactor Bldg - U2 ENERGIZED 3
2 2081112 EPS-25 BREAKER TO E224 480 V BUS (LC20811)
E-1615 R2.116 CLOSED 20811 2
BR 165 8000 PASSIVE E-124 (1022) 20811 Reactor Bldg -U2 CLOSED 3
2 2081113 EPS-2B BREAKER TO 480 V MCC 20837 E-1615 R2-116 CLOSED 20811 2
BR (E224-R-8) 165 8000 PASSIVE E224(1113) 20811 Resc"r Bldo. U2 CLOSED 3
2 2081114 EPS-28 BREAKER TO 480 V MCC 20860 E-1615 R2-116 CLOSED 20811 2
BR (E224-T-B) 165 8000 PASSIVE E224(1114) 20811 Reactor BSdg - U2 CLOSED 3
2 2081122 EPS-28 BREAKER TO MCC 00861 E-1615 R2.416 CLOSED 20811 2
BR 165 8000 PASSIVE E-224 (1122) 20811 Reactor Bldg - U2 CLOSED 3
2 2
S 8000 ACTIVE 20812 EPS-2C 480 V BUS E324 E-1617 R2-41 ENERGIZED 20X32 2081212 165 Reactor BMdg-U2 E-324(20012)
ENERGIZED Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrR*nnndl.nr.p. Nn
- RS-12-173 B-7
DOCUMENT NO. 0067.0084-0001 REVISION 2 PEACH BOTIOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3WsM6 PAGE 7 Norm state Motive power support System Doesed State Cra*r power Supp SyS d*
TRAIN Unit SQUG Ci Equip ID Evat reqld?
PIMS ID system Not"s Equip Desaiptfi-ROB Mother Comp Drewirg No.
Loc Code Room Elev Line No Furtion BuLdig 3
2 2081212 EPS-2C BREAKER TO E324 480 V BUS (LC20812). E-1617 R2-41 CLOSED 20812 2
BR 165 s80o PASSIVE E-324 (1212) 20812 Reactor BUD -U2 CLOSED 3
2 2081213 EPS-2C BREAKER TO 48D V MCC 20838 E-1617 R2-41 CLOSED 20812 2
BR (E324.R-8) 165 800m PASSIVE E324(1213) 20812 Reactor Bldg - U2 CLOSED 3
2 2061221 EPS-2C BREAKER TO MCC 00855 E-1617 R2-41 CLOSED 20812 2
BR 185 8000 PASSIVE E-324 (1221) 20812 Reactor Bldg - U2 CLOSED 3
2 2081222 EPS-2C BREAKER TO MCC OD849 E-1617 R2-41 CLOSED 20812 2
BR 165 8000 PASSIVE E-324 (1222) 20812 Reactor Bldg -U2 CLOSED 3
2 20913 EPS-2D 480 V BUS E424 E-1617 R2-1 16 ENERGIZED 20X33 2081312 2
S 165 6000 ACTIVE E-424(20813)
Reactor Bldg - U2 ENERGIZED 3
2 2081312 EPS-2D BREAKER TO E424 480 V BUS (LC20813)
E-1617 R2-116 CLOSED 20813 2
DR 165 8000 PASSIVE E-424 (1312) 20813 Reactor Bldg. U2 CLOSED 3
2 2081313 EPS-20 BREAKER TO 480 V MCC 20839 E-1617 R2-116 CLOSED 20813 2
OR (E424-W-A4 165 8000 PASSIVE E424(1313) 20813 Reactor Bldg -U2 CLOSED 3
2 2081322 EPS-2D BREAKER TO MCC OOO E-1617 R2.116 CLOSED 20013 2
BR 165 8000 PASSIVE E,424 (1322) 20813 Reactor Bldg
- U2 CLOSED 3
3 20A15 EPS-2A (20A015) EMERG AUX SWITCHGEAR E-8 12-171 ENERGIZED 20At,50 20A1503 2
S 135 8100 ACTIVE 20A015 Turbine Bdg - U2 ENERGIZED 3
3 20A1501 EPS-2A E312 BKR FROM XFMR 0SX04 E-8 T2-171 OPEN 20A15 2
BR 135 8101 PASSIVE 20A1501 20A15 Tubi BI-dg
-U2 OPEN 20D21 3
3 20A1503 EPS-2A E12 SKR FROM El DIG OAG12 E-8 12-171 OPEN OAG1S 2
BR 135 8102 ACTIVE 20A1503 20A15 Turine Bldg -U2 CLOSED 20021 3
3 20A1505 EPS-2A E124 BKR TO XFMR 2OX30 E-8 12-171 CLOSED 20A15 2
BR 135 8103 ACTIVE 20A1505 20A15 Tubine blg
-U2 OPERABLE 20021 3
3 20A1506 EPS-2A BREAKER TO A RHR PUMP 2AP35 E-8 12-171 OPEN 20A15 ER ACTIVE 135 Tuwbine Bg. U2 8104 20A1506 20A15 OPENICLOSED 20021 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrP.qnnnnrlnr.r Nn' RR-19-173 B-8
DOCUMENT NO. 0067-0004-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Motie power Conte Power DATE: 3128WN PAGE 8 TRAIN Unit SOUG CC Eyad req'd?
Equip ID PIUS ID System Notes Equip DesOtion ROB Mother Comp Drawing No.
Loc Code Roon Elev Noffn state Desied State Support System Supp Sys dwg Line No Fuction Burn 3
3 20AS107 EPS-2A BREAKER TO A HP SER WATER PUMP E-8 12-171 OPEN 20A15 2
"R 2AP42 135 8105 ACTIVE 20A1 507 20A15 Turbine Bldg -U2 CLOSED 20021 3
3 20A1508 EPS-2A E212 BKR FROM XFMR OAX04 E-8 T2-171 CLOSED 20A15 2
BR 135 8106 ACTIVE 20A1508 20A15 Twul*i 8ldg -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-2B E322 8XR FROM XFMR 08X04 E-8 T2-71 OPEN 2DA16 2
BR 135 8201 PASSIVE E22 (1601) 20A16 Turbine Bldg. U2 OPEN 280306 3
3 20A1602 EPS-28 BREAKER TO 8 RMR PUMP 2SP35 E-8 T2-71 OPEN 20A16 2
BR 135 8202 ACTIVE E22 (102) 20A16 Turbie Bldg - U2 OPEN/CLOSED 20022 280306 3
3 20A1605 EPS-28 E224 8KR TO XFMR 20X31 E-8 T2-71 CLOSED 20A16 2
OR 135 8204 ACTIVE E22 (1605) 20A16 Turbine Bldg - U2 OPERABLE 20022 28D306 3
3 20A1606 EPS-26 E22 SKR FROM E2 D/G 08G12 E-8 T2-71 OPEN OBG12 2
BR 135 8205 ACTIVE E22 (1606) 20A16 Turbine Bldg - U2 CLOSED 20022 280306 3
3 20A1607 EPS-2B BREAKER TO 8 HP SERV WATER PUMP E-8 T2.71 OPEN 20A16 2
BR 2BP42 135 8206 ACTIVE E22 (1607) 20A16 Turbine Bldg -U2 CLOSED 20022 280306 3
3 20A1608 EPS-2B E222 8KR FROM XFMR OAX04 E-8 T2-71 CLOSED 20A16 2
OR 135 8207 ACTIVE E22 (1608) 20A16 TurbinefBdg - U2 CLOSEDIOPEN 280306 3
3 20AI7 EPS-2C (20A017) EMERG AUX SWITCHGEAR E-8 12-170 ENERGIZED 20A1704 20A1704 2
S 135 20A1708 8300 ACTIVE E32 Turbine Bl*ig L2 ENERGIZED 3
3 20A1701 EPS-2C E332 8KR FROM XFMR OX04 E-.12-170 OPEN 20A17 2
OR 135 8301 PASSIVE E32 (1701) 20A17 Turbne Bldg - U2 OPEN 30023 3
3 20A1702 EPS-2C BREAKER TO C RHR PUMP 2CP35 E-.
T2-170 OPEN 20A17 2
OR 135 8302 ACTIVE E32 (1702) 20A17 Tubie 8d1g -U2 OPENICLOSED 30023 3
3 20A1704 EPS-2C E32 BKR FROM E3 D/G OCGI2 E-8 T2-170 OPEN 0CG12 2
OR ACTIVE 135 Turbine Blg -U2 CLOSED 30D23 E32 (1704) 20At7 Peach Bottom Atomic Power Station Unit 3 B-9 MPR-3812, Revision 3
('nrr.qnnnd.nr. Nn* RR-12-173
DATE: 3r2M PAGE 9 DOCIMENT NO. 0067-00084-DMO REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl Equ~ip1 Eval feq4?
PUMSID Function System Not*s Equ9 Desciption ROB Molw Conp Orawfri NO.
Loc Code Room Elev Norm State Desird State Motive powe Conv power Support System Supp Sys d" 3
3 20A1706 EPS-2C E324 BKR TO XFMR 2OX32 E-8 T24170 CLOSED 20A17 2
SR 135 6304 ACTIVE E32 (1705) 20A17 Turwine Bldg -U2 OPERABLE 30023 3
3 20A1707 EPS-2C BREAKER TO C HP SERV WATER PUMP E-.
T2-170 OPEN 20A17 2
OR 2CP42 135 8305 ACTIVE E32 (1707) 20A17 TokioBldg - U2 CLOSED 30023 3
3 2oA1708 EPS-2C E232 BKR FROM XFMR OAX04 E-8 T2-170 CLOSED 20A17 2
BR 135 8307 ACTIVE E32 (1708) 20A17 Turbine Bldg-U2 CLOSEDIOPEN 30D23 3
3 20A18 EPS-20 (20A018) EMERG AUX SWITCHGEAR E-8 T2-172 ON 20AI807 20A1807 2
S 135 8400 ACTIVE E42 Twtbme Bklg -U2 ON 3
3 20A1801 EPS-20 E342 8KR FROM XFMR 08X04 E-.12-172 OPEN 20A18 2
BR 135 8401 PASSIVE E42 (1801) 20A18 Tutine Bd9 - U2 OPEN 3D0306 3
3 20A1802 EPS-2D BREAKER TO 0 RHR PUMP 2DP35 E-8 12-172 OPEN 20A18 2
BR 135 8402 ACTIVE E42 (1802) 20A18 Tudwlno Bdg -U2 OPENICLOSED 30024 300306 3
3 20A1804 EPS-20 BREAKER TO O HP SER WATER PUMP E-8 12.172 OPEN 20A18 2
OR 20P42 135 8403 ACTIVE E42 (1804) 20A18 Turbioe Bd9 -U2 CLOSED 30024 300306 3
3 20Ai808 EPS-20 E424 6KR TO XFMR 20X33 E-8 72-172 CLOSED 20A18 2
BR 135 8404 ACTIVE E42 (1806) 20A18 Tulrine Bldg - U2 OPERABLE 30D24 300306 3
3 20A1807 EPS-2D E42 EKR FROM E4 DIG O0G12 E-8 T2-172 OPEN 0DG12 2
BR 135 8405 ACTIVE E42 (1807) 20A18 Tuftbine g u2 CLOSED 30024 300308 3
3 20A1808 EPS-20 E242 BKRFROM XFMR AAX04 E-8 T2.172 CLOSED 20A48 2
BR 135 8408 ACTIVE E42 (1808) 20A18 Turbine Bldg - U2 CLOSEDIOPEN 30D308 3
4 20X133 EPS-2A PANEL 20Y33 TRANSFORMER E-28, SHT. 1 12.171 ENERGIZED 20859 2
S 135 8000 ACTIVE 20(133 Turbine Bldg - U2 ENERGIZED 3
4 20X135 EPS-2C PANEL 20Y35 TRANSFORMER E-28, SN4T I R2-29 ENERGIZED 20838 2
S 135 8001 ACTIVE 20(135 Reactor Bdg - U2 ENERGIZED 3
4 20X150 EPS-2A PANEL 20YS0 TRANSFORMER E-28. SHT. 1 T2-171 ENERGIZED 20638 S
ACTIVE 135 Turine 81d9 - U2 ENERGIZED 20X150 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
,nrrp.qnnndP.nr.c Nn
- RR-1 9-173 B-1 0
DOCUMENT NO. 0067-00084-0001 REVISION 2 TRAIN SOUG Cl unit Eval*r*d?
PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EaUIPMENT LIST Norm satea Motvepme Desire State Cads P.w DATE: 3/28M96 PAGE 10 Equip ID PIMS ID system Notes Equip Desrion ROB Mothe Camp Drawing No.
Loc Code Room Eiev SuppoPt System Supp Sys dwg Line No Function Building 3
4 20X30 EPS-2A LOAD CENTER XFMR E124 E-1615 R2-41 ENERGIZED 2CA1505 2
S 165 8000 ACTIVE 20X030 Reactr Bldg - U1 ENERGIZED i
ASBSeis Rep 3
4 20X31 EPS-2B LOAD CENTER XFMR E224 E-1615 R2.116 ENERGIZED 20A1605 2
S 165 a000 ACTIVE 20X03i Reactor BU2 - U2 ENERGIZED A
P.BB Sea Rep 3
4 20=32 EPS-2C LOAD CENTER XFMR E324 E-1617 R2-41 ENERGIZED 20A1705 2
S 165 8000 ACTIVE E-1617(20X32)
Reactor Bldg - U2 ENERGIZED ABS Seas Rep) 3 4
20M33 F-PS-20 LOAD CENTER XFMR E424 E-1617 R2-116 ENERGIZED 20A1B05 2
S 165 8000 ACTIVE E-1617(20X33)
Reactor BI
- U2 ENERGIZED ABS Seis Rep) 1 5
20K2 HPCI HPCI GLAND SEAL COSR VACUUM PUMP M-366, SHlT I R2-13 OFF 20011 2
OR 068 3211 ACTIVE 20KD02 20E33 Reactr BIdg -U2 ON 5
20P26 HPCI HPCI AUXILIARY LUBE OIL PUMP M-366, SHT 1 R2-13 OFF 20011 2
BR 88 ACTIVE 20P026 20E33 Reactr Oft. U2 ON 1
5 2OP28 HPCI HPCI GLAND SEAL CONDENSER COND M-366. SHlT I R2-13 OFF 20D1I 2
OR PUMP 088 3214 ACTIVE 20P028 20E33 Reactor Bldg - U2 ON I
5 20P33 h"PCi IPCi BOOSTER PUMP M-36. SWT I R2-43 OFF N/A 2
B 088 3226 ACTIVE 20P033 20P38 React" Bldg -U2 OPERABLE NWA 1
5 20P38 HPCI NPCI PUMP M-366. SHlT 1 R2-13 OFF NIA 2
S 088 3227 ACTIVE 20P038 Reactr Bldg -U2 OPERABLE NIA Veno E.4707 1
5 20S37 HPCI U2" HPCI TURBINE M-366, SHT 1 R2-13 OPERABLE NIA 2
S 088 3205 ACTIVE 20S037 Reactor Bld - U2 OPERABLE NIA 2
5 2AP35 RHR-A RHR PUMP A M-361. SHT 1 R2-5 OFF 20A15 20A1506 2
S 091 4103 ACTIVE 2AP035 Reactor Btdg - U2 OFFION M-1-H-41-2, S-1146 1
5 28P35 RHR-B RHR PIMP B M-361, SHT 2 R24-OFF 20A16 20A1602 2
S 091 4203 ACTIVE 2OP035 Reactor BOd - U2 OFFION i
M--14441-2, S-1146 2
5 2CP35 RHR-C RII PUMP C M-361. SHT I R2-7 OFF 2DA17 20A1702 S
ACTIVE 091 ReaW 8de -ldgU2 OFFION 4303 2CP035 3
M-1-H-41-2. S-1146 B-11 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrr*..nnndf.nr.A Nn ' RR-12-173
DATE: 3X28M PAGE 11 DOCUMENT NO. 0067-0008440001 REVISION 2 TRAIN SOUGCI C
"ID Uni Eval reqd?
PINS ID Lin No Fun*tion PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST omwing N system Notes Equip Descion ROB Mother Camp Loc Code Room Etev 64M Norm $1a81 Desired SWat Motie pWer Contr power Support System
&tpp Sys dwg 1
5 2DP35 RHR-O RHR PUMP0 M-361. SHT2 R2-8 OFF 20A18 20A1802 2
S 091 4403 ACTIVE 20P03S 3
Resotor
-ldg U2 OFF/ON M-1.H-41.2, S.1 148 2
6 2AP42 HPSW HIGH PRESSURE SERVICE WATER M4315, SHT 1 PM4 OFF 20A1507 2
S PUMPA 111 5517 "ACTIE 2AP042 Pump House ON M-11-29. E8-108-1 1
6 2BP42 HPSW HIGH PRESSURE SERVICE WATER M-315, SHT 1 Pi"44 OFF 20A1I07 2
S PUMPa 111 5519 ACTIVE 28P042 Pump House ON M-1 1-29. E8-106-1 lOP 6
2CP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT I PiH-6 OFF 20A1707 2
S PUMP C 111 5521 ACTIVE 2CP042 3
Puip House ON M-11-29. ES-10-1 20P 6
20P42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 1 P/H-6 OFF 20A1804 2
S PUMP 0 Ill 5523 ACTIVE 2P0/42 3
Pump House ON M-11-29. ES-108-1 3
7 A02-01-480A MSIN A MAIN STEAM LINE INBOARD M-351. SHT 1 0/W2-18 OPEN NZA SV2-164080A-1 2
S ISOLATION VALVE 134 SV2-16-080A-2 2200 ACTIVE AO-2-01A-080A DryweI -U2 CLOSED NIA M-1.R-12J1,2 3
7 A02-014-080 MSV 8 MAIN STEAM LINE INBOARD I-351.
SHT I D1Y2-18 OPEN NWA SV2-16-0808-1 2
S ISOLATION VALVE 134 SV2-16-0A8-2 2202 ACTIVE AO-2-OIA-08B Drywe - U2 CLOSED NIA M-I -R-1 2/I.2 3
7 A02-01..OC)
MSrI C MAN SVT UNE INPOAD M-351. SHT 2 Dm2-19 OPEN WA SV2-i6.080C.1 2
S ISOLATION VALVE 134 SV2-16-080C-2 2204 ACTIVE AO-2-01A-080C Drwe -U2 CLOSED NWA M-I-R-12/1.2 3
7 A02-01.OI-D MSIV D MAIN STEAM LINE INBOARD M.351. SHT 2 DN2-20 OPEN NWA SV2-16-080D-1 2
S ISOLATION VALVE 134 SV2-16-=00D-2 2206 ACTIVE AO-2-OIA-OSOD DweG - U2 CLOSED NWA M-I-R-1211.2 3
7 A02-01.086A MSIV A MAIN STEAM LINE OUTBOARD M-351. SHT I R2-30 OPEN N/A SV2-I6.-08A-1 2
S ISOLATION VALVE 135 SV2-16-08SA-2 2201 ACTIVE AO-2-0IA-086A Reactor ldg -U2 CLOSED NWA M-1-R-1211,2 3
7 A02-01-0868 MStV 8 MAIN STEAM LINE OUTBOARD M-351, SHT 1 R2-30 OPEN NWA SV2-16-0058-1 2
S ISOLATION VALVE 135 SV2-16-8O6B-2 2203 ACTIVE AO-2-OIA-086B ReacW SI
- U2 CLOSED NIA M-I-R-12/1.2 3
7 A02-01-OBSC MSIV C MAIN STEAM LINE OUTBOARD M-351, SPIT 2 R2-30 OPEN NIA S
S ISOLATION VALVE 135 SV2-16486C-2 2205 ACTIVE AO-2-01A-086C Reactor ldg - U2 CLOSED N/A M-I-R-12/1,2 3
.2 2207 7
S ACTIVE A02-01-0860 MSIV U MAIN STE AM LINIE iU I OUTA ISOLATION VALVE M-351. SHT 2 R2-30 OPEN 135 Reao* Bldg. U2 CLOSED WA NIA AO-2-OIA-O86D SV2-l6.086D-2 M-1-R-12/1,2 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (onrrP.mnnndt1nrP No
- R-1 2-173 B-12
DOCUMENT NO. c0874=084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Motivepower Gontrpower DATE: 312896 PAGE 12 TRAIN Unit SOUG CI Ev*l t*d?
Equ ID PIMS ID System Notes Eq4i De~Io-"
ROB MO~he Cxnip DrmwbgNO.
Loe Code Roomn Eev Norm state Desied SIaM SupLtW System Supp Sys diwg Line No Function Buildg 3
7 AO2.03-32A CRD SCRAM DISCHARGE VOLUME INBOARD M.356. SHT I R2-26 OPEN WfA SV2.3-32A 2
S ISOLATION VENT W 135 1102 ACTIVE AO-2-03-032A Reactor Bldg-U2 CLOSED N/A M-143-1"-
3 7
A02-03-320 CRD SCRAM DISCHARGE VOLUME INBOARD M.-3M. SHT 1 R2-24 OPEN MIA SV2-3-32B 2
S ISOLATION VENT W 135 1104 ACTIVE AO-2-03-O32B Reactor Bldgg. U2 CLOSED NIA M-1 -D-1 1-3 3
7 A0203-33 CRD SCRAM DISCHARGE VOLUME INBOARD M-356, SHT I R2-22 OPEN WA SV2-3-33 2
S ISOLATION DRAIN W 135 1110 ACTIVE AO-2-03-W33 Reactor BWg - U2 CLOSED NIA vendor 6-9M207-52 3
7 A0203-35A CRO SCRAM DISCHARGE VOLUME M-356, SHT 1 R2-26 OPEN NWA SV2-3-35A 2
S OUTBOARD ISOLATION VENT W 135 1106 ACTIVE AO-24)3-035A ReaCtor Bldg U2 CLOSED MIA M-1-0-162 3
7 A02-03-358 CRD SCRAM DISCHARGE VOLUME M.35C SHIT I R2-24 OPEN N/A SV2-%3 2
S OUTBOARD ISOLATION VENT W 135 1108 ACTIVE AO-2,O34)358 Reactor Bldg. U2 CLOSED NIA M-1-D-162 3
7 A023-.36 CRD SCRAM DISCHARGE VOLUME M-356, SHT 1 R2-22 OPEN WA SV2-3-36 2
S OUTBOARD ISOLATION DRAIN W 135 1112 ACTIVE AO-24336 Reactor Bldg. U2 CLOSED NWA 1
7 H02-23C-4512 HPCI HPCI TURBINE GOVERNOR. CONTROL M-366. SHT 1 R2-13 OPEN NWA 2
B VALVE Gas 3204 ACTIVE HO-2-23C-4512 20S37 Reactor Bldg - U2 OPERABLE NWA 1
7 H02-23C-4513 IIPCI HPCI TURBINE STOP VALVE M-36W. SHT 1 R2-13 OPEN WA SV2-23A-4543 2
B 088 3203 ACTIVE HO-2-23C-4513 20S37 Reactor Bldg - U2 OPEN NIA M-1-J-20 1
7 PCV2-23B-50 HPCI HPCI COOLING WATER TO LO. COOLER M366. SH4T 1 R2-13 OPERABLE WA 2
S AND GLAND SEAL CDSR 088 3213 PASSIVE PCV-2-23-050 Reactor Bldg U2 OPERABLE NWA 3
7 RV2.02-071A SRV A SAFETY RELIEF VALVE M-351. SlIT I D1W2-27 CLOSED 20021 2
SR 154-9 2100 ACTIVE RV.2.02-071A 4
Drywo - U2 OPENICLOSED B SAETY ELIE VALE M-I-R-I-1.
M-1-R.5-4, 3
7 RV2-02-7II8 SRV 8 SAFETY RELIEF VALVE M-351. SHlT 1 DAW2-27 CLOSED 20021 2
SR 154-r9 2105 ACTIVE RV-2-02-071B 4
Drywall. U2 OPENICLOSED M-1-R-1-12, M-"-R-5-4, 3
7 RV2-02-071C SRV C SAFETY RELIEF VALVE M-351. sGT I DON2-27 CLOSED 20D21 2
SR 154-9" 2110 ACTIVE RV-2-02*071C 4
Drywall - U2 OPENICLOSED M-I-R-1-12, M-1-R-5-4, 3
7 RV2-02.071D SRV D SAFETY RELIEF VALVE M-351, SGIT I DOA2-27 CLOSED 20021 INSTR.2 SR ACTIVE 2115 RV-22M-0710 4
154'-V Drywafll-U2 OPENICLOSED M-I-R-l-12. M-I-R-5.4, B-13 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrPmnnndP.nrA. Nn RS-19-17.1
DATE: 3128136 PAGE 13 DOCUMENT NO. 0067-00084O001 REVISION 2 TRAIN SOUG CI uni Eval (old?
Line No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST Equip ID PIMS I0 Equip Desapliotn ROB NMoer Comp Dmrwng No.
Loc Code Room Eler Buieldb Norm stale Desired State MOWS power C., P...
Supot -ytr SLupp SYs dwo 3
7 RV2-02.071E SRV E SAFETY RELIEF VALVE M-351, SHIT 1 DAV2-27 CLOSED 20021 INSTR. N2 2
SR 154.9 2117 ACTIVE RV.2-02.071E 4
D"wg - U2 OPEN/CLOSED M-1-R-.-12. M-1-A-S-.4 3
7 RV2-02-071F SRV F SAFETY RELIEF VALVE M"351, SilT 1 OM2-27 CLOSED 20021 INSTR. N2 2
SR 154C-9" 2119 ACTIVE RV-2.02-071F 4
OIrrell - U2 OPEN/CLOSED M-I-R-l-12. M-1-R-5-4.
3 7
RV2-02-071G SRV G SAFETY RELIEF VALVE M-351, SHT2 D02-27 CLOSED 20021 2
SR 1S4-2121 ACTIVE RV-2-02-071G 4
Drawel - U2 OPEN/CLOSED M.1-R-12. M-1-R-6-4.
3 7
RV2.02.071H SRV H SAFETY RELIEF VALVE M-51. SHlT 2 DNV2-27 CLOSED 20121 INSTR. N2 2
SR 154-I9 2126 ACTIVE RV-2-02-071H 4
Drywal -U2 OPEN/CLOSED M-1-R-1-12. M-I-R.-54.
3 7
RV2-02-071J SRV J SAFETY RELIEF VALVE M-351. SHlT 2 DMW2-27 CLOSED 20D21 INSTR. N2 2
SR 154"-9 2128 ACTIVE RV-2-02-071J 4
Drywl -U2 OPEN/CLOSED M-I-R-1-12. M-1-R-5-4, 3
7 RV2-02-071K SRV K SAFETY RELIEF VALVE M-351, SHT 2 01W2-27 CLOSED 20021 2
SR 15A-9 2130 ACTIVE RV-2-02-071K 4
O Bywell
-U2 OPEN/CLOSED M-I-R-1-12, M-1-R-5-4, 3
7 RV2-02-071L SRV L SAFETY RELIEF VALVE M-351, SHlT 2 DW2-27 CLOSED 20021 INSTR. N2 2
SR 154r-9" 2135 ACTIVE RV-2-02-071L 4
Drywall. U2 OPEN/CLOSED M-1-R-1-12, M-1-R-5-4.
1 7
RV2-23-034 HPCI HPCI PUMP SUCTION HEADER RELIEF M-366, SHT I R2-13 OPERABLE N/A 2
S VALVE 08 3225 PASSIVE RV-2-23B-034 Reactor ldg - U2 OPERABLE N/A DS-M-20413 2
8 CV2-10-2677A RHR-A RHR PUMP 2AP035 DISCHARGE M-381. SHT 1 R2.5 OPEN NIR 2
N/A CONTROL VALVE 091 4107 PASSIVE CV-2-10-2677A 8
Reacor Bldg -U2 OPEN NIR I
8 CV2-10-2677D RHR-D RHR PUMP 2DP035 DISCHARGE M-361. SHT 2 R2-8 OPEN NIR 2
N/A CONTROL VALVE 091 4406 PASSIVE CV-2-10-2677D 3,8 Reac tor
-dg U2 OPEN NMR 3
8 M02-02-74 MSIV MAIN STEAM LINES INBOARD DRAIN M-4351. SHT 1 DW2-.1B CLOSED NMR 2
R ISOL VALVE 134 2208 PASSIVE MO-2-01A-074 Orywe0 - U2 CLOSED N/R 1
8 M02-06.029A HPCI FEEDWATER STOP VALVE M-351. SIT 1 DmW2-33 OPEN NMR 2
R 154 3235 PASSIVE MO-2-06-029A Dtyg -L12 OPEN N/R I
a MO02-06-38A HPCI VAW LVNG PT E
ECIRC ISOLATION VALVE W-351. SHlT I R
PASSIVE MO-2-06-O38A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrP.nnndo.nrP. No
- RS-19-173 R2-30 CLOSED 135 Reactor Bldg - U2 CLOSED N/R N/R B-14
DOCUMENT NO. 0067-40084-0001 REVISION 2 TRAIN SOUG CI Equip D Uit Eval red?
PIUS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LtST Norm state Motive power Desired State Canr&
power DATE: 3/21191 PAGE 14 System Note$
Equip Descripllan ROB Moltor Camp Drawing No Laoc Coda Room Elev Support Syte StaPP SYS dwo LOD No Function Euhdkn9 2
8 M02.10-013A RHR-A RHR PUMP 2AP035 TORUS SUCTION M-361. SHT 1 R2-5 OPEN N/R 2
R 091 4101 PASSIVE MO-2-10-013A Reatr Bldg -U2 OPEN N/R I
a M02-10-0138 RHR-8 RHR PUMP 2OP035 TORUS SUCTION M-361. SHT 2 R2-6 OPEN N/R 2
R 091 4201 PASSIVE MO-2-10-013B Reacto Bldg - U2 OPEN NHR 2
8 M02-10-013C RHR-C RHR PUMP 2CP035 TORUS SUCTION M-361. SHT 1 R2-7 OPEN NIR 2
R 091 4301 PASSIVE MO-2-10-013C 3
Reactor B.U2 OPEN N/R I
B M02-10-013D RHR-D RHR PUMP 2OP035 TORUS SUCTION M-361, SHT 2 R2-8 OPEN
/fR 2
R 091 4401 PASSIVE MO-2-10-0130 3
Reactor Bdg - U2 OPEN N/fR 2
a M02-10-OISA RHR-A RHR PUMP 2AP035 SHUTDOWN M-361. SHT 1 R2-5 CLOSED N/R 2
R COOLING SUCTION 091 4102 PASSIVE MO-2-10-015A Reactor W1. U2 CLOSED N/R 1
8 M02-10-0158 RHR-8 RHR PUMP 28P035 SHUTDOWN M-361. SHT 2 R2.18 CLOSED N/R 2
R COOLING SUCTION 116 4202 PASSIVE MO-2-10-O158 Reactor Bdg - U2 CLOSED N/R 2
8 M02-10-015C RHR-C RHR PUMP 2CP035 SHUTDOWN M-361, SHT I R2-17 CLOSED NOR 2
R COOLING SUCTION 116 4302 PASSIVE MO-2-10-015C 3
Reactor Bldg. U2 CLOSED N/R 1
8 M02-104150 RHR-D RNR PUMP 20P035 SHUTDOWN M-361, SlIT 2 R2-8 CLOSED N/fR 2
R COOUNG SUCTION 091 4402 PASSIVE MO-2.10-015D 3
Reactor dg. U2 CLOSED NfR 2
GA M02-10-016A RHR-A RHR PUMP 2AP035 MINIMUM FLOW M-361. SHT 1 R2-5 CLOSED 20936 2
SR VALVE 091 4104 ACTIVE MO-2-1O-016A Reacto 8ig. U2 OPEN/CLOSED M-1028-49 B
aA M02-10-0168 RHR-8 RHR PUIMP 20P035 MINIMUM FLOW M-381, SHT 2 R2-6 CLOSED 2037?
2 SR VALVE 091 4204 ACTIVE MO-2-10-0168 Reactor Bld -U2 OPEN/CLOSED f
1028-49 2
8A M02-10-016C RN/R-C RHR PUMP 2CP035 MINIMUM FLOW M-361, SHIT I R2.7 CLOSED 20838 2
SR VALVE 091 4304 ACTIVE MO-2-10-016C 3
Reactor BOlg - U2 OPEN/CLOSED M4-1028-49 I
SA M02-10-016D R oR-D RHR PUMP 2DP035 MINIMUM FLOW M-361. SHT 2 R2-8 CLOSED 20839 2
SR VALVE 091 1
4404 ACTIVE MO-2-10-0160 3
Reactor Bldg - U2 OPEN/CLOSED M
3 8
M02-10-018 RHR RHR SHUTDOWN COOLING SUCT M-361. SHT 1 DNW2-17 CLOSED N/R 2
2212 R
PASSIVE MO-2-10-018 INBOARD ISOLATION VALVE 134 oywel - U2 CLOSED N/R Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(,nrrP..nnnri-nr.Pn No
- R-1 2-173 B-1 5
DOCUMENT NO. 0067-0084-0001 REVISION 2 TRAN SOUG C Equip ID Unit Eval reqd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power DeaWo Stat CorWrPowe DATE: 32M PAGE 18 Notes Equip Descition ROB Mother Comp DrawkVg No.
Loc Code Room Elov SuppO System Supp Sys dwg Lime No Function Bjn I
2 SA M02-10-025A RHR-A RHR LOOP A INBOARD DISCHARGE M-361. SHT I R2-25 CLOSED 20938 2
SR VALVE M
4117 ACTIVE MO-2-10-025A 10 Reactor BMdg U2 CLOSEDIOPEN 1
I SA M02-10,0250 RHR-B RHR LOOP S INBOARD DISCHARGE M-361, SliT 2 R2.27 CLOSED 20839 2
SR VALVE 135 4216 ACTIVE MO-2-10-0258 10 Reactor Bd9 - U2 CLOSEOPEN M-144-31-5 2
8 M02.10-026A RHR-A RHR LOOP A OAN SPRAY OUTBOARD M-361. SHT 1 R2-25 CLOSED NIR 2
R ISOLATION VALVE 135 4112 PASSIVE MO-2-10-026A Reactor Biig. U2 CLOSED N/R 1
8 M02-10-0268 RHR-8 RHR LOOP B DAN SPRAY OUTBOARD M-361. SHIT 2 R2-27 CLOSED NIR 2
R ISOLATION VALVE 135 4211 PASSIVE M0-2-10.0268 Reactor BN. -U2 CLOSED NIR 2
BA M02-110434A RHR-A RHR LOOP A FULL FLOW TEST VALVE M-361. SHT I R2-110 CLOSED 20638 2
SR (SUPPRESSON POOL COOLING) 125 4114 ACTIVE MO-2-10-034A 9
Reacr SkI. U2 CLOSEDIOPEN M-1O2B-62 I
8A M02-10-0348 RHR-B RHR LOOP 8 FULL FLOW TEST VALVE M-361. SIT 2 R2-105 CLOSED 20939 2
SR 125 4213 ACTIVE M6-2-10-034B 9
Reac OBldg
-U2 OPEN M-102862 2
8A M02-10-039A RHR-A RHR LOOP A TORUS HEADER M-361. SHT 1 R2-1110 CLOSED 20838 2
SR 125 4113 ACTIVE MO-2-10-039A 9
Reactor M9dg. n2 CLOSEODOPEN M-"4--32 I
A M02.10-0398 RHR-S RHR LOOP 1 TORUS HEADER 1681. SHT 2 R2-104 CLOSED 20839 2
SR 125 4212 ACTIVE M0-2-10-0398 9
Reactor
- g. -U2 OPENWCLOSED M-I-1H-32 2
a M02-10-154A RHR-A RHR LOOP A OUTBOARD DISCHARGE M-361, SHT I R2-99 OPEN NIR 2
R VALVE 116 4115 PASSIVE MO-2-10-154A Reactor Blg. U2 OPEN N/R 1
8 M02-10-1548 RHR.8 RHR LOOP B OUTBOARD DISCHARGE M-381. SHT 2 R2-93 OPEN NMR 2
R VALVE 116 4214 PASSIVE MO-2-10-1548 Reactor Bldg - U2 OPEN N/R 1
6 M02-10-176 HPSW HPSW TO RHR EMERGENCY OUTER M.315,. SHT 1 R2-6 CLOSED NIR 2
R CROSS-TIE 091 5516 PASSIVE MO-2-10-176 Reactor tdg-U2 CLOSED NIR 2
8A M02-10-89A HPSW RHR HX 2AE024 HPSW OUTLET VALVE M-315. SHT I R2-16 CLOSED 20836 2
SR 116 5512 ACTIVE MO-2-104MA Reactor 9Mg -U2 OPENICLOSED M.-1028-60 I
GA M02-10-890 HPSW RHR HX 2BE024 HPSW OUTLET VALVE M-315. SHT I R2-18 CLOSED 20837 2
SR ACTIVE 116 React Bldg - U2 OPENICLOSED M0-2-10-0899 M-1028-60 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr.qnnnd1nrm-. Nn* R.-12-173 B-16
DATE: 3128106 PAGE 16 DOCUMENT NO. 0067-00084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Nom slat Motw epower Desied Slate Canm power TRAIN uni SOUG CI Eval re*d?
Equip ID PIMS ID Systsm Equip oescipion ROB Mothe camp Drawmng No.
Loc Code Room Elev Support System SuppSys d*0 Line No Flm Building 2
8A M02-10-89C HPSW RHR HX 2CE024 HPSW OUTLET VALVE M-315. SHIT I R2-17 CLOSED 20838 2
SR 116 5514 ACTIVE MO-2-I0-089C Reactor
- U2 CLOSEDIOPEN M-1021-60 I
BA M02.104)90 HPSW RHR HX 2DE24 HPSW OUTLET VALVE M-315, SHT I R2-19 CLOSED 20839 2
SR 116 5515 ACTIVE MO-2-10-0890 Reator Bl-U2 CLOSED/OPEN 1M-102B,.0 3
8A M02-12-015 ISIV RWCU INLET INBOARD ISOLATION M-354, SHT 1 DNW2-26 OPEN 20838 2
SR VALVE
'134 2209 ACTIVE MO.2-12-015 Dr*wea-l2 CLOSED U
M-1028-33 3
8A M02-12-018 MSf RWCU INLET OUTBOARD ISOLATION M-354, SHIT 1 R2-33 OPEN 20D11 2
SR VALVE 165 2210 ACTIVE MO-2-12-018 Reactor Bldg -U2 CLOSED M-1028-33 8A M02.23.014 HPCI HPI TURBINE STEAM SUPPLY VALVE M.-385, SHT I R2-13 CLOSED 20011 2
SR 088 3202 ACTIVE MO-2-23-014 Reactor Bdg -U2 OPEN M-1028-42 1
8 M02.23-015 HPCI HPCI TURBINE STEAM LINE INBOARD M-385, SHlT 1 DOW2-17 OPEN N/R 2
R ISOLATION VALVE 134 3200 PASSIVE MO-2-23-015 Drywall -U2 OPEN N/R 1
8 M02-23-016 HPCI HPCI TURBINE STEAM LINE OUTBOARD M-365. SlIT 1 R2-27 OPEN NIR 2
R ISOLATION VALVE 135 3201 PASSIVE MO-2-23-016 Reactor Bldg - U2 OPEN NIR 1
BA M02-23-017 HPCI HPCi CONDENSATE STORAGE TANK M-365. SHT 1 R2-13 OPEN 200Dl 2
SR SUCTION 088 3224 ACTIVE MO-2-23-017 Reactor BMg.
2 OPEN/CLOSED U
I BA M02-23-019 HPCI HPCI DISCHARGE TO FEEDWATER LINE M-365, SHT I R2-30 CLOSED 20D11 2
SR A
135 3231 ACTIVE MO-2-23-019 Reactor Bldg -U2 OPEN M-1028-29-7 1
8 M02-23.020 HPCI HPCI PUMP DISCHARGE VALVE M-365. SHT 1 R2-13 OPEN MIR 2
R 08 3229 PASSIVE MO-2-23-020 Reactor Bldg - U2 OPEN NIR 1
8 M02-23-021 HPCI HPCI FULL FLOW TEST VALVE M-365, SHT 1 R2-4 CLOSED NIR 2
R 092 3230 PASSIVE MO-2-23-021 Reactor BIdg - U2 CLOSED NIR 1
SA M02-23-025 HPCI HPCI MINIMUM FLOW VALVE M-365, SHlT I R2-13 CLOSED 20011 2
SR 088 3228 ACTIVE MO-2-23-025 Reactor Bldg - U2 OPEN/CLOSED M-1--44-"
B BA M02-23-057 HPCI HPCI TORUS SUCTION OUTBOARD M1-35, SHT I R2-13 CLOSED 20011 I
rISOLATION VALVE ACTIVE 3222 MO-2-23-057 Ram Reactor Bldg -U2 OPEN M-102B-33F-1 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrr..nnnAnri.P Nn
- RR-12-173 B-1 7
DOCUMENT NO. 0067400-84-DO01 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST SLzpoi System S44pp Sys dwg DATE: 3121198 PAGE 17 REVISION 2 TRAIN SOUGCCI Equi 0 Eval rs~d PI111If)
Function System Nots Equip Descrwon ROB Mow Comp Dn-V No.
Loc Code Room Elev Norm state Mod, power Desked State Camr pow" 1
SA MA02-23-058 HPCI HPCI TORUS SUCTION INBOARD 1-35. SHT 1 R2-13 CLOSED 2001 I 2
SR ISOLATION VALVE 088 1
3221 ACTIVE MO-2-23-058 Reactor Bdg - U2 OPEN M-102B-33F-1 1
8 M02-23C-4244A HPCI HPCI TURBINE EXHAUST LINE VACUUM M-365. SlIT 1 R2-94 OPEN NIR 2
R BREAKER ISOL VALVE 118 3219 PASSIVE MO-2-238.4245 14 Reactor Btdg-U2 OPEN NR 3
BA M02-30.2233A ESW & HPSW UNIT 2 A SLUICE GATE M.-330 S/-4 OPEN 00862 2
SR 116 5627 ACTIVE MO-2-30-2233A Screen House CLOSED C-316 3
SA M02-30-22338 ESW & HPSW UNIT 2 8 SLUICE GATE M-330 S/H-4 OPEN 00861 2
SR 116 5628 ACTIVE MO-2.30-22338 Screen "ouse CLOSED C-316 3 OP 8
M02-32.2344 HPSW HPSW LOOPS 2A TO 28 CROSSTIE W.315, SHT 1 P1H-6 CLOSED NIR 2
SR 111 5538 ACTIVE M0-2-32-2344 5
Pump House CLOSED N/R 3
SA M02-32-2486 HPSW HPSW RETURN VALVE TO DISCHARGE M-330 ODG-2 OPEN 00854 2
SR POND 121 5610 ACTIVE MO-2-32-2486 Diesel Generator CLOSED M-.1028-1255S15 3
8A M02-32-2803 HPSW HPSW RETURN VALVE TO EMERGENCY M-330 DIG-2 CLOSED 00855 2
SR COOUNG TOWER 121 5612 ACTIVE MO-2-32-2803 l Generat OPEN 3
8 M02-33-2972 ESW & HPSW U/2 SAFEGUARDS AND RSCW HX iSOL M-315, SHT 5 T2-45 OPEN NIR 2
R FROM ESW PUMP 0BP057 116 5564 PASSIVE M1-2-33-2972 Turbine Bldg - U2 OPEN NIR 3
BA M02-48-2804A ESW & HPSW U12 HPSW DISCH INLET OUTER M-330 ECT-1 CLOSED 00898 2
SR 114 5633 ACTIVE MO-2-48-2804A Emergency Cooung OPEN Towers 3
SA M02.48-28048 ESW & HPSW U/2 HPSW BAY INLET INNER M-330 ECT-1 CLOSED 00899 2
SR 114 5634 ACTIVE MO-2-.48-2904B Emergency Coolftg OPEN Towers 3
88 SV-8130A BACKUP INST N2 BACKUP NITROGEN TO ADS A SUPPLY M-333, SHIT I R2-23 OEENERGIZED 20Y35 2
SR 135 6100 ACTIVE SV-2-16A-8130A Reactor Bldg -U2 ENERGIZED 3
88 SV-8130B BACKUP INST N2 BACKUP NITROGEN TO ADS B SUPPLY M-333. SHT I R2-23 DEENERGIZED 00Y03 2
SR 135 6101 ACTIVE SV-2-16A-81308 Reactor Bldg -U2 ENERGIZED a
BR.
ACTIVE SV2-16-080A-1 MSIV SV-2.164OBOA-1 TO AO-2.O1A.00A A02-014MMO DJW2-IS 134 Drywall-L2 ENERGIZED NIR DEENERGIZED N/R 2216 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrp. nnondp nrp. Non RS-1 9-173 B-18
DOCUMENT NO. 006740084-0001 REVISION 2 TRAIN SOUG C0 Equp IW Unit Eval mrd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Ma"m Powe Conrdpoer DATE: WfSM PAGE 18 system NoWa Equip Desciption ROB MoIwhComp Drawing N&
Loc Code Room Ebv Norm state Desired State Support System Saupp SYS dwg Line No Function Buildirg 3
8 SV2.16-080A.2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHIT 1 DNW2-i8 ENERGIZED NIR 2
OR TO AO-2-01A4*OA 134 2217 ACTIVE SV-2-i6-080A-2 A02.O1-080A Mywef.
