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Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 1 of 4
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Site:	Oyster Creek
Issue date:	11/06/2012
From:	Delaney M; Stevenson & Associates
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U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 19, 2012 Page 5 Enclosure 1 Seismic Walkdown Report In Response To The 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1, Report Number: 12Q0108.80-R-001, Rev. 1 (569 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 OYSTER CREEK GENERATING STATION UNIT I ROUTE 9 South P.O. BOX 388, FORKED RIVER, NJ 08731 Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 Correspondence No.: RS-12-177 n-" Exelon Exelon Generation Company, LLC (Exelon)

PO Box 805398 Chicago, IL60680-5398 Prepared by:

Stevenson &Associates 1661 Feehanvllle Drive, Suite 150 Mount Prospect, IL60056 Report Number: 12C0108.80-R-001, Rev. 1 I dl -@NamrIn Sionatu Qgo Preparer: Madene Delaney 11/6/2012 Revlkw. Tony Perez 11 6/2012 Approver. Tony Perez 11/6/2012 Peer Review Team Leader: Wafter Djord*evic kizS*21- 11/6/2012 Lead Responsible EngIneer. WIA1- HO0 (4/4 h Branch Mana er Senior Manager f ## ,t

,j 1-d - ,iIH It'll Design Engineering: 122 1/I 14 t* * !

Corporate Acceptance:

Document

Title:

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the OYSTER CREEK GENERATING STATION UNIT 1 Document Type: Report Report Number: 12Q0108.80-R-001 Project Name:

NTTF R2.3 Seismic Walkdowns for Exelon - Oyster Creek Job No.: 12Q0108.80 Client: O Exeton This document has been prepared in accordance with the S&A Quality Assurance Program Manual, Revision 17 and project requirements:

Rev. 1

_., Date: 10/30/2012 Prepared by: Marlene Delaney Reviewed by: Tony Perez - Date:10/30/2012 Approved by: Tony Perez -Date: 10/30/2012 -------

Revision Record:

Revision Prepared by/ Reviewed by/ Approved by/ Description of Revision No. Date Date Date 1 M. Delaney T. Perez T. Perez Replaced pages 5-8, 6-1, 11/6/2012 11/6/2012 11/6/2012 9-2, C-7, E-1, and E-3.

DOCUMENT CONTRACT NO.

APPROVAL SHEET 12Q0108 Stevenson &Associates

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Contents List of Tables ......................................................................................................... iii Executive Summary ................................................................................................. iv 1 Introduction..................................................................................................................... 1-1 1.1 Purpose ................................................................................................................... 1-1 1.2 Background ............................................................................................................. 1-1 1.3 Plant Overview ......................................... ............................................................... 1-1 1.4 Approach ................................................................................................................ 1-2 1.5 Conclusion .............................................................................................................. 1-2 2 Seismic Licensing Basis............................................................................................ 2-1 2.1 Overview ................................................................................................................ 2-1 2.2 Safe Shutdown Earthquake (SSE) .......................................................................... 2-1 2.3 Design of Seismic Category I SSCs ....................................................................... 2-1 2.3.1 Summary of Seismic Design .......................................................................... 2-1 2.3.2 Summary of Codes and Standards ................................................................ 2-2 3 PersonnelQualifications........................................................................................... 3-1 3.1 Overview ................................................................................................................. 3-1 3.2 Project Personnel .................................................................................................... 3-1 3.2.1 Stevenson & Associates Personnel ............................................................... 3-2 3.2.2 Additional Personnel ...................................................................................... 3-4 4 Selection of SSCs ....................................................................................................... 4-1 4.1 Overview ................................................................................................................. 4-1 4.2 SW EL Development ................................................................................................ 4-1 4.3 SW EL 1 Development ............................................................................................. 4-1 4.3.1 SWEL 1 - Sample of Required Items for the Five Safety Functions ............. 4-1 4.4 SW EL 2 Development ......................................................................................... 4-4 4.4.1 SW EL 2 - Spent Fuel Pool Related Items ..................................................... 4-4 5 Seism ic Walkdowns and Area Walk-Bys ................................................................. 5-1 5.1 Overview ................................................................................................................. 5-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 5.2 S eism ic Walkdow ns ................................................................................................ 5-1 5.2.1 Adverse Anchorage Conditions ..................................................................... 5-2 5.2.2 Configuration Verification ............................................................................... 5-2 5.2.3 Adverse Seismic Spatial Interactions ............................................................ 5-3 5.2.4 Other Adverse Seismic Conditions ................................................................ 5-4 5.2.5 Conditions Identification during Seismic Walkdowns ..................................... 5-4 5.3 A rea W alk-Bys .................................................................................................... 5-4 5.3.1 Conditions Identification during Area Walk-bys ............................................. 5-6 5.4 Supplemental Information on Electrical Cabinet Inspections ................................ 5-6 6 Licensing Basis Evaluations.................................................................................... 6-1 7 IPEEE VulnerabilitiesResolution Report ................................................................ 7-1 8 Peer Review .................................................................................................................... 8-1 9 References ......................................................................... *............................................ 9-1 Appendices A ProjectPersonnelResumes and SWE Certificates............................................... A-1 B Equipment Lists........................................................................................................... B-1 C Seismic Walkdown Checklists (SWCs) .................................................................. C-1 D Area Walk-By Checklists (AWCs) .................................... D.

E Plan for Future Seismic Walkdown of InaccessibleEquipment ............................ E-1 F Peer Review Report........................................................................................................ F-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 List of Tables Table 3-1. Personnel Roles .................................................................................... 3-1 Table 5-1. Anchorage Configuration Confirmation ...................................................... 5-3 Table 5-2. Conditions Identified during Seismic Walkdowns ............................................ 5-7 Table 5-3. Conditions Identified during Area Walk-Bys ................................................... 5-8 Table B-1. Base List 1 ........................................................................................... B-3 Table B-2. Base List 2 .......................................................................................... B-83 Table B-3. SW EL 1 ............................................................................................. B-87 Table B-5. SW EL 2 ............................................................................................. B-93 Table C-1. Summary of Seismic Walkdown Checklists .............................................. C-2 Table D-1. Summary of Area Walk-By Checklists ...................................................... D-2 Table E-1. Inaccessible and Deferred Equipment List ..................... ............................ E-2 Table E-2. Supplemental Cabinet Internal Inspection List ............ ............ E-4 iii

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Executive Summary The purpose of this report is to provide information as requested by the Nuclear Regulatory Commission (NRC) in its March 12, 2012 letter issued to all power reactor licensees and holders of construction permits in active or deferred status. (Ref. 13) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 13)

Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near Term Task Force (NTTF) in response to Commission direction. The NTTF issued a report - Recommendations for EnhancingReactor Safety in the 2 1st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 14) On March 12, 2012, the NRC issued a letter to all power reactor licensees in accordance with 10CFR50.54(f). The 50.54(f) letter requests information to assure that certain NTTF recommendations are addressed by all U.S. nuclear power plants. (Ref. 13) The 50.54(f) letter requires, in part, all U.S.

nuclear power plants to perform seismic walkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration is within the current seismic licensing basis. This report documents the seismic walkdowns performed at Oyster Creek Generating Station Unit 1 in response, in part, to the 50.54(f) letter issued by the NRC.

The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 13) The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012; henceforth, referred to as the "EPRI guidance document." (Ref. 1) Exelon/Oyster Creek has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1)

The EPRI guidance document was used to perform the engineering walkdowns and evaluations described in this report. In accordance with the EPRI guidance document, the following topics are addressed in the subsequent sections of this report.

" Seismic Licensing Basis

Personnel Qualifications

Selection of Systems, Structures, and Components (SSC)

Seismic Walkdowns and Area Walk-Bys

Seismic Licensing Basis Evaluations

IPEEE Vulnerabilities Resolution Report

Peer Review iv

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Seismic Licensing Basis The Seismic Licensing Basis is briefly described in Section 2 of this report. The original seismic design for the Oyster Creek Nuclear Generating Station critical structures and equipment is based on dynamic analyses using acceleration response spectrum curves which were based on a peak ground acceleration of 0.22g for the Safe Shutdown Earthquake (SSE). Beginning in September, 1995, seismic design of equipment and structures is based on a peak ground acceleration of 0.184g for the SSE. (Ref. 2 section 3.7)

Personnel Qualifications Personnel qualifications are discussed in Section 3 of this report. The personnel who performed the key activities required to fulfill the objectives and requirements of the 50.54(f) letter are qualified and trained as required in the EPRI guidance document.