DU2 EENERGIZED NIR 3
8 SV2.16-0808-1 MSI BACKUP DC SOLENOID FOR N2 SUPPLY M-351, SHT I D/W2-18 ENERGIZED NmR 2
BR TO AO-2-O1A-OS0 134 2228 ACTIVE SV.2-164i808-1 A02-O1-080B DOyweUl-U2 DEENERGIZED NJR 3
8 SV2-16-080B-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351, SlT 1 DN92-18 ENERGIZED WR 2
OR TO AO-2-OA-080B 134 2229 ACTIVE SV-2-164.O0B-2 A02-01-080M D8yw - U2 DEENERGIZED NWR 3
8 SV2-16-O80C-1 MSv BACKUP DC SOLENOID FOR N2 SUPPLY M-351. SHIT 2
DAm2-19 ENERGIZED N/R 2
BR TO AO-2-01A-080C 134 2222 ACTIVE SV-2-16-0-OC-1 A02-01-080C Drywell. -2 DEENERGIZED MIR 3
8 SV2-16-080C-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 2 DIW2-19 ENERGIZED NWR 2
R TO AO-2O0IA-0SOC 134 2223 ACTIVE SV-2.16-080C-2 A02-01-00C Drywal - U2 DEENERGIZED WA 3
8 SV2-1608OD-1 MSN BACKUP DC SOLENOID FOR N2 SUPPLY
"-35I. SHT 2 OND2-20 ENERGIZED IRA 2
BR TO AO-2-01A-O800 134 2234 ACTIVE SV-2-16-O00D-1 AO2-01-0800 Orefl - U2 DEENERGIZED NWR 3
8 SV2-16-0800-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351, SHT 2 DAN2-20 ENERGIZED WRA 2
OR TO AO-2-01A-0800 134 2235 ACTIVE SV-2-16-OSOD-2 A02-01-0800
.w
-U2 DEENERGIZED NWR 8Ia SV2-23A-4543 HPCI HPCi TURBINE STOP VALVE REMOTE M-366. SHlT 1 R2-13 CLOSED 20022 2
BR TRIP VALVE 088 ACTIVE SV-2-23A-4543 20S37 Reacdor Bldg -U2 OPEN 1
88 SV2-23C-54 HPCI HPCI TURBINE EXHAUST DRAIN POT M-3M8. SHlT I R2-13 CLOSED 2O022 2
SR DRAIN SOLENOID VALVE 088 3209 ACTIVE SV-2-23-054 Reactor bg -U2 OPEN M-205-0-21 3
8 SV2-3-2A CRD INSTR AIR SOLENOID VALVE FOR M-35. SHT 1 R2-22 ENERGIZED NIR 2
BR AO-2-03-032A 135 1103 ACTIVE SV-2-03-032A AO2-03-32A Reactor g -
D2 OEENERGIZED NWR 3
8 SV2-3-32B CRD INSTR AIR SOLENOID VALVE FOR M356, SlIT 1 R2-22 ENERGIZED NWR 2
OR AO-2.03-032B 135 1106 ACTIVE SV-2-03-032B AO2-03-32B Reactcr Bdg. U2 DEEERGIZED WIR 3
a SV2-3-33 CRD INSTR AIR SOLENOID VALVE FOR M-4%S, SILT 1 R2-22 ENERGIZED NWR 2
BR AO-20333 135 11t11 ACTIVE SV-2-034033 A02-03-33 Reactor Bldg - U2 DEENERGIZED NIR 3
8 SV2-3-35A CRD INSTR AIR SOLENOID VALVE FOR M-356. SHT I R2-22 ENERGIZED NWR BR ACTIVE SV-2-03-035A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(,nrr..nnnd.nt-.. Nn - RR-19-17.1 AO-2-03-035A A02-03-35A 135 Reactr Bld. U2 DEENERGIZED NWR B-19
DATE: 3r29 PAGE 19 DOCUMENT NO. 0067-00084-DOD0 REVISION 2 TRAIN SOUG Cl Equ* ID Urn?
Eval reqd?
PIMS ID Line No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST System Notes Equil Descr~oio ROD Mothe Cam Dmwbng No, Lo¢ Code Room 0ev Norm state Motive power Desired State Conlr power SuIPPofl System Supp Sys dwg 3
a SV2-3-35B CRO INSTR AIR SOLENOID VALVE FOR M-3w, SHT I R2-22 ENERGIZED N/R 2
BR AO-2433-0358 1351 1109 ACTIVE SV-2-03-0358 A02-03-35M Reactor Sldg. U2 DEENERGIZED NIR 3
8 SV2-3-36 CRD INSTR AIR SOLENOID VALVE FOR M-358, SkIT 1 R2-22 ENERGIZED NIR 2
BR AO-20.036 135 1113 ACTIVE SV.2.03-036 A02-0336 Reactor Bldg - U2 DEENERGIZED NJR 3
8 28.3-081lA MSrV BACKUP OC SOLENOID FOR I/A SUPPLY M-351. SHIT 1 R2-30 ENERGIZED NIR 2
BR TO AO-2.01A-086A 135 2219 ACTIVE SV-2-368.086A-1 A02-0165A Reacto rBdg. U2 DEENERGIZED M/R 3
8 SV2-368-08A-2 MSIV AC SOLENOID FOR VA SUPPLY TO M-351. SHT I R2-30 ENERGIZED NWR 2
BR AO-2-01A-O8SA 135 2220 ACTIVE SV-2-368-086A-2 A02-0148A Reactor Bldg - U2 DEENERGIZED NWR 3
8 SV2-36-086B-1 MSIV BACKUP DC SOLENOID FOR IVA SUPLY M-351. SHT I R2-30 ENERGIZED NWR 2
BR TO AO-2-01A-0M8 135 2231 ACTIVE SV-2-368-0858-1 A02-01-086B Reactor BWO
- U2 OEENERGLZED NWR 3
a SV2-364868-2 MSIV AC SOLENOID FOR VA SUPPLY TO M-351. SHT 1 R2-30 ENERGIZED NWR 2
BR AO-2-OIA-0868 135 2232 ACTIVE SV.2-368-O868-2 A02-01-0888 Reactor Bldg -
D2 EENERGIZED WIR 3
8 SV2-36-08SC-1 MSIV BACKUP DC SOLENOID FOR IVA SUPPLY I-351.
SlIT 2 R2-30 ENERGIZED NIR 2
BR TO AO-2-O1A-086C 135 2225 ACTIVE SV-2-368-088C-1 A02-01-086C Reactor Bldg - U2 DEENERGIZED N/R 3
8 SV2-364.088-2 MSIV AC SOLENOID FOR VIA SUPPLY TO M-351. SHT 2 R2-30 ENERGIZED NWR 2
BR AO-2-01 8C 135 2226 ACTIVE SV-2-36S-088C-2 A02-01-088C Reacto Slg
- U2 DEENERGIZED NWR 3
8 SV2-36-086D-1 MSIV BACKUP DC SOLENOID FOR IfA SUPPLY M4-351. SHT 2 R2-30 ENERGIZED NWR 2
SR TO AO-2-O1A-08*D 135 2237 ACTIVE SV-2-361-086D-1 A02-01-0860 Reactor Bldg -U2 DEENERGIZED N/R 3
8 SV2-36-088D-2 MSIV AC SOLENOID FOR IVA SUPPLY TO M4-351.
SHlT 2 R2-30 ENERGIZED NSR 2
SR AO-2-01A-0861 135 2238 ACTIVE SV-2-365-0860-2 A02-01.088D Reactor Bldg. U2 OEENERGIZED MIR 1
9 2AV060 HPSNVHVAC HPSW PUMP ROOM SUPPLY FAN A M-386, SHIT I P/H-6 AUTO 2
SR 112 ACTIVE Pump House ON 1
9 2AV083 HPSW HVAC HPSW PUMP ROOM EXHAUST FAN A M--396. SHlT 1 P1144 AUTO 2
SR 112 ACTIVE Pump House ON 9
SR ACTIVE 2BV060 KPSWHVAC HPSW PUMP ROOM SUPPLY FAN 8 M-396. SKT I P/H-6 112 Pun*o House AUTO ON Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrmrqnnndP.nr.*. Nn R.R-2-1-71 B-20
DOCUMENT NO. 0067.60084-D001 REVISION 2 TRAIN SOUG Cl Equp ID Unit Eval reqd?
PUS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3?28M96 PAGE 20 Norm state Motive power Suppor System Desied State Contr pow Supp Sys tWg Equp Descmiption ROD Mothe COMp Drawing No.
Loc Code Room Elev Lim No Function Buiddg 1
9 2BV083 HPSW WVAC HPSW PUMP ROOM EXHAUST FAN B M-396, SHT I PI4`6 AUTO 2
SR 112 ACTIVE Pump House ON 3
10 2AE55 ESW RCIC PUMP ROOM COOLING COIL A M-315, SHT 5 R2-14 WA NIR 2
S 91-6 5561 PASSIVE 2AE055 POO Reactor SIWg - U2 NWA NIR M-77 Series 3
t0 2AESS ESW HPCI PUMP ROOM COOLING COIL A M-315. SHT 2 R2-13 NIA NIR 2
S 91-5551 PASSIVE 2AE056 POO Reactor Bsg -U2 NIA NIR M-77 Seris 3
10 2AE57 ESW A CORE SPRAY ROOM COOLING COIL A M-315, SHlT S R2-9 WA NIR 2
S 91-6 555 PASSIVE 2AE057 POO Reacr Bldg - U2 NA NIR M-77 Series 3
10 2AE56 ESW A RHR ROOM COOLING COIL A M-315, SHT 2 R2-16 WA NIR 2
S 116 5543 PASSIVE 2AE058 PBO Reactor Bidg - U2 WA WAR M-77 Series 3
10 2BE55 ESW RCIC PUMP ROOM COOLING COIL B M-315,SHT5 R2-14 NIA N/R 2
S 91-6 5562 PASSIVE 28E055 PBO Reactor Bld9 - U2 NWA NIR M-77 Series 3
10 28E56 ESW HPCI PUMP ROOM COOLING COIL B M-315, SHT2 R2-13 N/A NWR 2
S 91-6 5552 PASSIVE 2BE056 PO Peactor Bldg -U2 WA NR M-77 Series 3
10 28E57 ESW A CORE SPRAY ROOM COOLING COIL 0 M-315, SHT 5 R2-9 NWA NWR 2
5 9146 5554 PASSIVE 2BE057 P8O Reactor Sidig. U2 WA NIR M-77 Series 3
10 2ES ESW A RHR ROOM COOLING COIL 8 M-315. SHT 2 R2-5 WA NWR 2
S 91-6 5544 PASSIVE 28E058 Pao Reactor BIdg. U2 WA NWR M4-77 Series 3
10 2CE57 ESW C CORE SPRAY ROOM COOLING COIL C M-315. SHT S R2-11 MIA NR 2
S 9146 555*
PASSIVE 2CE057 PBO Reactor Bldg - U2 WA NWR M-77 Series 3
tO 2CESS ESW C RHR ROOM COOLING COIL C M-315, SHT 2 R2-7 NWA NWR 2
S 914 5545 PASSIVE 2CE058 P80 Reactor Bldg - U2 NWA NWR M-77 Series 3
10 20E57 ESW C CORE SPRAY ROOM COOLING COIL D M-315. SHT 5 R2.11 NWA NWR 2
S 91-6 5556 PASSIVE 2DE057 PBO Reactor Bg - U2 NA NWR M.77 Series 3
10 20E58 ESW C RHR ROOM COOLING COIL 0 M-315. SHT 2 R2-7 NWA NWR 2
5546 S
PASSIVE 2DE058 Pao Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrrP..nnndr.nr.P Nn - RR-19-173 9146
- Reactor Bldg -U2 WA NIR M-77 Series B-21
DOCUMENT NO. 00674*084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNiTS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST Norm state Motive power Desied State Con, po wer DATE: 3r28/6 PAGE 21 TRAIN SOUG CI Equip ID Eval eq'd?
PIMS ID System Notes Equip Descripion ROB mom~ Comnp Drwinvng No.
Loc Code Roam Elev Suppor System Supp Sys dwg Line No Functioln Bulding 3
10 2EE57 ESW B CORE SPRAY ROOM COOLING COIL E M-315. SIT 5 R2-10 WA NMR 2
S 9146 555?
PASSIVE 2EE57 Pao Reactor B19 - U2 WA MR M-77 Series 3
10 2EE58 ESW 8 RHR ROOM COOLING COIL E M-345. SHT 2 R2-6 N/A NIR 2
S 9146 5547 PASSIVE 2EE058 Pao Reasctor Bg - U2 NA NIR M-77 Series 3
10 2FE57 ESW 8 CORE SPRAY ROOM COOLING COIL F M-315. 5HT 5 R2-10 NWA N/R 2
S 914 5558 PASSIVE 2FE0'7 PSO Reactor B6d1 - U2 NWA NMR M-T? Series 3
10 2FE58 ESW B RHR ROOM COOLING COIL F M-315. SHT 2 R2-6 WA N/R 2
5 9146 5548 PASSIVE 2FE058 P80 Reactor Bidg - U2 WA NMR M-T7 Series 3
10 2GE57 ESW D CORE SPRAY ROOM COOLING COIL G M-315. SHT 5 R2-12 NIA N/R 2
S 91.6 5559 PASSIVE 2GE057 Pao ReaioW Bldg - U2 WA NMR M-77 Series 3
10 2GE58 ESW O RHR ROOM COOLING COILG M-315. SHT 2 R2-19 WIA NMR 2
S 11 554&
PASSIVE 2GE068 PGO Reactor Bldg - U2 NA NIR M-77 Series 3
10 2HE57 ESW 0 CORE SPRAY ROOM COOLING COIL H M-315, SHT 5 R2-12 NIA NR 2
5 9146 56 PASSIVE 21NE057 Pao Reactor Bldg -U2 WA NMR M-77 Series 3
10 2HE58 ESW 0 RHR ROOM COOLING COIL H M-315. SHIT 2 R2-8 NWA NMR 2
S 91-6 5550 PASSIVE 2HE068 Pao Reactor Bldg - U2 NIA NMR M-77 Series 1
10 P020223-1 HPSWHVAC HPSW PUMP ROOM "B'LOOP SUPPLY M-396, SlIT 1 P/1-6 OPEN 2
S DAMPER 112 ACTIVE Pump House OPEN 1
10 P020223-2 HPSW HVAC HPSW PUMP ROOM "B* LOOP EXHAUST M-396, SIT 1 P/116 OPEN 2
S DAMPER 112 ACTIVE P=mP House OPEN t
10 P020223-3 RPSW HVAC HPSW PUMP ROOM A" LOOP SUPPLY M-396. SHIT 1 PM-6 CLOSED 2
S DAMPER 112 ACTIVE Pump House CLOSEDIOPEN 1
10 P020223-4 HPSW HVAC HPSW PUMP ROOM A LOOP EXHAUST M396. SHT I PA"-6 CLOSED I
2 DAMPER 112 ACTIVE Pump Hoam CLOSED/OPEN 3
14 20021 EPS-2A 125V DC STATION DISTRIBUTION PANEL E-26. SHT 1 12.81 ENERGIZED 2ADO03 2AD19 ACTIVE 200021 ITeO Turtilne Bldg - U2 ENERGIZED E-16-l.0 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
'nrrP..nnnd*.n-Nn - RR-12-173 B-22
DATE: 328mG PAGE 22 DOCUMENT NO. 006740084-001 REVISION 2 PEACH BOlTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST TRAN Unit sOUG C.
Eq4 tol Eval req'd?
PIMS ID Functionl System Notes Equip DMoOtion ROB Mothe Camp Orawing No.
LoC Coda Room Elev Bu"n0 Norm state MoVe power Desked State Cany power Support System Supp Sy$ 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 Bdg. U2 ENERGIZED E-16-1-8 3
14 20023 EPS-2C 125VDC STATION DISTRIBUTION PANEL E-26. SHT 1 T2-1 ENERGIZED 2CD03 2C019 2
S 150 8312 ACTIVE 200023 Tuftne Bldg. L2 ENERGIZED E.16-1-O 3
14 20S315 EPS.28 BYPASSIISOLATION SWITCH E.28, SHT. I T2.81 ENERGIZED 20037 2
SR 150 8000 ACTIVE 20S315 Tuoine Blg - U2 ENERGIZED 3
14 20Y33 EPS-2A 120VAC DISTRIBUTION PANEL E-28. SHT. 1 T2-61 ENERGIZED 20X133 2
S 150 8a00 ACTIVE 20YO33 Tutdbne ldg - U2 ENERGIZED 3
14 20Y35 EPS-2C 120VAC DISTRIBUTION PANEL E-28, SHT I R2-29 ENERGIZED 20X135 2
S 135 8001 ACTIVE 20Y035 Reactor f - U2 ENERGIZED 3
14 20Y50 EPS-28 120VAC DISTRIBUTION PANEL E-28, SHT 1 12481 ENERGIZED 20008 20037 2
S 150 20X150 a0 ACTIVE 20Y060 Toute S9 - LU2 ENERGIZED 3
14 2A017 EPS-2A 250 VOLT FUSE BOX E-26. SHT 1 T2-169 ENERGIZED N/A 2ADDt 2
S MD5 8108 ACTIVE 2AD017 Tuabine Bldg - U2 ENERGIZED E16-2-6 3
14 2AD19 EPS-2A 250VOLT FUSE BOx E-26, SHT 1 12-169 ENERGIZED N/A 2AD17 2
S 135 2AD03 8109 ACTIVE 2AD019 Twbie Bmlg. L2 ENERGIZED EIS-2.6 3
14 28017 EPS-20 250 VOLT FUSE BOX E-28. SKlT 1 T2-169 ENERGIZED NWA 28001 2
S 135 8209 ACTIVE 2D0017 Tubine Bldg. U2 ENERGIZED E16-2-6 3
14 26018 EPS-28 20P8 250V DC DISTRIBUTION PANEL E.26. SHIT I 12-169 ENERGIZED 28003 28017 2
S 280018 135 20017 8212 ACTIVE 280018 Turbine S1lg - U2 ENERGIZED 2DD03 E1S-2.6 3
14 28D19 EPS-28 250 VOLT FUSE BOX E-26, SHT I T2-169 ENERGIZED N/A 28017 2
S 135 280003 8210 ACTIVE 280019 Twbine Bdg - U2 ENERGIZED E62 E181-2-6 3
14 280306 EPS-28 125VDC DIST. PANEL (280306)
E-26. SHT 1 T2-71 ENERGIZED 28003 2
S 135 8000 ACTIVE 28D306 Turine Bldg -
2 ENERGIZED U2 ONLY??
3 14 2CD17 EPS-2C 250 VOLT FUSE BOX E-26. SHT I 12-169 ENERGIZED N/A I
2CD01 S
ACTIVE 135 Turbine Bldg - U2 ENERGIZED 2C0017 E16-2-6 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr..nnneirnc.p Nn
- R.R-19-173 B-23
DOCUMENT NO. 00674-004-O001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT UST REVISION 2 TRAIN Norm s$aWe Woe power Desd State Cow power DATE: 31286 PAGE 23 SOUG C Equip I Eval reqd?
PIMS ID system Nowe Equip Oesoiplion ROBMoheComp Dswit No.
Loc Code Room Elev SuPPolt System Supp Sys dag ieis No Function BuAdin 3
14 2CD19 EPS-2C 250 VOLT FUSE BOX E-26, SHT 1 T2-169 ENERGIZED WUA 2A'17 2
6 135 8310 ACTIVE 2CD019 Turbine Bldg - U2 ENERGIZED E1S-2-6 3
14 20017 EPS-20 250 VOLT DC FUSE BOX E-26. SHT I 12-169 ENERGIZED NWA 20001 2
S 135 8408 ACTIVE 2D0017 Turbine Bldg -U2 ENERGIZED E16-2-6 3
14 20019 EPS-2D 250 VOLT FUSE 8OX E-26, SHT 1 T2-169 ENERGIZED NWA 28D17 2
S 135 200003 8409 ACTIVE 2DD019 Turbine Bldg - U2 ENERGIZED E16 3 15 2A001 EPS-2A W2A" 125V OC BATTERY E-26. SHT I T2-70 ENERGIZED 2A003 2
S 135 8107 ACTIVE 2AD001 TwitSU Bdg* -U2 ENERGIZED E-13-34 to 37.
3 15 28001 EPS-28
'28" 125V OC BATTERY E-26. SlT 1 12-169 ENERGIZED 28D03 2
S 135 8208 ACTIVE 280001 Tbine Bldg - U2 ENERGIZED E.13-34 to 37, 3
15
.2CO01 EPS-2C 2C 125VDC BATTERY E-26. SliT 1 12-70 ENERGIZED 2CD03 2
S 135 830a ACTIVE 2CD001 Tuwbine ldg - U2 ENERGIZED E-13-341to 37.
3 15 20001 EPS-20 "2D" 125V DC BATTERY E-26, SHT 1 12-169 ENERGIZED 20D03 2
S 135 8407 ACTIVE 2D0001 Twbine Wg9
- U2 ENERGIZED E-1 3.34 to 37, 3
16 20037 EPS-2B STATIC INVERTER E-28. SHT. 1 T2-73 ENERGIZED 20008 2
SR 135 20X150 8000 ACTIVE 200037 Turbie ldg -U2 ENERGIZED 0
6280-E45 3
16 2AD03 EPS-2A 2A 125V STATION BATTERY CHARGER E-26. SlIT I T2-171 ON 20159(N) 2 S
135 8110 ACTIVE 2AOaM Trbine Bldg. U2 ON 30859(A)
NE-102 3
16 28D03 EPS-2B "28" 125V STATION BATTERY CHARGER E-26, SHT 1 12-171 ON 20860(N) 2BS456 2
S 135 8211 ACTIVE 280D03 TurbineeBlg.U2 ON 30860(A)
NE-102 3
16 2C003 EPS-2C 2C 125V STATION BATTERY CHARGER E-26. SHT 1 12-171 ON 20838 2
S 135 8311 ACTIVE 2CD003 Turiane Bldg -U2 ON NE-102 3
16 2D003 EPS-2D "21" 125V STATION BATTERY CHARGER E-26. SHT I 12-172 ON 20839(N) 20S456 2
S 135 8410 ACTIVE 200003 TurWbneBd9 -U2 ON 30860(A)
NE-102 3
18 20C87 EPS HPCI INSTRUMENT RACK R2-15 OPERABLE NWA S
ACTIVE 088 Reactor Oltg. U2 OPERABLE NWA 8a00 20C087 M-1-EE.180. M-W8 B-24 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr..qnnndrinr-. Nn RR-2-1-7.3
DATE: 3r28/6 PAGE 24 DOCUMENT NO. 0067.o4d-)0801 REVISION 2 TRAIN SQUG Cl Unit Eval 040d?
Line No Fundion PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Drmwng No.
Equip ID PIMS ID System Note*
Equip Descition ROB Moahe Comp Loc Code Room El, BuMcg Noon stake Desied State Motiv power Contr power SLpf system SUPP SYS deg 3
18 20C95 EPS RCIC INSTRUMENT RACK R2-15 OPERABLE NIA 2
S D88 8000 ACTIVE 200095 Reactr Bldg
18 2AC65 EPS RX VESSEL LVL AND PRESSURE INST R2-40 OPERABLE NIA 2
S RACKA 165 8000 ACTIVE 2AC0S5 Reactor ldOg
- U2 OPERABLE NIA M-1-.EE-168, M-1 -CE-l70 3
18 2AC9I EPS JET PUMP INST RACK A R2-1 OPERABLE NWA 2
S 135 8000 ACTIVE 2AC091 React" oldg - U2 OPERABLE WA 3
Is 28C65 EPS RX VESSEL LVL AND PRESSURE INST R2-40 OPERABLE NIA 2
S RACK B 165 8000 ACTIVE 2BC065 Readr Bldg. U2 OPERABLE NIA M-1-EE-168. M-1-EE-170 3
18 28C91 EPS JET PUMP INST RACK B R2-29 OPERABLE NWA 2
S 135 8000 ACTIVE 28091; Reactor Bldg -U2 OPERABLE WA 18 OPS20224-1 HPSW HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-3*6. SHT I P/H-8 OPERABLE 2S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE I
18 DPS20224-2 HPSW HVAC HPSWPUMP ROOM/EXHAUST PLENUM M-3g6, SHlT 1 P/IN-OPERABLE 2S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump mouse OPERABLE 18 DPS20224-3 HPSWHVAC HPSW PUMP ROOM I SUPPLY PLENUM M-396. SHT 1 P11-8 OPERABLE 2S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE pump House OPERABLE 18 DPS20224-4 HPSWHVAC HPSW PUMP ROOM I EXHAUST PLENUM M-396. SHIT 1 P/H-8 OPERABLE 2S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE 18 LS2 PROC MON INSTM SUPPRESSION POOL UMIT SWITCH AY M-365, SHT 1 OPERABLE 2R VALVE M02-13-039 ACTIVE M02-13-039 OPERABLE 1
18 LS2 PROC MON INSTM SUPPRESSION POOL LUMIT SWITCH AY M-365. SHIT 1 OPERABLE B2R VALVE M02-13-041 ACTIVE M02-13-041 OPERABLE 18 LS2-23-57 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON M-3M. SIlT I OPERABLE 2
BR VALVE M02-23-57 ACTIVE M02-23-57 OPERABLE 18 LS2-23-58 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON m-359, SHT 1 OPERABLE BR ACTIVE Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrP.qnnnd.n.P. Nn - RR-9-17.'3 VA.LVE M02. M402-23-58 OPERABLE B-25
DATE: 3=21196 PAGE 25 DOCUMENT NMO. 006-00084-D001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI E44p 11 Evalr qd?
PIMS ID Equp Deription ROB Mother Comp Drawki No.
LaOC Code Roomt ev Norm state Mote poer Deaied Slate Co, power SUPp Systg Notes Lune No Function Builrg I
18 LS2-23-74 PROC MON INSTm CONDENSATE STORAGE TANK LEVEL M.309, SHlT I T2-55 OPERABLE 2
SR SWITCH 135 ACTIVE Twble Bldg - U2 OPERABLE I
18 LS2-23-75 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309, SHT I T2-55 OPERABLE 2SR SWITCH 135 ACTIVE Tubine Bldg - U2 OPERABLE 18 LS2.23.91A PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359. SHT I R2-10 OPERABLE 2
SR 91-6 ACTIVE Recor Bpd9 - U2 OPERABLE I
18 LS2-23-G18 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 LT-8027A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365, SHT I R2-10 OPERABLE 20Y33 2
S FOR LR-027 091 7129 ACTIVE LT-8027A Reactor Bldg. U2 OPERABLE 3
18 LT-.027B PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-366, SHT I R2-10 OPERABLE 20Y50 2
S FOR L1.-027 091 7127 ACTIVE LT-0279 Reactor Bdg - U2 OPERABLE 3
Is LT-6123A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365, SHT 1 R24-0 OPERABLE 20Y35 2
S FOR LI-8123A 091 7128 ACTIVE LT-8123A Reactor Bldg -U2 OPERABLE 3
18 LT-81238 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SliT I R2-6 OPERABLE O0Y03 2
S FOR LR-81238 091 7130 ACTIVE LT-8123B Reactor Bdg - U2 OPERABLE 3
18 LT-8453 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309. SHT 1 amH8 OPERABLE 20Y50 2
N/A TRANSMITTER FOR U-.453 116 7132 ACTIVE LT-8453 Level NR. Transfer ACooriogTower OPERABLE tariction wig be picit UP I
18 LT2-13-170 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M.35, SHT I T2-14 OPERABLE 2SR FOR RCIC INITIATION 116 ACTIVE Tuwlne Bldg -
2 OPERABLE 18 LT2-13-171 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365, SHT I T2-14 OPERABLE SR FOR RCIC INITIATION 116 ACTIVE Turbine Bdg -U2 OPERABLE 3
18 LT2-2-3-61 PROC MON INSTM REACTOR VESSEL WATER LEVEL M-352, SHT 1 R2-40 OPERABLE 20Y33 2
8 TRANSMITTER FOR L.2-2-34-6 165 7131 ACTIVE LT-2-02-3-061 2AC06S Reactor Bklg - U2 OPERABLE 3
18 PT-2508B PROC MON INSTM CONTAINMENT ATMOS ORYWELL M-367, SHT 1 R2-53 OPERABLE 20023 e
PRESS TRANSMITTER FOR PR-2508 20Y35 ACTIVE Reactor Blg - 12 OPERABLE 7140 PT-2508B Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrp..nnndpnr.-.
Nn " RS-19-173 B-26
DATE: 3rA9 PAGE 26 DOCUMENT NO. 0067-0054-000 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl EquipIW Eval red?
PIMS D Fadictio System Notes Equip 0ascrition ROB Monter Camp orawing No.
Loc Code Room Elev Bid Norm state Motwe power Oesred State Cordn power Sup~port System SUPP SYS "V 3
18 PT-4805 PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M"3?7. SHT 1 R2-20 OPERABLE 20Y50 2
S FOR PR-4805 116 7141 ACTIVE PT-4805 Reactor l9 - U2 OPERABLE 3
18 PT8102A PROC MON INSTM ORYW.ELL PRESSURE TRANSMITTER M-361. SHT I R2-3 OPERABLE 20Y35 2
a FOR PR8102A 165 7135 ACTIVE PT-8102A 2AC65 Reactor Bldg - U2 OPERABLE 3
18 PT-SI2.S PROC MON INSTM ORYWELL PRESSURE TRANSMITTER M-361, SHT 2 R243 OPERABLE 00Y03 2
8 FOR PR-8102B 165 7137 ACTIVE PTrI12B 2BC65 Reactor Bldg - U2 OPERABLE 3
18 PT-8102C PROC MON INSTM ORYWELL PRESSURE TRANSMITTER M-361. SHT I R2-63 OPERABLE 20Y35 2
a FOR PR-8102A 165 7134 ACTIVE PT-6102C 2AC65 Reactor Bldg - U2 OPERABLE 3
Is PT-810(20 PROC MON INSTM ORYWELL PRESSURE TRANSMITTER M-361. SHT 2 R2-3 OPERABLE 00Y03 2
a FOR PR-81028 165 7136 ACTIVE PT-8102D 2BC65 React BM9g-U2 OPERABLE 3
18 PT2-2-3-404A PROC MON INSTM REACTOR PRESSURE TRANSMITTER M-352, SHT I R2-40 OPERABLE 20Y35 2
8 FOR PR2.2-3404A 165 7138 ACTIVE PT-22M-3-404A 2ACC65 Reactor Bldg - U2 OPERABLE 3
18 PT2-2-3-404B PROC MON INSTM REACTOR PRESSURE TRANSMITTER M-352, SHT 2 R2-40 OPERABLE 00Y03 2
B FOR PR2-2-3-404B 165 7139 ACTIVE PT-2-02-3-404B 28C065 Reactor Bldg - U2 OPERABLE 3
18 PT2--53A PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352, SHT I R2-40 OPERABLE 20Y50 2
8 TRANSMITTER FOR P12-6-OA 165 7132 ACTIVE PT-2-06-053A 2AC065 Reactor Sldg -U2 OPERABLE 3
18 PT2-4-538 PROC MON INS`TM REACTOR WIDE RANGE PRESSURE M-352, SHlT 2 R2-40 OPERABLE 20Y50 2
B TRANSMITTER FOR P126-908 165 7133 ACTIVE PT-2-06-0538 2BC065 Reactor Bidg -U2 OPERABLE 1
18 TtC20223 4PSW HVAC HPSW PUMP ROOM EXHAUST TEMP M-398. SHT 1 PS-8 OPERABLE 2
S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE 18 TS20224-1 HPSW HVAC HPSW PUMP ROOM "A LOOP M-396. SHT 1 PM-6 OPERABLE 2S AUTOMATIC TEMPERATURE SENSOR 112 ACTIVE Pump House OPERABLE I
18 TS20224-2 HPSW HVAC HPSW PUMP ROOM B" LOOP M-3966 SHT I P144 OPERABLE S
AUTOMATIC TEMPERATURE SENSOR 112 ACTIVE Pump House OPERABLE iU S
ACTIVE HPIW-HVA(
TEMPE rURE TW CJANVSM IT TEMPERATURE TRANSMITTER M-396. SHT 1 P1-8 112 Po Houe OPERABLE OPERABLE Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrrp..qnnnfi.nrn. No
- RR-1 -173 B-27
DATE: 31281W PAGE 27 DOCUMENT NO. 00574)(KNW-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST REVISION 2 TRAIN Uni SQUO CI EQ4 ID Evsel eid?
PIMS ID Function System Notes Equ* DescOtpion ROB Modiet Comnp Dreming No.
Loc Code Room EIv B
-udi Norm state Desird State mot"v Power 1
SLWMov Systemn C.nt power Sapp Sys d.og 3
20 209324 EPS M02-23-015 MOTOR CONTROL POWER T247 OPERABLE NIA 2
S TRANSFER SWITCH 135 8000 ACTIVE 205324 Turbine B-U2 OPERABLE WA 3
20 20C003 EPS REACTOR AND CONTAINMENT COOLING 12-100 OPERABLE WA 2
S AND ISOLATION 165 8000 ACTIVE 20C003 Turbine B6dg - U2 OPERABLE NIA 3
20 20C004C EPS RCIC CONTROL PANEL 12-100 OPERABLE WA 2
S 165 8000 ACTIVE 20C004C Tuftd* ft - U2 OPERABLE NIA 3
20 20C005A EPS REACTOR MANUAL CONTROL PANEL T12-100 OPERABLE N/A 2
S 165 8000 ACTIVE 20COOSA Turbine Bt.- U2 OPERABLE NIA 3
20 20C006C EPS MAIN CONTROL ROOM CONSOLE 12.100 OPERABLE NIA 2
B 165 8000 ACTIVE 20COOSC 20C005A Turbino Bldg. U2 OPERABLE NIA 3
20 20C012 EPS PLANT SERVICES CONSOLE T2-100 OPERABLE EWA 2
S 165-8000 ACTIVE 20C012 Tubine Bldg -U2 OPERABLE NIA I
E-17-4212 3
20 2OCi24 EPS CRT AND RFPT TEST PANEL 12-100 OPERABLE NIA 2
S 165 8000 ACTIVE 2OC124 Tuf*ne BMg - U2 OPERABLE WVA 1
20 20C139 HPSWHVAC HPSW PUMP ROOM LOCAL CONTROL E202 P,1446 OPERABLE B62 2S PANEL 112 ACTIVE pump "Ouse OPERABLE 3
20 20C32 EPS ENGINEERING SUB SYSTEM I RELAY T12-81 OPERABLE NIA 2
S CABINET ISO 8000 ACTIVE 20C032 Turbine Bldg -U2 OPERABLE WZA S-1198/1-3. M-1-EE-241 3
20 20C33 EPS ENGINEERING SUB SYSTEM II RELAY T2.81 OPERABLE WIA 2
S CABINET 150 8000 ACTIVE 20C033 Turblne Bld.-U2 OPERABLE NIA S-1 19811-3. M-1-EE-241 3
20 20C34 EPS RCIC RELAY PANEL T12-81 OPERABLE MIA 2
S 150 8000 ACTIVE 20C034 Turbine Bldg - U2 OPERABLE NVA S-119B11-3. M-I-EE-84-24 3
20 20C39 EPS HPCI RELAY CABINET 12-81 OPERABLE NIA 2
S 150 8000 ACTIVE 20C039 Turbe Bldg. U2 OPERABLE NIA S-119*81-3. M-l-EE-98 20 S
ACTIVE 20C722A 20C722A EPS ACCUIJDEN T IMUNI i UKING INSTRUMENTATION PANEL T2.81 150 Tuwine Bldg -U2 OPERABLE NIA OPERABLE MIA 5-11981-3. M-1-EE-405 B-28 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrp..nnnrd.mnrp Nn
- RS-1 9-173
DOCUMENT NO. 001740054-0001 REVISION 2 TRAIN SOUG Cl Und Eval remd?
Li.e No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST Motwe Power Contr power DATE: 3/28r06 PAGE 28 Equ*p ID PIMS ID system Notes Equip Desuiption ROB Moge Comp Drwetv No.
Loc Code Room Elev Bulddin Norm state Desid State Support System Supp Sys dwg 3
20 20C7228 EPS ACCIDENT MONITORING T2.81 OPERABLE N/A 2
6 INSTRUMENTATION PANEL ISO sowo ACTIVE 20C722B Tuwine Bldg - U2 OPERABLE NIA S-1198/1-3.M-1.EE-405 3
20 20041 EPS HPCI GLAND SEAL CONDENSER VACUUM R2-13 OPERABLE NIA 2
S PUMP STARTER 085 8000 ACTIVE 200041 Rea or Bkld. 1U2 OPERABLE NIA 3
20 20D42 EPS HPCI GLAND SEAL CONDENSER VACUUM R2-13 OPERABLE MIA 2
B PUMP STARTER 088 8000 ACTIVE 200042 20041 Reactor Bldg - U2 OPERABLE N/A 3
20 20D43 EPS HPCI AUX LUBE OIL PUMP STARTER R2-13 OPERABLE NIA 2
a 088 6000 ACTIVE 200043 20D41 Reactor Bldg - U2 OPERABLE NWA U2 ONLY??
20 20S37-PANEL HPCI U2 HCI TURBINE M-366, SHT I R2-13 OPERABLE WA 2
S 088 ACTIVE 20S037-PANEL Reactor Bldg - U2 OPERABLE NWA 3
20 2AC265 EPS RESERVOIR FLOW PUMP BAY MO-2804A ECT-I OPERABLE NIA 2
S 114 8000 ACTIVE 2AC265 Emergency Cooing OPERABLE NWA Tower 62A-O-117-49.3 3
20 2AC272 EPS HPCI STEAM LEAK DETECTION CABINET 1T2.100 OPERABLE WA 2
S 165 8000 ACTIVE 2AC272 Turbne Bidg -U2 OPERABLE NWA M241-10 3
20 28C265 EPS RESERVOIR FLOW PUMP BAY MO-2804B ECT-1 OPERABLE NWA 2
S 114 8000 ACTIVE 2BC265 Emergency Coolbg OPERABLE WA Tower 62A.O-117.49-3 3
20 2BC272 EPS HPCI STEAM LEAK DETECTION CABINET T2.100 OPERABLE NIA 2
S 165 8000 ACTIVE 2BC272 Tuwbine Bdg - U2 OPERABLE NWA M241-10 3
20 2CC133 EPS FAN ROOM H&V RELAY PANEL RIW-32 OPERABLE NWA 2
S 165 8000 ACTIVE 2CC133 Radwaste Bldg OPERABLE W/A U2 ONLY??
3 20 LI43027 PROC MON INSTM TORUS WATER LEVEL M-365. SHT 1 12-100 OPERABLE 20Y50 2
BR 1165 7100 ACTIVE L-=027 20C003 Turbine Bldg -U2 OPERABLE 3
20 LI-8123A PROC MON INSTM WVDE RANGE SUPPRESSION POOL M-3M5, SHT I 12-100 OPERABLE 20Y35 LT-8123A 2
BR LEVEL INDICATOR 165 7101 ACTIVE LW123A 20C003 Tuna Bidg - U2 OPERABLE 3
20 LI-8453 PROC MON INSTM CST LEVEL INDICATOR M-309. SHT 2 T2-100 OPERABLE 20Y50 LT-8453 2
7102 BR ACTIVE LI-8453 20C004C Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrr.nnndnrnre.p Nn
DATE: 31aB PAGE 29 DOCUMENT NOI 0067-000I-OOO1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG G Eval reWd?
Equip ID PIMS ID System Notes Equip Oes$a* n ROB Modher Comp Drawig No.
LOC Code Room Elev N
state Desired State Motive power Support System Corer power Supp Sys dwg Line No Function Buidi 3
20 LI2-2-3-113 PROC MON INSTM REACTOR WATER LEVEL M-352. SHlT S "2-100 OPERABLE 20Y50 LT2-2-3-113 2
BR 165 7124 ACTIVE LI-2-02-3-113 20C003 Turbine Bldg. U2 OPERABLE 3
20 L12.2.3-2SA PROC MON INSTM REACTOR VESSEL HIGH WATER M-352. SHT 5 T2-100 OPERABLE 20Y35 LT2.2-3-72A OR 73A 2
BR 165 7125 ACTIVE U-2-02-3-085A 20C005A Tulwbt Bldg. U2 OPERABLE 3
20 L12-2-3-48S PROC MON INSTM REACTOR VESSEL HIGH WATER M-352, SHT5 T2-10O OPERABLE OOY03 LT2-2-3-72B OR 738 2
OR 165 7126 ACTIVE LI-2.02-3.0858 20C006A Tubkine Bldg -U2 OPERABLE 3
20 L12-2-3-M6 PROC MON INSTM REACTOR VESSEL HIGH WATER M-352. SHT I T2-100 OPERABLE 20Y33 LT2-2-341 2
BR 165 7107 ACTIVE 1.-2-02-3-088 20CO03A Tubi Bldge
- U2 OPERABLE 3
20 LR48027 PROC MON INSTM TORUS WATER LEVEL M-365. SHT I T2-100 OPERABLE 20Y33 LT-8027A 2
BR 165 7102 ACTIVE LR-=027 20C003 Turbire 81dg - U2 OPERABLE 3
20 LR-81238 PROC MON INSTM TORUS WATER LEVELfTEMPERATURE M-385, SHT I T2.100 OPERABLE 00YC3 LT-81238 2
OR RECORDER 165 7103 ACTIVE LRITR-8123B 20C003 Tuwbke Bldg - U2 OPERABLE 3
20 LR2-2-3-110A PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352. SHT 5 T2-100 OPERABLE 20Y35 LT2-2-3-72C OR 73C 2
BR 165 7104 ACTIVE LR-2-02-3-1IDA 20C004C Turbine Bldg - U2 OPERABLE 3
20 LR2-2-3-1108 PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352, SIT 5 T2-100 OPERABLE 00Y03 LT2-2-3-720 OR 730 2
BR 165 7105 ACTIVE LR-2.02-3.1 108 20C003 Turbine Bldg.U2 OPERABLE 3
20 P12.-S4OA PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-3S2, SHlT I T2-100 OPERABLE 20Y50 PT2-6-53A 2
BR 165 7108 ACTIVE PI-2-06-O0DA 20COOSA Tubne tdg. U2 OPERABLE 3
20 P12-6-908 PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-342. SHT 2 T2-100 OPERABLE 20Y50 PT24.-3E 2
OR 165 7109 ACTIVE PI-2.06-09B 20COOSC Tubine Bldg -U2 OPERABLE 3
20 PR-2508 PROC MON INSTM CONTAIN ATMOS ORYWELL PRESS M-367. SilT I T2.100 OPERABLE 20Y36 PT.25088 2
BR 165 20023 7110 ACTIVE PR-2508 20C003 Turbine Bldg -U2 OPERABLE 3
20 PR-4805 PROC MON INSTM CONTAINMENT PRESSURE M-47, SHT I T2-100 OPERABLE 20Y50 PT4805 2
BR 165 7111 ACTIVE PR-4805 20C003 Turbine ldg -U2 OPERABLE 3
20 PR-8102A PROC MON INSTM ORYWELL PRESSURE M4361. SIT 1 ¶T2-100 OPERABLE 20Y35 PT-8102A 2
BR 7112 ACTIVE PR-8102A 20C003 165 Turbire Bldg. U2 OPERABLE PT-8102C Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C.nrrP.mnnndP.nrP. Nnf RS-12-173 B-30
DOCUMENT NO. 00674-0084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LST DATE: XA2 PAGE 30 Norm state Mcoive power SuJport Systemn Desired State Contr power Sup)p SYS dwg TRAIN souO Cl Equip ED Eval re(d?
PINS ID System Nots Equip Desription ROB Mcltt Comp Drawing No.
Loc COe Room Eley Lkie No Function Builfdki 3
20 PR-B102B PROC MON INSTM OR'YELL PRESSURE M-361, SHT 2 T2-100 OPERABLE 00Y03 PT-8B028 2
OR 166 PT-8102D 7113 ACTIVE PR.8102B 20CO03 Tin Bldg. -U2 OPERABLE 3
20 PR2-2-3404A PROC MON INSTM REACTOR PRESSIRV WATER LEVEL M-S, SHT 1 2-100 (CO4C)
OPERABLE 20Y35 PT2-2-3-404A 2
BR 165 7114 ACTIVE PRALR-2-02-3404A 2DC004C Turbne Bag -U2 OPERABLE 3
20 PR2-2B3-4048 PROC MON INSTM REACTOR PRESSURE M-3, SKT 2 12-100 OPERABLE ODY03 PT2-2-3-4048 2
BR 165 7115 ACTIVE PR-2-02-3404B 20CO03 Tiabie B10g - U2 OPERABLE 3
20 PR24-96 PROC MON INSTM REACTOR LEVELSTM FLOW RATIO M-352. SHTS T2-100 OPERABLE 20Y50 PT24-105 2
OR 165 7106 ACTIVE PRAR-206096 20COOSA T udw Bld9 - U2 OPERABLE 3
20 TIS-2-2-71A PROC MON INSTM TORUS WATER TEMPERATURE M
I361.
SlT 1 T2-100 OPERABLE 20Y35 TE2-2-71A1 2 -
OR INDICATING SWITCH 165 THRU 7118 ACTIVE TIS-202-071A 2DC124 Tubine Bldg -
OPERABLE TE2-2-71N1 3
20 TIS-2-2-718 PROC MON INSTM TORUS WATER TEMPERATURE 1, SHT 2 T2-100 OPERABLE O0Y03 TE2-2-71A2 2
BR INDICATING SWITCH 165 THRU 7119 ACTIVE TIS-2-02-071B 20C124 Tutrine Bldg - U2 OPERABLE TE2-2-71N2 1
21 20EI05 PCI HPC TURS LUSE OIL COOLER (23.2)
Maw SHT 1 R2-13 OPERABLE WA 2
B 088 3212 PASSIVE 20E105 6M6094 Reader Bldg - 12 OPERABLE NIA Vendor Dwg 21(0MB0SA 1
21 20E33 HPCI HPCI GLAND SEAL CONDENSER (23-2)
M-366, SHT I R2-13 OPERABLE NIA 2
S 088 3210 PASSIVE 20EO33 Reactor Bdg -U2 OPERABLE WA 3
21 2AE124 ESW 2A RHR PUMP SEAL COOLER M-315. SHT 2 R2-5 NIA N/R 2
B 091 5639 PASSIVE 2AE124 2AP35 Reactor Bldg - U2 WA NfR 2
21 2AE24 RHRA RHR HEAT ExCHANGFR A M-361. SHT 1 R2.16 OPERABLE WA 2
S 116 4106.5525 PASSIVE 2AE024 Reactor Bldg - U2 OPERABLE WIA M-1-H-4-7, M-141-12-6, 3
21 2AS377 BACKUP INST N2 BACK-UP H2 SUPPLY TO ADS RVS M-M. SHT 1 R2.6 OPERABLE WA 2
S 135 6102 PASSIVE 2AS377 Reactor BMd - U2 OPERABLE NA M-1786-5 3
21 2AT545 SR INSTRUMENT N2 ACCUMULATOR FOR M-351, SHIT I D2-27 OPERABLE WA INSTR.N2 2
S RV-71A
" 154 2101 PASSIVE 2AT545 Dryieal - U OPERABLE NIA M433 3
21 2SE124 ESW 2B RHR PUMP SEAL COOLER M-315, SIlT 2 R2-6 NA N/R B
PASSIVE 2BE124 091 Reactor BIOd - U2 MIA NIR 5541 2BP35 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
'nrrP..nnnd.nr.. Nn
- R-1 -1773 B-31
DOCUMENT NO. 006740064-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3228196 PAGE 31 NHrm etate Motive power Suppor System Desired State Cony power Sutp Sysdwg TRAIN Unit SOUG C Equip ID Eval e(040 PLUS510 System Notes Equip Descipton ROB Mother C*m Drawfg No.
Loc Code Room Elev Line No Function Buing 1
21 28E24 RHR-8 RHR HEAT EXCHANGER B M-361. SHT 2 R2-18 OPERABLE N/A 2
S 116 4206.5527 PASSIVE 25E024 Reactor BSg - U2 OPERABLE NIA M.-4-7. M--14-125.,
3 21 2BS377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333= SHT I R2-23 OPERABLE NIA 2
S 135 6103 PASSIVE 2OS377 Reactor Bldg - U2 OPERABLE NWA I
M-1786-S 3
21 2BT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-35i, SlT 1 D/W2-27 OPERABLE NWA INSTR. N2 2
S RV-71B 154 2106 PASSIVE 2BTS45 Orywel - U2 OPERABLE NIA M-33 3
21 2CE124 ESW
-2C* RHR PUMP SEAL COOLER M-315, SHIT 2
R2-7 NIA N/R 2
B 091 5640 PASSIVE 2CE124 2CP35 Reactor Bldg. U2 NIA NWR 2
21 2CE24 RHR-A RHR HEAT EXCHANGER C "31.
SHT 1 12-17 NWA NWA 2
S 091 4109. 5526 PASSIVE 2CE024 Reactor Bldg-U2 OPERABLE NIA M-"-H-4-7. M-141-12-5, 3
21 2C.377 BACKUP INST N2 BACKUP NITROGEN SUPPLY FOR ADS M-333, SHT I R2-23 OPERABLE WA 2
S 135 6104 PASSIVE 2CS377 Reactor Bkdg. U2 OPERABLE NWA M-1788-5 3
21 2CT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 1 0N2-27 OPERABLE N/A INSTR N2 2
S RV-71C 154 2111 PASSIVE 2CT545 Drwll - U2 OPERABLE NWA M-333 3
21 2DE124 ESW "20" RR PUMP SEAL COOLER M-315, SHT 2 R2-8 NIA NWR 2
B 091
,542 PASSIVE 20E124 20P35 Reactor B1dg -U2 NWA NWR 1
21 2OF24 RHR-B AHM HEAT EXCHANGER 0 M-361. SHT 2 R2-19 NWA WIA 2
S 116 4209.5528 PASSIVE 2DE024 Reactor ftg U,2 OPERABLE NWA M-1-H-4-7. M--14-124.
3 21 2GT54S SRV INSTRUMENT N2 ACCUMULATOR FOR M-351, SHlT 2 D/W2-35 OPERABLE WUA INSTR N2 2
S RV-71G 154 2122 PASSIVE 2GT545 ODywea
- U2 OPERABLE W/A M-333 3
21 2KT545 SRV INSTRUMENT N2 ACCUMULATOR I3.1, SHlT 2 DN2-34 OPERABLE NWA T
INSTR. N2 2
S 154 2131 PASSIVE 2XT545 Dyel - U2 OPERABLE NIA SM-33 R
0 16A-33205A SRV ADS BACKUP N2 SUPPLY CHK W TO I351.
SKlT 3 DAM3-27 OPERABLE NWA 3
NWA RV-3-2-071A 154 2103 PASSIVE CHK-3-16A-33205A Drywll - U3 OPERABLE NWA 3
0 1SA-332058 SRV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT 3 D/W3-29 OPERABLE WA 3
NWA 2109 PASSIVE RV-3-2-0710 154 Drywal-U3 OPERABLE WA C1"-3-16A-332058 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrrp*.nnndp.nr.p. Nn ' RS-12-173 B-32
DOCUMENT NO. 00b7-008440001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3W2816 PAGE 32 Norm date Mooe powe Sppol System Desired State Cam power SuppSysdwg TRAIN SOUG CI Equiap D
Eval reqd?
P085 10 System Notes Equ4 esaiptiori ROB Motater Cmp DrawilgNM L.o Code Room Elev Lhw No Funcion BlAf 3
0 16A-33205C SRV ADS BACKIJP N2 SUPPLY CHK W TO "I,51. SHT 3 DAW3-27 OPERABLE N/A 3
NIA RV-32-071C 154 2115 PASSIVE CHK-3-16A-33205C Drywa U3 OPERABLE N/A 3
0 16A-332050 SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT 4 DIW3-35 OPERABLE NIA 3
NIA RV-3.2.071G 184 2127 PASSIVE CHK-3.16A-33205G Dryweo - U3 OPERABLE WA 3
0 16A-33205K SRV ADS BACKUP N2 SUPPLY CHK W TO M1-351, SHT 4 DNW3.34 OPERABLE NIA 3
NWA RV-3-2-071K 164 2137 PASSIVE CHK-3-16A-33205K Drywa - U3 OPERABLE NIA 1
0 346-096B RCIC FEEDWATER CHECK VALVE LOOP B
"-351. SHT 4 R3-30 OPEN NIA 3
N/A OUTER 135 3134 PASSIVE CHK-3-0S-68 Reactore*lg -U3 CLOSED N/A 2
0 3.10-177 RHR-C HIGH PRESSURE SERVICE WATER TO M-315, SHT 3 R3-7 CLOSED NUA 3
NWA RHR CROSSTIE CHECK VALVE 091 4309 PASSIVE CHK-3-10-177 Reactor Big -U.3 CLOSED NIA 2
0 3.10-184A RHR-C RHR PRESSURING LINE INNER CHECK I-361, SHT 3 R3-24 CLOSED N/A 3
WA VALVE TO RHR LOOP A 135 4315 PASSIVE CHK-3-10.184A Reactor Bldg -U3 CLOSED WA 1
0 3.10-1848 RHR-O RHR PRESSURING LINE INNER CHECK M-361. SHT 4 R3-26 CLOSED N/A 3
NWA VALVE TO RHR LOOP B 135 4415 PASSIVE CHK-3-10-184B Reactor lg - U3 CLOSED N/A 2
0 3-10-48A RHR-C RHR PUMP 3AP035 DiSCHARGE CHECK "I-31. SHT 3 R3-5 CLOSED N/A 3
NWA VALVE 091 4308 PASSIVE CHK-3-10-48A Reactor Blg - U3 OPERABLE WA 1
0 3-10.488 RHRu D RHR PUMP 3BP035 DISCHARGE CHECK I-361.
SHT 4 R3-6 CLOSED W/A 3
NZA VALVE 091 4410 PASSIVE CHK-3-10.4a8 Reactor B* - LU3 OPERABLE NIA 2
0 3-10-48C RHR-A RHR PUMP 3CP035 DISCHARGE CHECK M-361. SHT 3 R3-7 CLOSED NWA 3
N/A VALVE 091 4107 PASSIVE CHK-3-10-48C 3
Reactor Bdg - U3 OPERABLE NWA 2
0 3-10-480 RHR-B RHR PUMP 3OP035 DISCHARGE CHECK M-351. SHT 4 R3-8 CLOSED WIA 3
N/A VALVE 091 4206 PASSIVE CHK-3-10-480 3
Reactor Si -U3 OPERABLE N/A 3
0 3-10.257A SRV INSTR N2 CHECK VALVE TO RV-3-2-071A M-351. SHT 3 DAN3-27 OPERABLE N/A 3
N/A 154 2104 PASSIVE CHK-3-16-257A Drywael - U3 OPERABLE N/A 3
0 3-16-2578 SRV INSTR N2 CHECK VALVE TO RV-3.2-071B M-351, SHT 3 DIW3.29 OPERABLE WA 3
hWA 2110 PASSIVE CHK-3-16-257B 154 Drywell -U3 OPERABLE NIA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrP..nnndp.nr.e Nn
- RS-19-173 B-33
DOCUMENT NO. 006784-D0OI REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST DATE: 3128185 PAGE 33 Nom state MoUve power Suppor System OeSwed StMe Car* power Supp Sys dwg TRAIN SOUGC0 EWOpID Eval recd?
PIMS ID Equp Deseripioll ROB MoVte COMPW onswirg No.
Loc Code Room Elev Lkb No Fnotbon 3
0 3-16-257C SRV INSTR N2 CHECK VALVE TO RV-3-2<71C M-351, SHT3 D0W3-26 OPERABLE NZA 3
WA 154 2116 PASSIVE CHK-3-16-257C Oryee -U3 OPERABLE NIA 3
0 3-16-257G SRV INSTR N2 CHECK VALVE TO RV-3-2-07IG 14-351. SHT4 DNI3-35 OPERABLE MIA 3
N/A 154 2128 PASSIVE CHK-3-16-257G Onywf - U3 OPERABLE NZA 3
0 3-16-257K SRV INSTR N2 CHECK VALVE TO RV-3-2-071K M-35t. SHT4 DIW3-34 OPERABLE N/A 3
NIA 154 2138 PASSIVE CHK-3-16-257K Dywei - U3 OPERABLE N/A 2
0 3-32-502A HPSW HPSW 3AP042 DISCHARGE CHECK M-315, SHT 3 PMH-J OPERABLE NWA 3
NIA VALVE III 5596 PASSIVE CHK-32-5MA Pump "am OPERABLE NIA 0
3-32-5028 HPSW HPSW36PO42 DISCHARGE CHECK M-315. SHT 3 P/144 OPERABLE NWA 3
NWA VALVE 111 5600 PASSIVE CHK-3-32-502B Pump House OPERABLE NWA 2
0 3-32,50MC HPSW HPSW3CPO42 DISCHARGE CHECK M-315. SHT 3 P"-B OPERABLE W/A 3
NIA VALVE 111 5602 PASSIVE CHK-3-32-50C Pump House OPERABLE WA 1
0 3-32-502D HPSW HPSW 3OP042 DISCHARGE CHECK M-345, SHT 3 PMH-9 OPERABLE NZA 3
WA VALVE 111 5604 PASSIVE CHK-3-32-502D Ponp House OPERABLE NWA 3
0 3-33-514 ESW SERVICE WATER TO ESW CROSS TIE i&351, SiT 4 T3-45 NIA NIA 3
NIA CHECK VALVE 116 5591 PASSIVE CHK-3-33-514 TubrieBWB9.1U3 CLOSED NWA 3
0 3-3A-13 CRD HYDRAULIC CONTROL UNITS, TYPICAL MW.357 SPIT 2 R3-24 OPERABLE NWA 3
S OF 185 135 1100 ACTIVE U3 HCU 02-19 1
Reactor SWO -U3 OPERABLE NIA 1
0 3-6-96A HPCI FEEDWATER CHECK VALVE LOOP A M-351, SHT 3 R3-30 OPEN NWA 3
NIA OUTER 135 3233 PASSIVE CHK-3-06-16A Reactor Bldg - U3 CLOSED WA 2
0 3AS769 RHR-3A RHR PP 3AP035 SUCTION STRAINER M-361. SHT 3 Torus OPERABLE N/A 3
S 111 4100 PASSIVE 3AS769 3
TonM Proper-U3 OPERABLE NWA M-31. M-4578, 1
0 38S769 RHR-3B RHR PP 30P035 SUCTION STRAINER M-361. SHT 4 Toms OPERABLE WA 3
S 111 0PASSIVE 38S69 3
TonM Proper -U3 OPERABLE WA 1M-361, M-4578, 2
0 3CS769 RHR-3C RHR PP 3CP035 SUCTION STRAINER M-361. SHT 3 TonM OPERABLE NIA S
PASSIVE 3CS769 111 Torus Pf.oe-U3 OPERABLE NWA M-361. M-4578.
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (CnrrR..,nnndP.nr. Nn
- RR-19-173 B-34
DOCUMENT NO. 0067.00364-0OO REVISION 2 TRAIN SOUG CI EquipID Unit Eval reatd?
PIMS id PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Dramwn Nw Norm state Motive power Suppot System Desied State Con powr Supp Sys dwg DATE: 312816 PAGE 34 System Now Equip Descripion ROB Mal~w Camp Loc Code Room Etev Line NO Function BuilNfl 1
0 3DS769 RHR-30 RHR PP 3DP035 SUCTION STRAINER M-361. SHT 4 Tons OPERABLE WA 3
S III 4400 PASSIVE 31)5769 Tonm Proper - U3 OPERABLE NZA M-361. M-4578, 3
0 A03-104348B MSIV RHR LOOP S CHECK VALVE M-361, SHT 4 DNW3-16 CLOSED N/R 3
N/A 134 2213 PASSIVE AO-3.10446B Orywenf. U3 CLOSED NMR 2
0 A03-10-46A RHR-C RHR LOOP A CHECK VALVE M-361, SHT 3 DmW3-21 CLOSED WA 3
S 134 4317 PASSIVE AO-3-10-046A Ow - IU3 OPERABLE WA M-14,1-21-7 1
0 A03,10-468 RHR-O RHR LOOP S CHECK VALVE M-361. SHT 4 DN03-16 CLOSED WA 3
S 134 4417 PASSIVE AO.3-10-B Oryw45 - U3 OPERABLE WA M-1-H-21-7 3
0 A03.14013A CS CORE SPRAY LOOP A CHECK VALVE M-382. SHT 2 DAW3-21 CLOSED N/R 3
N/A 134 2214 PASSIVE AO-3-14-013A Orfeil-U3 CLOSED NIR 3
0 A03-14-0138 CS CORE SPRAY LOOP B CHECK VALVE M-362, SHT 2 D3.-16 CLOSED NiR 3
N/A 134 2215 PASSIVE AO-3-14-0138 Dywal -U3 CLOSED N/R 1
0 A03-23-018 HPCI HPCI DISCHARGE CHECK VALVE M-365. SHT 2 R3-30 OPERABLE WA 3
S 135 3232 PASSIVE AO-3-23-018 Reactor Bldg -U3 OPERABLE NWA Vendor 1607412 3
0 M03410-020 RHR-C RHR LOOPS AdS X-TIE M-361, SHT 3 R3-91 CLOSED WA 3
MIA 116 4310.4408 PASSIVE M0-3-10-020 11 Reactor1dgo -U3 CLOSED WA 3
0 M03-48-3213 ESW UNIT 3 ESW PUMP SLUICE GATE M-330 S4 OPEN N/R 3
R 116 5632 PASSIVE MO-3413-3213 scree House OPEN N/R 3
0 PCV-9917A BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT 2 R3-23 OPERABLE N/A 3
S BACKUP SUPPLY TO ADS 135 6105 ACTIVE PCV-3-16A-9917A Reactor 8ldg - U3 OPERABLE WA 3
0 PCV-99178 BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SPIT 2 R3-23 OPERABLE WA 3
5 BACKUP SUPPLY TO ADS 135 6106 ACTIVE PCV-3-16A-99178 Reactor Bldg -U3 OPERABLE NIA 3
0 PCV-9917C BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333, SHT 2 R3.23 OPERABLE WA 3
S BACKUP SUPPLY TO ADS 135 6107 ACTIVE PCV-3-16A-9917C Reaoor Bldg-U3 OPERABLE N/A 1
0 PSD3-23-006 HPCI HPCI TURBINE EXHAUST RUPTURE DISC W-366, SHT 4 R3-13 OPERABLE NIA 3
NIA 3206 PASSIVE PSD-3-234006 068 Reaactor Bldg -U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 f'nrrP.nnndP.nrA Nn " RS-12-17.3 B-35
DATE: 2126198 DOCUMENT NO.W07-00840-001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 35 REWiSION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG C!
Eq ID Syshm Equ" DeSO
-n Drwv No.
Loc Code Norm $We MotIve power SuLPo System Unk Eval req'd?
PIMS ID Notes ROB Motw COM Rom 8ev DesWd State Conr power Supp Sys daq Lne No Function Bu-ld 1
0 SUCTION HPCI HPCI SUCTION STRAINER M-385. SIT 2 ToMs OPERABLE WA 3
S STRAINER-3HPCI 11 3220 PASSIVE Reactor Bdg - U3 OPERABLE WA 3
0 VRV3-2..09SA SRV VACUUM RELIEF VALVE FOR MAIN
"-51. SHT 3 OfW3-26 OPERABLE WA 3
S STEAM LINE RELIEF W A 154 2105 ACTIVE VRV-302-9096A Drywefl - U3 OPERABLE WA M120-75-1 3
0 VRV3-2-9096B SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 3 D0W3-29 OPERABLE NWA 3
S STEAM LINE RELIEF W 8 164 2111 ACTIVE VRV-3S-0 968 Drywd-U3 OPERABLE NIA M120-75-1 3
0 VRV3-2-9096C SRV VACUUM RELIEF VALVE FOR MAIN M-351. SlHT 3 01*3-26 OPERABLE WA 3
S STEAM LINE RELIEF W C 154 211?
ACTIVE VRV-3-02-9096C Dryw5I - U3 OPERABLE NIA M120-75-1 3
0 VRV3-2-9096D SRV VACUUM RELIEF VALVE FOR MAIN I-351.
SHT 3 DJW3-27 OPERABLE N/A 3
S STEAM LINE RELIEF W 0 154 2119 ACTIVE VRV4.02-90960 Drywa.
U3 OPERABLE W/A M120-75-1 3
0 VRV3-2-9096E SRV VACUUM RELIEF VALVE FOR MAIN I-351.
SiHT 3 0/W3-29 OPERABLE NWA 3
S STEAM LINE REUEF W E 154 2121 ACTIVE VRV-3-02.9096E ll - U3 OPERABLE NWA M120-75-1 3
0 VRV3-2-9096F SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 3 DNY3-29 OPERABLE NWA 3
S STEAM UNE REUEF W F 154 2123 ACTIVE VRV-3-02-9096F J - U3 OPERABLE NWA M120-75-1 3
0 VRV3-2-40GD SRV VACUUM RELIEF VALVE FOR "IJ,4-351.
SHT 4 DWS4-35 OPERABLE WA 3
S STEAM LINE RELIEF W G 154 2129 ACTIVE VRV-3-02-909SG Dtyw
- U3 OPERABLE N/A M120-75-1 3
0 VRV3-2-4O96H SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 4 DAW3-35 OPERABLE NWA 3
S STEAM LINE RELIEF W H 154 2131 ACTIVE VRV-3-02-9096H Drywal - U3 OPERABLE WA M120-75-1 3
0 VRV3-2-G096J SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHlT 4 01*3-32 OPERABLE NWA 3
S STEAM LINE RELIEF W J 154 2133 ACTIVE VRV-3-02-OM Drywal - U3 OPERABLE WA M120-75-1 3
0 VRV3-2-9096K SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 4 ONW3-34 OPERABLE WA 3
S STEAM LINE RELIEF W K 154 2139 ACTIVE VRV-3-02-95K6 DK
- U3 OPERABLE WA M120-75-1 3
0 VRV3-2--906L SRV VACUUM RELIEF VALVE FOR MAIN I-351.
S STEAM LINE RELIEF W L 154 I
2141 ACTIVE VRV-3-02-8096L O
IJnM
- U3 OPERABLE WA 1M120-75-1 1
0 VRV3-23C-140A HPCI HPCI TURBINE EXHAUST TO. TORUS M.365. SHT 2 R3-%9 OPERABLE WA 3
WA VACUUM RELIEF VALVE 116 3215 PASSIVE VRV--23C-140A Rector Bo - U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 3 B-36 MPR-3812, Revision 3
.nrrp.mnnndpnrn. No
- RR-19-17Rl
DATE: 30121M PAGE 36 DOCUMENT NO. 00674.084-0001 REVISION 2 TRAIN SOUG CA Equip ID Unit Eval raq'd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST system Notes Equip Description ROB Mo~her Comp D-wkV No.
Loc Code Room EleO Norm state Dere Side Motie power Cone power Sup~port system Supp Sys dwg Lhe No Functn B.ilf 1
0 VRV3-23C-1409 HPCI HPCI TURBINE EXHAUST TO. TORUS M.365, SHT 2 R3-99 OPERABLE N/A 3
N/A VACUUM RELIEF VALVE 116 3216 PASSIVE VRV-3-23C-140B Reactor Bldg - U3 OPERABLE NIA 1
0 VRV3-23C-140C HPCI HPCI TURBINE EXHAUST TO. TORUS M-365. SHT 2 R3-99 OPERABLE N/A 3
N/A VACUUM RELIEF VALVE 116 3217 PASSIVE VRV-3-23C-140C Reactor ldg - U3 OPERABLE N/A 1
0 VRV3-23C-1400 HPCI HPCI TURBINE EXHAUST TO TORUS M-36. SHIT 2 R3-99 OPERABLE N/A 3
N/A VACUUM RELIEF VALVE 116 3218 PASSIVE VRV4.23C-1400 Reactor Blg -U3 OPERABLE N/A 1
0 VRV3-23C-59 HPCI HPCI TURBINE EXHAUST VACUUM.
M-366. SHT 4 R3-13 CLOSED N/A 3
N/A RELIEF VALVE 088 3207 PASSIVE VRV-3-23C-5998A Reacor Bldg. U3 CLOSED N/A 1
0 VRV3-23C-5998B HPCI HPCI TURBINE EXHAUST VACUUM.
M-366. SHT 4 R3-13 CLOSED N/A 3
N/A RELIEF VALVE O88 3208 PASSIVE VRV-3.23C-599 Reactor Bldg -U3 CLOSED N/A 3
1 30936 EPS-3A 480V RADWASTE AREA EL 116' MCC E-1715 T3-44 ENERGIZED 3081013 3
S 30836 (E134-W-A) 118 8000 ACTIVE Ei34-W-A(30B36)
Turbire Bldg - U3 ENERGIZED E-11-143 3
1 30B37 EPS-30 480 V REACTOR AREA EL 135I MCC E-1715 R3-23 ENERGIZED 3081113 3
S 30837(E234-R5) 135 8000 ACTIVE E234-R-S(30W37)
Reactor Bldg-U3 ENERGIZED E-11-144 3
1 30838 EPS-3C 4,0V REACTOR AREAEL 135 MCC E-1117 R3-22 ENERGIZED 3081213 3
30838(E334.IFB) 135 8000 ACTIVE E334-R-4(90838)
Reactor Bft. U3 ENERGIZED E-11-145 3
1 30B39 EPS-30 480V REACTOR AREA EL 135 MCC E-1717 R3-23 ENERGIZED 3081313 3
S30839 (E434-R-B) 135 8000 ACTIVE E434-R4930M39)
Reactor Bldg - U3 ENERGIZED E-11-146 3
1 30859 EPS-3A 480 V TURBINE AREA EL 135! MCC E-1715 13-171 ENERGIZED 3091014 3
S 30859 (E134-T-8) 135 8000 ACTIVE E134-T-8(30859)
Turbie Bldg - U3 ENERGIZED 3
1 30880 EPS-38 480V TURBINE AREA EL 136 1MCC E-1715 T3-171 ENERGIZED 3081114 3
S 30860E234-T-8) 155 8000 ACTIVE E234-T-8{30B60)
Tufbt*e Bldg - U3 ENERGIZED 3
1 30011 EPS-38 (30D011) RX BUILDING DC MOTOR E-27. SHT 1 R3-26 ENERGIZED 31D18 38D18 3
S CONTROL CENTER 135 8613 ACTIVE 3DB0R-0 Reactor fdg - U3 ENERGIZED E-11-157 3
2 30810 EPS-3A 48 V BUS E134 E-Ill5 R3-116 ENERGIZED 30X(30 3081012 S
ACTIVE 165 Reacto Bldg -U3 ENERGIZED 309010 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrP..-nnndAnP. Nn
- RR-1 2-173 B-37
DATE-3A2M PAGE 37 DOCUMENT NO. 00674K0844(101 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST TRAIN SQUG CI Equip ID Eval reqd?
PIMS ID Function System Equi Description ROB Mother camp Dnawiig No.
Loc Code Room Elev Bulcio Norm state Motme power Desired State Contr pwer Suppor System Supp Sys dwo 3
2 3081012 EPS-3A BREAKER TO E134 480 V BUS (LC30810)
E-1715 R3-116 CLOSED 30810 3
SR 165 S000 PASSIVE 3081012 30910 Reo Bdg. U3 CLOSED 3
2 3081013 EPS-3A BREAKER TO 480V RADWASTE AREA E-1715 RP3.116 CLOSED 30810 3
BR EL 116' MCC 30836 (EI34-W-A) 165 8000 PASSIVE 3081013 30810 Reactor B
-U3 CLOSED 3
2 3081014 EPS-3A BREAKER TO 480 V TURBINE AREA EL E-1715 R3-1116 CLOSED 30810 3
BR 13S' MCC 308 (E134.T-8) 165 8000 PASSIVE 3081014 30610 Reactor Bldg. U3 CLOSED 3
2 30811 EPS-38 480 V BUS E234 E-1715 R3-41 ENERGIZED 30X31 3081112 3
S 165 6000 ACTIVE 308I0 Reactor Bl:g -U3 ENERGIZED E-10-80 3
2 3081112 EPS-38 BREAKER TO E234 480 V BUS (LC30I11)
E-1715 R3-41 CLOSED 30811 3
BR 165 a000 PASSIVE 3081112 30811 Reactor Bldg -U3 CLOSED 3
2 30B1113 EPS-38 BREAKER TO 480 V REACTOR AREA EL E-1715 R3-41 CLOSED 30811 3
BR 135' MCC 30837 (E234-R-8) 165 8000 PASSIVE 3081113 30811 Reactor Bog -U3 CLOSED 3
2 3081114 EPS-38 BREAKER TO 480 V TURBINE AREA EL E-1715 R3.41 CLOSED 30811 3
BR 136 MCC 30860 (E234-T-8) 165 8000 PASSIVE 3081114 30811 Reactor wEg. U3 CLOSED 3
2 3081121 EPS-38 BREA-ER TO 0 V E2 DIG MCC QC54 E-1715 R.3-41 CLOSED 30811 3
BR (E234-4-A) 165 8000 PASSIVE 3081121 30Bl1 R aacorflg-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 BOg -U3 ENERGIZED 3
2 3081212 EPS-3C BREAKER TO E334 480 V 8US (LC30B12)
E-1717 R3-115 CLOSED 30812 3
BR 165 8000 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
BR 13S' MCC 30838 (E334-R-8) 165 I
6000 PASSIVE 3081213 30B12 Reactor Sldg-U3 CLOSED 3
2 30813 EPS-3D 480 V BUS E434 E-1717 R3.41 ENERGIZED 30X33 3081312 3
5 165 8000 ACTIVE 308013 Reactor 1dg - U3 ENERGIZED 3
2 3
BR 3081312 EPS-3D BREAKER TO E434 480 V BUS (LC30813)
E-1717 30813 R3-41 CLOSED 30813 165 Reactor Bld - U3 CLOSED 8000 PASSIVE 3081312 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrplnnndpnr.R No - RS-12-173 B-38
DATE: 3128=9 PAGE 38 DOCUMENT NO. 0067410084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl EquipID Eval ro~d?
PUMS ID Funcionw NoteGm Notes Equip Des'iptlon ROB More Co*p Dmwbg No.
LOC COdN Room Elev
- Buldir, Norm stat Motive Power Dotted State Contr power Support Systemn 8tupp Sys dwo 3
2 3081313 EPS-30 BREAKER TO 480 V REACTOR AREA EL.
E-1717 R3-41 CLOSED 30813 3
SR 135 MCC 30839 (E434-R4) 165 8000 PASSIVE 3081313 30813 Reacto 8do - LU3 CLOSED 3
2 3081321 EPS-3D BREAKER TO 480 V E4 DIG MCC 00856 E-1717 R3.41 CLOSED 30813 3
BR (E434-DA) 165 8000 PASSIVE E-67(1321) 30813 Reactr B1dg - U3 CLOSED 3
3 30A15 EPS-3A (304015) EMERG AUX SWITCHGEAR E-12 13.171 ENERGIZED 30A1503 3A1503 3
S 135 8500 ACTIVE E13 Turbrke Bldk -U3 ENERGIZED 3
3 30A1501 EPS-3A E313 BKR FROM XFMR OBX04 E-12 T3-171 CLOSED 30AI5 3
OR 135 8501 ACTIVE E13 (1501) 30A15 Twrbine Bd - U3 CLOSED/OPEN 20021 3
3 30A1502 EPS-3A E13A BKR (EM CLG TWR) TO XMFR E-12 T3-171 CLOSED 30ATS 3
BR OAX26 135 8502 ACTIVE E13 (1502) 30A15 Turbine Bldg. U3 OPERABLE 20D21 3
3 30AIS03 EPS-3A E13 8KR FROM El DIG OAG12 E-12 13-171 OPEN OAG12 3
BR 135 8503 ACTIVE E13(1503) 3aA1S Turbie Bldg - U3 CLOSED 20021 3
3 30A1505 EPS-3A Et34BKRTOXFMR3OX3O E-12 T3-171 CLOSED 30A15 3
BR 135 8504 ACTIVE E13 (1505) 30AIS Turbine Bf - U3 OPERABLE 20021 3
3 30A1506 EPS-3A BREAKER TO 3A RHR PUMP 3AP35 E-12 13-171 OPEN 30A15 3
BR 135 8505 ACTIVE E13 (1506) 30A15 Turbne BIdg -U3 OPEN/CLOSED 20021 3
3 30Al507 EPS-3A BREAKER TO 3A HP SER WATER PUMP E-12 T3-171 OPEN 30AIS 3
OR 3AP42 135 8506 ACTIVE E13(1607) 30A15 Turbine Bdg - U3 CLOSED 20021 3
3 30A1508 EPS-3A F.213 BRA FROM XF&IR OAXO4 E-12 T3-171 OPEN 30A15 3
BR 135 8507 PASSIVE E13 (1508) 30A15 Tuwbne ldg -U OPEN 20021 3
3 30AI6 EPS-38 (30A016) EMERG AUX SWITCHGEAR E-12 13-171 ENERGIZED 30A1606 30A1606 3
S 135 8600 ACTIVE E23 Turbine SIQ -U3 ENERGIZED 3
3 30A1601 EPS-3B E323 BlR FROM XFMR 08X04 E-12 T3-71 CLOSED 30A16 3
OR 135 8601 ACTIVE E23 (1601) 3GA16 Turbie Bldg -U3 CLOSED/OPEN 280306 3
30A1602 EPS-38 BREAKER TO 38 RHR PUMP 38P35 E-12 3
BR 8602 ACTIVE E23 (1602)
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrA..nnnd(nr.nP Nn
- RR-12-173 T3-71 OPEN 30A16 135 Turbine Bldg -U3 OPEN/CLOSED 20022 20D306 30A16 B-39
DATE* 3128196 PAGE 39 DOCUMENT NO. 0067.000844.O0M REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN Uril SOUG Cl Equip ID Eva] reqd?
PIMS ID Function System Notes Equip Desition ROB Mother Comp rawbv No, Loc Code Room Elev Bulkin Norm state D0esired State Moti powe Contr power Support System Supp Sys dwg 3
3 30A1605 EPS-38 E234 BREAKER TO XFMR 30X31 E-12 13-71 CLOSED 30A16 3
BR 135 8a03 ACTIVE E23 (1606) 30A16 TufbWbtne 8
- U3 OPERABLE 20022 26030S 3
3 30A1606 EPS-38 E23 8KR FROM E2 DIG 08G12 E-12 T3-71 OPEN 08G12 3
BR 135 0
8604 ACTIVE E23 (1606) 30A16 Turbine Bidg -U3 CLOSED 20022 2SO306 3
3 30A1607 EPS-38 BREAKER TO 38 HP SER WATER PUMP E-12 T3-71 OPEN 30A16 3
SR 3BP42 135 8806 ACTIVE E23 (1607) 30A16 Turitne 6idg - U3 CLOSED 20D22 2B0306 3
3 30A1608 EPS-38 E223 BKR FROM XFMR OAX04 E-12 T3-71 OPEN 30A16 3
BR 135 8506 PASSIVE FE23 (1608) 3GA16 Turbine 8Jdo - U3 OPEN 260306 3
3 30A1609 EPS-38 E23A BKR (EM CLG TWR) TO XFMR E-12 T3-71 CLOSED 30A16 3
BR 08X26 135 8607 ACTIVE E23(1609) 30A16 TwneW9 - U3 OPERABLE 20022 280306 3
3 30A17 EPS-3C (30A017) EMERG AUX SWITCHGEAR E-12 T3-170 ENERGIZED 30A1704 30A1704 3
S 135 8700 ACTIVE E33 Tubine Bldg - U3 ENERGIZED 3
3 30A1701 EPS-3C BR E333 FROM XFMR 08X04 E-12 T3-170 CLOSED 30A17 3
BR 136 8701 ACTIVE E33 (1701) 30AI7 Turbine Bldg -U3 CLOSEDIOPEN 30023 3
3 30A1702 EPS-3C BREAKER TO 3C RJR PUMP 3CP35 E-12 13-170 OPEN 30Ai?
3 BR 135 8702 ACTIVE E33 (1702) 30A17 Tubine Bldg - U3 OPENICLOSED 30023 3
3 304AI704 EPS-3C E33 6KR FROM E3 DIG OCGI2 E-12 T3-170 OPEN OCG12 3
BR 135 8703 ACTIVE E33 (1704) 30A17 Turbine Bldg -U3 CLOSED 30023 3
3 30A1705 EPS-3C E334 BCR TO XFMR 30X32 E-12 T3-170 CLOSED 30A17 3
BR 135 8704 ACTIVE E33 (1705) 30A17 Tubine *
-U3 OPERABLE 30023 3
3 30A1707 EPS-3C BREAKER TO 3C HP SERV WATER E-12 T3-170 OPEN 30A17 3
BR PUMP 3CP42 135 8705 ACTIVE E33 (1707) 30A17 Turbine Bldg - U3 CLOSED 30023 3
3 30A1708 EPS-3C E223 BKR FROM XFMR OAXD4 E-12 T3-170 OPEN 30A17 3
OR 135 8706 PASSIVE E33 (1708) 30A17 Turbine ldg - U3 OPEN 30023 3
3 30A18 EPS-30 (30A018) EMERG AUX SWITCHGEAR E-12 3
S 8800 ACTIVE E43 13-172 135 Turbine Bldg-U3 ENERGIZED ENERGIZED 30AI807 30A1807 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C*nrrP.qnnniPtnr.. Nn
- RR-19-171 B-40
DOCUMENT NO. 007410018410001 DATE: 3r26 PAGE 40 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST REVISION 2 TRAIN SOUG CI Equip ID Eval reold?
PIMS ID Functio System Notes Equip Desciplion ROB Mother Comp OmvDOi No.
Lac Code Room Eev Build1g Nonrm ate Desined State mob" power Contr powe Suppot System Supp Sys dwg 3
3 30A1801 EPS-3D E343 8KR FROM XFMR OBX04 E-12 T3-172 CLOSED 30QAB 3
OR 135 8801 ACTIVE E43 (1801) 30AMB Turbie Bkdg -U3 CLOSED/OPEN 300306 3
3 30A1802 EPS-3D BREAKER TO 30 RHR PUMP 3DP35 E-12 T3-172 OPEN 30A18 3
BR 135 8802 ACTIVE E43 (1802) 30A18 Turine B1dg-U3 OPENICLOSED 30024 300306 3
3 30A1804 EPS-30 BREAKER TO 30 HP SER WATER PUMP E-12 T3-172 OPEN 30AM8 3
BR 3DP42 135 8803 ACTIVE E43 (1804) 30At8 Turbine Bldg -U3 CLOSED 30024 30D306 3
3 30AIS05 EPS-3D E43A BKR (EM CLG TWR) TO XFMR E-12 T3-172 CLOSED 30A18 3
BR 0CX28 135 8804 ACTIVE E43 (1806) 30A18 Turbine Bldg - U3 OPERABLE 30D24 30D306 3
3 30A1806 EPS-30 E434 SKR TO XFMR 30X33 E-12 T3-172 CLOSED 30A18 3
OR 135 8806 ACTIVE E43 (1806) 30AMB Tubi*e Bldg - U3 OPERABLE 30024 30306 3
3 30A1807 EPS-30 E43 BKR FROM E4 D/G00G12 E-12 T3-172 OPEN 0DG12 3
BR 135 8806 ACTIVE E43 (1807) 30A8 TIm*no Bldg -U3 CLOSED 30024 300306 3
3 30A1808 EPS-3D E243 9KR FROM XFMR 0AX004 E-12 13-172 OPEN 30A18 3
BR 135 8807 PASSIVE E43 (1BM) 30A18 Turbine Bldg -U3 OPEN 300306 3
4 30X133 EPS-3A PANEL 30Y33 TRANSFORMER E-29 T3-81 ENERGIZED 30859 3
S 150 8000 ACTIVE 30X133 Tubine Bldg - U3 ENERGIZED 3
- 4.
30X135 EPS-3C PANEL 30Y35 TRANSFORMER E-29 R3-29 ENERGIZED 30M38 3
S 135 8001 ACTIVE 30X135 acto Odg - U3 ENERGIZED E123813. SPEC E1313 3
4 30X150 EPS-3A PANEL 30Y50 TRANSFORMER E-29 T3-171 ENERGIZED 30859 3
S 135 8000 ACTIVE 30X150 Turbine Bldg -L3 ENERGIZED 3
4 30=30 EPS-3A E134 LOAD CENTER XFMR (30M30)
E-1715 R3-116 ENERGIZED 30A1505 3
S 165 8000 ACTIVE 30X030 Reactor Bldg - U3 ENERGIZED ASB DSo Rep 3
4 30X31 EPS-3B E234 LOAD CENTER XFMR (30X31)
E-1715 R3-41 ENERGIZED 30A1605 3
5 165 8000 ACTIVE 30(031 Reo Bg -U3 ENERGIZED ASB Seis Rep 3
80OO 4
S ACTIVE EPS-3C E334 LOAD CENTER XFMR (30X32)
E-1717 R3.115 ENERGIZED 30A1705 165 Reactor Bldg - U3 ENERGIZED 30X032 ASS Seis Rep Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
.nrrp.;nnndPnrP. No " RR-12-173 B-41
DOCUMENT NO. 00674.0084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST Norm state Moae power Desied State Contr power DATE: 3128196 PAGE 41 REVISION 2 TRAIN SOUG CI Equp ID Eval re*d?
PIUS ID System Notes Equip Descption ROB Morner Comp Drawing No.
Loc Code Room Elev SupPo System Supp Sys "9 Line No Function Budding 3
4 30X33 EPS-3D E434 LOAD CENTER XFMR (30X33)
E-1717 R3-41 ENERGIZED 30A1806 3
S 165 8000 ACTIVE 30=xo3 Reactor Bdg - U3 ENERGIZED S
ASS Seis Rep 1
5 301M02 HPCI HPCI GLAND SEAL COSR VACUUM PUMP M-366, SHT 4 R3-13 OFF 30011 3
BR 088 3211 ACTIVE 30KO02 30E33 Reactor 8lg-U3 ON 1
5 30P26 HPCI HPCI AUXILIARY LUBE OIL PUMP M-366, SHT 4 R3-13 OFF 30011 3
OR 088 ACTIVE 30P026 30E33 Reactor Bldg - U3 ON 1
30P28 HPCI HPCI GLAND SEAL CONDENSER COND M-366, SHT 4 R3-13 OFF -
30D11 3
BR PUMP 088 3214 ACTIVE 30P028 30E33 Reactor td - U3 ON 1
5 3OP33 HPCI HPCI 8OOSTER PUMP M-366, SHT 4 R3-13 OFF N/A 3
8 088 3228 ACTIVE 30P033 30P38 Resa Bldg. U3 OPERABLE N/A 1
5 30P38 HPCI
-PCI PUMP M-366, SHT 4 R3-13 OFF WA 3
S 088 3227 ACTIVE 30P038 Reactor Bdg - U3 OPERABLE NA Vendor E4707 1
30S37 HPCI "U3 HPCI TURBINE M-366, SHIT 4 R3.13 OPERABLE WA 3
5 088 3205 ACTIVE 3050S7 Reactor Bldg -.
OPERABLE N/A 2
5 3AP35 RHR-A RHR PUMP A M-3"i, SHlT 3 R3-5 OFF 30A15 30A1506 3
SR 091 4103 ACTIVE 3AP035 3
Reactor Bldg - U3 0FF/ON M.1.H-41.2, S-1146 1
5 38P35 RHR-8 RHR PUMP B M-361, SHT 4 R3-6 OFF 30A16 30AI602 3
SR 091 4203 ACTIVE 38P035 3
Reactor Bldg - U3 OFF/ON M-14-4-41-2. S-1146 2
5 3CP35 RHR-C RHR PUMP C M-381. SHT 3 R3.7 OFF 30A17 30A1702 3
SR 091 4303 ACTIVE 3CP035 Reactor BIdg. U3 OFF/ON M-I-H-41-2, S-1 146 1
5 3OP35 RItR-D RHR PUMP D M-361, SHT 4 R3-8 OFF 30AM8 30A1802 3
SR 091 4403 ACTIVE 30P035 Reactor Bldg -U3 OFFION M-1-H-41-2, S.-1146 2
6 3AP42 HPSW HIGH PRESSURE SERVICE WATER M-315, SHT 3 PMH OFF 30A15 3DA1507 3
S PUMPA 111 5597 ACTIVE 3AP042 3
Pump Hal ON M-11-29, E8-108-1 1
6 3OP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 3 PJH.9 OFF 3GA16 30A1607 3
S PUMPB 111 A&-.nrSm...u..
ON rt*.s I ;Vi*
r q*
M-11-29, E-,108-1 B-42 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrrP.qnnndn.nrn. Nn " RS-12-173
DATE: 3128196 PAGE 42 DOCUMENT NO. 00674-0004-001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN LUit Line No SOUG Cl Eval fold?
Function Equi ID PIMS ID Notes Equp DescXiion ROB Mother Cams Drawinv No.