(Ref. 1) These personnel are responsible for:

Selecting the SSCs that should be placed on the Seismic Walkdown Equipment List (SWEL),

Performing the Seismic Walkdowns and Area Walk-Bys,

" Performing the seismic licensing basis evaluations, as applicable,

" Identifying the list of plant-specific vulnerabilities identified during the IPEEE program and describing the actions taken to eliminate or reduce them,

Performing the peer reviews Selection of SSCs Selection of SSCs is discussed in Section 4 of this report. The process used to select the items that were included in the overall Seismic Walkdown Equipment List (SWEL) is described in detail in the EPRI guidance document, Section 3: Selection of SSCs. (Ref.

1) The SWEL is comprised of two groups of items, which are described at a high level in the following subsections.

Sample of Required Items for the Five Safety Functions - SWEL 1 Screen #1 narrowed the scope of SSCs in the plant to those that are designed to Seismic Category I requirements because they have a seismic licensing basis.

Screen #2 narrowed the scope of SSCs by selecting only those that do not regularly undergo inspections to confirm that their configuration continues to be consistent with the plant licensing basis.

Screen #3 narrowed the scope of SSCs included on SWEL 1 as only those associated with maintaining the five safety functions. These five safety functions include the four safe shutdown functions (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, and decay heat removal, which includes the Ultimate Heat Sink), plus the containment functions.

Screen #4 was a process intended to result in a SWEL 1 that sufficiently represented the broader population of plant equipment and systems needed to meet the objectives of the 50.54(f) letter. The following five sample attributes were used:

A variety of types of systems v

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

Major new or replacement equipment e A variety of types of equipment e A variety of environments a Equipment enhanced due to vulnerabilities identified during the IPEEE program Spent Fuel Pool Related Items - SWEL 2 Screen #1 and Screen #2 were used to narrow the scope of spent fuel pool related SSCs to those that have a seismic licensing basis and those that are appropriate for an equipment walkdown process. Screen #3 was a process intended to result in SWEL 2 that sufficiently represents the broader population of spent fuel pool Seismic Category I equipment and systems to meet the objectives of the 50.54(f) letter, and included the following sample selection attributes:

" A variety of types of systems

" Major new or replacement equipment

A variety of types of equipment

" A variety of environments Screen #4 identified items of the spent fuel pool that could potentially cause a rapid drain-down of the pool, even if such items are not Seismic Category I. Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the earthquake. Any items identified as having the potential for rapidly draining the spent fuel pool were to be added to SWEL 2.

For Oyster Creek Unit 1, the SWEL is comprised of:

, SWEL 1 resulted with 98 items for walkdown.

, SWEL 2 resulted with 19 items for walkdown.

No items associated with spent fuel pool rapid drain-down are included on SWEL 2.

Seismic Walkdowns and Area Walk-Bys Section 5, Appendix C, and Appendix D of this report documents the equipment Seismic Walkdowns and the Area Walk-Bys. The online seismic walkdowns for Oyster Creek Unit 1 were performed during the week of August 20, 2012. During the majority of the walkdown activities, the walkdown team consisted of two (2) Seismic Walkdown Engineers (SWE), the station Lead Responsible Engineer (LRE), and a station Operations person.

The seismic walkdowns focused on the seismic adequacy of the items on the SWEL.

The walkdowns focused on the following:

, Adverse anchorage conditions

, Adverse seismic spatial interactions

" Other adverse seismic conditions (e.g., degradation, configuration, etc.,)

vi

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Area Walk-Bys were conducted in each area of the plant that contained an item on the SWEL (generally within 35 feet of the SWEL component). The Area Walk-By was performed to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item. The key examination factors that were considered in the Area Walk-Bys included the following:

Anchorage conditions.(if visible without opening equipment)

Significantly degraded equipment in the area

Potential seismic interaction

A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays)

Potential adverse interactions that could cause flooding/spray and fire in the area

Other housekeeping items, including temporary installations The seismic walkdown team inspected 101 of the 117 components on the SWEL (comprised of SWEL 1 and SWEL 2). Walkdowns for 16 components were deferred due to accessibility issues such as being located in containment or energized equipment.

The 16 remaining Unit 1 items will be walked down during a unit outage or another time when the equipment is accessible, as appropriate. Anchorage verification was required for a minimum of 30 components. (Ref. 1) A total of 47 anchorage configurations were confirmed to be installed in accordance with the station documentation.

Following the completion of the online seismic walkdowns, the industry was made aware that the NRC staff had clarified a position on opening electrical cabinets to inspect for other adverse seismic conditions. Supplemental inspections of 16 electrical cabinets are planned and will be completed, as required, during a unit outage or another time when the equipment becomes accessible. The list of electrical cabinets along with the milestone completion schedule is provided in Table E-2.

During the seismic walkdowns at Oyster Creek Unit 1 ten (10) Issue Reports (IRs) were issued for observed conditions. After evaluation through the CAP, it was determined that none of the conditions identified in the IRs were found to be adverse seismic conditions.'

Seismic Licensing Basis Evaluations The EPRI guidance document, Section 5: Seismic Licensing Basis Evaluation provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified. The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). In lieu of this process, Exelon/Oyster Creek utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/Oyster Creek processes and procedures, all questionable conditions identified by the SWEs during the walkdowns were entered into the station CAP to be further evaluated and addressed as required. The SWEs provided input to support the identification and evaluation (including seismic licensing basis evaluations, as required) of the potentially adverse seismic conditions entered into the CAP. The vii

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 station corrective action program is a more robust process than that provided in the EPRI guidance document; in part, ensuring each condition is properly evaluated for conformance with design and licensing bases and corrected as required.

Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP. For those conditions that required, seismic licensing basis evaluations were completed and documented within the IR. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.

IPEEE Vulnerabilities IPEEE vulnerabilities are addressed in Section 7 of this report. No vulnerabilities were identified as a result of the effort that addressed the Individual Plant Examination of External Events (IPEEE). (Ref. 10) All IPEEE plant improvements and associated actions are complete.

Peer Reviews A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI guidance document. The Peer Review process included the following activities:

" Review of the selection of SSCs included on the SWEL

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

Review of licensing basis evaluations, as applicable

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

Review of the submittal report

Provided a summary report of the peer review process in the submittal report Section 8 of this report contains a summary of the Peer Review. The Peer Review determined that the objectives and requirements of the 50.54(f) letter are met. Further, it was concluded by the peer reviews that the efforts completed and documented within this report are in accordance with the EPRI guidance document.

Summary In summary, seismic walkdowns have been performed at the Oyster Creek Generating Station Unit 1 in accordance with the NRC endorsed walkdown methodology. All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program.

Evaluations of the identified conditions are complete and documented within the CAP.

These evaluations determined the Seismic Walkdowns resulted with no adverse anchorage conditions, no adverse seismic spatial interactions, and no other adverse seismic conditions associated with the items on the SWEL. Similarly, the Area Walk-Bys resulted with no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).

The Seismic Walkdowns identified a limited set of minor conditions with no discernible trend. Other than these minor conditions, the Seismic Walkdowns identified no degraded, nonconforming, or unanalyzed conditions that required either immediate or viii

12QO108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 follow-on action. No planned or newly identified protection or mitigation features have resulted from the efforts to address the 50.54(f) letter.

Follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of 16 items deferred due to inaccessibility along with supplemental inspections of 16 electrical cabinets. Area Walk-Bys will be complete, as required, during these follow-on activities.

ix

12..108.80-R-oo1, Rev. 1 Correspondence No.: RS-12-177 I

Introduction 1.1 PURPOSE The purpose of this report is to provide information as requested by the Nuclear Regulatory Commission (NRC) in its March 12, 2012 letter issued to all power reactor licensees and holders of construction permits in active or deferred status. (Ref. 13) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 13)

1.2 BACKGROUND

Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near Term Task Force (NTTF) in response to Commission direction. The NTTF issued a report - Recommendations for Enhancing Reactor Safety in the 2 1 st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 14) On March 12, 2012, the NRC issued a letter to all power reactor licensees in accordance with 10CFR50.54(f). The 50.54(f) letter requests information to assure that certain NTTF recommendations are addressed by all U.S. nuclear power plants. (Ref. 5) The 50.54(f) letter requires, in part, all U.S.

nuclear power plants to perform seismic walkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration is within the current seismic licensing basis. This report documents the seismic walkdowns performed at Oyster Creek Generating Station Unit 1 in response, in part, to the 50.54(f) letter issued by the NRC.

The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 13) The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012; henceforth, referred to as the "EPRI guidance document." (Ref. 1) Exelon/Oyster Creek has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1) 1.3 PLANT OVERVIEW The Oyster Creek Nuclear Generating Station, a single unit facility, is located in Lacey Township, Ocean County, New Jersey. The unit was placed in commercial operation on December 23, 1969 under a Provisional Operating License. On July 2, 1991, the NRC issued a Full Term Operating License (No. DPR-16) permitting steady-state reactor core power levels not in excess of 1930 megawatts (thermal). The General Electric Company, 1-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 the prime contractor, utilized the services of Burns and Roe, Inc. for engineering support and construction management. The unit's steam is generated by a Boiling Water Reactor (BWR-2) with a Mark I type Containment designed by the Chicago Bridge and Iron Company under contract to Burns and Roe, Inc. (Ref. 2 section 1.1) 1.4 APPROACH The EPRI guidance document is used for the Oyster Creek 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

1.5 CONCLUSION

Seismic Walkdowns have been performed at the Oyster Creek Generating Station Unit 1 in accordance with the NRC endorsed walkdown methodology. All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program.

Evaluations of the identified conditions are complete and documented within the CAP.

These evaluations determined the Seismic Walkdowns resulted with no adverse anchorage conditions, no adverse seismic spatial interactions, and no other adverse seismic conditions associated with the items on the SWEL. Similarly, the Area Walk-Bys resulted with no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).

The Seismic Walkdowns identified a limited set of minor conditions with no discernible trend. Other than these minor conditions, the Seismic Walkdowns identified no degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on action. No planned or newly identified protection or mitigation features have resulted from the efforts to address the 50.54(f) letter.

Follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of 16 items deferred due to inaccessibility along with supplemental inspections of 16 electrical cabinets. Area Walk-Bys will be complete, as required, during these follow-on activities.

1-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the Oyster Creek Nuclear Generating Station Unit 1. The safe shutdown earthquake and a summary of the codes, standards, and methods used in the design of Seismic Category I SSCs are presented. This section does not establish or change the seismic licensing basis of the facility and is intended to provide a fundamental understanding of the seismic licensing basis of the facility.

2.2 SAFE SHUTDOWN EARTHQUAKE (SSE)

The original seismic design for the Oyster Creek Nuclear Generating Station critical structures and equipment is based on dynamic analyses using acceleration response spectrum curves which were based on a peak ground acceleration of 0.22g for the Safe Shutdown Earthquake (SSE). Beginning in September, 1995, seismic design of equipment and structures is based on a peak ground acceleration of 0.1 84g for the SSE.

(Ref. 2 section 3.7) 2.3 DESIGN OF SEISMIC CATEGORY I SSCs A full description of the Safe Shutdown Earthquake along with the codes, standards, and methods used in the design of the Seismic Category I SSCs for meeting the seismic licensing basis requirements is provided in the following Oyster Creek Generating Station UFSAR sections:

3.7 Seismic Design

3.8 Design of Category I Structures

3.9 Mechanical Systems and Components

3.10 Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment These UFSAR sections should be referred to for a detailed understanding of the seismic licensing basis.

2.3.1 Summary of Seismic Design The original seismic design for the Oyster Creek Nuclear Generating Station critical structures and equipment is based on dynamic analyses using acceleration response spectrum curves which were based on a peak ground acceleration of 0.1 Ig for the Operating Basis Earthquake (OBE) and 0.22g for the Safe Shutdown Earthquake (SSE).

2-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Beginning in September, 1995, seismic design of equipment and structures is based on a peak ground acceleration of 0.092g for the OBE and 0.184g for the SSE. (Ref. 2 section 3.7)

The design of Class I structures and major pieces of equipment (UFSAR Table 3.7-1) was based on a dynamic analysis using the acceleration response spectrum curves shown in UFSAR Figure 3.2-1 which are based upon the recommendations of Dr.

George W. Housner. These curves are based on the seismology, geology, and other pertinent data at the site. (Ref. 2 section 3.7)

Beginning in September, 1995, equipment, components, supports and structural subsystems are designed on the basis of the SSE design response spectra shown in UFSAR Figures 3.7-18 and 3.7-19. The SSE Site Specific Response Spectra (SSRS) have a peak ground acceleration of 0.184g horizontal and 0.0952g vertical. (Ref. 2 section 3.7)

An acceleration time history for the Oyster Creek Site was developed by URS/Blume, and reported in the "Seismic Acceleration Floor Response Spectra for the Reactor Building at Oyster Creek Nuclear Power Plant", in December 1981. This report is included as UFSAR Appendix 3.7A. (Ref. 2 section 3.7)

For the SSI analysis using the SSRS developed by Weston, three artificial time histories (two horizontal and one vertical) are generated by EQE International. These time histories are shown in UFSAR Figures 3.7-20 to 3.7-22. The time histories envelope the SSE target spectra in that no more than 5 points of the time history response spectra fall below the target spectra and no more than 10% below at any point. The comparisons of the time history response spectra and the SSRS are shown in UFSAR Figures 3.7-23 to 3.7-25. (Ref. 2 section 3.7)

The percentages of critical damping used for the seismic analyses of Class I structures, systems and components are listed in UFSAR Table 3.7-2. The percentages of critical damping values used for the recirculation system piping and the Seismic Category I structures and components in the New Radwaste Building are those specified in NRC Regulatory Guide 1.61. (Ref. 2 section 3.7)

The percentages of critical damping used for seismic analysis after September, 1995, are those specified in NRC Regulatory Guide 1.61 or ASME Code Case N-411 for piping. (Ref. 2 section 3.7) 2.3.2 Summary of Codes and Standards

1. Concrete Containment The design, materials, fabrication, construction and inspection of the Containment System conform to, but are not necessarily limited to, the applicable sections of the following codes and specifications which are used to establish or implement design bases and methods, analytical techniques, material properties, construction techniques and quality control provisions.

2-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 American Society of Mechanical Engineers

Boiler and Pressure Vessel Code, Sections VIII and IX, latest edition at the time of design, with all applicable addenda; nuclear case interpretation 1270 N-5, 1271 N, 1272 N-5 and other applicable case interpretations.

Boiler and Pressure Vessel Code,Section II, latest edition at the time of design with all applicable addenda, for the following material specifications:

" SA-201 Carbon-Silicon Steel Plates of Intermediate Tensile Ranges for Fusion-Welded Boilers and Other Pressure Vessels o SA-212 High Tensile Strength Carbon-Silicon Steel Plates for Boilers and Other Pressure Vessels o SA-300 Steel Plates for Pressure Vessels for Service at Low Temperature

" SA-333 Seamless and Welded Steel Pipe for Low Temperature Service o SA-350 Forged or Rolled Carbon and Alloy Steel Flanges, Forged Fittings, and Valves and Parts for Low Temperature Service American Society for Testinq and Materials Standards

A36 Structural Steel

A193 Specification for Alloy Steel and Stainless Steel Bolting Material for High Temperature Service A307 Specification for Low Carbon Steel Externally and Internally Threaded Standard Fasteners American Institute of Steel Construction

Specification for the design, fabrication and erection of structural steel for buildings Modifications subsequent to the basic Containment System design and construction have transpired over a number of years after being initiated in 1975. As such, numerous codes and code revisions have been utilized in carrying out the design and construction efforts.

The following codes, standards and specifications have been supplied to indicate the basic nature of the documents being employed. Specific information 'relative to actual governing documents used, must be obtained from the individual modification's "System Design Description" for the Oyster Creek plant.

American Society of Mechanical Engineers

ASME Boiler and Pressure Vessel Code,Section III, Subsection NE," Class MC Components," (1977 Edition through Summer 1977 Addenda).

ASME Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," Division 1, (1977 Edition through Summer 1978 Addenda).

ASME Boiler and Pressure Vessel Code,Section II, "Material Specifications,"

(1977 Edition through Summer 1978 Addenda).

ASME Boiler and Pressure Vessel Code,Section III, Subsection NF, "Component Supports," (1977 Edition through Summer 1977 Addenda).

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 American Concrete Institute

ACI 349-76, "Code Requirements for Nuclear Safety-Related Concrete Structures," (through 1979 Supplement).

2. Other Seismic Category IStructures The design, materials, fabrication, construction and inspection of other seismic Category I structures (including concrete and steel internal structures of steel or concrete containments) conform to, but are not necessarily limited to, the applicable sections of the listed codes and specifications which are used to establish or implement design bases and methods, analytical techniques, material properties, construction techniques and quality control provisions.