Loc Code Room Eiev Norm state Moive paW Camr Power Suppor System Supp So*d" 2
6 3CP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 3 P/H-9 OFF 30A17 30A1707 3
S PUMP C 111 5601 ACTIVE 3CP042 Pump Hos ON M-#11-29. ES-108-1 1
3DP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 3 P/H-9 OFF 30A18 30A1004 3
S PUMP 0 111 5603 ACTIVE 3DP042 Pump House ON M-11-29. ES-108-1 3
7 AO3-O1-O0QA MSIV A MAIN STEAM LINE INBOARD M-351. SHT 3 DNY3-18 OPEN N/A SV3-16-4BOA-1 3
s ISOLATION VALVE 134 SV3-16.080A-2 22W ACTIVE AO-3,0IA-OS0A Drywl - U3 CLOSED N/A M
M-1-R-12/1,2 3
7 A03O1-OSO8 MSIV B MAIN STEAM LINE INBOARD M-351. SHT 3 O/WV318 OPEN N/A SV3-1640808.1 3
S ISOLATION VALVE 134 SV3-16-0808-2 2202 ACTIVE AO*01A-e0DB DtYweI - U3 CLOSED N/A M-l-R-12/1.2 3
7 A03,0140C MSIV C MAIN STEAM LINE INBOARD M451. SHT 4 DAN3-19 OPEN NIA SV3-1-S-SOC-l 3
S ISOLATION VALVE 134 SV3-16-0800-2 2204 ACTIVE AO-3.OIA-SOBC Den -U3 CLOSED N/A M-1-R-12/l,2 3
7 A03-01-4=O MSIV 0 MAIN STEAM LINE INBOARD M-351. SHT 4 DN93-20 OPEN NIA SV3-16-0800-1 3
s ISOLATION VALVE 134 SV3-16-O800-2 2206 ACTIVE AO-34OIA-O800D Drwe - U3 CLOSED N/A M-1-R-12/1,2 3
7 A03o-oiosA MSIV A MAIN STEAM UNE OUTBOARD M-351. SHT 3 R3-31 OPEN MIA V3-16.088A.1 3
S ISOLATION VALVE 135 SV3-16-086A-2 2201 ACTIVE AO-30IAA86A Reactor 8Mdg
- U3 CLOSED WA M-1-R-12/1.2 3
7 AO301-0*5 MSli n,
MAIN STEAM LI*E OUTBOARD M-351. SHT 3 R3-30 OPEN NWA SV3-16-0868-i 3
S ISOLATION VALVE 135 SV3-16-0868-2 2203 ACTIVE AO.,1A.0868 Reactor Bg - U3 CLOSED N/A M-1-R-1211*2 3
7 A03-01-086C MSIV C MAIN STEAM LINE OUTBOARD M-351. SHT 4 R3-30 OPEN N/A 5V3-16-086C-l 3
S ISOLATION VALVE M
SV3-16-08SC-2 2205 ACTIVE AO-A-01A486C Reactor Bdg -U3 CLOSED N/A M-I-R-1211,2 3
7 A03-01-OOM MSIV D MAIN STEAM LINE OUTBOARD M-351. SHT 4 R3-30 OPEN NIA f
SV3-16-0860-3 S
ISOLATION VALVE 1356 SV3-6-086D.2 2207 ACTIVE AO-3-018D Reactor Bdg -U3 CLOSED NIA M-1-R-12J1,2 3
7 A03-32A CR0 SCRAM DISCHARGE VOLUME INBOARD M#-3S. SmT 1 R3-22 OPEN N/A SV3-3.32A 3
S ISOLATION VENT W 135 1102 ACTIVE AO-3-.032A Reactor BSg - U3 CLOSED NIA 3
7 A03-03-32B CRD SCRAM DISCHARGE VOLUME INBOARD M-358. SlIT 1 R3.23 OPEN N/A SV3-3-328 3
S ISOLATION VENT W 135 1104 ACTIVE AO-3-03-032B Reaor Bldg - U3 CLOSED NfA M-1-0-11,.3 7
S ACTIVE A03-033 AO-303-33 CR0 SCRAM DISCHARGE VOLUME INBOARD ISOLATION DRAIN W M#.358 SHT 2 R3-22 OPEN R135 Reactor B* -U3 CLOSED N)A NIA SV3-3-33 1110 vendor 6-SM207-62 B-43 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrrp*.nnndp.nA-. Nre RS-12-173
DATE: 3128196 PAGE 43 DOCUMENT NO. 0067.40X44001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUWIMENT LIST REVISION 2 TRAIN SOUC CI Equip D Evallreld?
PINS ID Fwiclion Sy"sl Equip Descriptio ROB Mo01w Comp Dmwin No.
Loc Code Roon Elev Norm state Desied State Motiv powe Contr powe Suppor System Sum Sys "0g 3
7 AO303-35A CRD SCRAM DISCHARGE VOLUME M-356. SHT 1 R3-26 OPEN N/A SV3-3-3A 3
S OUTBOARD ISOLATION VENT W 135 1106 ACTIVE AO-3-03-035A Reado Bldg - U3 CLOSED N/A M--6 3
7 A03-03-358 CRO SCRAM DISCHARGE VOLUME M-356. SHT I R3-24 OPEN NIA 5V3-3.35 3
S OUTBOARD ISOLATION VENT W 135 1106 ACTIVE AO-303-0358 Reactor Bldg - U3 CLOSED N/A M-1-0-162 3
7 A03 CRD SCRAM DISCHARGE VOLUME M435, SHT 2 R3-22 OPEN NWA SV3-3-3B 3
S OUTBOARD ISOLATION DRAIN W 135 1112 ACTIVE A0-3-03-M Reactor Bldg - U3 CLOSED N/A 1
7 H03-230-5512 HPCI HPCI TURBINE GOVERNOR CONTROL M-366, SHIT 4 R3-13 OPEN N/A 3
B VALVE 088 3204 ACTIVE HO-3-23C-5512 30S37 Reactor Bldg - U3 OPERABLE N/A 1
7 H03-23C-5513 HPCI HPCI TURBINE STOP VALVE M-366. SHT 4 R3-13 OPEN NZA SV3-23A-5543 3
B 088 3203 ACTIVE HO-3-23C-5513 3DS37 Reactor Bldg - U3 OPEN NWA M-1-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 COSR Gas 3213 PASSIVE PCV-3-23-050 Reactor Blg -U3 OPERABLE N/A 3
7 RV3-02.071A SRV A SAFETY RELIEF VALVE
-351. SHIT 3 DNW3-27 CLOSED 30D23 3
SR 154 2100 ACTIVE RV-3-02-O71A 4
Oryweu - U3 OPEN/CLOSED f
M-I-R-1-12. M1R54 3
7 RV3.024)718 SRV B SAFETY RELIEF VALVE M-351. SHT 3 D/W3-29 CLOSED 30D23 3
SR 154 2106 ACTIVE RV-3-02-071B 4
Dry"wal
- U3 OPEN/CLOSED M-I-R-1-12. M-1-R-5-4.
3 7
RV302-071C SRV C SAFETY RELIEF VALVE M-351. SHT 3 h/W3-25 CLOSED 30023 3
SR 154 2112 ACTIVE RV-3-02-071C 4
Dcywl - U3 OPEN/CLOSED M-1-R-1-12. M.I-R-5-4.
3 7
RV3.02-0710 SRV 0 SAFETY RELIEF VALVE "I35, SHT 3 DNW3-26 CLOSED 30023 INSTRrN2 3
SR 154 2118 ACTIVE RV-3-02-71DO 4
Drywe. - U3 OPEN/CLOSED M-1-.R1-12. M-1-R-,5.4 3
7 RV3-02-071E SRV E SAFETY RELIEF VALVE
-351, SIHT 3 DNW3-29 CLOSED 30023 INSTR. N2 3
SR 154 2120 ACTIVE RV-3-02-071E 4
ODywal - U3 OPEN/CLOSED M-I-R-1-12. *1-1-R--4.
3 7
RV3.02-071F SRV F SAFETY RELIEF VALVE M-351. SHlT 3 DMW3-29 CLOSED 30023 INSTR. N2 3
SR 154 2122 ACTIVE RV-3-02-071F 4
Drywall - U3 OPEN/CLOSED M-1-R-1-12, M-1-R-5-4.
3 7
RV3-02-07IG SRV G SAFETY RELIEF VALVE M-351. SHT4 DM/3-29 CLOSED 30023 SR ACTIVE 154 Drywel - U3 OPEN/CLOSED 2124 RV-3-02-.071G I4-11-R-1-12, 14-1-12-5-4, B-44 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 onrrPnondp.n.e.
Nn
DATE: WAM PAGE 44 DOCUMENT NO. 0067.0084-0001 REVISION 2 TRAIN SQUG C4 Equ ID Uni Eval uqjd?
PIMS ID Lkia No Funcion PEACH BOlrOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System Notes Equip DeSoapd ROB Moghtr Comp Drawing No Loc Code Room Elev BWdUdi Natm stale Motive power Deaired State Conte power SuWppou System SUPP Sys d"g 3
7 RV3-02-071H SRV H SAFETY RELIEF VALVE M-351, SHT 4 D&W3-35 CLOSED 30023 INSTR. N2 3
SR 154 2130 ACTIVE RV-3-02-071H 4
rell. - U3 OPENICLOSED M-i-R-1-12. M-1-R-5-4.
3 7
RV3-02-071J SRV J SAFETY RELIEF VALVE "I.351 SHT 4 DWN-32 CLOSED 30023 INSTA. N2 3
SR 154 2132 ACTIVE RV-3-02-071J 4
Drywel - U3 OPENICLOSED J
M-1-R-1-12. ----.
3 7
RV3-02-07iK SRV K SAFETY RELIEF VALVE M-351. SHT 4 DIW3-34 CLOSED 30023 3
SR 154 2134 ACTIVE RV-3-02-071K 4
DweD - U3 OPENICLOSED I
M-I.R-I-12. M-I-R-5-4, 3
7 RV3-02-071L SRV L SAFETY RELIEF VALVE M-351, SHT 4 D&V3-32 CLOSED 30023 INSTR N2 3
SR 154 2140 ACTIVE RV-3.02-0?IL 4
Drywinl - U3 OPENICLOSED M-1-R-1-12, M-I-R-5-4, 1
7 RV3-23-034 HPCI HPCI PUMP SUCTION HEADER RELIEF M-3, SHT 4 R3-13 OPERABLE NIA 3
S VALVE 68 3225 PASSIVE RV-3-238-034 Reactor Bldg. U3 OPERABLE N/A DS-M.204f3 2
a CV3-10-3677A RHR-A RHR PUMP 3AP035 DISCHARGE M-361, SHT 3 R3-5 OPEN NfR 3
N/A CONTROL VALVE 091 4106 PASSIVE CV-3.10-3677A 3.8 Reactor Bdg - U3 OPEN NMR I
8 CV3-10-36T7D RHR-O RHR PUMP 3DP035 DISCHARGE M-361, SHT 4 R3-8 OPEN NIR 3
NIA CONTROL VALVE 091 4405 PASSIVE CV-3-10-S?70 a
Reactor Bldg - U3 OPEN NmR 3
8 M043-2-74 MSiV MAiN ST -,AM LINES IBOARD DRAIN M-351, SHT 3 DAN3-i9 CLOSED NIR 3
R ISOL VALVE 134 2208 PASSIVE MO-3-0IA-074 Dywll - U3 CLOSED N/R 1
8 M03.06-029A HPCI FEEDWATER STOP VALVE M-351, SHT 3 01W3-29 OPEN N/R 3
R 154 3235 PASSIVE MO-3-08-O22A Drywou - U OPEN NIR 1
8 M036-O-038A HPCI FW LONG PATH RECIRC ISOLATION M-351. SKT 3 R3-30 CLOSED N)R 3
R VALVE 135 3234 PASSIVE MO-3-064038A Reactor Bldg -U3 CLOSED NIR 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 B-g. U3 OPEN NIR 1
8 M03-10-0138 RHR.B RHR PUMP 38P035 TORUS SUCTION M-361, SHT 4 R3.6 OPEN NIR 3
R ISOLATION W 091 4201 PASSIVE MO-3-10-0138 3
Reactor Bidg -U3 OPEN MIR 8
R M03-10,013C RHR-C RHR PUMP 3CP035 TORUS SUCTION ISOLATION W "l,381, SHT 3 R3-7 OPEN 091 Reactora9 -U3 OPEN NR NIR PASSIVE MO-3-10O013C Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (onrrp.nnndr.nrA Nn - RS-12l-173 B-45
DOCUMENT NO. 006740084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Mori sitat Motive powe Deskred State Con~ti power DATE: 3/28116 PAGE 45 TRAIN Uni SOUG CI Equip ID Eval ret4o?
PIMS ID System Notes Equip Dewipti-ROB Moiher Comp Orawing No.
Loc Code Room Elev Suipport Syslmn Supp SYS dwg Line No Function Buil 1
8 M03-100131 RAR-)
RHR PUMP 30P035 TORUS SUCTION
",361, SlT 4 R3-8 OPEN N/R 3
R ISOLATION W 091 4401 PASSIVE MO-3-10-0130 Reactor 10dg
-U3 OPEN NMR 2
a M03-.1OISA RHR-A RHR PUMP 3AP035 SHUTDOWN M-.361, SHT3 R3-5 CLOSED N/R 3
R COOLING SUCTION 091 4102 PASSIVE MO-3-10-OISA 3
Reactor Bldg. U3 CLOSED FOR 1
a M03-10-015B RHR-B RHR PUMP 3BP035 SUCTION FOR M-361. SHT 4 R3-18 CLOSED N/R 3
R SHUTDOWN CLG 116 4202 PASSIVE MO-3-10-OI5B 3
ReaCWON BO -U3 CLOSED N/R 2
8 M03-10-015C RHR-C RHR PUMP 3CP035 SUCTION FOR I-361.
SHT 3 R3-17 CLOSED N/R 3
R SHUTOOWN CLG 116 4302 PASSIVE MO-3-10-O15C Reactor Bldg.
3 CLOSED N/R 1
8 M03-10-0150 RHR-O RHR PUMP 3DP035 SUCTION FOR
"-361, SHT 4 R34-CLOSED N/R 3
R SHUTDOWN CLG 091 4402 PASSIVE MO-3-10-015D Reactor Bldg. U3 CLOSED W/R 2
SA M03-10-0I6A RHR-A RHR PUMP 3AP035 MIN FLOW RECIRC M-361. SHlT 3 R3-5 CLOSED 30036 3
SR BLOCK VALVE 091 4104 ACTIVE MO-3-10-016A 3
Reactor Bd0 -U3 OPEN/CLOSED 4-1028-49 1
8A M03-10-0168 RHR-B RHR PUMP 38P035 MIN FLOW RECIRC M-361. SBiT 4 R3-6 CLOSED 30837 3
SR BLOCK VALVE 091 4204 ACTIVE MO-3.10O-16B 3
Reactor Bldg - U3 OPEN/CLOSED f M-1028 -49 2
SA M03.10.016C RHR-C PR' PUMP 1-M'" FLW RECIRC i.38, SI*T 3 R3-7 CLOSED 30B338 3
SR BLOCK VALVE 091 4304 ACTIVE MO-3-10-016C Reactor Bldg - U3 OPENICLOSED M-402B-49 I
8A M03-10-0160 RHR-D RHR PUMP 3DP035 MIN FLOW RECIRC M-361, SHT 4 R3-8 CLOSED 30039 3
SR BLOCK VALVE 091 4404 ACTIVE MO-3-10-0160 Reactor BOg -U3 OPEN/CLOSED M-102849 3
8 M03-10-018 RHR RHR PUMPS SUCTION FOR SHUT1DOWN M"I6. SHT 3 DNW3-15 CLOSED N/R 3
R COOLING 0I4O ISOL 134 2212 PASSIVE MO-3-10-018 Drywel. U3 CLOSED N/R 2
&A M03-104025A RHR-C RHR INNER INJECTION VALVE TO M-361, SHIT 3 R3.25 CLOSED 30836 3
SR RECIRC LOOP A 135 4316 ACTIVE MO-3-10-025A 10 Reactor Bldg - U3 CLOSEDIOPEN M-I-H-31-5 1
8A M03-10025 RHR4)
RHR AINNER INJECTION VALVE TO M-361, SHT 4 R3-27 CLOSED 30839 3
SR RECIRC LOOP S 135 4416 ACTIVE MO-3-10-0258 10 Reactor Bldg -U3 CLOSED/OPEN M-144-31-5 2
8 M03-10.026A RHR-C RHR CONTAINMENT SPRAY OUTER M-361. SHT 3 R3-25 CLOSED N/R R
PASSIVE MO-3-10-026A ISOLATION VALVE 135 Reacto Bldg -U3.
4311 CLOSED N/R Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrrp..nnndrpnrp. No" R-R.-12-173 B-46
DATE: 31=96 PAGE 48 DOCUMENT NO. 0067.0084-D90 REVISION 2 TRAIN SQUCG CI Unit Eval req*d?
PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm sate Motve power Desired State Coen, pow Eqip ID PIMS ID Notes Equip Desciption ROB Mote Comp DrewbV No.
Loc Code Room Elev Supot System Supp Sys dwg Line No Function BLAI 1
8 M03-10-=268 RHR-D RHR CONTAINMENT SPRAY OUTER
"-3I. SHT 4 R3-27 CLOSED MR 3
R ISOLATION VALVE M35 4411 PASSIVE MO-3-104268 Reactor Bldg - U3 CLOSED NR 2
SA MO3-10434A RHR-C RHR LOOP A FULL FLOWTEST LINE M-361. SHT 3 R3-110 CLOSED 30838 3
SR BLOCK W 125 4313 ACTIVE MO-3-104034A 9
Reactor Blg U3 CLOSEDOPEN 1
CA M03-1O-034-RHR-O RHR LOOP B FULL FLOW TEST LINE M-361. SHT 4 R3-105 CLOSED 30839 3
SR BLOCK VALVE 125 4413 ACTIVE MO-3-10-0348 9
Reacor CLOSED/OPEN M-102842 2
CA 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-I0-03GA 9
Reactor Bldg U3 CLOSED/OPEN N-1-H-32 1
CA M03-10-0398 RHR-O RHR LOOP 8 OUTER BLOCK FOR
-3.
SKT 4 R3.03 CLOSED 30839 3
SR TORUS COOLING SPRAY 116 4412 ACTIVE M0-3-100398 9
Reactor Bldg - U3 CLOSED/OPEN M-1 -H-32 2
8 M03-10-154A RHR-C RHR LOOP A RECIRC OUTER INJECTION M-361. SHT 3 R3-99 OPEN N/R 3
R VALVE 116 4314 PASSIVE MO-3-10-154A Reactor Bldg. U3 OPEN NJR 1
8 M03-10-154B RHR-O RHR LOOP B RECIRC OUTER INJECTION M-361, SHT 4 R3-92 OPEN N/R 3
R VALVE 116 4414 PASSIVE MO-3-10-I 548 Reactor Bldg - U3 OPEN N/R 2
8 M03-40-176 HPSW HPSW TO RHR SYSTEM OUTER M-315. SHT 3 R3-7 CLOSED N/R 3
R CROSS-TIE 091 5596 PASSIVE MO-3-10-176 Reactor Bldg - U3 CLOSED NMR 2
CA, M03-10-SA HPSW RHR HX 3AE024 HPSW OUTLET VALVE M-315. SHT 3 R3-16 CLOSED 30836 3
SR 118 5595 ACTIVE MO-3-104)BSA Reactor Bld - U3 CLOSED/OPEN
- 4-10284o0 C
SA M03-10-898 HPSW RHR HX 38E024 HPSW OUTLET VALVE M-315, SHT 3 R3-18 CLOSED 30837 3
SR 116 5594 ACTIVE MO-3-10-0698 Reactor Bldg - U3 CLOSED/OPEN 141028460 2
CA M03-1049C 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 Bldg - U3 OPEN/CLOSED M4-O0B-60 1
CA M03-10.49D HPSW RHR HX 3DE024 HPSW OUTLET VALVE M-315. SHT 3 R3-19 CLOSED 30839 3
SR 116 5592 ACTIVE MO-3-10-089D Reactor dg - U3 OPEN/CLOSEO M-102B-60 3
CA M03-12-015 MSIV RWCU INLET INBOARD ISOLATION M-354, SHT 2 D/W3-25 OPEN 30836 3
SR VALVE 154 2209 ACTIVE MO-3-12-015 Drywell - U3 CLOSED M-1028.33 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (onrrp.mnnndp.nrp. Nn
- RS-12-173 B-47
DATE: 3128196 PAGE 47 DOCUMENT NO. 006740054D000 REVISON 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN unit SOUG CI Eval nd?
Eq4m PINS ID System Notes Equ* Desoti~on ROB Modw Comp Drawkg No.
Loc Code Room Etew Norm $awe Desired State Moatt power Cong power S&port System Supp Sys dwg Lune No Fundion g_
3 BA M03-12-018 MSIV RWCU INLET OUTBOARD ISOLATION M-354. SHT 2 R3-33 OPEN 30011 3
SR VALVE 6s 2210 ACTIVE MO-3-12-018 Reactor Bklg - U3 CLOSED M-1028-33 I
BA M03-23-014 HPCI HPCI TURBINE STEAM SUPPLY VALVE M-365, SHT 2 R3-13 CLOSED 30011 3
SR 088 3202 ACTIVE MO-3-23-014 Reacor BMi9 - U3 OPEN M-1028-42 1
8 M03-23-015 HPCI HPCI TURBINE STEAM LINE INBOARD M-365, SHlT 2 DAV3-15 OPEN NIR 3
R ISOLATION VALVE 134 3200 PASSIVE M0-3-23-015 Oryw* - U3 OPEN NIR a8 M03-23-016 HPCI HPCI TURBINE STEAM UNE OUTBOARD M-365. SHT 2 R3-27 OPEN N/R 3
R ISOLATION VALVE 135 3201 PASSIVE MO-3-23-016 Reactor Bldg - U3 OPEN NIR I
8A M03-23-017 HPCI HPCI CONDENSATE STORAGE TANK M-365. SHT 2 R3-13 OPEN 30D11 3
SR SUCTION 08 3224 ACTIVE MO-3-23-017 Reactor Bldg. U3 OPEN/CLOSED 1
SA M03-23-019 HPCI HPCI DISCHARGE TO FEEDWATER LINE M*365. SHT 2 R3-30 CLOSED 30011 3
SR A
135 3231 ACTIVE MO-3-23-019 Reactor Bd9 - U3 OPEN M-102B-29-7 1
8 M03-23-020 HPCI HPCI PUMP DISCHARGE VALVE M-365, SHT 2 R3-13 OPEN NIR 3
R 088 3229 PASSIVE MO-3-23-020 Reactor L-U3 OPEN NIR 1
I MO3-.2SO2 1 HpC; HPCI FULL FLOW TEST VALVE M-365. SHT 2 R3-S6 CLOSED N/R 3
R 116 3230 PASSIVE M0-3-23-021 Reactor Bldg. U3 CLOSED N/R B
SA M03-23-025 HPCI HPCI MINIMUM FLOW VALVE M-365. SHT 2 R3-13 CLOSED 300Di 3
SR 088 3228 ACTIVE MO-323-025 Reactor Bbg - U3 OPEN/CLOSED M-1-J-44-4 I
BA M03-23-057 HPCI HPCI TORUS SUCTION OUTBOARD M-365, SHIT 2
R3-13 CLOSED 30011 3
SR ISOLATION VALVE O88 3222 ACTIVE MO-3-23-057 Reactor dg - U3 OPEN M-1028--3*1 I
SA M03-23-058 HPCI HPCI TORUS SUCTION INBOARD M-365, SKT 2 R3-13 CLOSED 30D11 3
SR ISOLATION VALVE 08 3221 ACTIVE MO-23-50 Reactor Bldg -U3 OPEN M-1028-33F-I I
8 M03-23C-5244A HPCI HPCI TURBINE EXHAUST LINE VACUUM M-365. SHT 2 R3-98 OPEN N/R 3
R BREAKER VALVE 116 3219 PASSIVE MO-3-238-5445 13 Reactor SIg. U3 OPEN NMR 3
BA MO.30.3233A ESW & HPSW UNIT 3 A SLUICE GATE M-330 S/H.4 OPEN 00862 SR ACTIVE l6 Screon Hais CLOSED MO-3-30-3233A C-316 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrrrqnnndpnr.p. Nn
- Rt-19-17.
B-48
DOCUMENT NO. 006740084-0001 REVISION 2 PEACH sO:TOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Uatfr ower Desired State cawti Power DATE: 3128/16 PAGE 48 TRAIN nut SUG CI EWii ID Eval re'd?
PIUS tD System Notes Equip De.&V ROD Motiw COMP Drawirn No.
Loc Code Room Elev Support System Suipp Sys dwg Lioe No Funcion BuDOV 3
8A M03-30-32338 ESW& HPSW UNIT 3 8 SLUICE GATE M-M330 SH-4 OPEN 00861 3
SR 116 5630 ACTIVE MO-3-30-32338 Sceen house CLOSED C
3 8A M03-32-3486 HPSW HPSW RETURN VALVE TO DISCHARGE M-330 D/G-2 OPEN 00954 3
SR POND 121 5511 ACTIVE MO-3-32-3486 Dies Generator CLOSED 81-1028-125 Slt5 3
SA M03-32-3803 HPSW HPSW RETURN VALVE TO EMERGENCY u-330 DJG-2 CLOSED 00856 3
SR COOUNG TOWER 121 5613 ACTIVE M0-32-3803 Diesel Generator OPEN 3
8 M03-33-3344 ESW & HPSW HPSW LOOP 3A TO LOOP 38 CROSSTIE M-316. SHT 3 Ph"-9 CLOSED NIR 3
SR 111 5609 ACTIVE M
-3344 5
Pump Noun CLOSED NIR 3
8 M03-33-3972 ESW & HPSW 1.3 SAFEGUARDS AND RBCW HX ISOL M-315. SHT 4 T3-4S OPEN N/R 3
R FROM ESW PUMP 0813057 116 5S90 PASSIVE MO-3-33-3972 Twbine 8ldg - U3 OPEN NIR 3
8A 103-48-3804A ESW & HPSW U/3 HPSW SAY INLET OUTER M-330 ECT-1 CLOSED 00838 3
SR 114 s635 ACTIVE MO-348-3804A Emergency Cooftin OPEN Towers 3
8A M03-48-3804B ESW& HPSW U/3 HPSW BAY INLET INNER M-330 ECT-1 CLOSED 00897 3
SR 114 EegnyCooling OPEN 5W ACTIVE MO-3-48-38048 Towers 3
88 SV-913BA BACKUP INST N2 ADS BACKUP NiT-ROGEN A NOR SUPPLY M-333. SHlT 2 R3-23 DEENERGIZED 30Y35 3
SR TO ORY'AELL 136 6100 ACTIVE SV-3-16A-9130A Reaclor Bldg - U3 ENERGIZED 3
88 SV-91300 BACKUP INST N2 ADS BACKUP NITROGEN B HDR SUPPLY M-333, SHT 2 R3-25 OEENERGIZED 00Y03 3
SR TO RYWELL 135 6101 ACTIVE SV-3-16A-91308 Reactor S1dg - U3 ENERGIZED 3
a SV3-16-080A-1 MS1 BACKUP DC SOLENOID FOR N2 SUPPLY
"-351. SHT 3 DOW3-18 ENERGIZED NMR 3
BR TO AO-3-0IA A
134 2216 ACTIVE SV-3-16.08OA-1 AO3-.014-O0A OrywoU - U3 DEENERGIZED NDR 3
8 SV3-16-OOA-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHlT 3 OND3-18 ENERGIZED N/R 3
BR TO AO-3-01A-O80A 134 2217 ACTIVE SV-3-16-080A-2 A03-O1-080A 0Drwall - U3 DEENERGIZED NIR 3
8 SV3-16.080B.1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M4151. SIlT 3 DhW3-18 ENERGIZED NIR 3
BR TO AO-3-01A-080B 134 2228 ACTIVE SV-3-16,8B-1 A03-01.08D0B D
a - U3 DEENERGIZED NAR 3
8 SV3-16-080O-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY I-351.
SlT 3 DNW3-B8 ENERGIZED NIR 3
BR TO AO-".0Aw080 A03-1OWS80 134 Drywall-U3 DEENERGIZED NIR 2229 ACTIVE SV-3-16-080B-2 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C*nrrpqnnnfi.nr.p.
Nn* RS-1 2-17.3 B-49
DATE: 3128/9 PAGE 49 DOCUMENT NO. 006740084-0001 REVISION 2 TRAIN SQUG CI Equip I0 Una Eval reqd?
PINS I0 Lirn No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System Notes Equip Dea'-tlioni ROB Mother Comp Drawir No.
Loc Code Room Elev Norm state Desied State mowsv power support System Contr power ISupp Sys dwg 3
a SV3-16.080C-I MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-351. SHT 4 DJW3-19 ENERGIZED NMR 3
DR TO AO.3-01.A1080C 134 2222 ACTIVE SV-3-16.080C-1 A03.01-OODC
-w iefl -U3 DEENERGIZED NIR 3
8 SV3-16.080C-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 4 D/3-19 ENERGIZED NMR 3
OR TO AO-3.O1A-080C 134 2223 ACTIVE SV-3-16.-OSC-2 AO3-01-080C wl-L3ENERGIZE N
3 8
SV3-16.08D-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-351, SHT 4 ONW3-20 ENERGIZED NMR 3
BR TOAO.3-OIA-O) 134 2234 ACTIVE SV-3.l8-0800-1 A03-01-O80D Orywl -.U3 OEENERGIZED NMR 3
8 SV3-16-00-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 4 DmW3-20 ENERGIZED NMR 3
OR TO AO-3.01A40 134 2235 ACTIVE SV-3-164-0800-2 A03.01-Dryw0a
- U3 DEENERGIZED NIR I
8a SV3-23A-5543 HPCI HPCI TURBINE STOP VALVE REMOTE M-366, SHT 4 R3-13 CLOSED 30D22 3
OR TRIP VALVE 080 ACTIVE SV-3-23A-5543 30S37 Reactor B1dg -U3 OPEN I8s SV3-23C-54 HPCI HPCI TURBINE EXHAUST HDR DRAIN M-366. SHT 4 R3-13 CLOSED 30022 3
SR POTS DRAIN VALVE 088 3209 ACTIVE SV-3-23-054 Reactor Bkg - U3 OPEN M-206.D-21 3
8 SV3-3-32A CRD INSTR AIR SOLENOID VALVE FOR M-156. SHT 2 R3-22 ENERGIZED NIR 3
BR A04433-0=M 1103 ACTIVE SV-3.3-O3 A03-03-32A Reactor Bldg -U3 DEENERGIZED NIR 3
8 SV343.328 CRO INSTR AIR SOLENOID VALVE FOR M-35.
SHlT 2 R3-23 ENERGIZED NMR 3
BR AO-3-03-0328 135 1105 ACTIVE SV-3-03-032B A03-03,328 Reactor Bldg - U3 DEENERGIZED NMR 3
88 SV3-3-33 CRD INSTR AIR SOLENOID VALVE FOR M-356. SHT 2 R3-22 ENERGIZED NMR 3
SR AO-3-03-033 135 111t ACTIVE SV-3-3-033 AO3-03-33 Reactor Bdg -U3 DEENERGIZED NMR 3
8 SV3-3-35A CRO INSTR AIR SOLENOID VALVE FOR M-356. SHT 2 R3-26 ENERGIZED NMR 3
BR AO-303-035A 135 1107
-ACTIVE SV-3-03-035A A03-35A Reactor Bldg -U3 CEENERGIZED NWR 3
8 SV3.3.358 CRD INSTR AIR SOLENOID VALVE FOR M-356. SHIT 2 R3-23 ENERGIZED NMR 3
R AO3-03-0358 135 1109 ACTIVE SV.3.03-035B AO3-03-35B Reactor Bldg. U3 DEENERGIZED N/R 3
8 SV3-3-36 CR0 INSTR AIR SOLENOID VALVE FOR M-3SS. SH'T 2 R3.22 ENERGIZED NMR 3
BR AO-3-03-035 13 1113 ACTIVE SV-3-03-036 A03-03-36 Reactor Bldg. U3 DEENERGIZED N/R U.....S.L.NOD..
OR....SUP..
Y...
1 SJT a
SV3-36-086A-1 MSIV BR ACTIVE SV-3-6-086A.1 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrrP..nnndrnr.- Nn
- RR-1 9-173 BACKUP DC SOLENOID FOR U/A SUPPLY M-351, SHT 3 TO AO-3-01A-086A A03-01-O86A R3-30 135 Reactor Blfg. U3 ENERGIZED NMR DEENERGIZED NMR B-50
DOCUMENT NO. 0067-00084.0001 REVISION 2 TRAIN SOUG Cl Equp ID unif Eval req'd?
PIMS ID PEACH BOTrOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm stma Motive power Support System Desed SU Conr power Supp sys dwg DATE:
=1196 PAGE 60 System No"t Equp Descito ROB Moter CWmp Drawing No.
Loc Code Room Elev Line No Function Busig 3
8 SV3-35-88A-2 MSIV AC SOLENOID FOR UA SUPPLY TO M-351. SHT 3 R3-30 ENERGIZED N/R 3
BR AO01A 6A135 2220 ACTIVE SV-3-368-088A-2 A03.01.8A Reactor U. U OEENERGIZED NJR 3
8 SV3-36-0868-1 MSIV BACKUP DC SOLENOID FOR VA SUPPLY l-351.
SHT 3 R3-30 ENERGIZED NMR 3
OR TO AO-3-01A-48 135 2231 ACTIVE SV-3-36840168-1 AO3-01-0868 Reactor Sg. - U3 DEENERGIZED NIR 3
8 SV3-38-0B8-2 MSIV AC SOLENOID FOR UA SUPPLY TO M-351. SHT 3 R3-30 ENERGIZED NIR 3
R AO01A-4868 135 2232 ACTIVE SV-3-368-08B-2 A03-O1-0868 Reactor Bldg -U3 DEENERGIZED N/R 3
8 SV3-38.088C-1 MIS BACKUP DC SOLENOID FOR VA SUPPLY M-351. SHT 4 R3-30 ENERGIZED MIR 3
OR TO AO-3-01A-086C 135 2225 ACTIVE SV-3-368-086C-i A03-01-084C Reactor Bldg -U3 DEENERGIZED NIR 3
8 SV3-364M6C.2 MSIV AC SOLENOID FOR UA SUPPLY TO M1351, SHT 4 R3-30 ENERGIZED MIR 3
BR AO-3-IA-096C 135 2226 ACTIVE SV-3-36B.086C-2 A03-01-086C ReatorBdg. U3 DEENERGIZED NIR 3
8 SV3%16.0D-1 MSIV BACKUP DC SOLENOID FOR UA SUPPLY M-351. SHT 4 R3-30 ENERGIZED NIR 3
OR TO AO-3-01A.0860 135 2237 ACTIVE SV-3-3688086D-1 A03.O1.0860 Reactor Blg - U3 DEENERGIZED NIR 3
8 SV3-360860-2 MSIV AC SOLENOID FOR UA SUPPLY TO M-351. SHT 4 R3-30 ENERGIZED NIR 3
AR AO-"-OIA-8R0B 135 2238 ACTIVE SV-36B08D-23-086 Reactor 135 U3 OEERGIZED i
3A9 W"
HPSW HVAC HPSW PUMP ROOM SUPPLY FAN A 11-3.6. Sl"T i P/r-B AUTO 3
SR 112 ACTIVE Purnp House ON 1
9 3AV083 HPSW HVAC HPSW PUMP ROOM EXHAUST FAN A M1,396 SHT 1 PHal-AUTO 3
SR 112 ACTIVE Pump oe ON 1
9 3BVVGO HPSW HVAC HPSW PUMP ROOM SUPPLY FAN B M-396. SNT 1 P/1-9 AUTO 3
SR 112 ACTIVE Pump Home ON 9
3BV083 HPSW HVAC HPSW PUMP ROOM EXHAUST FAN B M-398. SNT 1 P/H-9 AUTO 3
SR 112 ACTIVE Pump House ON 3
10 3AE55 ESW RCIC PUMP ROOM COOLING COIL A M-315, SHT 4 R3-14 N/A NMR 3
S 91-6 5586 PASSIVE 3AE055 POO React mgBU
- U3 N/A N/R M-77 Series 3
10 3AE56 ESW HPCI PUMP ROOM COOLING COIL A M415. SNT 4 R3-13 WA NIR S
PASSIVE 3AE056 PBO Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrPnqnnndp.nr.n Nn" R5-1-17.1 0146 Reactor Oft - L3 WA NAR M-77 Series B-51
OATE: 328196 PAGE 51 DOCUMENT NO. 0067400084-DO00 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CC Equp Io Eval rWd?
PIMS ID Fuiction Systam Notes Equip Desripliro RODi Mother Camp Drawys No.
Loc Code Roor Elev Norm state Mote poWe Support System Desced SUat Cc power SupI) Sys dwg 3
10 3AE57 ESW A CORE SPRAY ROOM COOLING COIL A M-315. SHT 4 R3-9 NZA NIR 3
S 91-6 5577 PASSIVE 3AE057 P80 Reactor m. - U3 WA NAR M-77 Series 3
10 3AE58 ESW A RHR ROOM COOLING COIL A M-315, SHT 4 R3-16 NZA NA 3
S 116 5.6 PASSIVE 3AE068 Pa0 Reactor Bldg - U3 WA NIR M.77 Series 3
10 38E55 ESW RCIC PUMP ROOM COOLING COIL B M-315. SHT 4 R3.14 WA NIR 3
S 91-6 85 PASSIVE 38055 P801 Reactor O -BLd U3 NWA NIR M-77 series 3
10 3BE56 ESW HPCI PUMP ROOM COOLING COIL B M-315. SHT 4 R3-13 NWA NJR 3
S 9146 5588 PASSIVE 3E056 PlO Reactor Bl.
-U3 WA NIR M-77 Series 3
10 38E57 ESW A CORE SPRAY ROOM COOLING COIL 8 M-315. SHT 4 R3-9 NIA NIR 3
S 91-6 5678 PASSIVE 38E057 P80 Reactor Bdg -U3 NWA NR
- 77 Series 3
10 38E58 ESW A RHR ROOM COOLING COIL B M-315, SHT 4 R3-5 WA NIR 3
S 9146 5566 PASSIVE 38E058 PO0 Reactor Bldg -U3 NIA NIR M-77 series 3
10 3CES?
ESW C CORE SPRAY ROOM COOLING COIL C M-315. SHT 4 R3-11 NWA NIR 3
S 9146 5579 PASSIVE 3CE057 PeO Reactor Bldg - U3 NWA NAR M-77 Seres 3
10 3CE56 E5W C RHR ROOM COOLING COIL C M-315. SHT 4 R3-7 NWA N/R 3
S 9146 5567 PASSIVE 3CE058 Pao Reactor Bkdg - U3 NfA NAR M-77 Series 3
10 30E57 ESW C CORE SPRAY ROOM COOUNG COIL 0 M-315. SKlT 4 R3-11 NWA NAR 3
S 91-6 5580 PASSIVE 30E057 POO Reactor B9dg -U3 NWA NAR M-?? Series 3
10 3DE58 ESW C RHR ROOM COOLING COIL 0 M-315, SHT 4 R3-7 NIA NIR 3
91-4 5568 PASSIVE 3OE058 PBO Reacto 8Wd9 - U3 WIA N/R M-77 Series 3
10 3EE57 ESW B CORE SPRAY ROOM COOLING COIL E M-315. SHIT 4
R3-10 WA NAR 3
S 91-6 5581 PASSIVE 3EE057 P80 Reactor Bldg - U3 NA NAR M-77 Series 3
10 3EE56 ESW B RHR ROOM COOLING COIL E M-315, SHIT 4
R36 NWA N
3 S
91-6 5569 PASSIVE 3EE058 POO Reactor Blg - U3 NWA NAR M-77 Series II0 3FE57 E.SW B CORE SPRAY ROOM COOLING COIL F M-315. SHT 4 R3-10 NWA NAR 3
S PASSIVE 3FE067 9146 Reactor Bldg -U3 POO WA NM W77 Series Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrP.qnnndrPnme Nn o RR-1 2-173 B-52
DATE: 3=21816 PAGE 52 DOCUMENT NO. 00674)0844)001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG C Equ IO Eval mqd?
PIMS ID Fuicion System Notes Equip De on ROB Mothw Comp DrawbV No.
Loc CodeS Room Elev Norm state Desired Slate Motive power comrpowrer Support System Supp Sys dw9 3
10 3FE58 ESW B RHR ROOM COOLING COIL F M-315, SHT 4 R3-NWA NMR 3
S 9145 5570 PASSIVE 3FE058 POO Reacto Okla - LU3 NWA NM N7 Sodas 3
10 3GE57 ESW 0 CORESPRAY ROOM COOLING COIL G M-315. SHT 4 R3-12 N/A NIR 3
S 91-6 5583 PASSIVE 3GE057 P80 Reactor BIdg - U3 N/7 NSi M-77 Series 3
10 3GESO ESW D RHR ROOM COOLING COIL 0 M-315. SHT 4 R3-19 WA NMR 3
S 116 6571 PASSIVE 3GE058 POO Reactor 81dg - U3 N/A NRM M-Tt Series 3
10 3HES7 ESW 0 CORE SPRAY ROOM COOLING COIL H M-315, SHT 4 R3-12 NWA NOR 3
S 91-6 584 PASSIVE 3HE057 POO Reactor BIa - U3 N/A NMr M-77 Seris 3
10 3HE58 ESW 0 RHR ROOM COOLING COIL H M-315M SHT 4 R3-N/A NR 3
S 91-6 5572 PASSIVE 3NE058 P80 Reactor Bkdg - U3 NfA NMR W.77 Series 1
10 P030223-1 HPSWHVAC HPSWPUMP ROOM 'W LOOP SUPPLY M-396, SHT 1 PIH-9 OPEN 3
S DAMPER 112 ACTIVE Pump House OPEN 1
10 P030223.2 HPSW HVAC HPSW PUMP ROOM "
LOOP EXHAUST M3gs, SHT 1 P1N-9 CLOSED 3
S DAMPER 112 ACTIVE Pump Houe CLOSED/OPEN 1
10 P030223-3 HPSW HVAC HPSW PUMP ROOM "A, LOOP SUPPLY M-396, SmT 1 PRI-9 OPEN 3
S DAMPER 112 ACTIVE Pump Hot" OPEN 1
10 P030223-4 HPSWHVAC HPSW PUMP ROOM `A* LOOP EXHAUST M-396, SHT 1 P/H-9 CLOSED-3 S
DAMPER 112 ACTIVE pump House CLOSED/OPEN 3
14 30022 EPS-38 3PP8 DISTRIBUTION PANEL 125VDC E-27, SHT I T381 ENERGIZED 38003 38019 3
S 150 8000 ACTIVE 30D022 Tubine Bldg
- U3 ENERGIZED E-16-1-8 3
14 30M23 EPS-3C 3PPC DISTRIBUTION PANEL 125V OC E-27, SHT I T3-81 ENERGIZED 3C003 3CO19 3
S 150 8711 ACTIVE 300023 Turbine Bldg - U3 ENERGIZED E-16-1-6 3
14 30024 EPS-3D 3PPO 125V DC DISTRIBUTION PANEL E-27. SHT 1 13-81 ENERGIZED 3D003 30019 3
S 150 8813 ACTIVE 300024 Turbine 8ldt - U3 ENERGIZED E-16-1-8 3
14 SR ACTIVE 305315 3DS315 EPS-30 BYPASSfISOLATION SWITCH E-29 T3-81 ENERGIZED 30037 150 Turbine Bidg -U3 ENERGIZED Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrr.qnnnrpnr-.m Nn ' RS-1 -173 B-53
DATE: 3128130 PAGE 53 DOCUMENT NO. 006740084-4001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl Equ ID System E"u Desciption Drawkn No.
Loc Coda Norm sum Motive power Support System Una Eval req'd PIMS ID Notes ROB Mother Comp Room SEbv Oed State Canlr power Supp Sys dwg Ltne No FunctioA 3
14 30Y33 EPS-3A 120VAC DISTRIBUTION PANEL E-29 T3-81 ENERGIZED 30X133 3
S ISO 8000 ACTIVE 30Y033 Twbut Bldg - U3 ENERGIZED 3
14 30Y35 EPS-3C 120VAC DISTRIBUTION PANEL E-29 R3-29 ENERGIZED 30X135 3
S 135 8001 ACTVE 30Y035 Reactor Bldg. 1U3 ENERGIZED 3
14 3OYsO EPS-38 120VAC DISTRIBUTION PANEL E.29 T3-81 ENERGIZED 30008 30D37 3
S 150 30X150 8000 ACTIVE 30YOSO Tu*ine BkIg - U3 ENERGIZED 3
14 31017 EPS-31 250 VOLT FUSE BOX E-27. SHT 1 T3-70 ENERGIZED N/A 3BDOI 3
S 135 8609 ACTIVE 380017 Tutbine d9 - U3 ENERGIZED E16-2-6 3
14 33D18 EPS-38 3DPO DISTRIBUTION PANEL, 250V DC E-27. SHT 1 T3-70 ENERGIZED 38D03 3BD17 3
5 135 3DD17 8612 ACTIVE 380018 Tuabine Bklg - U3 ENERGIZED 30D03 EIS-2.6 3
14 38D19 EPS-38 250 VOLT FUSE BOX E-27, SHT 1 T3-70 ENERGIZED MIA 3BD17 3
S 135 8810 ACTIVE 380019 Turbine Bldg - U3 ENERGIZED E16-2-6 3
14 3CD17 EPS-3C 250 VOLT FUSE BOX E-27, SHT I T3-70 ENERGIZED WA 3C001 3
S 135 8708 ACTIVE 3CD01?