American Concrete Institute Publications

ACI 315, Manual of Standard Practice for Detailing Reinforced Concrete Structures 0 ACI 318, Building Code Requirements for Reinforced Concrete

ACI 347, Recommended Practice for Concrete Formwork

ACI 613, Recommended Practice for Selecting Proportions for Concrete a ACI SP-4, Formwork for Concrete American Institute of Steel Construction Publications:

Code of Standard Practice for Steel Buildings and Bridges

Specifications for Structural Joints Using ASTM A325 Bolts r Specification for the Design, Fabrication and Erection of Structural Steel for Buildings Concrete Reinforcing Steel Institute

CRSI, A Manual of Standard Practice for Reinforced Concrete Construction Other Codes and Specifications

UBC-1964 Uniform Building Code

3. Codes and Specifications Used for the Ventilation Stack

ACI-505-54, American Concrete Institute Specification for the Design of Reinforced Concrete Chimneys

ACI-318-63, Building Code Requirement for Reinforced Concrete

" ASCE Paper No. 3269, Wind Forces on Structures, Final Report of the Task Committee on Wind Forces

4. Codes and Specifications Used for the New Radwaste Building

ACI 318-71, Building Code Requirement for Reinforced Concrete

ACI 301-72, Specifications for Structural Concrete for Buildings

ACI 306, Recommended Practice for Cold Weather Concreting

ACI 311, Manual of Concrete Inspection 2-4

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

ACI 315,Manual of Standard Practice for Detailing Reinforced Concrete Structures

" ACI 347, Recommended Practice for Concrete Formwork

ACI 605 ,Recommended Practice for Hot Weather Concreting

ACI 614, Recommended Practice for Measuring, Mixing and Placing Concrete

ACI 211, Recommended Practice for Selecting Proportions for Concrete

ACI 214, Recommended Practice for Evaluation of Compression Test Results of Field Concrete

AISC, Specification for the Design, Fabrication and Erection of Structural Steel Buildings

AISC, Code of Standard Practice

AISC, Specification for Structural Joints Using ASTM A325 or A490 Bolts

AWS, Code for Welding in Buildings D1.1

" ASME, Boiler and Pressure Vessel Code,Section VIII, Pressure Vessel, Division I

ASCE Paper No. 3269, Task Committee Report "Wind Forces on Structures"

" UBC-1973, Uniform Building Code of the International Conference of Building Officials

BOCA, The BOCA Basic Building Code

5. Seismic Category I Instrumentation and Electrical Equipment The design of the Oyster Creek Nuclear Generating Station (OCNGS) began approximately in January 1964. At that time, the seismic design for equipment structures was based on dynamic analyses using acceleration response spectrum curves which were based on a ground motion of 0.11 g. The intent for the design was to ensure a safe shutdown for ground motions of 0.22 g. For further information on seismic input refer to UFSAR Section 3.7. (Ref. 2, section 3.10)

The NRC initiated a generic program to develop criteria for the seismic qualification of electrical and mechanical equipment in operating plants as an unresolved safety issue (USI A-46). Under this program, an explicit set of guidelines that should be used to judge the adequacy of the seismic qualifications of safety related equipment at all operating plants was developed. (Ref. 2, section 3.10)

The resolution of USI A-46 for Oyster Creek was by implementation of the generic criteria and methodology of the Generic Implementation Procedure for seismic verification of Nuclear Plant Equipment developed by the Seismic Qualification Utility Group. (Ref. 2, section 3.10) 2-5

12Q0108.80-R-001, Rev. I Correspondence No.: RS-12-177 3

Personnel Qualifications 3.1 OVERVIEW This section of the report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI guidance document.

Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.

3.2 PROJECT PERSONNEL 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 Name Equipment Seismic Reiwr evwr NSelection eeliomnt Plant Walkdown Basis icensing IPEEE Peer Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE)_____

A. Perez XM K. Hull X T.K. Ram X M. Etre X X S. Baker X X W, Ho (Exelon) X X X T. Bacon X X(2)

W. Djordjevic E. DeMonch (Exelon) X Notes:

1. Peer Review Team member for SWEL review only.

2. Peer Review Team Leader.

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12- .108.80-R-01, Rev. 1 Correspondence No.: RS-12-177 3.2.1 Stevenson & Associates Personnel The following provides a synopsis of each individual's background and experiences.

Antonio Perez, P.E.: Mr. Perez is a Senior Engineer III and serves as the General Manager of the S&A Hudson, WI office. He earned his Bachelor of Science degree in Mechanical Engineering at Michigan Technological University and is a licensed Professional Engineer in the states of Wisconsin and Minnesota. Mr. Perez has over 15 years of experience in project management, project engineering, equipment design, and mechanical systems design and has served in the nuclear power industry for over 11 years. He has extensive experience in Program and Design Engineering and has held positions such as MOV Engineer, Responsible Design Engineer, Design Engineering Supervisor and STA Trainee in the nuclear power industry. Throughout his years serving in the nuclear power industry, Mr. Perez has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs. Mr. Perez has successfully completed the Near-Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Training Course.

Kim Hull: Mr. Hull is a Senior Engineer III in the S&A Hudson, WI office. He earned his Master of Science degree in Mechanical Engineering at Michigan State University. Mr.

Hull has over 30 years of experience in the nuclear power industry and has held positions such as Shift Technical Advisor, Principal Engineer, Senior Instructor, and Mechanical Design Supervisor. He has an extensive background in all aspects of nuclear power plant modifications with a thorough understanding of configuration control/management along with design and licensing basis of nuclear power plants.

Throughout his years serving in the nuclear power industry, Mr. Hull has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs. Mr. Hull has successfully completed the Near-Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Training Course..

Tribhawan K. Ram, P.E.: Mr. Ram is a Senior Engineer III in the S&A Phoenix, AZ Office. He has over 28 year experience in the nuclear power industry with expertise in plant systems and design engineering. Currently, Mr. Ram is leading the electrical engineering effort in support of Post-Fukushima Seismic Margin Analysis (SMA) for two Taiwan nuclear stations (PWR and BWR). This effort, in support of the plant Safe Shutdown Equipment List (SSEL), consists of relay list development, relay screening (using GERS, SQURTS or other available testing data), and relay chatter analysis. Mr.

Ram was involved in resolving USI A-46 relay outliers for several plants (Dresden, Quad Cities, Millstone, Palisades, and Pilgrim). He evaluated dozens of control circuits for relay chattering issues. To replace outliers, Mr. Ram developed and/or supervised the development of modification packages including: replacement relay selection; relay testing specification preparation; and seismic testing facility visits for relay qualification.

As a systems manager, Mr. Ram conducted periodic system walkdowns to discover and then pursue resolutions for any design, maintenance or operational issues with equipment. He has developed test plans for circuit breaker and other electrical equipment replacement, including involvement in test plan execution during refueling outages. Mr. Ram has interfaced, with NRC in their biennial Component Design Basis 3-2

12..108.80-R-O01, Rev. 1 Correspondence No.: RS-12-177 Inspections (CDBI), and with INPO in their biennial evaluations. Throughout his years serving in the nuclear power industry, Mr. Ram has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs. Mr. Ram has MS degrees in Nuclear and Electrical Engineering from the University of Cincinnati, and an MBA from Bowling Green State University. He is a licensed Professional Engineer (electrical) in Ohio. Mr. Ram has completed a six month training course in BWR systems.

Mark Etre: Mr. Etre is a Senior Engineer III in the S&A Boston, MA office. He has managed and led seismic walkdowns and analyses of structures and components. Mr.

Etre has more than 20 years of seismic experience serving the nuclear industry. Mr.

Etre has participated in numerous USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20. Mr. Etre has a Master of Science in Structural Engineering from the Worcester Polytechnic Institute. He has received industry training as a Seismic Capability Engineer (EPRI 5-day SQUG training) and has successfully completed the Near-Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Training Course.

Seth Baker: Mr. Baker is a Senior Engineer I in the S&A Boston, MA office, where he joined in 2008. He has performed seismic and other dynamic evaluations on a variety of nuclear structures including buildings, equipment frames, and cabinets, as well as having designed several structural modifications. He has completed the NTTF Recommendation 2.3 Training Course and has subsequently performed seismic walkdowns on seven US nuclear units. Mr. Baker holds a Master of Science degree in Civil Engineering from Stanford University and a Bachelor of Science degree from the Worcester Polytechnic Institute.

Todd Bacon: Mr. Bacon is a Senior Consultant in the S&A Boston, MA office. He has over 30 years of experience in evaluations of nuclear systems, structures and components, with specialization in the dynamic analysis and design of piping systems, structures and equipment for seismic, other dynamic, fluid, and wind loads. He has managed various ASME Code related tasks for numerous US and international utilities.

Mr. Bacon has been involved with the dynamic analyses of systems associated with the Main Steam and other NSSS systems, as well as many other plant systems. In addition, Mr. Bacon has led the analysis and subsequent regulatory response for a number of issues including GL 96-03 and masonry block wall assessments related to IEB 80-11.

He is a licensed Professional Engineer (civil) in the states of California, Ohio, and Georgia. Mr. Bacon has successfully completed the Near-Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Training Course.

Walter Diordievic, P.E. Mr. Djordjevic is a Senior Consultant and serves as President of S&A with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has managed and led seismic walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Mr. Djordjevic has 37 years of seismic experience serving the nuclear industry. Mr. Djordjevic performed and managed more than 20 USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20. Mr.

Djordjevic has a Master of Science in Structural Engineering from the Massachusetts Institute of Technology. He has received industry training as a Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, Seismic Fragility and Seismic Walkdown Engineer (SWE).

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1200108.80-R-OO1, Rev. I Correspondence No.: RS-12-177 3.2.2 Additional Personnel Exelon Plant Operations, E. DeMonch reviewed the SWEL. Mr. DeMonch was an operator on shift for 25 years in many positions from Entry level Control Room Licensed Operator up to a Shift Manager. From 2000 to 2010 he supported maintenance as the Fin SRO. From 2010 to 2011 he supported Operations Training as a (SME) SRO instructor. He is currently working as Operations representative, Previous SRO, Supervisor supporting the Fukushima Response project at Oyster Creek Station. He is familiar with all aspects of the station operating procedures.

Various 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.

Exelon Engineering staff member Mr. Wing Ho performed the IPEEE Vulnerabilities Review based, in part, on the Oyster Creek IPEEE submittal along with subsequent correspondence and station records. (Ref. 3) Mr. Ho is a Structural Engineer in the Exelon Engineering Department. He has worked at Oyster Creek since 2009. He has successfully completed the Near-Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Training Course.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 4

Selection of SSCs 4.1 OVERVIEW This section of the report describes the process used to select structures, systems, and components, (SSCs) that were included in the Seismic Walkdown Equipment List (SWEL). The actual equipment lists that were developed in this process are found in Appendix B and are as follows:

Table B-i, Base List 1 a Table B-2, Base List 2

Table B-3, SWEL 1

Table B-4, SWEL 2 4.2 SWEL DEVELOPMENT The selection of SSCs process described in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Ref. 1), was utilized to develop the SWEL list for Oyster Creek Generating Station.

The SWEL is comprised of two groups of items:

SWEL 1 is a sample of items to safely shut down the reactor and maintain containment integrity

SWEL 2 is a list of spent fuel pool related items 4.3 SWEL I DEVELOPMENT 4.3.1 SWEL 1 - Sample of Required Items for the Five Safety Functions The process for selecting a sample of SSCs for shutting down the reactor and maintaining containment integrity began with the Oyster Creek Individual Plant Examination for External Events (IPEEE) (Ref. 3). Table 3-3, Oyster Creek PRA Comp.

List, and Table 3-4, Additional Components, of Reference 3 were utilized as the initial list of equipment. The information provided in the Reference 3 tables was supplemented with two Excel Spreadsheets: a) "OC Q Component List.xls" (Ref, 5) and b) "Oyster Creek SSEL.xls" (Ref. 6). The three datasets were compiled into a single list of SSCs.

The components on this initial list were then subjected to the following four (4) screens to identify the items to be included on the first Seismic Walkdown Equipment List (SWEL 1):

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

1. Screen #1 - Seismic Category 1 As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. Each item on the initial list was reviewed to determine if it had a defined seismic licensing basis. All items identified as Class I, as defined in the Oyster Creek UFSAR Chapter 3, were identified as having a defined seismic licensing basis. (Ref. 2) Electrical enclosures containing Class I electrical devices were identified as Class I. Class I determination was made through a review of current design and licensing basis documentation.

As a means to expedite this process, the list of SSCs provided in Reference 5 included a QA Class and Seismic Cat. All items with a QA Class of "Q" and Seismic Cat of "W" or "X" were considered Class I. QA Class "Q" items are defined as Safety Related; Seismic Cat "W" items are defined as Seismic Class I, operable during and after an SSE; and Seismic Cat "X"items are defined as Seismic Class I, operable after an SSE.

Screen # 1 reduced the scope of items of the initial list to include only Class I items.

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 further reduced the components on the list of any Safety Category I Structures, Containment Penetrations, Safety Category I Piping Systems, cable/conduit raceways and HVAC ductwork.

3. Screen #3 - Support for the Five 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:

A. Reactor Reactivity Control (RRC)

B. Reactor Coolant Pressure Control (RCPC)

C. Reactor Coolant Inventory Control (RCIC)

D. Decay Heat Removal (DHR)

E. Containment Function (CF)

The first four functions are associated with bringing the reactor to a safe shutdown condition. The fifth function is associated with maintaining containment integrity.

As described in Appendix E of Reference 1, the safety function for each item on the final SWEL 1 list was identified. It is noted that items on SWEL 1 with a specific safety function(s) are considered frontline systems. Items with a safety-function designation of 'Support System HVAC', 'Support System AC Power', 'Support System DC Power', or 'Cooling Water' may be a frontline or support system. Items with a safety-function designation of 'Support System HVAC (SSHVAC), 'Support System AC Power' (SSAC), 'Support System DC Power' (SSDC), 'Support System Compressed Air' (SSCA) or 'Cooling Water' (UHS) support at least one of the five safety functions.

The resultant equipment list after Screen #3 is defined in the EPRI guidance document as Base List 1 and is included in Appendix B. (Ref. 1) 4-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

4. Screen #4- Sample Considerations This screen is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Category 1 equipment and systems to meet the objectives of the NRC 50.54(f) Letter. The following attributes were considered in the selection process for items included on SWEL 1:

A. A variety of types of systems The system is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample of several systems that perform one or more 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).

B. Major new and replacement equipment The equipment included on SWEL 1 includes several items that have been modified or replaced over the past several years. Each item on SWEL 1 that is new or replaced is identified.

C. 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 listed in Reference 1 Appendix B: Classes of Equipment. Where appropriate, at least one piece of equipment from each class is included on SWEL 1. Screening #1, #2, and #3 resulted in no equipment in the following classes:

(10) Air Handlers o (11) Chillers

(12) Compressors D. 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.

E. Equipment enhanced due to vulnerabilities identified during the IPEEE program A review of the IPEEE documents indicate no enhancements of Class I equipment resulted from the IPEEE program. (Ref. 3 and 10) This was confirmed in NRC IPEEE SER that two IPEEE program-related modifications involved non-safety related Combustion Turbines. (Section 2.16 of Attachment 1 of Ref. 10)

F. 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 importance for a Loss of Off-Site Power (LOOP) scenario from the internal plant PRA were used. Additionally, the list of risk-significant components for the LOOP PRA were compared with the draft SWEL 1 to 4-3

12Q0108.80-R-OO1, Rev. 1 Correspondence No.: RS-12-177 confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1. (Ref. 12) 4.4 SWEL 2 DEVELOPMENT 4.4.1 SWEL 2- Spent Fuel Pool Related Items The process for selecting a sample of SSCs associated with the spent fuel pool (SFP) began with a review of the station design and licensing basis documentation for the SFP and the interconnecting SFP cooling system. The following four screens narrowed the scope of SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2):

1. Screen #1 - Seismic Category I As described in Reference 1, the adequacy of the SFP structure is assessed by analysis as a Seismic Category 1 structure. Therefore, the SFP structure is assumed to be seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2.

As per Licensing Design Basis Memo MCC-E1 C320-92-1075, three portions of the SFPCS are regulatory required (RR), summarized as: a) the part of the SFPCS bounded by valves V-18-2 and V-18-19; b) the part bounded by valves V-18-2, 3, 4, 19, 25 to 28, 47, and 116. It includes- ----otherportions of the originalSFPCS to the extent that they will not become missiles--- and c) "----the balance of the RR scope ---- is that requiredby UFSAR section 9.1.3.1." (Ref. 9)

As per the UFSAR Section 9.1.3.3, "During 1986, a seismic analysis of the SFPC System revealed that the OriginalSFPC System did not satisfy Seismic Class I stress criteria.

However, the Augmented SFPC System, added as partof the SFSP expansion described in Amendment 78 of the originalFDSAR was found to satisfy Seismic Class I stress criteria.

A portion of the OriginalSFPC System was upgraded to Seismic Class I during the 1986 Cycle 11 Refueling Outage. Seismic qualificationwas based upon the SEP response spectra and and operability criteriaconsistent with ASME Section //1, Division I, Appendix F. The non upgradedportion of the originalSFPCS piping is located in the old Radwaste Building and the connecting tunnel. This piping became isolatableby the addition of a new gate valve, V-18-116, to the system."

Therefore, these portions described above are considered Seismic Class I components and representative elements are added to the SWEL 2.

The process for selecting the equipment sample came from searching the "OC Q Component List.xls", and the Oyster Creek Excel Spreadsheet titled "OC SFP Component List.xls" that meet the above licensing design basis and UFSAR requirements. (Ref. 5 & 8) The components listed on the three documents were then subjected to the following four screens to identify the items to be included on the second Seismic Walkdown Equipment List (SWEL 2):

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

2. Screen #2- Equipment or Systems This screen considers only those items associated with the SFP that are appropriate for an equipment walkdown process.