Tutine Bg - U3 ENERGIZED E16-2-6 3
14 3C019 EPS-3C 250 VOLT FUSE BOX E-27. SHlT I T3-70 ENERGIZED WfA 3CO17 3
S 135 8709 ACTIVE 3C0019 Turbine Bldg - U3 ENERGIZED E16-2-6 3
14 30D17 EPS-30 250 VOLT FUSE BOX E-27, SHT 1 T3-70 ENERGIZED WIA 30001 3
S 135 8810 ACTIVE 3DD017 Turtie efd - U3 ENERGIZED E16-2-6 3
14 3D019 EPS-30 250 VOLT FUSE BOX E-27. SHT I T3-70 ENERGIZED NWA 30917 3
S 135 8811 ACTIVE 300019 Turbine Bldg - U3 ENERGIZED E16-2-6 3
14 300306 EPS-30 125VDC DIST. PANEL (3PPD)
E-27, SHT 2 T3-172 ENERGIZED 3DO03 3
S 135 8000 ACTIVE 300306 Turbi Bldg - U3 ENERGIZED U3 ONLY??
3 15 3ADO1 EPS-3A "3ABATTERY 125V DC E-27. SliT 1 T3-70 ENERGIZED 3AD03 3
S 135 800D ACTIVE 3ADO1 Tu Oft- - L33 ENERGIZED E-13-34 to 37, 3
15 38001 EPS-3W W38 BATTERY 125V DC E-27. SHlT I T3.169 ENERGIZED 38003 3
S 135 8608 ACTIVE 38D01 Turbine BOdg - U3 ENERGIZED E
6-13-341t*37, Peach Bottom Atomic Power Station Unit 3 B-54 MPR-3812, Revision 3
'fnrrP..nnndnnr.P Nn ' RR-1 9-17.1
DOCUMENT NO. 006740084-0001 REVISION 2 TRAIN SOUG CI Equip ID Ufa Eval reqd?
PIMS ID Lne No Function System Note" Equip Descripon ROB Molw Comp PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Orawki Nix Loc Code Room Ele MontivewF DATE: 31281A6 PAGE 54 N~orm
$tate Desired Stae Support System Su4p Sys dwg 3
15 3C001 EPS-3C "3CBATTERY 125V DC E-27. SHT I T3-70 ENERGIZED 3C003 3
S 135 8707 ACTIVE 3CD000 TwLodeBldg - U3 ENERGIZED EE.13-34 to 37.
3 is 30D01 EPS-3D.
3D BATTERY 125VDC E-27, SHT 1 T3-169 ENERGIZED 3DD03 3
135 8109 ACTIVE 300001 Tuwbbne Bdg - U3 ENERGIZED EE-13-34 to 37.
3 16 30037 EPS-38 STATIC INVERTER E-29 13-74 ENERGIZED 30006 3
SR 135 8000 ACTIVE 30D037 Turble Bldg - U3 ENERGIZED 62O0-E45 3
16 3AD03 EPS-3A 3A 125V STATION BATTERY dHARGER E-27. SHT 1 T3-170 ON 30B59(N) 3 S
135 8000 ACTIVE 3AD003 Tubne Bldg. U3 ON 20859(A)
NE-102 3
16 38D03 EPS-38 38CB BATTERY CHARGER 125V DC E-27. SHT I T3-171 ON 30650 3
S 135 8611 ACTIVE 3803 Turbk* Bg - U3 ON NE-102 3
16 3CD03 EPS-3C 38CC BATTERY CHARGER. 125V. DC E-27. SHT 1 T3-170 ON 30038(N) 3CS456 3
S 135 30S704 8710 ACTIVE 3CD003 Turbine Bldg - U3 ON 00849(A)
NE-102 3
16 30003 EPS-30 3BCD BATTERY CHARGER, 125V OC E-27, SHT 1 1T3.172 ON 30839(N) 305709 3
S 135 8812 ACTIVE 30D003 Turb=ie BMd.- U3 ON 0085&(A)
NE-102 3
16 30C87 EPS HPCI INSTRUMENT RACK R3.15 ENERGIZED WA 3
S 088 8000 ACTIVE 30C0B7 Reactor Bg - U3 ENERGIZED NIA M-1-EE-180, M-580 3
18 30C95 EPS RCIC INSTRUMENT RACK R3-15 OPERABLE N/A 3
S O88 8000 ACTIVE 30Co95 Reactor Bwg. U3 OPERABLE NIA MI-EE-188 3
16 3AC65 EPS RPS INSTRUMENT RACK R3-40 OPERABLE NIA 3
S 165 8000 ACTIVE SACOBS Reactor Bldg - U3 OPERABLE N/A M-l-tEE-168, M-1-EE-170 3
18 3AC91 EPS JET PUMP INST RACK A R3-81 OPERABLE N/A 3
S 135 0ooo ACTIVE 3AC091 Reactor BeWg-U3 OPERABLE I&A 3
18 38C65 EPS RPS INSTRUMENT RACK R3.29 OPERABLE WA 3
S 135 8000 ACTIVE 38CO35 Reactor Blg - U3 OPERABLE NIA M-I-EE-168. M-I.EE.170 3
18 38C91 EPS JET PUMP INST RACK 8 R3.29 OPERABLE WUA ACTIVE 8am0 Reactor Sg-U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(,,nrm..*nnnd.nr..
Nn* RS-12-173 B-55
DOCUMENT NO. 006740084)001 REVISION 2 TRAIN SQUG CI Unh Eval rWd?
Line No Funicoti PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Motiv power Cordr power DATE: 3r28196 PAGE 55 Equip ID PIMS tD system Notes Equip Descritipon ROB Modltw Comp, DrawMl No.
Loc Code Room Eev BuSkdd Noom state Desird State S.LIPoit System SuPP Sys dwg I
18 0PS30224-1 HPSW HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-39N. SHT I P'lH-9 OPERABLE 3
S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE PUMP HOUsO OPERABLE 118 OPS30224-2 HPSW HVAC HPSW PUMP ROOM I EXHAUST PLENUM M-396, SHT I Phl-9 OPERABLE 3
DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump Hous OPERABLE 18 OPS3024-3 Hsw HwAC RPSW PUMP ROOM I SUPPLY PLENUM M-39., SHT 1 P/1-OPERABLE 3S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE 1
18 OPS30224-4 HPSW HVAC HPSW PUMP ROOM I EXHAUST PLENUM M-396, SHT I P/H-9 OPERABLE 3
S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE 1
18 L13 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH AY M-3M5, SHT 2 OPERABLE 3
BR VALVE M03-13-041 ACTIVE M03-13-041 OPERABLE I
18 LS3 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH AY M-365, SHIT 2 OPERABLE 3
BR VALVE M03-13-039 ACTIVE M03-13-039 OPERABLE I
18 LS3-23-57 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON M.-359. SHT 2 OPERABLE 3
BR VALVE M03-23-57 ACTIVE M03-23-57 OPERABLE 18 L53-23-56 PROC MON iNST-1 SUPPRESSION POOL LAIT SIVTCH ON M-359, SHT 2 OPERABLE 3R VALVE M03-23-58 ACTIVE M03-23-58 OPERABLE I
18 LS3-23-74 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-9. SlIT 2 T3-55 OPERABLE 3
SR SWITCH 135 ACTIVE Turitne Bldg - U3 OPERABLE,-
1 18 LS3-23-75 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-30%. SHIT 2 T3-55 OPERABLE 3
SR S"WITCH 135 ACTIVE Twuie Bldg - U3 OPERABLE 1
18 LS3-23-91A PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359, SHT 2 R3-111 OPERABLE 3
SR 91-6 ACTIVE Reacto Bldg1. U3 OPERABLE 18 sLS3-23-91B PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359. SHT 2 R3-11 OPERABLE 3
SR 9146 ACTIVE Reactor ldg - U3 OPERABLE 3
18 LT-9027A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365, SHT 2 C-Core Spray OPERABLE 30Y33 S
ACTIVE LT-9W27A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrmr.*nnndp.nr.
Nn* RS-17-173 FOR LR-9027 091 ReactorOft -U3 OPERABLE B-56
DOCUMENT NO. 0117-00084.4001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm slate MoNve power Desired State Contr power DATE: 3r89 PAGE 66 TRAIN Unit SQUG CI Equip ID Eveal req'd?
PIMS ID System Notes Equip Desiton ROB Mot1hr Camp Drawing No.
Loc Code Room Elev Support system Supp Sys *wg Line No Funclion Building 3
18 LT.9027B PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SHT 2 C-Core Spray OPERABLE 30Y50 3
S FOR LI-9027 091 7127 ACTIVE LT-90278 RealorOgf -U3 OPERABLE 3
18 LT-9123A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. StT 2 R3-1 1 OPERABLE 30Y35 3
S FOR L-9123A 091 7128 ACTIVE LT-9123A Reacor Bmtg. U3 OPERABLE I
3 1
LT-91238 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-385, SHT 2 R2.6 OPERABLE 30Y50 3
S FOR LR-91238 091 7130 ACTIVE LT-91238 Reactor Bldg. U3 OPERABLE 3
18 LT-94S3 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309. SHT 2 R3-20 OPERABLE 30Y50 3
N/A TRANSMITER FOR LI-9453 116 7132 ACTIVE LT-9453 Level N Transfer Readcr Bldg - U3 OPERABLE fufion wl be picke Ck Iocfl 1
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 Turbine Bldg -U3 OPERABLE I
18 LT3-13-171 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365. SIT 2 T3-17 OPERABLE 3
SR FOR RCIC INITIATION 116 ACTIVE Turbine Bldg - U3 OPERABLE 3
16 LT3-2-3-61 PROC MON INSTM REACT VESSEL WATER LEVEL M-352, SHT 3 R3-40 OPERABLE 30Y33 3
a TRANSMITTER FOR
.-2-.86 165 7131 ACTIVE LT-3-2-3-061 3ACO05 Reactor Bldg - U3 OPERABLE 18 PS30224-t HPSWHVAC HPSW PUMP ROOM A LOOP M-396. SHT 1 P/H-9 OPERABLE 3
S PRESSURE SWITCH 112 ACTIVE Pump House OPERABLE 118 PS30=24-2 HPSW HVAC HPSW PUMP ROOM B LOOP M1-396. SHT 1 P/H4-OPERABLE 3
PRESSURE SWITCH 112 ACTIVE Pump House OPERABLE 3
18 PT-3508B PROC MON INSTM CONTAINMENT ATMOS ORYWELL M-367, SHT 2 R3-53 OPERABLE 30Y35 3
S PRESS TRANSMITTER FOR PR.3508 195 30M 7139 ACTIVE PT-35068 React"or
. U OPERABLE U
M-367. E-17-55.56 3
18 PT-5S05 PROC MON INSTNI ORYWELL PRESSURE TRANSMITTER
"-387. SHT 2 R3-21 OPERABLE 30Y50 3
S FOR PR-5805 116 7140 ACTIVE PT-5805 Reactor Bldg U3 OPERABLE 3
18 PT-9102A PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-3S1. SHIT 3 R3-40 OPERABLE 30Y35 f
3 B
FOR PR-9io2A 165 7136 ACTIVE PT-9102A 3AC065 Reactor Bldg -U3 OPERABLE 3
18 PT-9102C PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-361, SHT 3 R3-40 OPERABLE 30Y35 B
ACTIVE FOR PR 902A 3ACOSS 165 React" Bd -U3 OPERABLE 7135 PT4102C Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrrpqnnndpnno. No
- RS-12-173 B-57
DOCUMENT NM 006740084-OOO1 REVISION 2 TRAIN SQUG CI Una Eval reetd?
Line No Functon PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST oraewir NO Room state Motivepower SpotSyste DATE: 3/'A216 PAGE 67 Equip ID POS ID Notes Equip Doesclpon ROB Mother Comp Loc Code Room Elev Sukn 3
18 PT3-2-3-404B PROC MON INSgM REACTOR PRESSURE TRANSMITTER M4352. SHT 4 R3-29 OPERABLE O0Y03 3
a FOR PR3-2-3-404B 135 7138 ACTIVE PT-3-02-3404B 38C065 Reactor Bldg - U3 OPERABLE 3
18 PT3-6-53A PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352. SHT 3 R3-40 OPERABLE 3MY50 3
a TRANSMITTER FOR P13-6-90A 165 7133 ACTIVE PT-36-053A 3ACS5 Reactor Bldg. U3 OPERABLE 3
18 PT3-6-538 PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352, SHT 4 R3-29 OPERABLE 30Y50 3
8 TRANSMITTER FOR P13-6-108 135 7134 ACTIVE PT-3B04M8 38C65 Reacto Bkl - U3 OPERABLE 1
18 TIC30223 HPSW HVAC HPSW PUMP ROOM EXHAUST TEMP M-39.S SHT I PMH-9 OPERABLE 3S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE 1
18 TIC30224-1 HPSW HVAC HPSW PUMP ROOM "A LOOP TEMP M-396, SHT I P1H-9 OPERABLE 3
S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE 18 TIC30224-2 HPSW HVAC HPSW PUMP ROOM W LOOP TEMP U-349. SHT 1 PIN-9 OPERABLE 3S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE I
18 TT30223 HPSW HVAC HPSW PUMP ROOM EXHAUST m44.W, SHT 1 P1H-9 OPERABLE 3S TEMPERATURE TRANSMITTER 112 ACTIVE Pump House OPERABLE 3
20 308324 EPS1 M03-23-015 MOTOR CONTROL POWER T34-7 OPERABLE NIA 3
S TRANSFER SWITCH 135 8000 ACTIVE 308324 Turbing Bldg - U3 OPERABLE NIA U3 ONLY??
3 20 30CO03 EPS REACTOR AND CONTAINMENT COOLING T3-100 OPERABLE NIA 3
S AND ISOLATION 165 8000 ACTIVE 30C003 Turbtn Bfdg - U3 OPERABLE WA 3
20 30C004C EPS RCIC VERTICAL BOARD T13-100 OPERABLE NIA 3
S 165 8000 ACTIVE 30C004C Tuobin* Blg. -U3 OPERABLE N/A 3
20 30C0O5A EPS REACTOR MANUAL CONTROL PANEL T3-100 OPERABLE WA 3
S 165 8000 ACTIVE 30C005A Turbne Bldg - L13 OPERABLE N/A 3
20 30C008C EPS MAIN CONTROL ROOM CONSOLE 13-100 OPERABLE WA B
ACTIVE 30C006C Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr.*nnndAnrP. Nn - RS-12-173
=0005A 165 Tur*e Bldg - U3 OPERABLE NIA B-58
DATE: 32/8 DOCUMENT NO. 00674008440D01 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 68 O2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl Equip ID System Equip Desciptmon Drawing NA Loc Code Morm dew Moaie Power Support System Unit Evalmreqd?
PUAS 1D Notes ROB Mohw Comp Room Elev Desird State Contr power Supp Sys "0 LineNo Function Bdng 3
20 30C012 EPS PLANT SERVICES CONSOLE T3-100 OPERABLE N/A 3
S 165 e000 ACTIVE 30C012 Tubie Bldg. U3 OPERABLE WA E-17.4122 3
20 3OC124 EPS CRT AND RFPT TEST PANEL 13.100 OPERABLE WA 3
S 165 8000 ACTIVE 30C124 Turbine Bldg. U3 OPERABLE NIA 1
20 30C139 HPSW HVAC HPSW PUMP ROOM LOCAL CONTROL E202 Ph"-4 ENERGIZED B61 3
S PANEL 112 ACTIVE Pump House ENERGIZED 3
20 30C32 EPS ENGINEERING SUB SYSTEM I RELAY T3-81 OPERABLE N/A 3
S CABINET ISO 8000 ACTIVE 30C032 Turbine 6klig. U3 OPERABLE NIA S.119811-3. M-1-EE-241 3
20 30C33 EPS ENGINEERING SUB SYSTEM II RELAY T31381 OPERABLE N/A 3
S CABINET 150 amc0 ACTIVE 30C033 Turbine Bg9 - U3 OPERABLE N/A S-i 198/I-3. M-1-EE-24t 3
20 30C34 EPS RCIC RELAY PANEL T3-81 OPERABLE NA 3
S 150 8000 ACTIVE 30C034 Turbine Bd9 - U3 OPERABLE NIA S-1198/1.3. M-1-EE-84-24 3
20 30C39 EPS HPCI RELAY CABINET T3-81 OPERABLE NIA 3
S 150 a000 ACTIVE 30C039 Tune Bldg - U3 OPERABLE N/A 8-1196/1-3. M-1 -EE-96 3
20 30C722A EPS ACCIDENT MONITORING T3-81 OPERABLE NIA 3
S INSTRUMENTATION PANEL 10 6O00 ACTIVE 30C722A Turbine Bld -g U3 OPERABLE N/A S-1198/1-3, M-1-EE-406 3
20 30C722B EPS ACCIDENT MONITORING T3-81 OPERABLE NZA 3
S INSTRUMENTATION PANEL ISO 800 ACTIVE 30C722B Turbine Bldg. U3 OPERABLE NIA S-1198/1-3, M-1-EE-405 3
20 30O41 EPS HPCI GLAND SEAL CONDENSER VACUUM R3.13 OPERABLE NIA 3
S PUMP STARTER 0S8 8000 ACTIVE 30D041 Reactor Bdg - U3 OPERABLE NIA 3
20 30D42 EPS HPCI GLAND SEAL CONDENSER VACUUM R3-13 OPERABLE NIA 3
a PUMP STARTER 088 a000 ACTIVE 300042 30041 Reactor Bldg -U3 OPERABLE NUA 3
20 30043 EPS HPCI AUX LUBE OIL PUMP STARTER R3.13 OPERABLE NIA 3
B 088 8000 ACTIVE 200043 30D41 Reactor Bldg -U3 OPERABLE NIA U?2ONLY??
20 30S37-PANEL HPCI 1W3 HPCI TURBINE R3-13 OPERABLE NIA 3
S O6 ACTIVE 30S037 - PANEL Reactor Bkdg -U3 OPERABLE NIA M-36a Peach Bottom Atomic Power Station Unit 3 B-59 MPR-3812, Revision 3 Cnrr.*nnndP.nrA. No " RS-19-173
DATE: 3421M96 DOCUMENT NO. 00674=04-4001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 59 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID System Equip Desalptlon DTawnIg No.
Loo Code Non State Motive power Suppoll System unk Eva] rfld?
PUAS ID NK01s ROB MOW Comp Room Eev Desked Ste Cona power S&Wp Sys dwg Lill No Funidin Buddng 3
20 3AC265 EPS RESERVOIR FLOW PUMP SAY MO03804A ECT-1 OPERABLE NIA 3
S 114 sow ACTIVE 3AC265 E-er Coo OPERABLE A
Tower 62A-0-117.49-3 3
20 3AC272 EPS HPCI STEAM LEAK DETECTION CABINET T3-100 OPERABLE NIA 3
S 165 80a0 ACTIVE 3AC272 Ttbmte Bldg - U3 OPERABLE WIA M241-10 3
20 3aC265 EPS RESERVOIR FLOW PUMP BAY MO.3804B ECT.1 OPERABLE NWA 3
S 114 8000 ACTIVE 3SC265 Emergency Cooing OPERABLE NIA Tower 62A-O-117-49-3 3
20 38C272 EPS HPCI STEAM LEAK DETECTION CABINET T3-100 OPERABLE WIA 3
S 165 8000 ACTIVE 3BC272 Turbine Bldg - U3 OPERABLE NWA M241-10 3
20 U-9027 PROC MON INSTM TORUS WATER LEVEL M-365. SHT 2 T3-100 OPERABLE 30Y33 LT-90278 3
ER 165 7101 ACTIVE LI-9027 30C003 Twbirin Bidg - U3 OPERABLE 3
20 LI-9123A PROC MON INSTM.
WIDE RANGE SUPPRESSION POOL M-365. SHT 2 T3-100 OPERABLE 30Y35 LT-9123A 3
OR LEVEL INDICATOR 165 7100 ACTIVE LI-9123A 30C003 Tuwbne Bdg - U3 OPERABLE 3
20 Ll-9453 PROC MON INSTM CST LEVEL INDICATOR M-3. SHT 2 T3-100 OPERABLE 30Y50 LT-9453 3
BR 165 7102 ACTIVE L-9453 30C004C Tuwbne Bldg - U3 OPERABLE 3
20 LO3-2-3-113 PROC MON INSTM REACTOR WATER LEVEL M-352. SlIT 6 T3-100 OPERABLE 30Y50 LT3-2-3-113 3
BR 165 7103 ACTIVE 1.14-3-0234113 30C003 Tubkne Bldg - U3 OPERABLE 3
20 L13-2-3-85A PROC MON INSTM REACTOR VESSEL HIGH WATER M-352. SHT 6 13-100 OPERABLE 30Y35 LT3-2-3-72A OR 73A 3
OR 165 7104 ACTIVE LI-3-02-3.085A 30COOSA Tutbine Bldg - U3 OPERABLE 3
20 L13-2-3-858 PROC MON INSTM REACTOR VESSEL HIGH WATER M-352. SHT 6 T3-100 OPERABLE 00Y03 LT3-2-3-72B OR 738 3
BR 165 7105 ACTIVE 1.-3-02-3-065B 30C006A Turwike B
- U3 OPERABLE 3
20 LI3-2-3-8B PROC MON INSTM REACTOR VESSEL HIGH WATER MU-=2. SlIT 3 T3-100 OPERABLE 30Y33 LT3-2-3-61 (C65A) 3 OR 165 7106 ACTIVE LI-3-02-3086 30COM Tuwbine Bldg - U3 OPERABLE 3
20 LR-9027 PROC MON INSTM TORUS WATER LEVEL RECORDER M-365. SHT 2 13-100 OPERABLE 30Y33 LT-O27A 3
OR lBS 7107 ACTIVE LR-9027 30C003 Tbin Bldg - U3 OPERABLE 3
20 LR-91238 PROC MON INSTM TORUS WATER LEVEI/TEMPERATURE M-365, SHT 2 13-100 OPERABLE 00Y03 LT-91238 3
BR RECORDER 165 7108 ACTIVE LRITR-91238 30C0D3 Turbmn Bldg. U3 OPERABLE Peach Bottom Atomic Power Station Unit 3 8-60 MPR-3812, Revision 3 C'nrrp*nndi.nrp..
No
DOCUMENT NO. 0067-000U-OC01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 312MM PAGE 60 Nomn state Motve *,
SWpW System Deshwd State Cr Supp Sys *,g TRAIN SQUG Cl Equi ID Eva[ reqtd?
PIMS ID System Notes EQu Descrl"M ROB Mothet Comp Orawang No.
Loc Code Room Elv Lkie No Functon BihQ 3
20 LR3-2-3-110A PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352. SlIT 6 T3-100 OPERABLE 3OY35 LT3-2-3-72C OR 73C 3
BR 165 7109 ACTIVE LR-34.2.3-1i1A 30CO04C Trbine Bdg - U3 OPERABLE 3
20 LR3-2-3-1108 PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352. SHIT 6 T3-100 OPERABLE 0DY03 LT3.2-3-72D OR 73D 3
OR 165 7110 ACTIVE LR-3-02-3-1108 30C0O3 Tbina Bldg -U3 OPERABLE 3
20 P14.90A PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-352= SHT 3 T3-100 OPERABLE 30Y50 PT3-6-53A 3
BR 165 7111 ACTIVE PI-3-064OOA 30CO0SA Turbe Bldg. U3 OPERABLE 3
20 PK34-S0B PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-352. SHT 4 T3-100 OPERABLE 30(Y50 PT3-6-538 3
BR 165 7112 ACTIVE PI-3-,6-0908 30C005C Tbffle 61dg -U3 OPERABLE 3
20 PR-350 PROC MON INSTM CONTAIN ATMOS ORYWELL PRESS M-367. SHT 2 T3-100 OPERABLE 30023 PT-35068 3
BR 165 30Y35 7113 ACTIVE PR-3508 30C003 Tabkne Bld -U3 OPERABLE 3
20 PR-5005 PROC MON INSTM CONTAINMENT PRESSURE M-367. SHT 2 T3-100 OPERABLE 30Y50 PT-50 3
BR 165 7114 ACTIVE PR-SOD0 30C013 Tutbin klg - U3 OPERABLE 3
20 PR-9102A PROC MON INSTM ORMWELL PRESSURE RECORDER M-361. SHT 3 T3-100 OPERABLE 30Y35 PT-9102A 3
OR 165 1
PT-9102C 7115 ACTIVE PR-9102A 30C003 Tubkoel l
- U3 OPERABLE I
3 20 PR3-2-3-404A PROC MON INSTM REACTOR PRESS/RPV WATER LEVEL M4-352. SHT 3 T3-100 OPERABLE 30Y35 PT3-2-3-404A 3
BR 165 7116 ACTIVE PRLR-3-02-3-404A 30C004C Tuibine 5Mg - U3 OPERABLE 3
20 PR3-2-3.4048 PROC MON INSTM REACTOR PRESSURE M-352. SHT 4 T3-100 OPERABLE O0Y03 PT3-2-3-4048 3
BR 165 7117 ACTIVE PR-302-3-404B 30CO03 Turbiner g - U3 OPERABLE 3
20 PR-%"
PROC MON INSTM REACTOR LEVEL/STM FLOW RATIO M-352 SHT 6 T3-100 OPERABLE 30Y50 PT3-6-105 3
BR 165 7110 ACTIVE PRULR-3-06-096 30CODSA TuineB elg -U3 OPERABLE 3
20 TIS-3-2-71A PROC MON INSTM TORUS WATER TEMPERATURE M-361, SNT 4 T3-100 OPERABLE 30Y35 TE3-2-71A1 THRU 3
OR INDICATING SWITCH 165 TE3-2-71Ni 7123 ACTIVE TIS-3-02-071A 30C124 Tutne Bldg. -U3 OPERABLE 3
20 TIS-3-2.718 PROC MON INSTM TORUS WATER TEMPERATURE M-361. SHT 3 T3-100 OPERABLE 00Y03 TE3-2-71A2 THRU 3
BR INDICATING SWITCH 1651 TE3-2.71N2 7124 ACTIVE TLS-3-02.0718 30C124 Turbim 0B9g
- U3 OPERABLE 1
21 30E105 HPCI HPCI TURO LUBE OIL COOLER (23-2)
M-366, SlIT 4 R3-13 OPERABLE N/A 3
B 3212 PASSIVE 30E05 6/18/94 O88 Reactor 0kO - U3 OPERABLE N/A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 onrr..nond.nrl.. Nn
- RS-19-173 Vendfor Owg 210MASMA3 B-61
DATE: 3W28n9 DOCUMENT NO. 006740084-4OMl PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 61 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG C Equi ID System Equip Desciption Drwivng No.
LoG Code Norm Sta Moie power Support System unit Evl rectd?
PIMS D Not" ROB Mote Cornp Rorn Elly DiredSft Coor, power Supp Sys dwg Life No Function Buitftn 1
21 30E33 HPCI HPCI GLAND SEAL CONDENSER (23-2)
M-3M8. SHT 4 R3-13 OPERABLE WA 3
S O88 3210 PASSIVE 30E033 Reactor
- U3 OPERABLE WA j
1 21 30T!0 RCIClHPCI CONDENSATE STORAGE TANK M-30M.
SHT 2 amB OPERABLE WA 3
NIA 116 3115. 3223 PASSIVE 30TO10 A Cooling Tower OPERABLE WA 3
21 3AE124 ESW "3A RHR PUMP SEAL COOLER M-315. SHT 4 R3-5 NWA NIR 3
a 091 5573 PASSIVE 3AE124 3AP35 Reactor B dg-U3 WA NCR 2
21 3AE24 RHR-C RHR HEAT EXCHANGER A "I-31, SHT 3 R3-16 WA NIA 3
S 091 4307. 5605 PASSIVE 3AE024 Reactor Bldg -U3 OPERABLE WA M.1.H-4-7, M-.144-12-5.
3 21 3AS377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333. SHT 2 R3-23 OPERABLE WA 3
S 135 6102 PASSIVE 3AS3?7 Reactor Bldg -U3 OPERABLE WA 1-1788-5 3
21 3AT540 SRV INSTRUMENT H2 ACCUMULATOR FOR M-351. SHT 3 01W3-27 OPERABLE WA 3
S RV-71A 154 2102 PASSIVE 3AT540 Drywael -U3 OPERABLE WIA M-3237 3
21 3AT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351, SHT 3 0/W3-27 OPERABLE WA INSTAR.
N2 3
s RV.71A 154 2101 PASSIVE 3AT545 Drywae -U3 OPERABLE IVA M-68-.,M-333 3
21 38E124 ESW
- 3 RHR PUMP SEAL COOLER M-315, SHT 4 R3-6 NWA N/R 3
B 091 5574 PASSIVE 38E124 38P35 Reactor Bldg - U3 N(A NIR 1
21 38E24 RHR-O RHR HEAT EXCHANGER B M-361, SHT 4 R3-18 NWA WA 3
5 091 4409.5607 PASSIVE 38E024 Reactor Bidg - U3 OPERABLE WA M-.14,-4-7, M-1-4-.12-S.
3 21 38S377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-.333. SLIT 2 R3-23 OPERABLE NWA 3
S 135 6103 PASSIVE 385377 Reactor 9dg
-U3 OPERABLE WA M..1786-5 3
21 3ST540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 OND3-27 OPERABLE W/A 3
RV-71B 154 2108 PASSIVE 38T540 Orywell -U3 OPERABLE WA M-3237 3
21 3ST545 SRV INSTRUMENT N42 ACCUMULATOR FOR M-351. SHT 3 DOW3-27 OPERABLE WA J INSTR. #42 3
S RV-7Ia 154 2107 PASSIVE 3BTS45 UDy
-U3 OPERABLE WA M-333 3
21 3CE124 E5W "3C" RHR PUMP SEAL COOLER M-315, SKT 4 R3-7 MIA N/R 3
B 091 5575 PASSIVE 3CE124 3CP35 Reactor Bldg -U3 WA N/R Peach Bottom Atomic Power Station Unit 3 B-62 MPR-3812, Revision 3 C'nrrp.-;nnndrlnrp. Nn
- R5-1l9-173
DATE: 3128/9=
DOCUMENT NO. 0067 840-60001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 62 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG Cl Equip ID System Equp Descripion Drawkn NO, Loc Code Nsrm state Motive power suppor System Eval reqd?
PIUS ID Noes RO8 Motti Camp Room Elev Desired State Con* power Supp Sys dwg Line No Function BuL" 2
21 3CF24 RHR-C RHR HEAT EXCHANGER C M-361. SHT 3 R3-17 OPERABLE WA 3
S 091 4306, $6 PASSIVE 3CE024 Reactor Bldg - U3 OPERABLE N/A U-i 4"1-4-7. U-I 4-1-2-5.
3 21 3CS377 BACKCUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333. SHT 2 R3.23 OPERABLE N/A 3
S 135 6104 PASSIVE 3CS377 Reactor l9.LU3 OPERABLE N/A 11.1786-5 3
21 3CT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 OJW3-27 OPERABLE N/A T
3 S
RV.71C 154 2114 PASSIVE 3CT540 Drywell -U3 OPERABLE N/A M-3237 3
21 3CT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 D1W3-27 OPERABLE N/A INSTR. N2 3
S RV-71C 154 2113 PASSIVE 3CTS45 Drywe - U3 OPERABLE N/A U-333 3
21 3DE124 ESW 3D RHR PUMP SEAL COOLER M-315. SHY 4 R3-8 N/A N/R 3
B 091 5576 PASSIVE 3DE124 30P35 Reac8tor1g - U3 N/A N/R 1
21 30E24 RHR-D RHR HEAT EXCHANGER D M-361. SHT 4 R3-19 OPERABLE N/A 3
s 091 4407.5608 PASSIVE 3DE024 Reactor Bldg-U3 OPERABLE N/A M-1-H-4-7. M-l-H-12-5.
3 21 3GT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 DAV3-27 OPERABLE N/A 3
S RV-71G 154 2126 PASSIVE 3GT540 Dry"wa - U3 OPERABLE N/A M-3237 3
21 3GT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 DAN3-35 OPERABLE N/A INSTRN2 3
S RV-71G 154 2125 PASSIVE 3GT545 Drywel - U3 OPERABLE N/A M-333 3
21 3KT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-.351, SHT 4 DJW3-27 OPERABLE N/A 3
S RV-71K 154 2136 PASSIVE 3KT540 Dwe - U3 OPERABLE N/A M-3237 3
21 3KT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 DMW3-34 OPERABLE N/A INSTR. N2 3
S RV-71K 154 2135 PASSIVE 3KT5 Dry/wall -U3 OPERABLE WUA M-333 3
0 0-48-506 ESW & HPSW EMERGENCY COOLING WATER PUMP M-330 ECT-2 CLOSED N/A COMMON N/A COPISDISCH CHECKVW 153 5=26 PASSIVE CHK-O4&506 Emergency CoodMng CLOSED N/A Towers 3
0 0AF349 SDG-A - FUEL OIL El D/G FUEL OIL INLET FILTER M-37?. SHT 4 D/G-3 OPERABLE N/A COMMON 9
127 5148 PASSIVE 0AF349 0AG12 Diesel Generator OPERABLE N/A 3
0 0SF349 SDG,8 - FUEL OIL E2 DIG FUEL OIL INLET FILTER M-377. SHT 4 D/G-s OPERABLE N/A COMMON a
127 5248 PASSIVE 0BF349 05G12 Diesel Genertor OPERABLE N/A Peach Bottom Atomic Power Station Unit 3 B-63 MPR-3812, Revision 3 tnrrP.qnnndrnrP.n Nn - RS-19-173
DATE: 3128/96 DOCUMENT NO. 0067-00084-O001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 63 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Eq4ip ID System Equip Desipion Drawing No.
Lac Code Noam sat Motive power Support Systm Ung Eval recfd?
PIMS ID Notes ROB Mother Camp Roop Elev Contr power SP Sys dwg Line No Fuancion Buing 3
0 0CF349 SDG-C - FUEL OIL E3 0/G FUEL OIL INLET FILTER M-377. SHT 4 01G-7 OPERABLE N/A COMMON 8
127 5348 PASSIVE OCF349 OCGi2 Diesel cenersw OPERABLE N/A 3
0 0DF349 SOGO - FUEL OIL E4 D/G FUEL OIL INLET FILTER M-377, SHT 4 D/G-8 OPERABLE N/A COMMON a
127 5448 PASSIVE 0DF349 ODG12 Diesel Generatr OPERABLE NtAo 3
0 52C-10075A SDG-A - STARTING El D/G STARTING AIR RSVR (AUTO)
M-377, SHT I D/G-3 OPERABLE N/A COMMON N/A AIR 0BT095 INLET CHECK 127 5101 PASSIVE C)J-O-52C-10075A oies, Generator OPERABLE N/A 3
0 52C-100758 SDG-B-STARTING E2 DIG STARTING AIR RSVR (AUTO)
M-377, SHT i D/G-5 OPERABLE N/A COMMON N/A AIR 00T095 INLET CHECK 127 5201 PASSIVE CHK.O-52C-100758
'Diesel Generator OPERABLE N/A 3
0 52C-10075C SDG-C -STARTING E3 DIG STARTING AIR RSVR (AUTO)
M-377. SHT I DfG-7 OPERABLE NIA COMMON N/A AIR 0FT095 INLET CHECK 127 5301 PASSIVE CHK.O.52C-10075C Die Generator OPERABLE N/A 3
0 52C-100750 SDG-O - STARTING E4 DIG STARTING AIR RSVR (AUTO)
M-377. SHlT I O/G-9 OPERABLE N/A COMMON N/A AIR OHTOSS INLET CHECK 127 5401 PASSIVE CHKO-52C-100750 Diesal Generator OPERABLE NA 3
0 BS-52D-0570A SOG-A-FUEL OIL El DiG FUEL OIL PUMPS SUCTION M-377. SHT 4 D/G-3 OPERABLE NIA COMMON a
STRNR 127 5145 PASSIVE BS-0570A GAG12 Diesel Generator OPERABLE N/A 3
0 BS-52D-0O708 SDG-B -FUEL OIL E2 ODG FUEL OIL PUMPS SUCTION
.M-377, SHT 4 D/G-5 OPERABLE N/A COMMON a
STRNR 127 5245 PASSIVE 8S-05701 08G12 Diesel Generator OPERABLE N/A 3
0 BS-52D-0570C SDG-C - FUEL OIL E3 DIG FUEL OIL PUMPS SUCTION M-377. SHT 4 D/G-7 OPERABLE N/A COMMON a
STRNR 127 5345 PASSIVE BS-0570C OCGI2 Diesol Generator OPERABLE NIA 3
0 BS-520-06700 SO"-0 -FUEL OIL E4 D/G FUEL OIL PUMPS SUCTION M-377, SHit 4 0/0-9 OPERABLE N/A COMMON 8
STRNR 127 5445 PASSIVE BS-05700 0DG12 Otesel Generator OPERABLE N/A 3
0 CHKNO36B-17977 HVAC SECORY VA INNER CHK 0BV035 OAV034 +
M-399, SHT 4 RAN-32 OPEN N/A COMMON WA 08V034 FANS PO WS 165 5911 ACTIVE CHK-0-361-17977 Radwaste Bldg CLOSED N/A 3
0 CHKO-368-17991 HVAC PRI IZA INNER CHK TO 0OV035 GAV034 +
M-399. SHT I R/W-32 OPEN N/A COMMON N/A 08VO34 FANS POWS 165 5904 ACTIVE CHK-0-368-17991 Rpadwste Bldg CLOSED N/A 3
0 CHKO-36B-18056 IVAC B/U YA INNER CHI W FOR 0(A.B)V034 M-399, SHT I RNV-32 OPEN N/A COMMON N/A INLET*OUT OMPRS 165 ACTIVE CHK-O.36B-18056 Radwaste Bldg CLOSED N/A Peach Bottom Atomic Power Station Unit 3 B-64 MPR-3812, Revision 3 C'nrrm.qnnndP.nr.m Nn
- RR-1 -17.
DOCUMENT NO. 006?4'084000 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3123196 PAGE 4
Norm state Matow power Suppor System Deskc State Corr poerI stpp Sys "wg TRAIN SOUG Cl Equip fD Eval rmq'd PIMS ID Noles Equip De-m0 ROB MoWr COmp Drawng No.
Loc Code Room Elev Lin NO Functin Buing 3
0 N/A SDG-A DIESEL 'A EXHAUST SILENCER M.377, SHT 5 01"-3 OPERABLE WA COMMON S
127 5149 PASSIVE Diesel Generator OPERABLE WA Vendor 11914759 3
0 WA SOG-8 DIESEL SB EXHAUST SILENCER M-377. SHT 5 ow OPERABLE NIA COMMON S
127 5249 PASSIVE Generator OPERABLE WA Vendor 11914759 3
0 WA SDG-C DIESEL
" EXHAUST SILENCER M-377, SHT S D0G-7 OPERABLE WA COMMON S
127 5349 PASSIVE Diesel Generator OPERABLE WA Vendor 11914759 3
0 WfA 50G-D DIESEL Dr EXHAUST SILENCER M-377. SHT 5 010 OPERABLE N/A COMMON S
127 5449 PASSIVE Diesel Generator OPERABLE WA Vendor 11914759 3
0 RVO416B40779 HVAC INSTR AIR RELIEF VALVE FOR M-399, SHT 4 RIW-32 CLOSED WA-COMMON a
P04)-4W4)01-01+=10201 165 5923 PASSIVE RV-O-368-00779 PO-O-40W-4
-001.O 100031-02 Radwaslte Olg CLOSED WA 3
0 RV0-368-0O780 HVAC INSTR AIR RELIEF VALVE FOR M-399. SHT 4 RNW-32 CLOSED WA COMMON B
PO-O4)--
-01*0003242 165 5925 PASSIVE RV-O-361-00780 PO-O,4N-00032.01 100032-02 Radwaste Bldg CLOSED WA 3
0 RVA-36B-0081 4
WVAC INSTR AIR RELIEF VALVE FOR M-399. SlIT 4 RJW-32 CLOSED WA COMMON B
PO-0-4OW-00025-01+0002602 165 5C O
PASSIE RV-0-368-00784 P0-40WX000256.1100025-02 Redwasle Bldg CLOSED WA 3
0 RV-36B082 hISTR AIR RELIEF VALVE FOR M4-399, SHT i RAW-32 CLOSED IWA COMMON a
P0 00-O 0i-01+00019*02 165 5919 PASSIVE RV-)-36B-00812 PO4)0AW-00019-01 *0019-Q2 Radwaste 8Qdg CLOSED WA 3
0 RV0-368.0*13 HVAC INSTR AIR RELIEF VALVE FOR M-399, SHT 1 RNW-32 CLOSED WA COMMON B
PO-O-40W-020-OI 40002002 165 5920 PASSIVE RV-O-365.0813 PO-O-4W-00020-1 10002,002 Redwaste Bldg CLOSED NWA 3
0 RVO-36B-00*14 HVAC INSTR AIR RELIEF VALVE FOR M-9. SHT 4 RNW-32 CLOSED WA COMMON B
PO-0-40W4X00-01+009S202 165 5921 PASSIVE RV-0-368-00814 PO-0-40WQN0026..1 100026-02 Radwaste Bld CLOSED WA 3
1 00849 EPS 480 V TURBINE AREA MCC 00849 E-1621 12-172 ENERGIZED 2081222 COMMON S
(E324-T-B) 135 8000 ACTIVE 00849 Turblne B9 -U2 ENERGIZED E-I 1-50 3
1 00350 EPS 480 V TURBINE AREA MCC 00950 E-1621 T3-172 ENERGIZED 2081322 I
COMMON S
(E424-T-8) 136 8000 ACTIVE 00850 Turbine Bldg-U2 ENERGIZED E-l1-51.E-11-197 3
1 00B53 EPS 480 V El DIG MCC 00953 (E124-D-A)
E-1619 01G-4 ENERGIZED 2081021 COMMON S
8000 ACTIVE 127 Diesel Generator ENERGIZED E-1l-108 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 ConrrF-.nnndPnr-.n Nn
- R;-19-17.3 B-65
DATE: 3128r);
PAGE 65 DOC1UMENT NO& 0067-00014-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LiST REVISION 2 TRAIN Unit SOUG CA Equip ID Eval reqd?
PIMS ID System EqDescrn ROB Morner Comp Loc Code Room Elev Nom sle Motive power Desired State Coam power Support System Supp Sys dwg 3
1 00854 EPS 480 V E2 DIG MCC 00854 (E234-D-A)
E-1619 O/G-6 ENERGIZED 3081121 COMMON S
127 8000 ACTIVE E234 ENERGIZED E-11-109 3
1 00845 EPS 480 V E3 DIG MCC 00856 (E324-DA)
E-1819 DfG-8 ENERGIZED 2081221 COMMON S
127 8000 ACTIVE E324 Diesel Generator ENERGIZED E.11-106 3
1 00858 EPS 480 V E4 DIG MCC 00856 (E4344)-A)
E-1619 D0G-10 ENERGIZED 3081321 COMMON S
127 8000 ACTIVE E434 Diesel Generator ENERGIZED E-11-107 3
1 00o61 EPS 480 V PUMP STRUCTURE MCC 00861 E-1621 U.2 ENERGIZED 2081122 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 00862 pump House ENERGIZED E-10-31 3
1 00897 EPS 480 V MCC 00897 (EI3A4-EC-A)
E-1627 ECT-3 ENERGIZED 0089414 COMMON S
153 8000 ACTIVE 00897 Emergency Cootng ENERGIZED Towers E-1 1-161. E-1 1-278 3
1 00898 EPS 480V MCC 00B98 (E23A4-EC-A)
E-1627 ECT-4 ENERGIZED 0089514 COMMON S
153 8000 ACTIVE 00898 Emergency Cooing ENERGIZED Towers E.11.162 3
I 00899 EPS 480 V MCC 00899 (E43A4-EC-A)
E-1627 ECT-6 ENERGIZED 0089614 COMMON S
153 8000 ACTIVE 00899 Emergency Cooling ENERGIZED Towers E-11-163 3
2 00894 EPS 480 V BUS E13A4 E-1827 ECT-3 ENERGIZED 0AX26 0089412 COMMON S
153 8000 ACTIVE 00894 Emergency Cooling ENERGIZED Towers 3
2 00a9412 EPS BREAKER TO E13A4 480 V BUS (LC00894 E-1627 ECT-3 CLOSED 00894 COMMON BR 153 8000 PASSIVE E-73 (9412) 00894 Emergency Cooling CLOSED Towers 3
2 0089413 EPS BREAKER TO EMERG. CLG. TOWER E-1627 ECT-3 OPEN 00894 COMMON BR FAN 081K32 153 8000 ACTIVE E.321(9413) 00894 Emergency Cooling OPENICLOSED Towers 3
2 0089414 EPS BREAKER TO 480 V MCC 00897 E-1627 ECT-3 CLOSED 00894 COMMON BR (13,A-EC-A) 153
[
8000 PASSIVE E,67(9414) 00894 Emergency Cooling CLOSED Towers 3
2 COMMON S
00895 EPS 480 V BUS E23A4 E-1627 ECT-4 153 Emergency Cooling Towers ENERGIZED 00BX26 0089512 ENERGIZED 8=0O ACTIVE 00895 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(.nrrpmnndp.nnr.. Nn - RR-19-17.'