3. Screen #3- Sample Considerations This screen represents a process that is intended to result in a SWEL 2 that sufficiently represents a population of SFP Seismic Category 1 equipment and systems to meet the objectives of the NRC 50.54(f) letter. The following attributes were considered in the development of SWEL 2:

4. A variety of types of systems The equipment included on SWEL 2 is a representative sample of the systems associated with the SFP and its cooling systems (Spent Fuel Pool Cooling and Augmented Spent Fuel Pool Cooling).

A. Major new and replacement equipment Though there are no major new or replacement equipment, Mod Package ECR 08-01114 provided the ability to connect fire water system to the SPFCS via new valves. Seismic Class I valve V-18-1266 has been added to SWEL 2 to account for this modification B. A variety of types of equipment The equipment class is identified for each item on SWEL 2. The equipment included on SWEL 2 is a representative sample from each of the classes of equipment listed in Reference 1 Appendix B: Classes of Equipment. Where appropriate, at least one piece of equipment from each class is included on SWEL 2.

The classes/types of equipment include; (00) Other (manual valves), (05)

Horizontal Pumps, (18) Instrument Racks, (19) Temperature Sensors, and (21) Tanks and Heat Exchangers.

C. A variety of environments The location for each item is identified on SWEL 2. The equipment included on SWEL 2 should be a representative sample from a variety of environments (locations) for equipment associated with the SFP and its cooling system. All items are in the reactor building.

5. Screen #4- Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly.

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 it is assumed the SFP gates are 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 without failure and do not allow for a rapid drain-down of the SFP.

The SSCs identified in this screen are not limited to Seismic Category I (Class I) items, but is limited to those items that could allow rapid drain-down of the SFP.

Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the earthquake.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Excerpts from the Oyster Creek UFSAR sections state:

9.1.2.2.1: "... The liner is liquid tight, serving as a barrierto any moisture loss from the concrete."

"... To avoid unintentionaldrainingof the pool, there are no penetrations that would permit the pool to be drainedbelow one foot above the active fuel. All lines extending below this level are equipped with suitable valving to prevent backflow."

9.1.3.3: "The SFPC System is designed to prevent the loss of pool water inventory by providing suction for the system flow from the surface of the pool, and returning the coolant through diffusers, which are provided with backflow prevention devices to eliminate the potential for siphoning" The Class I spent fuel cooling system shown in Drawing GE 237E756 consists of two complete cooling trains. (Ref. 4)

Oyster Creek UFSAR section 9.1.2.2.1 states:

"----The spent fuel storage pool is a reinforced concrete structure, completely lined with seam welded stainless steel sheets, themselves welded to reinforcing members embedded in the concrete. The pool was designed to withstand the anticipatedearthquake loadings as a Class I structure."

With this design feature in place, rapid drain-down associated with cracking of the SFP structure is not considered a credible event during the postulated earthquake.

No rapid drain-down components are included on the SWEL 2 list.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 5

Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by a two (2) person team of trained Seismic Walkdown Engineers (SWEs), in accordance with the EPRI guidance document during the week of August 20, 2012. The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sub-sections.

Consistent with the EPRI guidance document, Section 4: Seismic Walkdowns and Area Walk-Bys, the SWEs used their engineering judgment, based on their experience and training, to identify potentially adverse seismic conditions. Where needed, the engineers were provided the latitude to rely upon new or existing analyses to inform their judgment.

The SWEs conducted the Seismic Walkdowns and Area Walk-Bys together as a team.

During the evaluations, the SWEs actively discussed their observations and judgments with each other. The results of the Seismic Walkdowns and Area Walk-Bys reported herein are based on the comprehensive agreement of the SWEs.

5.2 SEISMIC WALKDOWNS The Seismic Walkdowns focused on the seismic adequacy of the items on the SWEL

.(SWEL 1 and SWEL 2) as provided in Appendix B of this report. The Seismic Walkdowns also evaluated the potential for nearby SSCs to cause adverse seismic interactions with the SWEL items. The Seismic Walkdowns focused on the following adverse seismic conditions associated with the subject item of equipment:

" Adverse anchorage conditions

Adverse seismic spatial interactions

Other adverse seismic conditions The results of the Seismic Walkdowns have been documented on the Seismic Walkdown Checklist (SWC) provided in the EPRI guidance document, Appendix C.

Seismic Walkdowns were performed and a SWC completed for 101 of the 117 items identified on the Oyster Creek Generating Station SWEL. Additionally, photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC. Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management. system.

Seismic Walkdowns are deferred for the remaining 16 items to a time when the equipment is accessible. These items could not be walked down during the 180-day period following the issuance of the 1 OCFR50.54(f) letter due to their being inaccessible.

Inaccessibility of this equipment was either based on the location of the equipment (environment that posed personnel safety concerns while the unit is operating) or due to the electrical safety hazards posed while the equipment is operating. Appendix E of this 5-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 report identifies the inaccessible equipment along with the plan for future Seismic Walkdowns.

The, following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions during the Seismic Walkdowns.

5.2.1 Adverse Anchorage Conditions Guidance for identifying anchorage that could be degraded, non-conforming, or unanalyzed relied on visual inspections of the anchorage and verification of anchorage configuration. Details for these two types of evaluations are provided in the following two subsections.

The evaluation of potentially adverse anchorage conditions described in this subsection applies to the anchorage connections that attach the identified item of equipment to the civil structure on which it is mounted. For example, the welded connections that secure the base of a Motor Control Center (MCC) to the steel embedment in the concrete floor would be evaluated in this subsection. Evaluation of the connections that secure components within the MCC is covered later in the subsection "Other Adverse Seismic Conditions."

Visual Inspections The purpose of the visual inspections was to identify whether any of the following potentially adverse anchorage conditions were present:

Bent, broken, missing, or loose hardware

Corrosion that is more than mild surface oxidation

Visible cracks in the concrete near the anchors

Other potentially adverse seismic conditions Based on the results of the visual inspection, the SWEs judged whether the anchorage was potentially degraded, non-conforming, or unanalyzed. The results of the visual inspection were documented on the SWC, as appropriate. If there was clearly no evidence of degraded, nonconforming, or unanalyzed conditions, then it was indicated on the checklist and a licensing basis evaluation was not necessary. However, if it was not possible to judge whether the anchorage is degraded, nonconforming, or unanalyzed, then the condition was entered into the Corrective Action Program as a potentially adverse seismic condition.

5.2.2 ConfigurationVerification In addition to the visual inspections of the anchorage as described above, the configuration of the installed anchorage was verified to be consistent with existing plant documentation for at least 50% of the items on the SWEL.

Line-mounted equipment (e.g., valves mounted on pipelines without separate anchorage) was not evaluated for anchorage adequacy and was not counted in establishing the 50% sample size.

Examples of documentation that was considered to verify that the anchorage installation configurations are consistent with the plant documentation include the following:

0 Design drawings 5-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

Seismic qualification reports of analyses or shake table tests

IPEEE program documentation, as applicable The Table C-1 of Appendix C indicates the anchorage verification status for components as follows:

N/A: components that are line-mounted and/or are not directly anchored (with separate anchorage) to the civil structure and therefore do not count in the anchorage confirmation total Y: components that are anchored to the civil structure which were confirmed to be consistent with design drawings and/or other plant documentation N: components that are anchored to the civil structure for which anchorage drawings were not identified and/or retrieved See Table 5-1 below for the accounting of the 50% anchorage configuration confirmations, and the individual SWC forms in Appendix C for the specific drawings used for each anchorage verification confirmation.

Table 5-1. Anchorage Configuration Confirmation No. of SWEL NIA Items Required to SWEL Items Confirm? Items Confirmed (A) (B) (A-B)/2 Total of SWEL1 117 58 30 47 and SWEL 2 5.2.3 Adverse Seismic SpatialInteractions An adverse seismic spatial interaction is the physical interaction between the SWEL item and a nearby SSC caused by relative motion between the two during an earthquake. An inspection was performed in the area adjacent to and surrounding the SWEL item to identify any seismic interaction conditions that could adversely affect the capability of that SWEL item to perform its intended safety-related functions.

The three types of seismic spatial interaction effects that were considered are as follows:

Proximity

" Failure and falling of SSCs (Seismic II over I)

Flexibility of attached lines and cables Detailed guidance for evaluating each of these types of seismic spatial interactions is described in the EPRI guidance document, Appendix D: Seismic Spatial Interaction.

The Seismic Walkdown Engineers exercised their judgment to identify seismic interaction hazards. Section 5.2.5 provides a summary of issues identified during the Seismic Walkdowns.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 5.2.4 OtherAdverse Seismic Conditions In addition to adverse anchorage conditions and adverse seismic interactions, described above, other potentially adverse seismic conditions that could challenge the seismic adequacy of a SWEL item could have been present. Examples of the types of conditions that could pose potentially adverse seismic conditions include the following:

Degraded conditions

Loose or missing fasteners that secure internal or external components to equipment

" Large, heavy components mounted on a cabinet that are not typically included by the original equipment manufacturer

Cabinet doors or panels that are not latched or fastened

Other adverse conditions Any identified other adverse seismic conditions are documented on the items' SWC, as applicable.