B-66
DOCUMENT NO. 006"-00084-001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state MOtive power Desied State CiofhPower*
DATE3,289r6 PAGE 66 REVISION 2 TRAIN SOUGCCI E44 10 Eval reld?
PLIMS ID System Equ* Descdgton ROB Mother Camnp Drawkig No.
Loc Code Room Elev Slpport Systemn Supp Sys dwg Line NO Function BuIIdMI 3
2 0089512 EPS BREAKER TO E23A4 480V BUS (LC00895 E-1627 ECT-4 CLOSED 00895 COMMON BR 153 8000 PASSIVE E-73 (9512) 00B95 Emergen Cooling; 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) 0089M Emergency Cooi OPENICLOSED Towers 3
2 00O9514 EPS BREAKER TO 480 V MCC 00198 E-1627 ECT-4 CLOSED 00895 COMMON BR (23A4-EC.A) 153 8000 PASSIVE E-67(9514) 00895 Emergency Cooli CLOSED Towers 3
2 00B96 EPS 480 V BUS E43A4 E.1627 ECT-5 ENERGIZED 0CX25 0089612 COMMON S
153 8000 ACTIVE 00898 Emergency Cooing ENERGIZED Towers 3
2 0089612 EPS BREAKER TO E43A4 480 V BUS (LC00896 E-1627 ECT-5 CLOSED 00896 COMMON OR 153 8000 PASSIVE E-73 (98612) 00896 Emergency Cooling CLOSED Towers 3
2 0089513 EPS BREAKER TO EMERG. CLG. TOWER E-1627 ECT-5 OPEN 00896 COMMON BR FAN 0CK32 153 SO00 ACTIVE E-321(9613) 00896 Em*,gency Coi OPENICLOSED Towers 3
2 0089614 EPS BREAKER TO 480 V MCC 00899 E.1627 ECT-5 CLOSED 00896 COMMON BR (43A4-EC.A) 153 8000 PASSIVE E-67(9614) 00898 Emergency Coolig CLOSED Towers 3
3 20A1603 EPS-2 BREAKER TO A EMER SERV TRn PP E-6 T2-71 OPEN 20A16 COMMON BR 0AP57 135 8203 ACTIVE E22 (1603) 20A16 Turne Blg - U2 CLOSED 20022 2BD30 6
3 3
20A1609 EPS-2B BKR TO EMERG. SERV. WATER E-8 T2-71 OPEN 20A16 COMMON BR BOOSTER PUMP (0AP163) 135 8207A ACTIVE E22(1609) 20A16 Tutine Bld - U2 OPEN/CLOSED 20022 280306 3
3 20A1706 EPS-2C BREAKER TO B EMERG SERV WATER E-8 12-170 OPEN 20A17 COMMON BR PUMP 0BP57 135 8305 ACTIVE E32 (1706) 20A17 Turbine Bldg. U2 CLOSED 30023 3
3 20A1709 EPS-2C E232 8KIR TO EMERG, SERV. WATER E-8 T2-170 OPEN 20A17 COMMON BR BOOSTER PUmP (08P163) 135 8307A ACTIVE E32 (1709) 2DA17 Turtw eBldg - U2 OPENICLOSED 30023 3
4 00X103 EPS PANEL 00Y03 TRANSFORMER E-28, SHT I RNW-21 ENERGIZED 00850 COMMON S
135 8001 ACTIVE 00X103 Radweste dg ENERGIZED 3
4 OAX26 EPS LOAD CENTER XFMR (0AX26)
E-1627 ECT-3 ENERGIZED 30A1502 COMMON S
80 ACTIVE E-13A4(OAX26) 153 Emergency Cooln ENERGIZED Towers Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(.nrrp.qnnndp.nr.. Nn
- RR-1 -173 B-67
DOCUMENT NO. 0067-0084-0001 REVISION 2 TRAIN SQUG CI Eepo ID unit Eval rec'd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3/25196 PAGE 67 Norm stte Motive power Sq)Pon Syslem Desired State Cotr powr SLIpp Sys do~
system Notes Equ* Descr~iean ROB Mothe Camp Dre"w NO.
Laoc Code Room Eiev Line No Functi R
n 3
4 0BX26 EPS LOAD CENTER XFMR (0BX26)
E-1627 ECT-4 ENERGIZED 30A1609 COMMON S
153 m000 ACTIVE E-23A4(08X26)
Eme-gency Coorng ENERGIZED Towers 3
4 0CX26 EPS LOAD CENTER XFMR (OCX26)
E-1627 ECT-5 ENERGIZED 30A1805 COMMON S
153 8000 ACTIVE E-43A4(0CX25)
Emergency CosWn ENERGIZED 3
5 0AP163 ESW EMERGENCY SERVICE WATER M330 DIG-1 OFF 20A16 20A1609 COMMON S
BOOSTER PUMP A 121 5621 ACTIVE OAP163 Diesel Generalm OFF/ON M-19-14-4 3
5 OAP164 SDG-A - DIESEL El DIG AIR COOLANT AUXILIARY PUMP M-377, SHT 2 0/G-4 OPERABLE N/A COMMON S
COOLING 127 5125 PASSIE sAP164 Generor OPERABLE N/A 3
5 0AP165 SOG-A - DIESEL El D/G JACKET COOLANT STANDBY M-377. SHT 2 D/G-3 OPERABLE N/A COMMON B
COOLING CIRC PUMP 127 5126 PASSIVE 0AO 65 Diesel Generato OPERABLE N/A 3
5 0AP166 SOG-A - DIESEL El DIG JACKET COOLANT AUX PUMP M-377. SIT 2 0/0-4 OPERABLE WA COMMON S
COOLING 127
$124 PASSIVE OAP166 Oiesel Genator OPERABLE NWA Vendor 44O5B120 3
5 OAP17 SOG-A - LUBE OIL El DIG LUBE OIL AUXILIARY PUMP M-377. SHT 3 DIG-3 OPERABLE N/A COMMON S
127 5132 ACTIVE OAP16?
Diesel GeewaW OPERABLE N/A Vendor NV-412 3
5 OAPt68 SOG-A - FUEL OIL EIDIG FUEL OIL AUXILIARY PUMP (OC)
M-377. SHT 4 0/O-3 OFF OADI3 COMMON BR 127 5147 ACTIVE AP IS8 OAGI2 Diesel Genetatr OFF/ON 3
5 0AP172 SDG-A-LUBE OIL El DIG LUBE OIL STANDBY CIRC PUMP M-377, SHT 3 D0G-3 OPERABLE N/A COMMON B
127 S130 PASSIVE OAP172 Diesel Generator OPERABLE NIA 3
5 0AP173 S$G-A-LUBE OIL El DIG LUBE OIL PRE LUBE PUMP M-377. SHIT 3 0/G-3 OPERABLE N/A COMMON B
127 5135 PASSIVE 0AP173 Diesel ceneraw OPERABLE N/A 3
5 0AP382 SDG-A - LUBE OIL El DIG LUBE OIL ENGINE DRIVEN PUMP M-377, SHT 3 D/0-3 OPERABLE N/A COMMON B
127 5133 ACTIVE 0AP382 OAGI2 Diesel Genewalor OPERABLE WA 3
5 OAP60 SDG-A - FUEL OIL El DIG FUEL OIL TRANSFER PUMP M-377, SlIT 4 D/G-3 OFF 0053 LS-0566A COMMON SR 127 5142 ACTIVE OAPO6O Diesel
- enere OFF/ON SPEC M-81 3
5 OPlS63 ESW EMERGENCY SERVICE WATER M-330 D0G-1 OFF 2GA17 20A1709 COMMON S
BOOSTER PUMP 8 OBP163 121 Diesel Generator OFF/ON 5622 ACTIVE M-19-14-4 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(.nrrF..nnnp~nnp N-.
N 9-173 B-68
DOCUMENT NOI 00674)0034-O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Mottre power suppo System Desired state Com pwer Stp Sys dwo OATE: 3r2f3 PAGE 6" TRAIN Unif SOUG Cl Equ~ip1 Eval recd?
PIUS ID Eq* Desa"on ROB Mo&e Comp Drawbi, No.
Loc Code Room Elev Line No Functbon 3
5 08P164 SOG-B - DIESEL E2 D/G AIR COOLANT AUXILIARY PUMP M-377. SHT 2 0/G-OPERABLE N/A COMMON S
COOLING 127 5225 PASSIVE 08P164 Diesel Generator OPERABLE N/A 3
O B8P165 SDG-B -DIESEL E2 D/G JACKET COOLANT STANDBY M-377. SHT 2 D/G-5 OPERABLE N/A COMMON B
COO.ING CIRC PUMP 127 5228 PASSIVE 08PISS OissI Generator OPERABLE N/A 3
5 0OP166 SDG-B -DIESEL E2 DIG JACKET COOLANT AUX PUMP M-377. SHT 2 D/Of OPERABLE N/A COMMON S
COOLING 127 6224 PASSIVE OBP166 D
G OPERABLE NZA Vendor 44058120 3
5 OSPI67 SDG LURE OIL E2 DIG LURE OIL AUXILIARY PUMP M-377, SHT 3 D/G-S OPERABLE N/A COMMON S
127 5232 ACTIVE 08P167 Diesel Generator OPERABLE N/A Vendor NV-412 3
5 OBP168 SOG FUEL OIL F2 DIG FUEL OIL AUXILIARY PUMP (Dc)
M-377, SHT 4 DIG-S OFF 08D13 COMMON SR 127 5247 ACTIVE 08P168 08G12 Diesel Geneator OFFION 3
5 0BP172 SDG LUBE OIL E2 DIG LUBE OIL STANDBY CIRC PUMP M-377. SHT 3 DIG-5 OPERABLE N/A COMMON 8
127 5230 PASSIVE 0BP172 Diesel Geator OPERABLE N/A 3
S 08P173 SDG-S - LUBE OIL E2 DIG LUBE OIL PRE LUBE PUMP M-377. SHT 3 0DI-S OPERABLE N/A COMMON a
127 5235 PASSIVE 09P173 Oiesel Generator OPERABLE N/A 3
5 0BP302 SDG-8 -LUSE OIL E2 DIG LUSE OIL ENGINE DRIVEN PUMP M-377. SHT 3 DI" OPERABLE MIA COMMON B
127 5233 ACTIVE 0BP382 OGt2 Diesel Gene'ator OPERABLE N/A 3
5 0SP60 SDG,-B -FUEL OIL E2 DIG FUEL OIL TRANSFER PUMP M-377, SHiT 4 DIG-5 OFF 00854 LS-05568 COMMON SR 127 5242 ACTIVE OSPOO Diesel Generator OFF/ON SPEC M-81 3
5 0OCP164 SDG-C - DIESEL E3 DIG AIR COOLANT AUXILIARY PUMP M-377. SHlT 2 DIG-B OPERABLE N/A COMMON S
COOLING 127 5325 PASSIVE 0CP164 Diesel Generator OPERABLE N/A 3
5 OCP165 SDG-C - DIESEL E3 DIG JACKET COOLANT STANDBY M-377. SHT 2 D/G-7 OPERABLE N/A COMMON a
COOLING CIRC PUMP 127 5326 PASSIVE OCPIS Diese Generator OPERABLE N/A 3
5 OCP166 SOG-C - DIESEL E3 DIG JACKET COOLANT AUX PUMP M-377, SMT 2 DIG-8 OPERABLE N/A COMMON S
COOLING 127 5324 PASSIVE 0CP168 Diesel Generator OPERABLE N/A Vendor 44D56120 3
5 OCP167 SDG-C - LUBE OIL E3 DIG LUBE OIL AUXILIARY PUMP M-377. SHT 3 DIG-?
OPERABLE N/A COMMON S
127 Diesel Generator OPERABLE N/A 5332 ACTIVE 0CP167 Vendor NV-412 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(,nrr.qnnnd*.nr..
Nn - RR-12-173 B-69
DOCUMENT NO. 07-00084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128W6 PAGE 69 Norm Wel Motve power SuPoat System Desired State Codr power Sjupp Sys dwg TRAIN SQUG CI Equip ID Eval reqd?
PIMS ID System Hotes Equip Description ROB Mobwe camp Drawing No.
Loc Code Room Elev Line NO Fujnction Builling 3
5 OCP168 SOG-C - FUEL OIL E3 D/G FUEL OIL AUXILIARY PUMP (OC)
M-377. SHT 4 D/G-?
OFF OCD13 COMMON BR 127 5347 ACTIVE OCP168 0CG12 Diesel Generator OFF/ON 3
5 OCP172 SDG-C - LUBE OIL E3 DIG LUBE OIL STANDBY CIRC PUMP M-377, SHT 3 DIG-7 OPERABLE NfA COMMON B
127 5=30 PASSIVE 0CP172 Diesel Generat OPERABLE NIA 3
5 OCPI73 SDG-C - LUSE OIL E3 D/G LUBE OIL PRE LUBE PUMP M-377. SHT 3 040.7 OPERABLE NWA COMMON B
127 5335 PASSIVE 0CP173 Diesel Generator OPERABLE NWA 3
5 0CP382 SDG-C - LUBE OIL E3 D/G LUBE OIL ENGINE DRIVEN PUMP M-377, SHT 3 DIG-?
OPERABLE WA COMMON B
127 5333 ACTIVE 0CP382 0CG12 Diesel Generator OPERABLE NWA 3
5 0CP60 SDG-C - FUEL OIL E3 DIG FUEL OIL TRANSFER PUMP M-377. SHT 4 O/G-7 OFF 00855 LS-0566C COMMON SR 127 5342 ACTIVE OC P060 Diesel Generator OFF/ON SPEC U-81 3
00P164 SDG-O - DIESEL E4 DG AIR COOLANT AUXILIARY PUMP M-377, SHT 2 DIG-10 OPERABLE NWA COMMON S
COOLING 127 5425 PASSIVE 0OD184 Diesel Generator OPERABLE WA 3
5 ODP165 SDG-O - DIESEL E4 DIG JACKET COOLANT STANDBY M-377. SHIT 2 D/G-9 OPERABLE NWA aCOMMON COOLING CIRC PUMP 127 5426 PASSIVE ODPIS5 Diesel Generator OPERABLE WA 3
5 0DP166 SDG-D - DIESEL E4 DIG JACKET COOLANTAAUX PUMP M-377, SlIT 2 0/G-10 OPERABLE N/A COMMON S
COOLING 127 5424 PASSIVE COPI66 Diesel Generator OPERABLE NIA Vendor 44D58120 3
5 ODPI67 SDG LUSE OIL E4 D/G LUBE OIL AUXILIARY PUMP M-377, SHIT 3
DIG-9 OPERABLE WA COMMON S
127 5432 ACTIVE 0DPI67 Oiesel Generator OPERABLE NWA Vendor NVW412 3
5 00P168 SDG-D - FUEL OIL E4 DIG FUEL OIL AUXILIARY PUMP (DC)
M-377. SHT 4 0/G-9 OFF 0D013 COMMON SR 127 5447 ACTIVE ODPI68 00G12 Diesel Geneator OFF/ON 3
5 0ODP172 SOG-C - LUBE OIL E4 DIG LUBE OIL STANDBY CIRC PUMP M-377. SHT 3 DIG-B OPERABLE WA COMMON B
127 5430 PASSIVE 0DP172 Diesel Generator OPERABLE NIA 3
5 0DP173 SDG0- - LUBE OIL E4 DIG LUBE OIL PRE LUSE PUMP M-377, SHT 3 D/G-9 OPERABLE WA COMMON B
127 5435 PASSIVE 0DP173 Diesel Generator OPERABLE WVA 3
5 0DP382 SDG-C - LUBE OIL E4 DIG LUBE OIL ENGINE DRIVEN PUMP M-377. SHT 3 DIG-9 OPERABLE WA COMMON B
127 Diesel Generator OPERABLE WA 5433 ACTIVE 0OP382 00D12 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (7nrrP.qnnndPnrP. Nn - RS-19-173 B-70
DATE: 3128G96 PAGE 70 DOCUMENT NO. 0067-0084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LOST TRAIN Unt LUne No SOUG C1 Equip ID Eval rec(d?
PIMS ID Funcion Systm Notes EqO es"on ROB MotW Camp DrawkV No.
Lao Code Roam Elev Buldng Norm stite Desred SIte MalMe powm Cami power Support System Supp Sys dwg 3
5 0OP60 SDG-O -FUEL OIL E4 D/G FUEL OIL TRANSFER PUMP M-377, SHT 4 0/G-9 OFF 00056 LS.05660 COMMON SR 127 5442 ACTIVE 00POo0 Diese Genrmor OFF/ON S
3 5
N/A SG-A - DIESEL AIR COOLANT PUMP. ENGINE DRIVEN M-377. SHT 2 DIG - 314 OPERABLE WA COMMON B
COOLING 127 5118 ACTIVE OAG12 Diesel Gener" OPERABLE N/A 3
5 N/A SDG-A -DIESEL JACKET COOLANT PUMP. ENGINE M-377, SHT 2 D/G -3/4 OPERABLE N/A COMMON B
COOUNG DRIVEN 127 6121 ACTIVE OAG12 Diesel Generator OPERABLE N/A 3
5 N/A SDG-B -DIESEL AIR COOLANT PUMP, ENGINE DRIVEN M-377, SlIT 2 D/G - S5 OPERABLE N/A COMMON a
COOLING 127 5218 ACTIVE 08G12 Diesei Genwalo OPERABLE NIA 3
5 N/A SO"- - DIESEL JACKET COOLANT PUMP. ENGINE M-377. SHT 2 DIG - S5o OPERABLE N/A COMMON B
COOLING DRIVEN 127 5221 ACTIVE 0BG12 DWese Generator OPERABLE N/A 3
5 N/A SOG-C -DIESEL AIR COOLANT PUMP. ENGINE DRIVEN M-377, SHT 2 OG - 7/8 OPERABLE N/A COMMON B
COOLING 127 5318 ACTIVE 0CG12 Des Genersto OPERABLE N/A 3
5 N/A SDG-C - DIESEL JACKET COOLANT PUMP. ENGINE M-377, SHT 2 D/G - 7/8 OPERABLE N/A COMMON a
COOLING DRIVEN 127 5321 ACTIVE 0CG12 Diesel Generatar OPERABLE N/A 3
5 N/A SOG.0 - DIESEL AIR COOLANT PUMP. ENGINE DRIVEN M-377, SLIT 2 DIG - 0110 OPERABLE N/A COMMON B
COOLING 127 5418 ACTIVE 0DG12 Diesel Gersator 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 0DG12 Diesel Generalo OPERABLE N/A 3
5 N/A SDG-A - FUEL OIL FUEL OIL PUMP. SHAFT DRIVEN M-377, SlT 4 D/G-3 OPERABLE N/A COMMON B
127 514W ACTIVE 0AG12 Diesel Genomtor OPERABLE N/A 3
5 N/A SOG-B - FUEL OIL FUEL OIL PUMP, SHAFT DRIVEN M-377. SlIT 4 D/G-5 OPERABLE N/A COMMON 8
127 5246 ACTIVE 08G12 Diesel Generator OPERABLE N/A 3
5 W/A S6G-C -FUEL OIL FUEL OIL PUMP, SHAFT DRIVEN M-377. SHT 4 D/G-7 OPERABLE N/A COMMON B
127 5346 ACTIVE OCG12 Dies Generar OPERABLE N/A 3
5 COMMON 8
6446 ACTIVE N/A SDG-O -FUEL OIL FUEL OIL PUMP. SHAFT DRIVEN 0DG12 M-377, SHT 4 DG-9 OPERABLE N/A Diesel Generawo OPERABLE N/A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
'nrrpn.nnrh.nr.. Nn R.-17-173 B-71
DOCUMENT NO. 0067400841-00011 REVISION 2 TRAIN SOUG CI Eq4p ID UnQ Eval reMd?
PIS ID PEACH 80TTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST NOrm state Moe. power Desied State Contr power DATE: 3/28/96 PAGE 71 System Notes EqR Osesoiplien ROB Miother Camp Orawkg No.
Loc Code Room Elov Support System Supp Sys d" Lif No FwLeion Bui 3
6 0AA57 ESW EMERGENCY SERVICE WATER PUMP A M-315. SNT I P/H-8 OFF 20AI6 20A1603 COMMON S
111 5537 ACTIVE GAP057 Pump House ON M-11-29, E-8-109-4 3
8 W6P57 ESW EMERGENCY SERVICE WATER PUMP B M-315. SkT 4 Pi-t OFF 20A17 20A1706 COMMON S
I11 5589 ACTIVE OBP057 Pump jous ON 96-11-29. E-8-109-1 3
7 AO-33.o241A E5W ESW OUTLET BLOCK VALVE FROM M-315, SHT I D/G-3 CLOSED N/A SV-3686-41A COMMON S
DIESEL GEN El COOLERS 127 5530 ACTIVE AO-o-33-0241A Diesel Generator OPEN N/A vendor 6-9M207-62 3
7 AO-33-02418 ESW ESWVOUTLET BLOCK VALVE FROM M-315. SHIT 1 D/G-5 CLOSED N/A SV-368-0241B COMMON S
DIESEL GEN E2 COOLERS 127 5532 ACTIVE A0.O33-0241B aisselnenor OPEN N/A vendor 6-%M207-52 3
7 AO-33-0241C ESW ESW OUTLET BLOCK VALVE FROM M-315, SHIT 1 D0G-7 CLOSED NWA SV-368-0241C COMMON S
DIESEL GEN E3 COOLERS 127 5534 ACTIVE AOO.33-0241C Diese Generator OPEN N/A vendor 6-9M207-52 3
7 AO.33.0241D ESW ESW OUTLET BLOCK VALVE FROM M-315. SPIT I D/G-9 CLOSED N/A SV-36850241D COMMON S
DIESEL GEN E4 COOLERS 127 5536 ACTIVE AO0-33-0241D Diesel Gnerwaior OPEN N/A vendor 6-%27-52 3
7 AO-52C-7231A SDG-A - STARTING El DIG AIR START SOLENOID VALVE M-377. SliT I DIG-3 CLOSED N/A SV-52C-7233A COMMON S
AIR 127 5104 ACTIVE AO,0-52C-7231A il Generator OPEN N/A 3
7 AO-S2C-7231B BOG- - STARTING E2 DIG AIR START SOLENOID VALVE
-M-377.
SHT 1 O/G-5 CLOSED N/A SV-52C-72338 COMMON S
AIR 127 5204 ACTIVE AOo-52C-7231B Diesel Generator OPEN N/A 3
7 AO52C-7231C SOG-C - STARTING E3 D/G AIR START SOLENOID VALVE M-377, SHT S D/G.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 SOG- - STARTING E4 D/G AIR START SOLENOID VALVE M-377. SHT 1 DIG-9 CLOSED N/A SV-52C-7233D COMMON S
AIR 127 5404 ACTIVE AO-.52C-7231 D Diesel Generator OPEN N/A 3
7 AO'52C-7232A SDG-A STARTING El DIG AIR START SOLENOID VALVE M-377. SHT I DIG-3 CLOSED N/A SV-52C-7234A COMMON S
AR 127 5105 ACTIVE AO.o.52C-7232A Diesel Generator OPEN WA 3
7 AO.,52C-7232B SDG-B - STARTING E2 DIG AIR START SOLENOID VALVE M-377, SHlT 1 D/G-5 CLOSED N/A SV-52C-72348 COMMON S
AIR 127 5205 ACTIVE AOO.52C.7232B 0iesel Genlaor OPEN N/A 3
7 AO-62C-7232C SDG-C-STARTING E3 DIG AIR START SOLENOID VALVE M-377. SHIT I O/G-7 CLOSED N/A SV-52C-7234C COMMON S
AIR 127 ACTIVE A0-O-52C-7232C Diesel Generator OPEN N/A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrr..nnndi.nrn. No
- RR-12-173 B-72
DOCUMENT NO. 0067-000-DO1 REVISION 2 TRAIN SQUG C!
Equip ID Unit Eval aqd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNfIS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 312619 PAGE 72 Norm stem Moiv. power Supou1 System Desked State Con power Supp Sys dwg Systm Not"s Equip DesCiptio ROB MOOMe Camp Dmwing No, Loc Code Room Elev Lin No Funiion Bukdx 3
7 AO-52C-72320 SOG-D - STARTING E4 DIG AIR START SOLENOID VALVE M-377. SKT I OJG-9 CLOSED N/A SV.52C-7234D COMMON S
AIR 127 5405 ACTIVE A04-62C-72320 Diesel Geneator OPEN NWA 3
7 AV-368-00016 HVAC EMERG SWGR & BTRY RMS SUPPLY M-399, SHT I RPW-32 OPERABLE WA COMMON B
VENT PNEUMATIC RELAY 165 5907 ACTIVE AV.00016 00F043 Radwaste Bldg OPERABLE MIA 3
7 PCV-40W-70088A HVAC t/N2 BAl SUP PRESS CRTL VLV FOR M-399, SHT 1 RNW-29 OPERABLE WA COMMON S
08V035 AND OA(B)V034 165 5901 ACTIVE PCV4"W-70088A Radwtae Bift OPERABLE NWA 3
7 PCV-40W-700888 HVAC UKN2 BAU SUP PRESS CRTL VLV FOR M-399, SHIT I RNW-29 OPERABLE WA COMMON.
S 08V035 AND 0A(B)V034 165 5903 ACTIVE PCVO-40W-700888 Radwasge Bldg OPERABLE WA 3
7 PCV-40W-70089A HVAC 1N2 BIU SUP PRESS CRTL VLV FOR M-399. SHT 4 RNV-32 OPERABLE WA COMMON S
0AV035 AND 0A(8)V036 165 5914 ACTIVE PCV-0-40W.70089A Rafsasle Bldg OPERABLE WA 3
7 PCV-40W-70089B HVAC I/N2 BIU SUP PRESS CRTL VLV FOR M-399, SHT 4 RJW-32 OPERABLE WA COMMON S
04VO36 AND 0A(B)V038 165 5916 ACTIVE PCV-0-40W-70089P Radwasle Bg OPERABLE NWA 3
7 PO.40W-OO083-01 HVAC EMERG SWGR + BATTERY ROOMS M-399. SHT 1 RPW-32 CLOSEDIOPEN WA HVAC N2 COMMON 8
VENT SUP FAN 08V034 INLET 165 5809 ACTIVE PO-O-40W..00803-01 P040W4.0020-1 Radwaste Bldg OPEN N/A M-399. SHT I 3
7 PO-40WO.0803-02 HVAC EMERG SWVGR
+ BATTERY ROOMS M-399, SHT 1 RIN-32 CLOSE-.OPEN WA HVAC N2 COMMON B
VENT SUP FAN 0BVD34 INLET 165 5810 ACTIVE POo-0 P0-OV-40W002001 Radwaste Blg OPEN WA M-399. SHT 1 3
7 PO-40WV00803-03 HVAC EMERG SWGR + BATTERY ROOMS M-399. SHT 1 RNW.32 CLOSED/OPEN NWA H/AC N2 COMMON a
VENT SUP FAN 08V034 INLET 165 5812 ACTIVE P0,0-40W-1.0803-03 PO.O-40W-00020-01 Radwasts BSlg OPEN NWA M-399, SHT 1 3
7 P0-40W-O0808 HVAC EMERG SWGR + BATTERY ROOMS M-399, SHT I RAN-32 OPEN WA HVAC N2 COMMON 8
VENT SUP FAN 0AV034 OUTLET 165 5808 PASSIVE PO-040W,0008 P0-O40W D001902 Radwaste Bkrg OPEN WA M-39.
SHT 1 3
7 PO-40W-00809 HVAC EMERG SWGR + BATTERY ROOMS M-399. SHIT I RN-32 CLOSED NWA HVAC N2 COMMON a
VENT SUP FAN 08V034 OUTLET 165 5816 ACTIVE PO-O-4W-m0809 P30--4W-00020-02 Redwas*le Bdg OPEN NWA M-399. SHlt 1 3
7 PO-40W-00815-01 HVAC EMERGENCY SWITCHGEAR VENT M-399, SKT 4 RIW-32 OPEN NWA HVAC N2 COMMON a
EXHAUST FAN OAV035 INLET 165 5824 PASSIVE PO-O-40W-06515.01 PO.O,40W-X0025.01 Rawa Bldg OPEN W&A M-3993 SPET 4 3
7 PO-40W1-00B15-01 HV/AC EM.ERGENCY-.SWTCHGEAR VENT 14-399, S*l 4
RMI-.32 CLOSED W/A HV/AC N2 COMMON B
5829 ACTIVE EXHAUST FAN OBV035 INLET P-0W-002X601 165 RadwastD Bldg OPEN WA P04-40W-0016-01 M,399. SHT 4 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrP..nnnd.nn* Nn" R.R-12-173 B-73
DOCUMENT NO. 0067.084-4001 REVISION 2 TRAIN S0UG a Equip D Unit Evel reqd?
PINS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT UST DATE: 3/28/r8 PAGE 73 Norm state Motn pow Support System Desk"e State Corr Power Supp Sys dwg System Notes Equ pesuition ROB Molhe Camp Orewing No.
Loc Coda Room Elv Line No Funcdlon BOW&
3 7
PO-40W.00816.02 HVAC EMERGENCY SWITCHGEAR VENT M-399, SHT 4 RAN-32 CLOSED NWA HVAC N2 COMMON B
EXHAUST FAN 08V035 OUTLET 165 6832 ACTIVE PO0440W.0B1602 PO-40W-00*G-02 Radwaste Bldg OPEN NIA M-399. SHT 4 3
7 PO-40W-00822-01 HVAC EMERG SWGR + BATTERY ROOMS M-399, SHT I RIW-.2 OPEN N/A HVAC N2 COMMON B
VENT SUP FAN OAV034 INLET 165 5801 PASSIVE PO-04OW-00822.01 P0-0-40W-00019.01 Radwaste Bldg OPEN N/A M-399, SHlT 1 3
7 PO-4W.-00822-02 HVAC EMERG SWGR + BATTERY ROOMS M1-399, SHT I RNY-32 OPEN NWA HVAC N2 COMMON B
VENT SUP FAN OAV034 INLET 165 5802 PASSIVE PO.-40W-00822-02 P0-040W-00019-01 Radwaste Bldg OPEN NWA M-499. SHT 1 3
7 PO-40W.00822-03 HVAC EMERG SWGR + BATTERY ROOMS M-399, SHT 1 RAV-32 OPEN WA HVAC N2 COMMON B
VENT SUP FAN GAV034 INLET 165 56M3 PASSIVE PO-40W-O0822-03 PO-O-40W-00019-01 Radwaste Bldg OPEN NIA M-399. SHT I 3
7 RV-40W-7149A HVAC B/U OR RELF VLV FOR 08035 AND M-399. SHT I RNV-29 CLOSED NWA COMMON S
0(A.BV034 FANS PO WS 166 5918 PASSIVE RV-O40W-7149A Radwaste BIdo CLOSED NIA 3
7 RV-40W-71498 NVAC B/U 1/N2 RELF VLV FOR 0AV035 AND U-399. SHT 4 RA/-32 CLOSED NWA COMMON S
0(A.B)V036 FANS PO WS
¶65 5924 PASSIVE RV-040W-7149B Rafts*t Bldg CLOSED NIA 3
7 TCV-52E-7239A SOG-A - DIESEL El DiG JACKET COOLANT 3-WAY M-377. SHT 2 0/0-3 OPEN/CLOSED NWA COMMON B
COOLING THERMOSTATIC CONTROL VALVE 127 5122 ACTIVE TCV-0-82E-7239A OAGO12 Diesel Geator OPEN/CLOSED NIA 3
7 TCV-52E-72305 SG DIESEL E2 DWG j.ACMT COOLANT 3-WAY M-377, SHT 2 D/G-S OPEN/CLOSED NiA COMMON B
COOLING THERMOSTATIC CONTROL VALVE 127 5222 ACTIVE TCV4M-52E-7239B 0BG012 Diesel Genmator OPEN/CLOSED NWA 3
7 TCV-52E-7239C SOG-C - DIESEL E3 DOG JACKET COOLANT 3-WAY M-377. SHT 2 D/G-7 OPEN/CLOSED N/A COMMON B
COOLING THERMOSTATIC CONTROL VALVE 127 5322 ACTIVE TCV-0-52E-7239C OCG012 Diesel Generator OPEN/CLOSED NIA 3
7 TCV-52E-7239S SDG4)- DIESEL E4 DIG JACKET COOLANT 3-WAY M-377, SHIT 2 D/G-9 OPEN/CLOSED WA COMMON a
COOLING THERMOSTATIC CONTROL VALVE 127 5422 ACTIVE TCV-0-52E-72390 ODG012 Diesel G OPEN/CLOSED NIA 3
7 TCV-52F-7238A SDG-A -DIESEL El DIG AIR COOLANT 3-WAY M-377, SHT 2 010-3 OPEN/CLOSED N/A COMMON B
COOLING THERMOSTATIC CONTROL VALVE 127 5117 ACTIVE TCV-0-52F-7238A 0AGO12 Diesel Generator OPEN/CLOSED N/A 3
7 TCV-52F.7238B SDG-B - DIESEL E2 DIG AIR COOLANT 3-WAY W377. SHT 2 D/G-5 OPEN/CLOSED NIA COMMON B
COOLING THERMOSTATIC CONTROL VALVE 127 5217 ACTIVE TCV-0-52F-7238B OBG012 Diesel Genralor OPEN/CLOSED NIA 3
7 TCV-52F-7238C SD-C - DIESEL E3 DIG AIR COOLANT 3-WAY M377. SPIT 2 DIG-7 OPEN/CLOSED N/A COMMON B
COOLING TCV-0-62F-7238C THERMOSTATIC CONTROL VALVE OCGO12 127 Diesel Generator OPEN/CLOSED NIA 5317 ACTIVE Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr.qnnndp.nr.. Nn RS-19-173 B-74
DOCUMENT NO. 006740054-40OI REVISION 2 TRAIN SOUG Cl Equip 0 Unit Evl reqd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Mote power Desired Stato C=t POWe DATE: 3r12M PAGE 74 System Notes Equi Description ROB Mother Comnp Drawing No.
Loc Code Room Elov Support Systm SUPP SyS dwo Line No Function 8udlino 3
7 TCV-52F-72380 SOG-D -DIESEL E4 D/G AIR COOLANT 3-WAY M-377. SHT 2 D104 OPENfCLOSED NWA COMMON a
COOLING THERMOSTATIC CONTROL VALVE 127 5417 ACTIVE TCV-0-52F-7238D 00G012 Diese Generator OPENICLOSED N/A 3
7 TCV.52G-7240A SDG-A - LUBE OIL El D/G LUBE OIL 3-WAY M-377. SHT 3 D/G-3 OPEN/CLOSED N/A COMMON B
THERMOSTATIC CONTROL VALVE 127O 5138 ACTIVE TCV-O-52G-7240A OAG012 Diesel Generator OPEN A
3 7
TCV-52G-7240B SDG WBE OIL E2 DIG LUBE OIL 3-WAY M-377. SHT 3 0/G-5 OPEN/CLOSED N/A COMMON B
THERMOSTATIC CONTROL VALVE 127 5238 ACTIVE TCV-O-52G-72408 08G012 Diesel Generator OPEN N/A 3
7 TCV-62G-7240C SDG-C - LUBE OIL E3 D/G LUSE OIL 3-WAY M-377. SHT 3 D0G-7 OPEN/CLOSED NZA COMMON B
THERMOSTATIC CONTROL VALVE 127 5338 ACTIVE TCV40-52G-7240C -
OCGO12 Oi8s Genemra OPEN N/A 3
7 TCV-52G.72400 SDG-D - LUBE OIL E4 DIG LUBE OIL 3-WAY M.-377, SHT 3 D/G-B OPENICLOSED N/A COMMON B
THERMOSTATIC CONTROL VALVE 127 5438 ACTIVE TCV-O-52G-72400 00G012 Diesel Generator OPEN N/A 3
SA MO-33-0498 ESW EMERGENCY SERVICE WATER RETURN M-330 D/G-2 OPEN 00856 COMMON SiR TO DISCH POND 121 5M20 ACTIVE MO.0-33-O498 Diesel Generator CLOSED 3
8A MO-48-OSGIA ESW ESWA INLET TO ECT RESERVOIR M-330 ECT-1 OPEN 00898 COMMON SR 114 5623 ACTIVE MO-0-48-OMIA Emrgey OPEN/CLOSED Towers 3
SA M04845018 ESW ESW B INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00897 COMMON SR 114 5624 ACTIVE MO-0-48-05018 Emergency Cooling OPEN/CLOSED Towers 3
SA MO1-48501C ESW ESWC INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00899 COMMON SR 114 5625 ACTIVE MO-0-48-001C Emergec Cooing OPENICLOSED Towers 3
8 MO-18-0502A HPSW HPSW A INLET TO ECT RESERVOIR M-330 ECT-1 OPEN NIR COMMON R
114 5614 PASSIVE MD.O-480602A Emergency Coo&g OPEN NIR Towers 3
8 MO-48.05028 HPSW HPSW B INLET TO ECT RESERVOIR 1M330 ECT-1 OPEN NWR COMMON R
114 5615 PASSIVE M1-0-48-05028 Enmergency Cooling OPEN NJR Towers 3
BA MO-48-0502C HPSW HPSW C INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00899 COMMON SR 114 5616 ACTIVE MO.048,0502C Emrgency Coorling OPEN Towers 3
8 SV-0)540-1 SOG-A -
INSTRUMENT AIR BLOCK VALVE FOR M-385 D0G-4 DEENERGIZED 00853 VENTILATION PO-0-40F-00540-01 5114 ACTIVE SV-0,-OB4X540.01 OAV91 14e DEENIENER Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrr..qnnndpnnrn No
- RS-19-173 B-75
DOCUMENT NO. 0067-00084-0001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval req'd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128/9 PAGE 78 Norm state M
P-S*vo suppor system ODs-ed Stde Coanr power Supp Sys dwg System Notes Equip Oesorptim ROB Moom Comp Orawft No.
LaO Cod.
Room Elev Lire No Function Buldb 3
8 SV.00540-2 SDG INSTRUMENT AIR BLOCK VALVE FOR M-385 01G-6 DEENERGIZED 00054 COMMON BR VENTILATION PO-O-40F-(O540D-2 127 5214 ACTIVE SV.O-368-(050-02 0OVOi Diesel Generato DEENIENER 3
8 SV-00540-3
$0G.C -
INSTRUMENT AIR BLOCK VALVE FOR M.-85 00G-.
DEENERGIZED 00855 COMMON BR VENTILATION PO-0-40F-00640-03 127 5314 ACTIVE SV_00003 OCV91 Diesel Generator DEENIENER 3
8 SV.00540-4 SOG-D -
INSTRUMENT AIR BLOCK VALVE FOR M-385 DIG-10 DEENERGIZED 00856 COMMON BR VENTILATION PO<-40F-0054O-O4 127 5414 ACTIVE SV-0,3684160-04 ODV91 Diesel Generator DEEN/ENER 3
as SV-368-00019 HVAC
/A SOLENOID VALVE FOR M-399. SHT I RNV-32 ENER/DEEN 00849 0AV34 COMMON SR PO-O-40W-00019-01
- 00019-02. 80, 822-01.
165 580MO ACTIVE SVSR.36 OZ0319 Radwaste Blg ENERGIZED M-119-48 3
as SV-368-00020 HVAC VA SOLENOID VALVE FOR M-399, SHT I RNW-32 DEENIENER 00850 09V34 COMMON SR PO-0-40W-0002001 + 0002002. 809, 803-01.
165 590 ACTIVE SV-O-368-0002D
-02,03 Radwaste Bldg ENERGIZED M
3 88 SV-368-=0025 HVAC UA SOLENOID VALVE FOR m-399. SHT 4 RIW-32 ENERIDEEN 00849 0AV35 COMMON SR P040W-0002-01 + 00025-02 165 5912 ACTIVE SV4)405 Rap gas Bldg ENERGIZED M
hi-I19-48 3
8a SV-368-00026 HVAC VA SOLENOID VALVE FOR M1-399 SHT 4 RNW-32 DEENIENER 00850 08V35 COMMON SR PO*-40W-0)2&I
- 00026-0. 00816-01 165 00818-2EERIE 5912 ACTIVE SV-0-36-00020 Radwaste Bldg ENERGIZED M-119-48 3
8 SV-388-O3I HVAC IuA SOLENOID VALVE FOR M-399, SHT 4 RAW-32 ENERIDEEN 00849 OAV36 COMMON 8
PO-0.40W-00031-01 + 00031-02 166 5917 ACTIVE SV-O-36B-00031 PO-O-40W-00031-01102 Radwaste Bldg ENERGIZED 3
as SV-368-00032 WVAC I/A SOLENOID VALVE FOR M-399, SHT 4 RNW-32 DEENIENER 00B50 0BV36 COMMON SR PO-O-40W-00032-O1 + 00032-02 165 5917 ACTIVE SV-O-368-00032 Radwaste Bldg ENERGIZED 3
as SV-388.0241A ESW VA SOLENOID W FOR AO-0241A DIG El1 M-315, SHT 1 D/G-3 ENERGIZED NIR COMMON BR ESW OUTLET 127 5529 ACTIVE SV-O-36B-0241A AO-33-0241A Ditesl Gerator DEENERGIZED NIR 3
88 SV-368-02418 ESW VA SOLENOID W FOR AO-02418 DIG E2 M-315, SHlT 1 DIG-S ENERGIZED NIR COMMON BR ESW OUTLET 127 5531 ACTIVE SVoO36B-41B A0-33-02418 Diesel Geneetor DEENERGIZED N/t 3
as SV-360.0241C ESW VA SOLENOID W FOR AO-0241C 0DG E3 m-315, SHT I DIG-7 ENERGIZED NIR COMMON BR ESWOUTLET 127 S533 ACTIVE SV-0-366-0241C AO-33-0241C Di.ese GenENEGraDtoRr 3
a8 SV-366-02410 ESW I/A SOLENOID W FOR AO"02410 DIG E4 M.-315. SHT I O/G-9 ENERGIZED NIR ESW OUTLET
ýW _V.
-Ji g'
5535 ACTIVE SV-0-368-02410 AO-33-0241D Diesel Generator DEENERGIZED INR Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C7,nrrP.qnnnIP~nr.A Nn o RS-19-1773 B-76
DOCUMENT NO. 0067-00084-O01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Moltl power Deskd State Cnt powe I
DATE: 3r22596 PAGE 76 TRAIN Unti SOUG a Equip i Eval read?
PIMS ID system Notes Equip Descripton ROB Mother Camp Drawing No.
Loc Code Room Elev support system supp Sys deg Line No Function BI*bv 3
8 SV-52C-7233A SDG-A - STARTING El DfG AIR START SOLENOID VALVE M-377, SHT I DIG-3 DE-ENERGIZE 8AO13 COMMON BR AIR (CONTROLS AO-7231A) 127E 5106 ACTIVE SV-O-52C-7233A AO-52C-7231A Diesel Generat ENERGIZED 3
8 SV-52C-72330 SDG4.- -STARTING E2 DIG AIR START SOLENOID VALVE M-.T, SHT I DIG-S DE-ENERGIZE 08D13 COMMON
- R AIR (CONTROLS AO-7231B) 127 6205 ACTIVE SV-O-52C-72330 AO-52C-7231B Diesel Geneator ENERGIZED 3
8 SV-52C-7233C SOG-C - STARTING E3 DIG AIR START SOLENOID VALVE M-377, SHT I DIG-7 DE-ENERGIZE 0C013 COMMON BR AIR (CONTROLS AO-7231C) 127 6306 ACTIVE SV-O-52C-7233C AO-52C-7231C Diesel Generator ENERGIZED 3
8 SV-52C-72330 SDG4) - STARTING E4 D/G AIR START SOLENOID VALVE M-377, SHlT I D/G-9 CE-ENERGIZE 00013 COMMON SR AIR (CONTROLS AO-72310) 127 5406 ACTIVE SV-0-52C-7233D AO-2C-7231D DWe Generator ENERGIZED 3
8 SV-52C-7234A SDGA - STARTING El DiG AIR START SOLENOID VALVE M-377. SHT 1 DIG.3 DE-ENERGIZE 0AD13 COMMON BR AIR (CONTROLS AO-7232A) 127 5107 ACTIVE SV.O-52C-7234A AO-52C-7232A Diesel Generator ENERGIZEDO 3
8 SV-52C-72348 SG-B - STARTING' E2 DIG AIR START SOLENOID VALVE M-377, SHT 1 DIG-S DE-ENERGIZE 08D13 COMMON BR AIR (CONTROLS AO-7232B) 127 5207 ACTIVE SV-O-52C-7234B AO-62C-72328 Diesel Generator ENERGIZE 3
8a SV-52C-7234C SDG-C - STARTING E3 DIG AIR START SOLENOID VALVE M-1*7, SHT 1 DIG-7 CE-ENERGIZE OC013 COMMON OR AIR (CONTROLS AO-7232C) 127 5307 ACTIVE SV.O-62C-7234C AO-52C-7232C Diesel Generator ENERGIZED 3
8 SV-52C-7234D SDG-O - STARTING E4OiG AIR START SOLENOID VALVE M-377, SlT I DIG-9 DE-ENERGIZE 00013
.COMMON BR AIR (CONTROLS AO-72320) 127 5407 ACTIVE SV-0-52C-7234D AO-62C-7232D Disel Generator ENERGIZE 3
9 0AK032 ESW & HPSW A EMERGENCY COOLING TOWER FAN M-330 ECT-6 OFF 00895 0089513 COMMON S
195 5617 ACTIVE 0AK032 Emergency Cooln9 OFFION Tower M78-3-4 3
9 GAV03S HVAC EMERG SWITCHGEAR VENTILATION M-399, SHT 4 RAN-32 ONIOFF 00849 COMMON SR EXHAUST FAN A 165 5825 ACTIVE 0AV03S Radcwas* Bldg ON 3
9 GAV036 HVAC BATTERY ROOM EXHAUST FAN A M-399. SHT 4 RAW-32 ONIOFF 00649 COMMON SR 165 5818 ACTIVE 0AV036 Radwaste Bidg ON 3
9 OAV064 SG-A -
El DIG BUILDING VENTILATION SUPPLY M-3B5 DIG-13 OFF 00853 COMMON SR*
VENTILATION FAN A 151 5109 ACTIVE 0AV064 Diesel Generator ON S-979, M-S1-"7 69.77 3
9 0AV091 SDG-A -
El DIG BUILDING VENT SUPPLEMENT M-385 010-14 OFF 00853 COMMON SR VENTILATION SUPPLY FAN 151 Diesel Generator OFFION 5113 ACTIVE 00g911 VMAN M-70-35 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrrP..qnnnnrP.n Nn
- RS-12-173 B-77
DOCUMENT NO. 00974108460001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE. 3128M PAGE 77 Norm sltae Motive power SuPPort System Desired Slate Com power Supp Sys dwg REVISION 2 TRAIN Unit SQUG CI Equip ID Eval reqd?
PIMS ID System Notes EQR DesoiCtion ROB Mother Comp No.
Loc Code Room Elev Line No Fumction BuEk-A 3
g 08K032 ESW& HPSW
'W EMERGENCY COOLING TOWER FAN M-33O ECT-6 OFF 00894 0089413 COMMON S
195 5618 ACTIVE 0BKM32 Emergency Cooing OFF/ON Towers M78-3-4 3
9 08V035 HVAC EMERG SWITCHGEAR VENTILATION M-399, SHT 4 RIW-32 OFF/ON 00850 COMMON SR EXHAUST FAN B 165 S821 ACTIVE 08V035 Radwaste Bldg ON 3
9 S0VO36 HVAC BATTERY ROOM EXHAUST FAN 1 M-399, SHT 4 RAN-32 OFF/ON 00850 COMMON SR 165 5830 ACTIVE 08VO36 Rdwst Bd ON 3
9 0OV064 SDG-8 E2 D/G BUILDING VENTILATION SUPPLY M-385 DIG-15 OFF 008540 COMMON SR VENTILATION FAN S 151 5209 ACTIVE 0OV064 Diesel Generator ON S-979, M-51-57. 69, 77 3
9 OBV1 SDG-S.
E2 DIG BUILDING VENT SUPPLEMENT M-385 OIG-16 OFF 00854 COMMON SR VENTILATION SUPPLY FAN 151 5213 ACTIVE 0QM9 Diesel Generator OFF/ON VMAN M-70-35 3
- C EMERGENCY COOLING TOWER FAN M-0 ECT4 OFF 00896 0089613 COMMON S
195 5619 ACTIVE OCK032 Emergency Cooling OFF/ON Towers M76-3-4 3
9 0CV064 SDG-C -
E3 DIG BUILDING VENTILATION SUPPLY M385 D/G-17 OFF 00855 COMMON SR VENTILATION FAN C 151 50 ACTIVE OCV064 Diese Genrwator ON S-979, M-51-57. 69. 77 3
a ocvoai SDG-C -
E3 D=G UILDING VfENT SUPPLOAM-ENT M-385 0/G-18 OFF 00855 COMMON SR VENTILATION SUPPLY FAN 151 5313 ACTIVE OCV091 Diesel Generator OFF/ON VMAN M-70-35 3
9 0DV084 SDG)-
E4 DIG BUILDING VENTILATION SUPPLY M-385 DIG-19 OFF 00856 COMMON SR VENTILATION FAN 0 151 5409 ACTIVE 0OV064 Diesel Generator ON S-979. M-S1-67,69. 77 3
9 00DV91 SOG-O
- E4 DIG BUILDING VENT SUPPLEMENT M-385 DIG-20 OFF 00856 COMMON SR VENTILATION SUPPLY FAN 161 5413 ACTIVE 0DV91 Diesel Generator OFF/ON VMAN M-70-35 3
10 00F043 WVAC EMERG SWGR VENT SUPPLY M-399, SHT I RNW-32 OPERABLE N/A COMMON S
ROLL-FILTER 165 5110 PASSIVE 00F043 Radwaste Bldg N/A N/A 3
10 OAV034 WVAC EMERG SWGR AND STRY ROOM M-399. SlIT 1 RAW-32 ON/OFF 00849 COMMON SR VENTILATION SUPPLY FAN A 165 5806 ACTIVE OAV034 Radwasta Blg ON S-982 3
10 0BV034 HVAC EMERG SWGR AND STRY ROOM M-399. SHT I RAW-32 OFF/ON 00850 COMMON a
VENTILATION SUPPLY FAN B 165 5S14 ACTIVE 0BV034 0AV034 Radwaste Bldg ON S-982 Peach Bottom Atomic Power Station Unit 3 B-78 MPR-3812, Revision 3 Cnrrp*.*nnndr.nrp. No " R.-1 -173
DOCUMENT NO. 0067-000044O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Normtlate Motive power Sutow System DOesed State cwp pw Stpp Sys dw9 DATE: 3r2MS6 PAGE 78 TRAIN SOUG CI Equip ID Eval reqfd?
PIMS ID Notes Equip Doesciptin ROB Mother Comp ODrwki No.
Loc Code Room Elev Line No Function BuiL 3
10 P0-00272-1 SDGA-MASTER FOR ElDIG BLDG VENT SUP M-385 DIG-13 CLOSED NIA COMMON S
VENTILATION FAN OAV064 OUTSIDE AIR DAMPER 151 I
5110 ACTIVE PO-O-40F-OD272-oi Diesel Generator OPEN NIA 3
10 P0-00272-2 SOG A-MASTER FOR El D/G BLDG VENT SUP M-385 O/G-13 OPEN N/A COMMON S
VENTILATION FAN OAV064 RETURN AIR DAMPER 161 5111 ACTIVE P04401`40272-02 Wist Generato CLOSED N/A 3
10 POOV273.1 SDG8-MASTERFORE2D/GBLDG.VENTSUP M-385 0/0-IS CLOSED N/A COMMON S
VENTILATION FAN 08V054 OUTSIDE AIR DAMPER 151 6210 ACTIVE PO--40F-00]73.o1 Diesel Generaor OPEN N/A 3
10 P04.0273-2 SDGB-MASTER FOR E2 DIG BLDG VENT SUP M-385 DIG-I5 OPEN N/A COMMON S
VENTILATION FAN 0BV064 RETURN AIR DAMPER 151 5211 ACTIVE PO.-40F-00273-02 Diesel Generator CLOSED N/A 3
.10 PO00274.1 SG C -
MASTER FOR E3 DIG BLDG VENT SUP M-385 D/G-I1 CLOSED N/A COMMON S
VENTILATION FAN OCV064 OUTSIDE AIR DAMPER 151 5310 ACTIVE PO-O-40F-00274-01 Diesel Generator OPEN N/A 3
10 PO-00274-2 SOG C -
MASTER FOR E3 DIG BLDG VENT SUP M-385 0D0-17 OPEN N/A COMMON S
VENTILATION FAN OCV064 RETURN AIR DAMPER 151 5311 ACTIVE PO-O-40F-00]74-02 Diesel Generator CLOSED N/A 3
10 P0-00275-t SOGD-MASTER FOR E4 DIG BLDG VENT SUP M-385 DIG-a9 CLOSED N/A COMMON S
VENTILATION FAN 0DV064 OUTSIDE AIR DAMPER 151 5410 ACTIVE PO1-O-40F-002754Oi D1030 Generator OPEN N/A 3
10 PO-00275-2
$D0D-MASTER FOR E4 DMG BLDG VENT SUP M-385 0/G-19 OPEN N/A COMMON S
VENTILATION FAN 0DV064 RETURN AIR DAMPER 151 5411 ACTIVE PO-040F-0=275.02 Diesel Generator CLOSED NIA 3
10 PO-00540-1 SDG A.
El DIG BLDG VENT SUPPLEMENTAL SUP M-385 DJG-4 CLOSED N/A COMMON S
VENTILATION FAN OAV091 DAMPER 127 5115 ACTIVE PO-O-40F-0540O-01 Diesel Generator OPEN N/A 3
10 PO-00540-2 SDG B -
E2 DIG BLDG VENT SUPPLEMENTAL SUP M-385 ODG-"
CLOSED N/A COMMON S
VENTILATION FAN 08V091 DAMPER 127 5215 ACTIVE PO-0O-4F-006402 Diesel Generator OPEN N/A 3
10 PO-00540-3 SOG C-E3 DIG BLDG VENT SUPPLEMENTAL SUP M1485 DIG-CLOSED N/A COMMON S
VENTILATION FAN 0CV091 DAMPER 127 5315 ACTIVE PO.O.4F-o0540-.3 Die Generator OPEN NIA 3
10 PO-00540-4 S0OC -
E4 DIG BLDG VENT SUPPLEMENTAL SUP M.385 DIG-10 CLOSED N/A COMMON S
VENTILATION FAN 00V091 DAMPER 127 5415 ACTIVE PO-i40F4054OO4 Diesel Generator OPEN N/A 3
10 P0O4W-00l17-02 HVAC MASTER FOR EMERG SWGRWWTRY RMS M-399, SHT 4 RNW-32 OPEN NIA COMMON S
5833 ACTIVE VENT EXH TO CR ROOF DAMPER PO-0-4OW-00017-02 165 Radwasse Bldg CLOSED N/A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C.nrrs..nnndf.nr.. Nn ' RR-1 2-173 B-79
DOCUMENT NO, 006700004-O001 REVISION 2 TRAIN SOUG CI Unit Eval Wd?
PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST Nwtt sltow Motive Power Desied state Comtp'.e DATE: 328M98 PAGE 79 Equip 11 P1MS ID System Notes ROB Mowler Comp Drawng NO Loc Code Room Elev Sutpol System Supp SP deg Line No Function sit 3
10 PO-40W-00019.O1 HVAC EMERG SWGR
VENT SUP FAN 0AV034 INLET DAMPER 165 SV-0-369-oo19 5804 ACTIVE PO-0-40WC0019.O1 Radrage Bldg OPEN WA M
M-399. SHlT I 3
10 PO-ow00019-02 HVAC EMERG SWGR + BATTERY ROOMS M-399, SHT 1 RPW-32 OPEN/CLOSED NWA HVAC N2 COMMON S
VENT SUP FAN 0AV034 OUTLET 165 SV4-368-00019 5807 ACTIVE P044OW-00019-02 Radw~te Bldg OPEN NWA M-399, SHT 1 3
10 PO-W-00020-01 WVAC EMERG SNGR + BATTERY ROOMS 1M399, SHT IRPV-32 CLOSED/OPEN NWA T
HVAC N2 COMMON S
VENT SUP FAN 08VO34 INLET DAMPER 165B SV-0-36800020 5811 ACTIVE PO-40W0020-1 Radwaslo Bldg OPEN WA j
-399. SHTi 3
10 PO-4aA.0002042 HVAC EMERG SVGR + BATTERY ROOMS M-399. SHT I RNW-32 CLOSED/OPEN NIA IHVAC N2 COMMON S
VENT SUP FAN 08V034 OUTLET DAMPER 165 SV-0-368-00020 5815 ACTIVE PO)-O40W-000-02 Radwaste Skdg OPEN HIA 3
10 PO40W.00025-1 HVAC EMERGENCY SWITCHGEAR VENT M-399. SHT 4 RNW-32 OPEN NIA HVAC N2 COMMON S
EXHAUST FAN 0AV035 INLET DAMPER 165 SV-0-368-00025 PASSIVE sw1 Radwastp BM0 OPEN NIA 3
10 PO-49Y-00025.02 HVAC EMERGENCY SWITCHGEAR VENT M-399, SHT 4 RNV-32 OPEN MIA HVAC N2 COMMON S
EXHAUST FAN OAV035 OUTLET DAMPER 165 SV-0-36500025 5826 PASSIVE POW4)4002o025-0t Radwate Blg OPEN N/A M-399, SHT 4 3
10 PO-04WOX0O28O HVAC EMERGENCY SWITCHGEAR VENT M-399, SHT 4 RW-32 CLOSED NWA HVAC N2 COMMON S
EXHAUST FAN 0BV035 INLET DAMPER 165 SV-0-368-O002 5828 ACTIVE PO-O.40W-00X26.01 Radwaste Bldg OPEN NIA M-399. SHT 4 3
10 PO-4ow-00026.02 HVAC EMERGENCY SWiTCHGEAR VENT M-399. SHT 4 RNV-32 CLOSED N/A HVAC N2 COMMON S
EXHAUST FAN 0BV035 OUTLET DAMPER 165 SV-0-368-00026 5831 ACTIVE PO-0.40W-00026-02 Radwaste Oldg OPEN MIA M-399. SHT 4 3
10 PO-40W-00031O-1 HVAC BATTERY ROOM VENT EXHAUST FAN M-399, SHT 4 RNV-32 OPEN/CLOSED N/A HVAC N2 COMMON S
0AV036 INLET DAMPER 165 5V-0-368-00031 5817 ACTIVE PO-0.rW.40031-01 Radwaste Bldg OPEN NMA M-399. SHT 4 3
10 PO-40W-I0031.02 HVAC BATTERY ROOM VENT EXHAUST FAN M-399, SHT 4 RNW-32 OPEN/CLOSED NIA HVAC N2 COMMON S
OAVO36 OUTLET DAMPER 165 SV-O-3ý880031 5819 ACTIVE P-0-4OW-MMI031.02 Radwaste OBd OPEN WA I M-399 SHT 4 3
10 PO-40w.00032-01 HVAC BATTERY ROOM VENT EXHAUST FAN M-399, SHT 4 RIW-32 CLOSED/OPEN NIA HVAC N2 COMMON S
08V36 INLET DAMPER 165 SVo-38-Oo 5820 ACTIVE PO-04OW-00032-01 R, waste Bldg OPEN NWA M-399. SHT 4 3
10 PO-40W.00032.02 HVAC BATTERY ROOM VENT EXHAUST FAN M-399, SHT 4 R/N-32 CLOSED/OPEN NWA HVAC N2 COMMON S
08V036 OUTLET DAMPER 165 SV-0-8.00032 5822 ACTIVE P0OW4
-0=42 Radwaste Bkdg OPEN NIA M-399, SlT 4 3
14 O0Y03 EPS 120VAC DISTRIBUTION PANEL E-28, SHT 1 R/W-21 ENERGIZED 00X103 COMMON S
135 8001 ACTIVE 0Y/003 Radwaste Bldg ENERGIZED Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
- orr..nondp.nc.. No** RS-12-173 B-80
DOCUMENT NO. 0067-0005440001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUDIVN EQUIPMENT LIST DATE: 3/28/9M PAGE 80 Norm state Motive powet Support System Desid State CoW Ipowe Supp Sys dwg TRAIN Unit SOUG CI Equip ID Eval reqd?
PIMS ID Syster Not"s Equ" Descriptio ROB Motor Coamp Drawng NO.
Loc Code Room Eev Line No Fundion en; 3
14 0AD13 EPS 125V0C DIST. PANEL (0AD13)
E-26. SHT 2 01G-4 ENERGIZED 20021 COMMON S
127 8000 ACTIVE 0AD13 Diesel Genertor ENERGIZED 3
14 08013 EPS 125VDC DIST. PANEL (08013)
E-26. SHlT 2 D0G-6 ENERGIZED 30023 COMMON S
127 8000 ACTIVE 06013 ies Generator ENERGIZED 3
14 0C013 EPS 125VDC DIST. PANEL (OCD13)
E-26, SHIT 2 DIG-8 ENERGIZED 280306 COMMON S
127 8000 ACTIVE 06013 Dieso Generator ENERGIZED 3
14 00013 EPS 125VDC DIST. PANEL (0DD13)
E-26. SHT 2 DIG-10 ENERGIZED 3D0306 COMMON S
127 8000 ACTIVE 00D13 Diesel Generator ENERGIZED 3
17 0AG12 SDG-A El STANDBY DIESEL GENERATOR E-8 01/-3 OFF 0A013 COMMON SR 127 8001 ACTIVE OAGO12 Diesel Generator ON 6280-ES-155-1 3
17 080312 SDG-8 E2 STANDBY DIESEL GENERATOR E-8 DIG-5 OFF 08013 COMMON SR 127 6003 ACTIVE 09G012 Diesel Gnerator ON-6280-ES-155-1 3
17 0CG12 SDG-C E3 STANDBY DIESEL GENERATOR E-8 OKG-7 OFF 0CD13 COMMON SR 127 8006 ACTIVE 0CG012 Diesel Generator ON 6280-E5-155-1 3
17 0OG12 SDG-,
E4 STANDBY DIESEL GENERATOR E-8 D0G-9 OFF 0OD013 COMMON SR 127 8009 ACTIVE 00G012 Diesel Generator ON 6280-E5-155-I 3
18 PC-368-00016 WHAC EMERG SWGR AIR SUPPLY PRESS M-399. SHT 1 RAW-32 OPERABLE NIA COMMON a
CONTROL (HIGHEST PRESSURE RELAY) 165 5906 ACTIVE PC-0OW16 00F043 Ractaste Bldg OPERABLE N/A SK-M-651 3
19 HD-.50A SOGA El DIG CARDOX HEAT DETECTOR M-46,24. SHlT 2 D/G-3 OPERABLE WA COMMON 5
127 ACTIVE HD-550A Diesel Generator OPERABLE WA M-713-1.1 3
19 "D-5508 S0G-A El DiG CARDOX HEAT DETECTOR M-46-24. SHT 2 01G-3 OPERABLE NWA COMMON S
127 ACTIVE H0-550B DiOsel Geeator OPERABLE WA M-713-1-1 3
19 HD-551A SDG-A El DIG CARDOX HEAT DETECTOR M-46-24, SHIT 2
127 ACTIVE HD-551A Diesel Generator OPERABLE NIA M-713-1E1 3
19 HD0-551B SDG-A El D/G CARDOX HEAT DETECTOR M-46-24, SHlT 2 01G-3 OPERABLE W/A-COMMON S
ACTIVE KD-551S Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CorrPAqnnd-ncr. Nn.: RS-12-173 127 Diesel Generator OPERABLE WA M-713-1-1 B-81
DATE: &2M DOCUMENT NO. 0067.0008440001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 81 REVISION 2 SAFE SHUTDOWN EOUIPMENT LIST TRAIN SOUG Cl Equip ID System Equip Desciption Drawing No.
Loc Code Norm state Motive power Support System Uni Eval (04d?
PIM$ D0 Notes ROB Mo01w Comp RooD EI esired Slate ContrPower Supp Sys deg Lile No Function BSUN 3
19 HD-552A SDG-A El DIG CARDOX HEAT DETECTOR M-46-24. SiT 2 DIG-3 OPERABLE N/A COMMON S
127 ACTIVE HD-552A Diesel Gnator OPERABLE NIA M-713-1-I 3
19 HD-5528 SDG-A El D/G CARDOX HEAT DETECTOR M-46-24. SHT 2 DIG-3 OPERABLE N/A COMMON S
127 ACTIVE HD-5528 ODiel Geneator OPERABLE N/A 11.713-t-11 3
t9 HD-553A SDG-A El DIG CARDOX HEAT DETECTOR M146-24. SHT 2 DIG-3 OPERABLE N/A COMMON S
127 ACTIVE HO-53A Diesel Genertor OPERABLE N/A M-713-1-1 3
19 HD-5538 SOG-A El DIG CARDOX HEAT DETECTOR M-46-24. SHIT 2 D/G-3 OPERABLE N/A COMMON S
127 ACTIVE HD-553B Diesel Generator OPERABLE N/A M-713-1 3
19 HO-554A SDG-A El D/G CARDOX HEAT DETECTOR M-46-24. SHT 2 D/G-3 OPERABLE N/A COMMON S
127 ACTIVE HD-554A Diesel Generator OPERABLE N/A M-713-1-1 3
19 HD-5540
$OG-A El DIG CARDOX HEAT DETECTOR M-46,24, SHT 2 D/G-3 OPERABLE N/A COMMON S
127 ACTIVE HD-5540 Diesel Generator OPERABLE N/A M-713-1-1 3
19 HD-555A S0G-A El DIG CARDOX HEAT DETECTOR M-48-24. SHIT 2 0/G-3 OPERABLE N/A COMMON S
127 ACTIVE HO-51S Diesel Getrarmor OPERABLE N/A M-713-1 -1 3
19 HD55.8 SDG-A El DiG CARDOX HEAT DETECTOR M-46-24, SHT 2 DIG-3 OPERABLE N/A COMMON S
127 ACTIVE HD-5S5B Diesel Generator OPERABLE NWA M-713-1-1 3
19 HO-656A SDG-A El D/G CARDOX HEAT DETECTOR M-46-24. SHT 2 D/G-3 OPERABLE NIA COMMON S
127 ACTIVE HD-556A Die Generto OPERABLE N/A M-713-1-1 3
19 HD-556B SOG-A El DIG CARDOX HEAT DETECTOR M-46-24. SHT 2 0/0-3 OPERABLE N/A COMMON S
127 ACTIVE HD-556B Diesel Generator OPERABLE WA 3
19 HD-557A SO0-A El DIG CARDOX HEAT DETECTOR M-46-24. SNT 2 D/G-3 OPERABLE N/A COMMON S
127 ACTIVE HD-557A Diesel Generator OPERABLE N/A M-713-1-1 3
19 HD-5578 SDG-A El DIG CARDOX HEAT DETECTOR M.46-24. SHT 2 0/1-3 OPERABLE N/A COMMON S
127 ACTIVE HD0-57B Diesel Generator OPERABLE N/A M-713-1-1 3
19 MD-796A SOG-8 E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 O/G-5 OPERABLE N/A COMMON S
127 ACTIVE HD-796A Diesel Genwtor OPERABLE N/A M-713-1-1 Peach Bottom Atomic Power Station Unit 3 B-82 MPR-3812, Revision 3 CnrrP..nnndp.nrP. Nn - R.-17-173
DOCUMENT NO. 0067.00084-DO00 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE. 3&289A PAGE 82 Norm state Motive power Sscpor System Deswed State Corer pow Sys dwo TRAIN SOUG Ci Equip ED Eval eld7 PLUS tD Syse Notels Equip Desaviborn ROB MotM Comp Loc Code Room Elev Line No Funcion Buidng 3
19 HD-7968 SDG-8 E2 01G CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE WA COMMON S
127 ACTIVE HO-7968 Dies1 Generator OPERABLE NIA M-713-1-1 3
19 HD-797A SOG-8 E2 DIG CARDOX HEAT DETECTOR M-46-24, SHlT 3 DG-OPERABLE NIA COMMON S
127 ACTIVE HD-797A Diesel Generator OPERABLE N/A IM-713-1-1 3
19 OD-7978 SDG-8 E2 DIG CARDOX HEAT DETECTOR M46-24, SHT 3 D/G-5 OPERABLE NWA COMMON S
127 ACTIVE HD-7978 Diesel Generator OPERABLE NIA 3
19 HD-7SaA SOG-8 E2 DIG CARDOX HEAT DETECTOR M-46-24, SHIT 3 DIG-5 OPERABLE NIA COMMON S
127 ACTIVE HD-798A Diesel Generator OPERABLE NWA M-713-1-1 3
19 HD-7988 SDG-S E2 DMG CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE N/A COMMON S
127 ACTIVE HD-7908 Diesel Generator OPERABLE NIA M-713-1-1 3
19 HD-799A SOG3-E2 DIG CARDOX HEAT DETECTOR M446-24. SHT 3 D/G-5 OPERABLE N/A COMMON S
127 ACTIVE MD-799A Diesel Generator OPERABLE NWA M-7T3-1-1 3
19 NO-7998 SDGC-E2 D/G CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE NWA COMMON S
127 ACTIVE HD-7998 Diesel Generator OPERABLE NWA M-713-1-1 3
19 HD-1ODA SDG0B E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 DIG-6 OPERABLE NIA COMMON S
127 ACTIVE HO-SODA Diesel Generator OPERABLE NIA M-713-1-1 3
19 HD-80OO SDG3-E2 DIG CARDOX HEAT DETECTOR M4-6-24. SHT 3 D/G-5 OPERABLE N/A COMMON S
127 ACTIVE HD-400 Diesel Generator OPERABLE NIA M-713-1-1 3
19 HDO-DIA SDO-"
E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 DrG-S OPERABLE NIA COMMON 8
127 ACTIVE HD-801A Dies Gense ato OPERABLE NIA W-713-1-1 3
19 HD-801B SDG-B E2 I/G CARDOX HEAT DETECTOR M-46-24. SHT 3 DIG-5 OPERABLE N/A COMMON S
127 ACTIVE HD-8D1B Diesel Generator OPERABLE NIA M-713-1-1 3
19 HD-802A SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 O/G-5 OPERABLE NIA COMMON S
127 ACTIVE HD-802A Diesel Generator OPERABLE NIA M-T713-1-1 3
19 HO-8025 SOC-S E2 DIG CARDOX HEAT DETECTOR 11-45-24, SHT 3 DIG-S OPERABLE N/A COMMON S
ACTIVE 127 Diesel Generator OPERABLE NWA HD-602B M-713-1-1 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrP..*nnndrPnrA. Nn - RS-19-173 B-83
DOCUMENT NO. 006740084-I001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Nasmn SIMt Man"v Power support System Desired State CorII power SUPP SYS "0g DATE: 31211M PAGE 83 TRAIN SOUG Cl Equip 10 Evel reqd?
PUMS to systm Noles Equip Descition ROB Mamw Caxnp Dmelng No.
Loc Code Room Elov Line No Function 6ad&y0 3
19 HD-803A SG.-8 E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 DIG-6 OPERABLE N/A COMMON S
127 ACTIVE HD-803A Diesel Generator OPERABLE N/A 38-713-1-1 3
19 H-O8038 SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 DoG-"
OPERABLE N/A COMMON S
127 ACTIVE HD-S0=
Diesel Genetalr OPERABLE IA M-713-1-1 3
19 HD)804A SDG-C E3 D/G CAROOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE N/A COMMON S
127 ACTIVE HD-804A Diesel Generator OPERABLE N/A M-7113-1-14 3
19 D-D8048 SOG-C E3 D/G CARDOX HEAT DETECTOR M-48-24. SHT 4 DIG-7 OPERABLE N/A COMMON S
127 ACTIVE 0D-4048 Diesel Generator OPERABLE WA M-713-1-1 3
19 HD-805A So"-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 D/G-7 OPERABLE N/A COMMON S
127 ACTIVE 1-80.WA Diesel Generator OPERABLE N/A M-713-1-1 3
19 HO-80BS SDG-C E3 DIG CAROOX HEAT DETECTOR M-48-24. SHT 4 O/G-7 OPERABLE N/A COMMON S
127 ACTIVE HD-805B Diesel Generator OPERABLE N/A M-713-1.1 3
19 HD806A SDG-C E3 D/G CARDOX HEAT DETECTOR M-48-24. SHT 4 DIG-7 OPERABLE N/A COMMON S
127 ACTIVE HD-805A Diesel Generator OPERABLE N/A M-7113-11.1 3
19
,80436(
sDG-C E3 D/G CARDOX HEAT DETECTOR M4-6-24, SHT 4 DIG-?
OPERABLE N/A.
COMMON S
127 ACTIVE H-06B Diesel Generator OPERABLE N/A M-713-1-1 3
19 HD-807A SOG-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 N/A M-713-1-1 3
19 HD-8078 SOG-C E3 DIG CARDOX HEAT DETECTOR M-48-24, SHT 4 DIG-?
OPERABLE N/A COMMON S
127 ACTIVE HO-8078 Diesel Generator OPERABLE N/A M-713-1-1 3
19 HD-804A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 D/G-7 OPERABLE NIA COMMON S
127 ACTIVE D804M Die Generator OPERABLE NIA 3-713-1-1 3
19 H04088 SDG-C E3 DIG CAROOX HEAT DETECTOR M-48-24, SHT 4 DIG-?
OPERABLE N/A COMMON S
127 ACTIVE D4-08 Diesel Generator OPERABLE NWA M-713-1-1 3
19 HD-809A SDG-C E3 D/G CARDOX HEAT DETECTOR M-46-24. SHT 4 D/G-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 3 MPR-3812, Revision 3
(.nrrp*,nnndp.nr.e Nn - RR-19-173 B-84
DOCUMENT NO. 006740054-4O01 REVISION 2 TRAIN SOUGC Equi 11 UfM Eval tac'd?
PINS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 8AWE SHUTDOWN EQUIPMENT LIST DATE: 31281M6
~PAGE U4 N orm state M obire P vM S aW t System Desired State CaW powe SW Sys dwg Notes ERO hDesrionp ROB Mother Camp Dramirig NO.
Laoc Code Roan Elev Lim NO Function Budinkg 3
19 HDO-8M SG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 00G-7 OPERABLE WA COMMON S
127 ACTIVE HD-8098 Diesel Generator OPERABLE WA 14-713-1-1 3
19 HD-811A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE MIA COMMON 8
127 ACTIVE HD-10kA Diesel Generator OPERABLE NWA 1
3 19 H0-4108 SDG-C E3 D/G CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE WA COMMON S
127 ACTIVE HD-108 Diesel Generator OPERABLE NIA M-713-1-1 3
19 HO-811A SDG-C E3 DIG CARDOX HEAT DETECTOR M-48-24. SHT 4 DIG-7 OPERABLE NWA COMMON S
127 ACTIVE HD-811A DiUss Generator OPERABLE MIA W-713-1-1 3
19 HD-8118 SDG-C E3 DIG CAROOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE NZA COMMON S
127 ACTIVE Ho-aiis Diesel Generator OPERABLE WA M-713-11-1 3
19 HD-1I2A SDG)-
E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT S DIG-9 OPERABLE NIA COMMON S
127 ACTIVE HD-812A Diesel Generator OPERABLE NWA M-713-1-1 3
19 HD-812B 0DG-0 E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT S 01G-9 OPERABLE WA COMMON S
127 ACTIVE HO-8128 Diesel Generator OPERABLE NWA M-713-1.1 3
1 MD-1S3A SDG-0 E4 0iG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HO-813A Diesel Generator OPERABLE NWA M-713-1-1 3
Is H"8318 SOG-O E4 DIG CARDOX HEAT DETECTOR M-48-24, SHT 5 D0G-8 OPERABLE WUA COMMON S
127 ACTIVE HD-813B Diesel Generator OPERABLE WIA M-713-1-1 3
19 HD-814A SDG4)
E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT 5 DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HO-O1AA Diesel Generator OPERABLE WA M-713-1-1 3
19 HD-8148 SDG-0 E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT 5 DIG-9 OPERABLE NIA COMMON S
127 ACTIVE H"-814B Diesel Generator OPERABLE WA M-713-1-1 3
1 HD-815A SDG-O E4 0DG CARDOX HEAT DETECTOR M-46-24, SHT 5 DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HD-815A Diesel Generator OPERABLE NWA M-713-1-1 3
19 HD-8158 SOG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE NWA COMMON S
ACTIVE 127 Diesel Generator OPERABLE NWA HD-8150 M-713-I-1 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Cnrr.qnnnd*.nrP. Nn - RS-19-17.1 B-85
DOCUMENT NO. 0067-0084-D001 REVISION 2 TRAIN SOUG CI EquID Unft Eval req'd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST N orm M ost t
p ow e r Desired State Cont, power DATE: 3028136 PAGE U System Notes Equip Desaorptiw ROB Motde Crnp Orawkv No.
Loc Code Room Elev suppor Systm Supp SYs dwg Lk* No Fundion Buklkn 3
19 HD-816A SO")
E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 OIG-9 OPERABLE NIA COMMON S
127 ACTIVE HD-816A Oiese Generator OPERABLE NIA M-713-1-1 3
19 HO-8168 SOG-0 E4 DIG CARDOX HEAT DETECTOR M-46-24, BHT 5 DIG-OPERABLE N/A COMMON S
127 ACTIVE H0,8168 Diesel Generator OPERABLE NIA 3
19 ND-817A SDG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 D/G-9 OPERABLE NZA COMMON S
127 ACTIVE HD-817A Diesel Generator OPERABLE WA 44-713-1-1 3
19 HD-817B SDG-D E4 D/G CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE NIA COMMON S
127 ACTIVE HO-8178 Oiesel Generaor OPERABLE MIA M-713-1-1 3
19 HDNSl8A SDG-O E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HD-818A Diesel Generator OPERABLE W/A M-713-1-1 3
19 HD-8188 SDG-0 E4 DIG CAROOX HEAT DETECTOR M-46-24. SHIT 5 DIG-9 OPERABLE N/A COMMON S
127 ACTIVE MD-8188 Diese Generator OPERABLE N/A M-713-1-1 3
19 HO-SI1A SOG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT S DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HD-819A oiesel Gonerstor OPERABLE NIA M-713-1-1 3
Is hO-"198 SDG-0 E4 0G CARDOX HEAT DETECTOR M-4624. SIfT 5 DIG-9 OPERABLE NWA COMMON S
127 ACTIVE HO.8198 Diesel Generator OPERABLE NIA M-713-1.1 3
20 00C29A EPS EMERGENCY PROTECTION RELAY 1T2.100 OPERABLE NWA COMMON S
BOARD 165 8000 ACTIVE 00CO29A Turbie Oldg -U2 OPERABLE WA E-7-30. E17-539-1 3
20 00C298 EPS EMERGENCY PROTECTION RELAY T2-100 OPERABLE N/A COMMON S
BOARD 165 8000 ACTIVE 00C0298 Tunbe Bldg - U2 OPERABLE NIA E-7-30. E17-539-1 3
20 00C290 EPS EMERGENCY PROTECTION RELAY T2-I00 OPERABLE NWA COMMON S
BOARD 165 1
s000 ACTIVE 00CO29C Tubine t
- U2 OPERABLE WIA E-7-30. E17-539-1 3
20 00C290 EPS EMERGENCY PROTECTION RELAY T2-100 OPERABLE WA COMMON S
BOARD 165 8000 ACTIVE 00CO29D Turbine U2 OPERABLE NA E-7-30.E217-539-1 3
20 0AC097 SDG-A DIESEL GENERATOR 0AG12 CONTROL DG.-3 OPERABLE NWA E
COMMONuJ S
PANEL ACTIVE 0AC097 Diesel Genrator OPERABLE WZA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrt-.nnndPrn-.P Nn RR-1 2-173 B-86
DOCUMENT NO. 0067-504MOS44O1 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Noim stawe Motive power Support System Desod State Couur power Sutp Sys lgl DATE: 3/28/96 PAGE 8" REVISION 2 TRAIN UNt SQUO CI Eq'p IO Eval re(d?
PIMS ID system Notes Equip Descriti~ort ROB MottW Camp Loc Code Room Elev Life No Funcion
- ewf, 3
20 0AC142 SOG-A STANDBY DIESEL ENGINE CONTROL A DG-,3 OPERABLE NIA COMMON a
PANEL 127 ACTIVE OAC142 GAG12 D
20 OAC216 SOG.A DIESEL C02 SYSTEM ELECTRICAL DG-3 OPERABLE N/A COMMON S
CONTROL (20S102) 127 ACTIVE 0AC216 Diesel Genetor OPERABLE N/A M-713 3
20 0AC479 SDGA-El DIG ROOM SUPPLY TEMP CONTROL M-385 D/G-13 OPERABLE N/A COMMON S
VENTILATION 181 5112 ACTIVE TIC.0)272 Diesel Generator OPERABLE N/A 3
20 OAGl3 SOG.A El 0/G P.T. AND EXCITATION E-8 D/G-4 OFF OAD13 COMMON SR EQUIPMENT 127 8002 ACTIVE 0AGO13 Diesel Generator ON E-6-35-7 3
20 O8C097 SG43 DIESEL GENERATOR 08G12 CONTROL D/G-OPERABLE NIA COMMON S
PANEL 127 ACTIVE 08C097 Diesel Generator OPERABLE NIA 3
20 0SC142 SDG-8 STANDBY DIESEL ENGINE CONTROL B
-DG-S OPERABLE N/A COMMON a
PANEL 127 ACTIVE 0BC142 08G12 Diesel Generator OPERABLE N/A 3
20 0OC216 SG-8 DIESEL C02 SYSTEM ELECTRICAL D/G-5 OPERABLE N/A COMMON S
CONTROL (20SI02) 127 ACTIVE 0SC216 Diesel Genestor OPERABLE N/A I M-713 3
20 08C479 SDGB -
E2 DIG ROOM SUPPLY TEMP CONTROL M-385 0/G-15 OPERABLE N/A COMMON S
VENTILATION 151 5212 ACTIVE TIC-00273 Diesel Generas*
OPERABLE N/A 3
20 0813 SDG-B E2 D/G P.T. AND EXCITATION E-8 o/G-"
OFF 08013 COMMON SR EQUIPMENT 12?
SamS ACTIVE 0BGO33 Diesel Generator ON E-6-35.7 3
20 OCCO97 SOG-C DIESEL GENERATOR OCG12 CONTROL DIG-8 OPERABLE N/A COMMON S
PANEL 127 ACTIVE 0CCO97 Diesel Generator OPERABLE N/A 3
20 OCC142 SO" STANDBY DIESEL ENGINE CONTROL C D/G-7 OPERABLE N/A COMMON B
PANEL 127 ACTIVE 0CC142 OCG12 Diesel Generator OPERABLE N/A 3
20 0CC216 SO"-C DIESEL C02 SYSTEM ELECTRICAL DfG-?
OPERABLE N/A COMMON S
CONTROL (20S102) 127 ACTIVE OCC216 Diesel Generator OPERABLE N/A M-713 3
20 0CC479 SOS C -
E3 DIG ROOM SUPPLY TEMP CONTROL I4-385 D0G-I7 OPERABLE N/A COMMON S
5312 ACTIVE VENTILATION 151 Generator OPERABLE NIA TfC-00274 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 CnrrP.qnnndp.nr.A Nn
- RR-1 9-173 B-87
DOCUMENT NO. 0027-0004-001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3/28/96 PAGE 87 Norm state mob" power Support System Desired State Conr power Supp Sys daw TRAIN SQUG CI EquP ID Eval re'd?
PIUS ID System Notes Equ DesIprion ROB Mother Comp D(wavg NO.
Loc Code Room El.v Line No Function Building 3
20 OCGI3 SOG-C E3 DIG P.T. AND EXCITATION E-a O/G-8 OFF OCD13 COMMON SR EQUIPMENT IV 8008 ACTIVE 0CGM13 Diesel Generator ON E-5-35-7 3
20 ODC097 SDG.-
DIESEL GENERATOR 0DG12 CONTROL DIG-10 OPERABLE NIA COMMON S
PANEL 127 ACTIVE 0DCO97A Diesel Generator OPERABLE NWA 3
20 0DC142 SDG)-
STANDBY DIESEL ENGINE CONTROL 0 DOG-S OPERABLE NIA COMMON 8
PANEL 127 ACTIVE 0DC142 OD12 Diesel Generator OPERABLE NWA 3
20 0=C216 SOG-O DIESEL C02 SYSTEM ELECTRICAL D/G-9 OPERABLE WA COMMON S
CONTROL (206102)
IV ACTIVE 00C216 Diesel Generatr OPERABLE WA M-703 3
20 0DC479 SD;D -
E4 DIG ROOM SUPPLY TEMP CONTROL M-3M DIG-IS OPERABLE NWA COMMON S
VENTILATION 151 5412 ACTIVE TIC-00275 Diesel rator OPERABLE N/A 3
20 0DG13 SDG)-
E4 DIG P.T. AND EXCITATION E-8 DIG-10 OFF 00013 COMMON SR EQUIPMENT 127 8011 ACTIVE 0O0013 Diese Generator ON E-5-35-7 3
20 LIC-52G-7250A SD0-A - LUBE OIL El DIG LUBE OIL SUMP LEVEL M-377. SHT 3 O/G-4 OPERABLE NWA COMMON B
REGULATOR 127 5129 ACTIVE LIC-7250A a
OAG12 Diesel Generator OPERABLE NWA 3
20 LIC-52G-72508 SDG LUSE OiL E2 DIG LUSE O-l" SUMP LEVEL M-377, SHT 3 01/3.
OPERABLE NA COMMON B
REGULATOR 127 5229 ACTIVE LIC-72508 6
0BG12 Diesel Generator OPERABLE NWA 3
20 LIC-52G-7250C SDG-C - LUBE OIL E3 D/G LUBE OIL SUMP LEVEL M-377. SHT 3 O/G-8 OPERABLE WA COMMON B
REGULATOR 127 5329 ACTIVE UC-7250C 6
0CG12 Diesel Generator OPERABLE NWA 3
20 LIC-52G-72500 SDG-D - LUBE OIL E4 DIG LUBE OIL SUMP LEVEL M-377, SHT 3 DIG-10 OPERABLE N/A COMMON a
REGULATOR 127 5429 ACTIVE LIC-72500 6
00G12 0iesel Generator OPERABLE N/A 3
20 LS-0566A SOG-A - FUEL OIL El D/G FUEL OIL DAY TANK LEVEL M-377. SHT 4 0/G-3 OPERABLE N/A COMMON B
SWITCH FOR OAT40 127 5144 ACTIVE LS-05WA 0AT40 Diesel Generator OPERABLE N/A 3
20 LS-0566B SDG$-- FUEL OIL E2 D/G FUEL OIL DAY TANK LEVEL M-377. SHT 4 DIG-S OPERABLE N/A COMMON B
SWITCH FOR OBT40 127 5244 ACTIVE LS-05668 OBT40 Diesel Generator OPERABLE WA 3
20 LS-0566C SDG-C -FUEL OIL E3 DIG FUEL OIL DAY TANK LEVEL M-377. SHT 4 DIG-7 OPERABLE NWA SWITCH FOR OCT40 5344 ACTIVE LS-0566C OCT40 127 Diesel Genrtoator OPERABLE N/A Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
('nrrm.qnnnd.nr.p No
- RR-1 2-17.3 B-88
DOCUMENT NO. 0067-4004-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3121M19 PAGE 58 Norm state Moase power SuPPt Systea Oesred State Coam power Supp Sys dwg TRAIN unit SOUG Cl Equp D Eval re~d7 PlMS ID Noes Equi Desartion RO Moer Cofp 0wft No.
LoC Code Room Elev Lae No Fundimi Building 3
20 LS-05660 SOG-O - FUEL OIL E4DIG FUEL OIL DAY TANK LEVEL M-377, SHT 4 DIG-9 OPERABLE N/A COMMON B
SWITCH FOR 00T40 127 5444 ACTIVE LS-0566D 0DT40 Diesel Generator OPERABLE NZA 3
20 PS.0623A SOC-A El DIG CRANKCASE PRESSURE SWITCH M-377, SIHT3 DIG-3 OPERABLE WA COMMON 8
127 ACTIVE PS-0123A OAG12 Diesel Generator OPERABLE WA 3
20 PS-0623B SO-8 E2 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 DIG-5 OPERABLE WA COMMON B
127 ACTIVE PS-062 0BG12 Diesel Generator OPERABLE NIA 3
20 PS-0623C SG-C E3 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 01G-7 OPERABLE NWA COMMON a
127 ACTIVE PS-0623C 0CG12 Diesel G OPERABLE NIA 3
20 PS-08230 SOG-D E4 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 D/G-9 OPERABLE NIA COMMON 8
127 ACTIVE PS-0623D 00012 Diesel Generator OPERABLE NWA 3
20 PS-0624A SOG-A El 10G CRANKCASE PRESSURE SWITCH M-377, SHT 3 010.3 OPERABLE NIA COMMON B
127 ACTIVE PS-=624A 0AG12 Diesel Generator OPERABLE NWA 3
20 PS-06248 SOG-8 E2 0G CRANKCASE PRESSURE SWITCH M377, SHT 3 DIG.S OPERABLE WA COMMON 8
127 ACTIVE PS-06248 00G12 Diesel Generator OPERABLE NIA 3
20 PS-,624C SD"0 E=3 DIG CRANKCASE PRESSURE SWITCH M-3fl. SHT 3 D0G-7 OPERABLE WA COMMON a
127 ACTIVE PS-0624C 0CG12 Diesel Generator OPERABLE NIA 3
20 PS-0624D SOG-0 84 DIG CRANKCASE PRESSURE SWITCH M-377, SHlT 3 DIG-9 OPERABLE WA COMMON a
127 ACTIVE PS-06240 0DG12 Diesel Generator OPERABLE WA 3
20 PS-0625A SDG-A El DIG CRANKCASE PRESSURE SWITCH M-377. SHT 3 DIG-3 OPERABLE NWA COMMON B
127 ACTIVE PS-0625A OAG12 Diesel Generator OPERABLE NWA 3
20 PS4)6258 SDG-B E2 DIG CRANKCASE PRESSURE SWITCH M-377. SIT 3 DIG-S OPERABLE WA COMMON B
127 ACTIVE PS-06258 08G12 Diesel Generator OPERABLE WA 3
20 PS-06C SDG-C E3 DIG CRANKCASE PRESSURE SWITCH M-377. SHT 3 DIG-7 OPERABLE NWA COMMON a
127 ACTIVE PS.0625C OCG12 Diesel Generator OPERABLE NWA 3
20 PS-06250 SDG-D E4 DIG CRANKCASE PRESSURE SWITCH M-377. SHlT 3 DIG-9 OPERABLE NWA COMMON B
ACTIVE 127 Diesel Generator OPERABLE NWA PS-0625D 0OG12 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
.nrrPmnnnrlPnp Nn" RS-1 9-17.3 B-89
DOCUMENT NO. 006740084)001 REVISION 2 TRAIN SQUG Cl Equip ID Unit Eval reaqd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm slate Motlve power Suppor System Desired State Corn power Supp Sys dwg DATE: 3289 PAGE 89 System Notes Equip Desorlplon ROB Mother Camp Drawing No.
LoC Code Room Elev Line No Fuiclton Buulin 3
20 TIC-00272 SOG A-El DIG ROOM SUPPLY TEMP CONTROL M-385 DIG-13 OPERABLE NIA COMMON B
VENTILATION 161 5112 ACTIVE TIC400272 iesel rator OPERABLE NIA 3
20 TIC-0273 SDG B-E2 DIG ROOM SUPPLY TEMP CONTROL M-385 DIG-15 OPERABLE WA COMMON a
VENTILATION 151 5212 ACTIVE TIC..0W73 Diesel Generator OPERABLE NIA 3
20 TIC.30274 SDG C-E3 DIG ROOM SUPPLY TEMP CONTROL M-385 QfG-17 OPERABLE WA COMMON B
VENTILATION 151 5312 ACTIVE TIC-0274 Diesel Generator OPERABLE W/A 3
20 TIC-00275 S00 D -
E4 D/G ROOM SUPPLY TEMP CONTROL M-385 D/G-19 OPERABLE NWA COMMON a
VENTILATION 151 5412 ACTIVE TIC-0W75 Diesel Generator OPERABLE WA 3
20 TS-0587A SDG-A El DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-3 OPERABLE NWA COMMON B
127 ACTIVE TS-0687A D
20 TS-OS87B SDG-B E2 DIG LUSE OIL TEMPERATURE HI M-377. SHT 3 DIG-S OPERABLE NWA COMMON B
127 ACTIVE TS-0875 s Generator OPERABLE NWA 3
20 TS-0587C SOG-C E3 D/G LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-7 OPERABLE WA COMMON B
127 ACTIVE TS-0587C Diesel Generator OPERABLE N/A 3
20 TS.05870 SDG-O E4 D/G LUBE OIL TEMPERATURE HI M-377. SHY 3 D0G1 OPERABLE NIA COMMON a
127 ACTIVE TS-0587D Diese Genertor OPERABLE NWA 3
20 TS-O588A SDG-A El DIG LUBE OIL TEMPERATURE HI M-377, SHT 3 DIG-3 OPERABLE N/A COMMON B
127 ACTIVE TS-QS88A Diesel Generator OPERABLE NWA 3
20 TS-05888 SDG-B E2 DIG LUBE OIL TEMPERATURE HI M-377, SlT 3 DIG-5 OPERABLE WA COMMON 8
127 ACTIVE TS-0588B Diesel Generator OPERABLE WIA 3
20 TS-0588C SDG-C E3 DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-7 OPERABLE WNA COMMON 8
127 ACTIVE TS-O88C Diesel Generator OPERABLE NWA 3
20 TS-05880 SDG-D E4 DIG LUBE OIL TEMPERATURE HI M-377. SHlT 3 DIG-9 OPERABLE NWA COMMON B
127 ACTIVE TS-0588D Diesel Generator OPERABLE N/A 3
20 TS-0589A SDG-A El DIG LUBE OIL TEMPERATURE HI M-377. SIHT 3 DIG-3 OPERABLE NZA COMMON a
ACTIVE 127 Diesel Generator OPERABLE
- N/A TS-05MA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 fnrrP..qnnndPnr.P Nn
- RS-1 2-173 B-90
DOCUMENT NO. 0067-000544)(01 REVI*ON 2 TRAIN SOUG Cl Equp ID Unit Eval red?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3r28196 PAGE 90 Norm state Motive power Support System Desltrad State Cam powe Supp Sys dWg Sytem Notes Equpe Desption ROB MohWer Camp Drawft No.
Loc Code Room Elev Lue No Funcion Bulev 3
20 TS-0589B SOG-S E2 D/G LUBE OIL TEMPERATURE HI M,-377. SHT 3 D/G-5 OPERABLE N/A COMMON B
127 ACTIVE TS-05898 Disel Generator OPERABLE WA 3
20 TS0589C SDG-C E3 DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 0/G-7 OPERABLE WA COMMON B
127 ACTIVE TS-0589C Diesel Generator OPERABLE NIA 3
20 TS-0589D SG-O E4 0/G LUBE OIL TEMPERATURE HI M-377, SHT 3 0/C-9 OPERABLE WA T
COMMON a
127 ACTIVE TS-05WD Diesel Goneato OPERABLE NWA 3
20 TS-0605A SOG-A El DIG JACKET COOLANT M-377. SlIT 2 O/G-3 OPERABLE WA COMMON B
TEMPERATURE HI 127 ACTIVE TS-0605A Diesel Generator OPERABLE N/A 3
20 TS-0608 SDG-B E200G JACKET COOLANT M.-377, SHlT 2 DG.-5 OPERABLE N/A COMMON 8
TEMPERATURE HI 127 ACTIVE TS-06058 Diese Generator OPERABLE N/A 3
20 TS-0605C SDG-C E3 0/G JACKET COOLANT M-377. SHT 2 D/G-7 OPERABLE WA COMMON 9
TEMPERATURE HI 127 ACTIVE TS-0C Diesel Geno OPERABLE NWA 3
20 TS-06050 SOG-o E4 DIG JACKET COOLANT M-377, SHT 2 010-.
OPERABLE NWA COMMON B
TEMPERATURE HI 127 ACTIVE TS4-OSO Diesel GaernW OPERABLE NWA 3
20 TS-060A SDG-A El O/G JACKET COOLANT M-377, SHT 2 0/G-3 OPERABLE NWA COMMON B
TEMPERATURE HI 127 ACTIVE TS-060SA Diesel Geneato OPERABLE WA 3
20 TS-O66S SDG-8 E2 DIG JACKET COOLANT M-377. SKT 2 D/G-5 OPERABLE NWA COMMON B
TEMPERATURE HI 127 ACTIVE TS-06B Diesel Genertor OPERABLE NWA 3
20 TS-0606C SOG-C E3 I/G JACKET COOLANT M-377. SHIT 2 0/G-7 OPERABLE WA COMMON TEMPERATURE HI 127 ACTIVE
- DiGeneator OPERABLE WA 3
20 TS-06060 SDG-D E4 D/G JACKET COOLANT M-377. SHT 2 0/C-9 OPERABLE NWA COMMON B
TEMPERATURE HI 127 ACTIVE TS-06060 Diesel Generator OPERABLE WA 3
20 TS-O607A SOG-A El 0/G JACKET COOLANT M-377. SilT 2 0/G-3 OPERABLE NWA COMMON 6
TEMPERATURE HI 127 ACTIVE TS-0607A Diesel Generator OPERABLE NWA 3
20 TS-0607B SoG-a E2 Dr/ JACKET COOLANT M-377, SHT 2 D/G-5 OPERABLE WA COMMON 1
TEMPERATURE HI 4.7 ACTIVE TS-0607B Oiesel Generator OPERABLE NWA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3
(.nrrP.nnndP.nr. Nn
- RS-12 -173 B-91
DATE: 3128/g6 DOCUMENT NO. 0067-00084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 91 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip 10 System Equip Desciption Drawf No, Loc Code Norm Stt Motive power Support System Unif Eva Mq'd?
PiMS id Notes ROB Mother Comp Room E8ev Dwed State Coo power supp Sys ewg Line No Funcion Bat 3
20 TS-0607C SDG-C E3 D/G JACKET COOLANT M-377. SHT 2 DIG-7 OPERABLE IVA COMMON a
TEMPERATURE HI 127 ACTIVE TS-0607C Di" Generator OPERABLE N/A 3
20 TS-06070 SDG-D E4 DIG JACKET COOLANT M-377, SHT 2 DIG-9 OPERABLE N/A COMMON a
TEMPERATURE HI 127 ACTIVE TS-06O0D Diesel Generator OPERABLE A
3 21 0AE073 HVAC EMERG SWGR VENT SUP HEATING M-3s9, SHT 1 RNW-32 OFF N/A COMMON 8
COIL A 165 f805 PASSIVE 0AE073 OAV034 RadwaNe Bldg NA N/A 3
21 0AE126 SOG-A - LUSE OIL El D/G LUSE OIL STANDBY HEATER M-377. SHT 3 DIG-3 OPERABLE N/A COMMON 8
127 5131 PASSIVE 0AE126 Diesel Generator OPERABLE N/A 3
21 OAE376 SOG-A - DIESEL El DIG JACKET COOLANT COOLER M-377. SHT 2 DIG-3 OPERABLE N/A COMMON B
COOLING 127 5123.5500 PASSIVE 0AE376 Dies" Generator OPERABLE N/A Vendor 11905551 3
21 0AE377 SDG-A - LUBE OIL El DIG LUBE OIL COOLER M-377. SHT 3 DIG-3 OPERABLE N/A COMMON a
127 5139.5501 PASSIVE 0AE3T7 Diesene rator OPERABLE WA Vendor 11905551 3
21 OAE378 SDG-A-DIESEL El DIG AIR COOLANT COOLER M-377. SHT 2 DIG-3 OPERABLE WA COMMON a
COOLING 127 5116, 5502 PASSIVE 0AE378 Diesel Generator OPERABLE N/A Vendor 11906551 3
21 0AS384 HVAC BACKUP NITROGEN TO OBVD35 AND M4399. SHT I RNV-29 OPERABLE N/A COMMON S
OA&BV034 FAN DAMPERS 165 5900 PASSIVE 0AS354 Radwaste Bldg OPERABLE N/A M-2801-3.M-1876 3
21 0AS385 HVAC BACKUP NITROGEN TO 0V036 AND M-399, SHT 4 RAW-32 OPERABLE N/A COMMON B
OA&BV035 FAN DAMPERS 165 5913 PASSIVE OAS305 0BS385 Radwaste Bldg OPERABLE NZA M-2801-3.M-1876 3
21 OAT096 SOG-A - LUBE OIL E1 DIG LUBE OIL STORAGE TANK M-377. SHT 3 DIG-3 OPERABLE N/A COMMON S
127 5127 ACTIVE OAT06 7
Diesel Generator OPERABLE N/A E-5-40 3
21 OAT097 SDGA - DIESEL El DIG COOLANT EXPANSION TANK M-377. SHT 2 DIG-4 OPERABLE N/A COMMON S
COOLING 127 5120 PASSIVE CAT097 D
Generaor OPERABLE N/A E-5-38-4 3
21 0AT38 SDG-A -FUEL OIL DIESEL FUEL OIL STORAGE TANK M4-377. SKT 4 YARD OPERABLE N/A COMMON S
113 5140 PASSIVE 0AT038 Diese Generator OPERABLE N/A 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 CAT040 Diesel Generator OPERABLE N/A E-5-,1-6 Peach Bottom Atomic Power Station Unit 3 B-92 MPR-3812, Revision 3 onrrPqnnndrann*. Nn
- RR-1 9-173
DOCUMENT NO. 0067.001140001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval rewd?
PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Nomtae Motive power Swpot System Desied Sale ov& ower Supp Sys dwg DATE: 3/28WK PAGE 92 System Hsles Equip Desaripton ROe Molhe ComP Drawng NO, Lac Code Room Elev Line No Function Builng 3
21 0BE073 h'VAC EMERG SWGR VENT SUP HEATING M-399. SHT I RPW-32 OFF N/A COMMON B
COIL B 165 5813 PASSIVE 08073 0OV034 Radwaste BlDg WA NZA 3
21 08E126 SDG-B - LUBE OIL E2 D/G LUBE OIL STANDBY HEATER M-377. SHT 3 D/G-5 OPERABLE N/A COMMON a
127 6231 PASSIVE OBE126 Diesel Generator OPERABLE N/A 3
21 08E378 SOG-B - DIESEL E2 DIG JACKET COOLANT COOLER M-377. S.IT 2 DrG-.
OPERABLE N/A COMMON a
COOLING 127 5223, 5503 PASSIVE 0BE376 Diesel Generator OPERABLE NWA Vendor 11905551 3
21 0BE377 SDG-B - LUBE OIL E2 DIG LUBE OIL COOLER M-377. SKlT 3 D/G-3 OPERABLE N/A COMMON B
127 5239.5504 PASSIVE 03E377 Diesel Generator OPERABLE N/A Vendor 11905551 3
21 0BE378 SDG-B - DIESEL E2 DIG AIR COOLANT COOLER M-377. SHT 2 DIG-5 OPERABLE N/A COMMON B
COOLING 127 5216. 5505 PASSIVE 08E378 Diese Generao OPERABLE N/A Vendor 11905551 3
21 0BS385 HVAC BACKUP NITROGEN TO OAV35 AND M-399,.SHT 4 RNV-32 OPERABLE N/A COMMON S
0A&BV036 FAN DAMPERS 165 5902.5915 PASSIVE 0BS385 Radwaste Blg OPERABLE N/A W-2801-3.M-1876 3
21 OBT096 SDG-B -LUBE OIL E2 DIG LUBE OIL STORAGE TANK M-377. SiHT 3 00-OPERABLE N/A COMMON S
127 5227 ACTIVE OBT06 7
Diesel Generator OPERABLE N/A E-5-40 3
21 OBT097 SDG DIESEL E2 D/G COOLANT EXPANSION TANK M-377. S-iT 2 0/0-OPERABLE N/A COMMON S
COOLING 127 5220 PASSIVE 05T097 Diesel Generao OPERABLE N/A E-5-38-4 3
21 OBT38 SDG-B - FUEL OIL DIESEL FUEL OIL STORAGE TANK MW,377 SHT 4 YARD OPERABLE N/A COMMON S
113 5240 PASSIVE 08T038 Diesel Generator OPERABLE N/A Vendor M-6214. C-64 3
21 OBT40 SOG-B -FUEL OIL E2D/G FUEL OIL DAY TANK M-377. SHT 4 DIG-f OPERABLE N/A COMMON S
127 5243 PASSIVE 08T040 Diesel Generator
-OPERABLE NIA E-5-36-6 3
21 OBT95 SG-A - STARTING E I DIG STARTING AIR RESERVOIR M-377. SHT 1 D/G-3 OPERABLE N/A COMMON S
AIR (AUTOMATIC START) 127 5100 PASSIVE OT095 DieD Generator OPERABLE N/A E,-s.-I1.6 3
21 0CE126 SDG-C - LUBE OIL E3 D/G LUBE OIL STANDBY HEATER M-377. SHT 3 DIG-i OPERABLE N/A COMMON B
127 5331 PASSIVE 0CE126 Diesel Generator OPERABLE N/A 3
21 0CE376 SOG-C - DIESEL E30/G JACKET COOLANT COOLER M-377. SHT 2 O/G-7 OPERABLE N/A COMMON B
5323. 5506 PASSIVE OCE376 COOLING 127 Diesel Generator OPERABLE N/A Vendor 11905551 B-93 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C.nrrP.%nnndP.nr-n Nn ' RS-12-173
DOCUMENT NO. 006740004-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE: 342195 PAGE 93 Norm etate Molive pI*wm I Suppe System Desired State Contr power Supp Sys dw" TRAIN Uni SO CI Cl EqupID Evall eqd?
PIMS ID System Notesl Equd OsaiUon ROB Moree Camp Drawing No.
Laoc Code Room Elev Line No Funonliw 3
21 0CE3T7 SDG-C - LUSE OIL E3 DIG LUBE OIL COOLER M-377. SHT 3 OIG-3 OPERABLE NIA COMMON B
127 5339 5507 PASSIVE 0CE377 Diesa Generator OPERABLE NIA V
3 21 0CE378 SDG-C -DIESEL E3 DIG AIR COOLANT COOLER M-377. SHT 2 DIG-7 OPERABLE N/A COMMON B
COOLING 127 5316, 5508 PASSIVE 0CE378 Diesel Generator OPERABLE WA 3
21 OCT096 SDG-C -LUSE OIL E3 DIG LUBE OIL STORAGE TANK M-377. SHT 3 DIG-7 OPERABLE WA COMMON S
127 5327 ACTIVE 0CT096 7
Diesel Generator OPERABLE WA E-5-4O 3
21 0CT097 SDG-C DIESEL E3 DIG COOLANT EXPANSION TANK M-377. SHT 2 D/G-8 OPERABLE N/A COMMON S
COOLING 127 5320 PASSIVE OCT097 Diesel Generator OPERABLE NIA E-5-38.4 3
21 OCT38 SDG-C -FUEL OIL DIESEL FUEL OIL STORAGE TANK M-377. SHT 4 YARD OPERABLE NIA COMMON S
113 5340 PASSIVE 0CT38 Diesel Generator OPERABLE NWA Vendor M-6214. C-64 3
21 OCT40 SG-C - FUEL OIL E3 DIG FUEL OIL DAY TANK M-377. SHT 4 DIG-7 OPERABLE NWA COMMON S
127 5343 PASSIVE OCT040 Diel Generator OPERABLE NIA' 3
21 0OE12S SDG-D - LUSE OIL E4 DIG LUBE OIL STANDBY HEATER M-377, SlIT 3 DIG-9 OPERABLE NWA COMMON B
127 5431 PASSIVE DOE126 Di Generator OPERABLE MIA 3
21 ODE376 5.--D - DIESEL E4 DIG JACKET COOLANT COOLER M-377. SMiT 2 DIG-9 OPERABLE MIA COMMON B
COOLING 127 5423.5509 PASSIVE ODE376 Dies Generaor OPERABLE WA Vendor 11905551 3
21 0DE377 SO0-a - LUBE OIL E4 DIG LUBE OIL COOLER M-377, SHT 3 DIG-3 OPERABLE NWA COMMON B
127 5439.5510 PASSIVE 0WE377 Diesl Generator OPERABLE NWA Vendor 11905551 3
21 ODE378 SDG-$.
DIESEL E4 DIG AIR COOLANT COOLER M-377, SHlT 2 DIG-9 OPERABLE NWA COMMON B
COOLING 127 5416.5511 PASSIVE 00E378 Diesel Generator OPERABLE WA Vendor 11905551 3
21 ODTOG6 SDG-D - LUBE OIL E4 DIG LUBE OIL STORAGE TANK M-377. SHT 3 DG-9 OPERABLE NWA COMMON S
127 5427 ACTIVE OTn96 7
Diesel Generator OPERABLE NWA E-5-40 3
21 0OTO97 SOG-D - DIESEL E4 DIG COOLANT EXPANSION TANK M-377. SHT 2 DIG-10 OPERABLE NWA COMMON S
COOLING 127 5420 PASSIVE 0DT0B Diese Generator OPERABLE NIA E-5-38-4 3
21 ODT38 S6G FUEL OIL DIESEL FUEL OIL STORAGE TANK M-377. SHT 4 YARD OPERABLE WA COMMON S
5440 PASSIVE ODT038 113 Diesel Generator OPERABLE NWA Vendor M-6214, C644 B-94 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 C'nrr.-nondp.ne-.. Nn ' RR-12-173
DOCUMENT NO. 009640084-D40M REVISiON 2 TRAIN SOUG Cl Unil EvA retd?
Line No Funcion Equp ID PIMS 0)
Systm Notes EqW -ecro ROB Mollm COWi PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Drenm No LoC CCod Roon Elev Bullnt DATE: 3WrAS PAGE 94 Motive powif SLOW Sytm Caw* poer Supp Sys d"g Nofn, state Oesirec State 3
21 00T40 SDG-O - FUEL OIL E4 DIG FUEL OIL DAY TANK M-377. SHT 4 OIG-9 OPERABLE NIA COMMON S
127 5443 PASSIVE 0DT040 Diesel Genaresor OPERABLE WA E-6-36-5 3
21 GOTgS SOG-B - STARTING E2 DIG STARTING AIR RESERVOIR M-377. SHT 1 DIG-S OPERABLE NfA COMMON S
AIR (AUTOMATIC START) 127 5200 PASSIVE 0OTO96 Diese Genemlor OPERABLE WA E-6-11-6 3
21 OFT96 SDG-C - STARTING E3 DIG STARTING AIR RESERVOIR M-377, SHT I DIG-7 OPERABLE WA COMMON S
AIR (AUTOMATIC START) 127 5300 PASSIVE OFT05 Diesel Generator OPERABLE NWA E-6-114 3
211 0HTOS SDG-O - STARTING E4 DIG STARTING AIR RESERVOIR M-377. SliT I DIG-9 OPERABLE NA COMMON S
AIR (AUTOMATIC START) 127 5400 PASSIVE OKT095 Diesel Generator OPERABLE N/A E-6-1145 3
21 NWA SDGA - DIESEL TURBO COOLERS (2)
M-377, SliT 2 DIG - 314 OPERABLE NIA COMMON a
COOLING 127 5119 PASSIVE OAG12 Diesel Generao OPERABLE NIA 3
21 WA SDG DIESEL TURBO COOLERS (2)
M-377. SliT 2 DIG-5/8 OPERABLE NWA COMMON B
COOLING 127 5219 PASSIVE 0BG12 Diesel Generator OPERABLE WA 3
21 WA SDG-C - DIESEL TURBO COOLERS (2)
M-377, SHT 2 D0G-7/8 OPERABLE WA COMMON B
COOLING 127 5319 PASSIVE OCG12 ssrwator OPERABLE WA 3
211 WA SDG-D.- DIESEL TURBO COOLERS (2)
M-377. SHT 2 DIG - 9/10 OPERABLE WA COMMON 5419 a
PASSIVE COOULING 00G12 127 Diesel Generiator OPERABLE WA Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (7nrrF..qnnndpnnm-. Nn
- R-1 2-173 B-95
DOCUMENT NO. 0067-0004-00O1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAME SHUTDOWN EQUIPMENT LIST DATE. 5125M PAGE 95 I
Control Rod Hydraulic Control Unit - Typical of 185 2 Control Rod Drve - Typcal of 18S 3 Included In SPCL for Grandfather Purposes Only 4
Solenoid-Valve Integral to Ak'-Operated-Valve Requires Review As We 5 Open Valve to Cross-Tie Loops A and B of HPSW 6 Sight Glass 7 Seismic Fire Interaction 8 Valve Locked Open 9 Valve Opened for Suppression Pool Cooing 10 Valve Opened for LPCI and ASC 11 Valve Locked Closed 12 Seismic Cat 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 M02-23B-4246 15 Components listed with a -PBO1' in the NOTES field are required for Pressure Boundary Only I
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 rnrrpqnnndp.nr.p No - RR-19-173 B-96
Exelon NTTF 2.3: Seismic Walkdown Seismic Walkdown Equipment List (SWEL)
UNIT: PEACH BOTTOM UNIT 3 Ben Frazier, MPR PREPARER:
PEER REVIEWER:'.
Crail Swanner, MPR PEER REVIEW TEAM LEADER:
-PA" OBRAL PBAPS OPERATIONS REPRESENTATIVE:
Joe Hanleyr Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 (rnrrp.nnnlpnr.fiA NA RA-19-171 B-97
Table B-I. SWEL for Unit 3 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 3
30S037 HPCI Turbine (00) Other Reactor 88 R3-13 X
Y N
N 3
HCU-06-47 Hydraulic Control Unit (00) Other Reactor 135 R3-24 X
N N
Y 3
HCU-14-35 Hydraulic Control Unit (00) Other Reactor 135 R3-24 X
N N
Y MO-3-23-015 Motor (01) Motor Control Recirc mg
-X.
N N
N 3
30B324 Control Power Transfer Centers Turbine 135 set room Switch 3
30B325 MO-3-13-15 MotorControl (01) Motor Control Turbine 135 Recirc mg X
N N
N Starter Panel Centers set room 3
30B338 M03-10-16A Auto (01) Motor Control Turbine 135 Recirc mg X
N N
N Transfer Switch Centers set room 3
30B010 Emergency Aux Load (02) Low Voltage Reactor 165 R3-116 X
X X
X X
N N
Y Center El 34 Switchgear Switchgears 3
30B013 Emergency Aux Load (02) Low Voltage Reactor 165 R3-41 X
X X
X X
Y N
Y Center E434 Switchgear Switchgears Load Center E134 (04) Transformers Reactor 165 R3-116 X
X X
X X
N N
Y 3 30X033 Loansforter E3 3
30X033 Load Center E434 (04) Transformers Reactor 165 R3-41 X
X X
X X
Y N
Y Transformer 3
30X133 Panel 30Y33 Transformer (04) Transformers Turbine 135 T3-171 X
X X
X X
N N
Y
- 30P033, HPCI Booster Pump, (05) Horizontal Pumps Reactor 88 R3-13 X
Y N
N 130P038 Pump 3
30P036 &
RCIC Pump & Turbine (05) Horizontal Pumps Reactor 88 R3-14 X
Y N
N 30S038YNN 3
3AP035 RHR Pump A (06) Vertical Pumps Reactor 91 R3-5 X
N N
N 3
3AP037 Core Spray Pump A (06) Vertical Pumps Reactor 91 R3-9 X
N N
N 3
3CP035 RHR Pump C (06) Vertical Pumps Reactor 91 R3-7 X
N N
N 3
3CP042 High Pressure Service (06) Vertical Pumps Pump 112 PIH-9 X
N N
N Water Pump C Structure 3
A03-03-33 Scram Discharge Volume (07) Fluid (Air/Hyd)
Reactor 135 R3-22 X
N N
N Inboard Isolation Valve Valves 3
A03-03-36 Scram Discharge Volume (07) Fluid (Air/Hyd)
Reactor 135 R3-22 X
N N
N Outboard Isolation Valve Valves 3
H03-23C-HPCI Turbine Governor (07) Fluid (Air/Hyd)
Reactor 88 R3-13 X
N N
N 5512 Control Valve Valves 3
RV3-23-034 HPCI Pump Suction (07) Fluid (Air/Hyd)
Reactor 88 R3-13 X
N N
N Header Relief Valve Valves 3
M03-10-013C RHR Pump Torus Suction (08a) Motor Operated Reactor 91 R3-7 X
N N
N Valve Valves 3
M03-10-015C RHR Pump Shutdown (08a) Motor Operated Reactor 91 R3-5 X
N N
N Cooling Suction Valves 3
M03-10-89C RHR HX HPSW Outlet (08a) Motor Operated Reactor 116 R3-17 X
N N
N Valve Valves 3
M03 Unit 3A Sluice Gate (08a) Motor Operated Screen 116 S/H-4 X
X X
X X
N N
N 3233A Valves House Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-98
Table B-I. SWEL for Unit 3 NTTF 2.3 Function Unit Component Description EPRI Class Building Elevation Location Decay Significant?
Replace?
Enhancement?
SWEL ID Reactivity Pressure Inventory Heat Containment Diesel HPSW Return Valve to (08a) Motor Operated Generator 121 DIG-2 NXN-N 3 MO-3-32-3803 ECT ValvesGeeao 12
/-
xNNN Building MO-3 HPSW Bay Inlet Inner (08a) Motor Operated Emergency 3
3804B Valve Valves Cooling 114 ECT-1 X
N N
N Towers 3
MO-3-1 0-RHR Pump Suction Valve (08a) Motor Operated Reactor 91 R3-5 X
N N
N 013A A
Valves 3
SV3-3-33 Instrument Air Solenoid (08b) Solenoid Reactor 135 R3-22 X
N N
N Valve Operated Valves Instrument Air Solenoid (08b) Solenoid Reactor 135 R3-22 X
N N
N 3
SV3-3-36 Valve Operated Valves 3
3AV083 HPSW Pump Room (09) Fans Pump 112 P/H-9 X
N N
N Exhaust Fan Structure 3RHR Room A Cooling Coil (10) Air Handlers Reactor 116 R3-5 X
N N
N 3
3E5 RIRomCooling CoilN RCIC Room (10) Air Handlers Reactor 88 R3-14 X
N N
N 3
3AE56 HPCI Room Cooling Coil A (10) Air Handlers Reactor 88 R3-13 X
N N
N 3
3AE57 Core Spray Room AN Cooling Coil A (10) Air Handlers Reactor 91 R3-9 N
N 3 3B55
~
lC oomCooling CoilA RCIC Room (10) Air Handlers Reactor 88 R3-14 X
Coln.olN N
N 3
3BE57 BoeSryRo 3
Core Spray Room A (10) Air Handlers Reactor 91 R3-9 X
N N
N 38E57 Cooling Coil B 3
3BE58 RHR Room A Cooling Coil (10) Air Handlers Reactor 91 R3-5 X
N N
N B
POD-3-40H-HPSW Pump Room A (10) Air Handlers Pumpcture 30223-3 Loop Supply Damper Structure POD-3-40H-HPSW Pump Room B (10) Air Handlers Pump 112 P/H-9 X
X X
X X
N N
N 30223-4 Loop Exhaust Damper Structure 3
30S703 120V Inst. Panel 30Y035 (14) Distribution Panels Reactor 135 R3-29 X
X X
X X
N N
N Transfer Switch 3
30Y050 120V AC Distribution (14) Distribution Panels Turbine 150 T3-81 X
X X
X X
N N
N 3_
30Y050 Panel 3
30Y035 3PPD 125V DC (14) Distribution Panels Reactor 135 R3-29 X
X X
X X
N N
N Distribution Panel 3C 3
3BD025 3B 125 VDC Distribution (14) Distribution Panels Turbine 150 T3-81 X
X X
X X
N N
N Panel 3
3DC068 RPS SCRAM solenoid (14) Distribution Panels Reactor 135 R3-24 X
N N
N 3 _3DC068 fuse panel D 3
3BDO1 125 VDC Battery 3B (15) Batteries & Racks Turbine 135 T3-169 X
X X
X X
N N
Y 3
3CDO01 125 VDC Battery 3C (15) Batteries & Racks Turbine 135 T3-70 X
X X
X X
Y N
Y 3
3DD01 125 VDC Battery 3D (15) Batteries & Racks Turbine 135 T3-169 X
X X
X X
Y N
Y Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-99
Table B-I. SWEL for Unit 3 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 3
30D37 Static Inverter (16) Battery Chargers Turbine 135 T3-74 X
X X
X X
N N
N and Inverters 3
(16) Battery Chargers Turbine 135 T3-170 X
X X
X X
Y N
N 3 3CD03 Battery Charger 3C and Inverters 3
(16) Battery Chargers Turbine 135 T3-172 X
X X
X X
Y N
N 3DD03 Battery Charger 3D and Inverters 3
30C095 RCIC Instrument Rack (18) Instruments on Reactor 88 R3-15 X
N N
N Racks / Not on Racks 3
30C087 HPCI instrument Rack (18) Instruments on Reactor 88 R3-15 X
N N
N Racks / Not on Racks 3
3AC65 RPS Instrument Rack (18) instruments on Reactor 165 R3-40 X
N N
N Racks / Not on Racks 3
3BC065 RPS Instrument Rack B (18) Instruments on Reactor 135 R3-29 X
N N
N Racks / Not on Racks 3
LS3-23-91A Suppression Pool Level (18) Instruments on Switch Racks / Not on Racks Reactor 91 R3-111 X
N N
N 3
LT3-2-3-61 Reactor Vessel Water (18) Instruments on Level Transmitter Racks / Not on Racks Reactor 165 R3-40 X
N N
N 3
LT-9123A Torus Water Level (18) Instruments on Transmitter Racks / Not on Racks Reactor 91 R3-11 X
X N
N N
3 PS30224-2 HPSW Pump Room B (18) Instruments on Pump 112 PIH-9 X
X X
X X
N N
N Loop Pressure Switch Racks / Not on Racks Structure 3
PT3-2-3-404A Reactor Pressure (18) Instruments on Transmitter Racks / Not on Racks Reactor 165 R3-40 X
N N
N 3
PT3-6-53A Reactor Wide Range (18) Instruments on Reactor 165 R3-40 X
N N
N Pressure Transmitter Racks / Not on Racks 3
PT-5805 Drywell Pressure (18) Instruments on Transmitter Racks / Not on Racks Reactor 116 R3-21 X
N N
N 3
30C03 Reactor and Containment (20) Control Panels &
Turbine 165 T3-1 00 x
N N
N Cooling and Isolation Cabinets 3
30C004C RCIC Vertical Board (20) Control Panels &
Turbine 165 T3-100 X
N N
N Cabinets 3
30C005A Reactor Manual Control (20) Control Panels &
Turbine 165 T3-100 X
N N
N Board Cabinets 3
30C32 Egr Safeguard Sub-Sys 1 (20) Control Panels &
N N
Y Cabinets Turbine 150 T3-81 X
3 30C33 Egr Safeguard Sub-Sys 11 (20) Control Panels &
Turbine 150 T3-81 X
N N
N Cabinets 3
30C34 RClC Relay Panel (20) Control Panels &
Turbine 150 T3-81 X
N N
N Cabinets 3
30C722A Accident Monitoring (20) Control Panels &
Instrumentation Panel Cabinets Turbine 150 T3-81 X
N N
Y 3
30C722B Accident Monitoring (20) Control Panels &
Turbine 150 T3-81 X
N N
Y Instrumentation Panel Cabinets
_T_8_
NN_
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 correspondence No.: RS-12-173 B-100
Table B-1. SWEL for Unit 3 Unit Component DcpoEPRI Class Building Elevation Location
- 2.
ct y
Risk New or IPEEE SWEL ID Description EPICas Bidn lvto oainDecay Sgiiat elcEhneet Reactivity Pressure Inventory Heat Containment Significant?
Replace?
Enhancement?
3 30D043 HPCI Aux Lube Oil Pump (20) Control Panels &
Reactor 88 R3-13 X
N N
N Starter Cabinets 3
Steam B Leak Monitor (20) Control Panels &
Turbine 165 T3-100 X
N N
N 3 3BC270 Cabinet Cabinets 3
L-3-2-3-113 Reactor Water Level (20) Control Panels &
Turbine 165 T3-100 X
N N
N Cabinets 3
LI-9027 Torus Water Level (20) Control Panels &
Turbine 165 T3-100 X
X N
N N
Cabinets Torus Water (20) Control Panels &
Turbine 165 T3-100 X
X 3
LR/TR-9123B Level/Temperature Cabinets N
N N
Recorder 3
P13-6-90A Reactor Wide Range (20) Control Panels &
Turbine 165 T3-100 X
N N
N Pressure Indicator Cabinets 3
PR/RR3-2 Reactor Pressure/Drywell (20) Control Panels &
Turbine 165 T3-100 X
N N
N 404B Gas Recorder Cabinets 3
PRJTR-5805 Containment (20) Control Panels &
Turbine 165 T3-100 X
N N
N Pressure/Temp Cabinets RHR Pump 3A Seal (21) Tanks or Heat 3
3AE124 Cooler Exchangers Reactor 91 R3-5 X
N N
N 3 ECl(Horizontal) 1 3
3(21)
Tanks or Heat 3CE24 RHR Heat Exchanger C I Exchangers (Vertical)
Reactor 91 R3-17 X
-N N
N Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-101
Table B-2. SWEL for Unit 0 (common)
NTTF 2.3 Function Unit Component Description EPRI Class Building Elevation Location Decay Risk New or IPEEE SWEL_
IDReactivity Pressure Inventory Heat Containment Significant?
Replace?
Enhancement?
0 00B061 Pump Structure MCC (01) Motor Control Pump 112 P/H-6 X
X X
X X
N N
N E224-P-A Center Structure El D/G Fuel Oil Transfer Diesel 0
PAP060 Pump (05) Horizontal Pumps Generator 127 D/G-3 X
X X
X X
Y N
N Building Emergency Service Water Diesel 0Booster Pump A (05) Horizontal Pumps Generator 127 D/G-1 X
X X
X X
N N
N Building E4 D/G Fuel Oil Transfer Diesel 0
PDPp60 Pump (05) Horizontal Pumps Generator 127 D/G-9 X
X X
X X
Y N
N Pump__Building Emergency Service Water (06) Vertical Pumps Pump 112 P/H-9 X
X X
X X
N N
Y 0
0BP057 Pump B structure ESW Outlet Block Valve Diesel 0
AO-33-0241D from Diesel Generator E4 (07) Fluid (Air/Hyd)
Generator 127 D/G-9 X
X X
X X
N N
N Coolers Building TCV-0-52E-D/G Jacket Coolant 3-Diesel 7239A Way Thermostatic Control l
(Air/Hyd)
Generator 127 D/G-3 X
X X
X X
N N
N Valve Building Diesel 0
MO-0-33-0498 ESW Returnto Discharge (08a) Motor Operated Generator 127 D/G-2 X
X X
X X
Y N
Y Pond ValvesBulng____
Building ESW A Inlet to ECT (08a) Motor Operated Emergency 0Reservoir Valves Cooling 114 ECT-1 X
X X
X X
N N
N Towers 0
OAV030 Control Room Emerg (09) Fans Turbine 165 RNW-32 X
X X
X X
N N
N 0_
0AV030 Vent Supply Fan A 0
0AV036 Battery Room Exhaust Radwaste 165 RNV-32 X
X X
X X
N N
N Fan A (09) Fans Diesel DGBuilding Vent Supply NiesN 0
DAV064 Ga n (09) Fans Generator 151 D/G-19 X
X X
X X
N N
N 0Fan Building BEmergency Cooling Emergency 0
TBK032 ower Fan B (09) Fans Cooling 195 ECT-6 X
X X
X X
N N
N Towers 0
OBV030 Control Room Emergency (09) Fans Turbine 165 RNV-32 X
X X
X X
N N
N Ventilation Supply Fan B 0
OBV035 Emergency Switchgear (09) Fans Radwaste 165 RAN-32 X
X X
X X
N N
N Ventilation Exhaust Fan B 0
0BV036 Battery Room Exhaust (09) Fans Turbine 165 R/W-32 X
X X
X X
N N
N Fan B ODV064 D/G Building Vent Supply Diesel Fan (09) Fans Generator 151 DIG-20 X
X X
X X
N N
N Building Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-102
Table B-2. SWEL for Unit 0 (common)
NTTF 2.3 Function Unit Component Description EPRI Class Building Elevation Location Decay Risk New or IPEEE Reactivity Pressure Inventory Heat Containment Significant?
Replace?
Enhancement?
PO-0-40F-Master for El EDG Diesel 0
00272-01 Building Vent Supply Fan (10) Air Handlers Generator 151 D/G-19 X
X X
X X
N N
N Outside Air Damper Building PO-0-40F Master for El EDG Diesel 0
00272-02 Building Vent Supply Fan (10) Air Handlers Generator 151 DIG-19 X
X X
X X
N N
N Return Air Damper Building El Standby Diesel Diesel 0
0AG012 Generator (17) Engine Generators Generator 127 DIG-3 X
X X
X X
Y N
Y Ie t
Building GE4 Standby Diesel Diesel 0
ODG012 Generator (17) Engine Generators Generator 127 DIG-9 X
X X
X X
Y N
Y Building E4 D/G Jacket Coolant (19) Temperature Diesel 0
TS-0607D emperacke Cor Sensors Generator 127 DIG-9 X
X X
X X
N N
N Temperature Sensor Sensors Bidn Building 0
0OC29B Emergency Protection (20) Control Panels &
Turbine 165 T2-100 X
N N
Y Relay Board Cabinets Diesel Generator OAG12 (20) Control Panels &
Diesel 0
0AC097 Control Panel Generator 127 DIG-3 X
X X
X X
N N
N Control Panel Cabinets Bidn Building El Diesel Generator Lube (21) Tanks or Heat Diesel 0
OAT096 Oil Storage Tank Exchangers Generator 127 DIG-3 X
X X
X X
N N
N (Horizontal)
Building El Diesel Generator Fuel (21) Tanks or Heat Diesel 0
OAT040 Generator 127 DIG-3 X
X X
X X
N N
N Oil Day Tank Exchangers (Vertical)
Bidn Building II E4 Diesel Generator Lube (21) Tanks or Heat Diesel 0 OE7 OiColrEcagr(Vria)
Generator 127 DIG-S X
X X,
X X
N N
N 7 Oil Cooler Exchangers (Vertical)
Building E4 Diesel Generator Fuel (21) Tanks or Heat Diesel 0
ODT40 Generator 127 DIG-9 X
X X
X X
N N
N Oil Day Tank.
Exchangers (Vertical)
Building Diesel 0
OHT95 E4 Diesel Generator (21) Tanks or Heat Generator 127 DlG-9 X
X X
X X
N N
N Starting Air Reservoir Exchangers (Vertical)
Building I
Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-103
Table B-3. Deferred to RFO or Electrical Bus Outage: Inaccessible or Electrical Safety Concern Unit Component NTTF 2.3 Function Risk New or IPEEE Unit C
D Description EPRI Class Building Elevation Location Decay Risk Ne?
E ee SWEL ID Reactivity Pressure Inventory Heat Containment Significant?
Replace?
Enhancement?
3 30B37 480V Reactor Area MCC (01) Motor Control Reactor 135 R3-23 X
X X
X X
N N
N E234-R-B Centers 0
00B94 480V Bus E13A4 (02) Low Voltage Emergency Switchgears Cooling 153 ECT-3 X
X X
X X
N N
Y Tower 3
30B01 1 480V Load Center E234 (02) Low Voltage Reactor 165 R3-41 X
X X
X X
N N
N Switchgears 3
30A15 Emergency 4kV Aux (03) Medium Voltage Turbine 135 T3-171 X
X X
X X
N N
Y Switchgear Switchgears 3
Inboard Main Steam (07) Fluid (Air/Hyd)
Drywell 134 D/W3-18 X
N N
N A03-01-080A Isolation Valve A Valves 3
A03-01-080C Inboard Main Steam (07) Fluid (Air/Hyd)
Drywell 134 D/W3-19 X
N N
N Isolation Valve C Valves 3
RV3-02-071 D Safety Relief Valve D (07) Fluid (Air/Hyd)
Drywell 155 D/W3-26 X
N N
N Valves 3
RV3-02-071F Safety Relief Valve F (07) Fluid (Air/Hyd)
Drywell 155 D/W3-29 X
N N
N Valves M N
N N
3 M03-06-029A Feedwater Stop Valve (08a) Motor Operated HPC Tubin Stam Valves
______5____2 XN 3HPC Turbine Steam Line (08a) Motor Operated Inboard Isolation Valve Valves M03-23-019 HPCI Discharge to (08a) Motor Operated Reactor MI 3-23-01 9 Feedwater Line Valve Valves
[MSIV 135 R3-30 X
N N
N Room]
3 3BT540 Instrument N2 (21) Tanks or Heat Accumulator Exchangers (Vertical)
Drywell 155 DNV3-27 X
N N
N Instrument N2 (21) Tanks or Heat 3
3KT545 Accumulator Exchangers (Vertical)
Drywell 155 D/V3-34 X
N N
N Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173 B-104