5.2.5 Conditions Identification during Seismic Walkdowns Table 5-2 provides a summary of conditions identified during the equipment Seismic Walkdowns. The equipment Seismic Walkdowns resulted in a total of five (5) conditions identified and each of these was entered into the station's CAP. All of the identified conditions were assessed and it was concluded that the condition would not prevent the associated equipment from performing its safety-related function(s). None of the conditions identified by the SWEs during the equipment Seismic Walkdowns were concluded to be adverse seismic conditions.

5.3 AREA WALK-BYS The purpose of the Area Walk-Bys is to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL items. Vicinity is generally defined as the room containing the SWEL item. If the room is very large (e.g.,

Turbine Hall), then the vicinity is identified based on judgment, e.g., on the order of about 35 feet from the SWEL item. This vicinity is described on the Area Walk-By Checklist (AWC), shown in Appendix D of this report. A total of 28 AWCs were completed for Oyster Creek Unit 1.

The key examination factors that were considered during Area Walk-Bys include the following:

0 Anchorage conditions (if visible without opening equipment) 0 Significantly degraded equipment in the area

A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays) a Potentially adverse seismic interactions including those that could cause flooding, spray, and fires in the area 0 Other housekeeping items that could cause adverse seismic interaction (including temporary installations and equipment storage) 5-4

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177

Scaffold construction was inspected to meet Exelon Procedure MA-AA-796-024, Scaffold Installation Inspection and Removal

Seismic housekeeping was examined to meet station procedure 119.5, Loose Equipment Storage The Area Walk-Bys are intended to identify adverse seismic conditions that are readily identified by visual inspection, without necessarily stopping to open cabinets or taking an extended look. Therefore, the Area Walk-By took significantly less time than it took to conduct the Seismic Walkdowns described above for a SWEL item. If a potentially adverse seismic condition was identified during the Area Walk-By, then additional time was taken, as necessary, to evaluate adequately whether there was an adverse condition and to document any findings.

The results of the Area Walk-Bys are documented on the AWCs included in Appendix D of this report. A separate AWC was filled out for each area inspected. A single AWC was completed for areas where more than one SWEL item was located.

Additional details for evaluating the potential for adverse seismic interactions that could cause flooding, spray, or fire in the area are provided in the following two subsections.

Seismically-Induced Flooding/Spray Interactions Seismically-induced flooding/spray interactions are the effect of possible ruptures of vessels or piping systems that could spray, flood or cascade water into the area where SWEL items are located. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.

One area of particular concern to the industry is threaded fire protection piping with long unsupported spans. If adequate seismic supports are present or there are isolation valves near the tanks or charging sources, flooding may not be a concern. Numerous failures have been observed in past earthquakes resulting from sprinkler head impact.

Less frequent but commonly observed failures have occurred due to flexible headers and stiff branch pipes, non-ductile mechanical couplings, seismic anchor motion and failed supports.

Examples where seismically-induced flooding/spray interactions could occur include the following:

Fire protection piping with inadequate clearance around fusible-link sprinkler heads

Non-ductile mechanical and threaded piping couplings can fail and lead to flooding or spray of equipment

" Long, unsupported spans of threaded fire protection piping

" Flexible headers with stiffly supported branch lines

Non-Seismic Category I tanks The SWEs exercised their judgment to identify only those seismically-induced interactions that could lead to flooding or spray.

Seismically-Induced Fire Interactions Seismically-induced fire interactions can occur when equipment or systems containing hazardous/flammable material fail or rupture. This type of seismic interaction was 5-5

12Q0108.80-R-0O1, Rev. 1 Correspondence No.: RS-12-177 considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.

Examples where seismically-induced fire interactions could occur include the following:

Hazardous/flammable material stored in inadequately anchored drums, inadequately anchored shelves, or unlocked cabinets 0 Natural gas lines and their attachment to equipment or buildings

Bottles containing acetylene or similar flammable chemicals

Hydrogen lines and bottles Another example where seismically-induced fire interaction could occur is when there is relative motion between a high voltage item of equipment (e.g., 4160 volt transformer) and an adjacent support structure when they have different foundations. This relative motion can cause high voltage busbars, which pass between the two, to short out against the grounded bus duct surrounding the busbars and cause a fire.

The Seismic Walkdown Engineers exercised their judgment to identify only those seismically-induced interactions that could lead to fires.

5.3.1 Conditions Identification during Area Walk-bys Table 5-3 at the end of this section provides a summary of the conditions identified during the Area Walk-Bys. Five (5) conditions were identified during the Area Walk-Bys and entered into the station CAP. No potentially adverse seismic conditions were identified that resulted in a seismic licensing basis evaluation. No seismically-induced flooding or spray interactions were identified during the Area Walk-Bys. No seismically-induced fire interactions were identified during the Area Walk-Bys.

5.4 SUPPLEMENTAL INFORMATION ON ELECTRICAL CABINET INSPECTIONS Following the completion of the online seismic walkdowns, the industry was made aware that the NRC staff had clarified a position on opening electrical cabinets to inspect for other adverse seismic conditions. The purpose for opening these cabinets is to inspect for evidence of:

internal components not being adequately secured,

" whether fasteners securing adjacent cabinets together are in place, and

other adverse seismic conditions.

Appendix E of this report includes Table E-2 which identifies components in the specified equipment classes that would be considered as electrical cabinets:

1. Motor Control Centers and Wall-Mounted Contactors

2. Low Voltage Switchgear and Breaker Panels

3. Medium Voltage, Metal-Clad Switchgear

4. Transformers

14. Distribution Panels and Automatic Transfer Switches

16. Battery Chargers and Inverters

20. Instrumentation and Control Panels 5-6

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Components that are identified on Table E-1 (inaccessible and deferred components) are not listed on Table E-2 to avoid redundancy. Table E-2 indicates internal accessibility of each cabinet. Cabinets that have been identified as requiring these supplemental internal inspections are those with doors or panels with latches or thumbscrews and can be readily opened during normal maintenance activities. Also provided for each cabinet is a proposed milestone schedule for performing these internal inspections and the associated station tracking number (IR number).

The Seismic Walkdown Checklists (SWC) for the components identified in Table E-2 that can be opened for internal inspections will be revised at the time of the supplemental walkdown to indicate the results of these internal inspections.

Table 5-2. Conditions Identified during Seismic Walkdowns Actions Complete Description of Issue Action Request ID (IR) Yes/No Item ID 1A2-460V Loose bolts at 1A2-460V USS 1403294 No DC-F Loose thermometer at DC-F 1406823 Yes panel 1A21B-460V Open hooks at 1A21B-460V 1403305 No MCC MCC Broken bolts at containment H-21-1A spray heat exchangers H-21-1A 1403183 Yes and -1B_

Seismic interaction between valves V-15-133 and V-6-2917 Notes:

1) "Yes" indicates that any corrective actions resulting from the issue are complete

2) "No" indicates that any corrective actions resulting from the issue are NOT complete. Actions are tracked by the IRnumber in the station CAP.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Table 5-3. Conditions Identified during Area Walk-Bys Action Actions Item ID Description of Issue Request Complete ID (IR) Yes/No RK-3 Area Bent hanger rod by RB 51' airlock. 1402715 No Diesel se Fuel Oil1457 Ye Loose ladder adjacent to diesel oil tank 1405874 Yes Storage A-480V Switchgear Bent hanger rod at 1A23-460V MCC 1403359 Yes Room 4160V A&B Loose nut at strap hanger adjacent to 1B-4160V 1405576 No Room switchgear DG 1 Room Mislabeled level indicators at EDG day tanks 1405561 No Notes:

1) "Yes" indicates that any corrective actions resulting from the issue are complete

2) "No" indicates that any corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station CAP.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 6

Licensing Basis Evaluations The EPRI guidance document, Section 5: Seismic Licensing Basis Evaluation provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified. The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). In lieu of this process, Exelon/Oyster Creek utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/Oyster Creek processes and procedures, all questionable conditions identified by the SWEs during the walkdowns were entered into the station CAP to be further evaluated and addressed as required. The SWEs provided input to support the identification and evaluation (including seismic licensing basis evaluations, as required) of the potentially adverse seismic conditions entered into the CAP. The station corrective action program is a more robust process than that provided in the EPRI guidance document; in part, ensuring each condition is properly evaluated for conformance with design and licensing bases and corrected as required.

Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP. For those conditions that required, seismic licensing basis evaluations were completed and documented within the IR. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 7

IPEEE Vulnerabilities Resolution Report The term vulnerability is defined as any core damage sequence whose frequency exceeds 1 E-4 per year or any large early containment failure sequence whose frequency exceeds 1 E-6 per year (see Section 1.5.3 of the IPEEE Submittal Report (Ref. 3).

The Oyster Creek IPEEE Submittal Report (Ref. 3) did not identify any vulnerability, outlier, anomaly, or enhancement. However, the IPEEE report (Ref. 3) recommended two "improvements" on the Combustion Turbines:

Improvement 1: Ensure all bolts on the Forked River Combustion Turbine fin-fan coolers are installed and torqued properly. Although adequate capacity for withstanding the range of potential ground motions exist, additional margin could be obtained by ensuring all bolts are installed and torqued properly.

Improvement 2: Consider the addition of battery spacers in the Combustion Turbine battery compartments. Although the current battery spacing is sufficient to prevent battery failure due to interactions, additional margin could result with the use of battery spacers.

Based on the Oyster Creek Nuclear Generating Station letter to the NRC, "Response to the Supplemental Request for Additional Information, Oyster Creek Nuclear Generating Station, Seismic Portion of the Oyster Creek Individual Plant Examination for External Events," dated June 29, 2000, a third walkdown performed in support of these recommendations verified that little improvement would be achieved as a result of modifications to the battery compartments and the recommendation for Improvement 2 was closed. Fin-fan cooler bolts were added and torqued to complete Improvement 1.

(Ref. 15)

The NRC Staff Evaluation Report (see section 2.16 of Attachment 1, Reference 10) concurred that no vulnerability exists in Oyster Creek, and accepted the disposition of the improvements described above. Therefore, no open items exist as a result of the seismic portion of the IPEEE program.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 8

Peer Review A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI

.guidance document. The Peer Review process included the following activities:

Review of the selection of SSCs included on the SWEL

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

Review of Licensing basis evaluations, as applicable

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

Review of the submittal report

Provide a summary report of the peer review process in the submittal report The peer reviews were performed independently from this report and the summary Peer Review Report is provided in Appendix F of this report.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 9

References Reference drawings related to SWEL items are provided in the Seismic Walkdown Checklists and if applicable, in the Area-Walkdown Checklists.

1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.

2. Oyster Creek Generating Station Updated Final Safety Analysis Report (UFSAR)

Revision 17, dated October 2011

3. Oyster Creek Individual Plant Examination for External Events (IPEEE), dated December 1995 (OC-IPE-03)

4. Oyster Creek Station Drawing GE 237E756 Rev. 53, Spent Fuel Cooling System

5. Oyster Creek Excel Spreadsheet titled: "OC Q Component List

6. Oyster Creek Excel Spreadsheet titled: "Oyster Creek SSEL"

7. Not used

8. Oyster Creek Excel Spreadsheet: "SFP Component List"

9. Oyster Creek Licensing Design Basis for the Spent Fuel Pool Cooling Systems Memo MCC-E1 C320-92-1075, dated March 13,1992

10. NRC Letter from Helen N. Pastis to Ronald DeGrgorio, Dated February 8, 2001,

Subject:

Review of Oyster Creek Nuclear Generating Station (Oyster Creek)

Individual Plant Examination of External Events (IPEEE) Submittal (TAC NO.

M83652)

11. Not used

12. Internal RM Document, OC-MISC-009, Rev. 0, Oyster Creek Risk Importance listing to Support Development of the Seismic Walkdown Equipment List (SWEL)

13. NRC (E Leeds and M Johnson) Letter to All Power Reactor Licensees et al.,

"Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic," dated March 12, 2012 9-1

12Q0108.80-R-OO1, Rev. 1 Correspondence No.: RS-12-177

14. "Recommendations for Enhancing Reactor Safety in the 2 1 st Century: The Near-term Task Force Review of Insights from the Fukushima Dai-ichi Accident," ADAMS Accession No. ML11186107, July 12, 2011

15. Oyster Creek Letter from Sander Levin to U.S. Nuclear Regulatory Commission,

Subject:

"Reply to a Response for Additional Information: Individual Plant Examination of External Events," dated June 29, 2000 9-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 A

Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix A:

T.K. Ram, Equipment Selection Engineer ........................................................ A-2 K. Hull, Equipm ent Selection Engineer .............................................................. A-4 M. Etre, SW E, Licensing Basis Reviewer ........................................................... A-7 S. Baker, SWE, Licensing Basis Reviewer .................................................... A-10 W. Ho, SWE, Licensing Basis Reviewer, IPEEE Reviewer ................................. A-13 A. Perez, SW EL Peer Reviewer .................................................................. A-16 T. Bacon, Peer Review er ............................................................................. A-20 W. Djordjevic, Peer Review Team Leader ........................................................ A-25 A-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Tribhawan Ram EDUCATION:

B.S. - Electrical Engineering, Punjab University, India, 1972 M.S. - Electrical Engineering, University of Cincinnati, 1977 M.S. - Nuclear Engineering, University of Cincinnati, 1982 M.B.A. - Bowling Green State University, 1996 PROFESSIONAL REGISTRATION:

State of Ohio PROFESSIONAL HISTORY:

Stevenson & Associates, Inc., Senior Engineer, 2011 - present Public Service Electric & Gas Co., Senior Plant Systems Engineer, Hancock Bridge, NJ, 2007 - 2011 Entergy Corporation, Plymouth, Massachusetts, Senior Design Engineer, 2002-2007 Various Companies, Contract Consulting Project Engineer, 1996 - 2002 Public Service Electric & Gas Co., Senior Staff Engineer, Hancock Bridge, NJ, 1983-1990 Toledo Edison Co., Toledo, Ohio, Senior Assistant Engineer, Associate Engineer, 1978-1983 PROFESSIONAL EXPERIENCE:

Electrical and Controls Design Engineering 0 Plant Systems Engineering

Transformer and Relay(s) Spec Developer

Plant Modification Engineering a Systems and Component Test Engineering

Factory Testing Witness

6 Month BWR Systems Engineering Training

ETAP Trained

Arc Flash IEEE 1584 Trained Mr. Ram has over 28 years of electrical project, design and systems engineering experience in US nuclear plants. As part of the Seismic Margin Analysis (SMA) team, in 2012, Mr. Ram is leading the electrical engineering EPRI methodology effort to perform Post-Fukushima relay list development and evaluation to support Safe Shutdown Equipment List (SSEL), including relay functional screening and chatter analysis, for Taiwan nuclear plants (both PWR and BWR). In this effort, he is preparing the final reports including recommendations to replace any bad actor relays. Mr. Ram is preparing proposals to replace these bad actors including modification package development for field replacement of these relays. He has prepared proposals to lead similar forthcoming relay evaluation efforts for several Westinghouse plants in the USA. Mr. Ram has either prepared or peer reviewed the Seismic Walkdown Equipment Lists (SWEL 1 & 2) for several Exelon Plants.

A-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 As a senior plant systems engineer, Mr. Ram has: 1. Developed several test plans for modification packages for the replacement of low and medium voltage circuit breakers (ABB K-Line to Square D Masterpact; GE Magneblast to Wyle Siemens) and for the replacement of the entire Pressurizer Heater Bus switchgear; 2. Personally been involved in execution of these test plans during refueling outages;

3. Witnessed factory testing of Pressurizer Heater Bus Switchgear; 4. Interfaced with NRC in their biennial Component Design Basis Inspections (CDBI); Interfaced with INPO in their biennial evaluations; 5. Developed and executed Performance Centered Maintenance (PCM) strategies for Motor Control Centers (MCCs) and low and medium voltage circuit breakers and switchgear; 6.

Developed and executed margin improvement strategies for pressurizer heater busses, for twin units, through obtaining funds and then equipment replacement; 7. Developed refueling outage scoping for low and medium voltage circuit breakers and MCCs through working with outage group, maintenance, operations, and work MGMT; 8. Resolved breaker grease hardening issue for ABB K-Line breakers, over a two year period, through working with maintenance and work MGMT in implementing accelerated overhauls with better grease; 9. Trained operations and engineering personnel in the Engaging People and Behavior Change process, as part of a case study team and; 10.

Resolved day to day operations and maintenance issues with systems of responsibility (low and medium voltage systems)

Mr. Ram has regularly participated in the EPRI annual circuit breaker user group conferences; at the 2011 meeting, he made a presentation on circuit breaker as found testing vis-a-vis protection of equipment, cables, and containment penetrations, and selective coordination preservation.

As a Senior Design Engineer, Mr. Ram has: 1. Developed specifications and procured 345/4.16/4.16 kV and 23/4.16/4.16 kV transformers (ranging up to $1.25 million); 2. Prepared a modification package to install the 23 kV/4.16 kV/4.16 kV transformer, including leading the project team to get this transformer successfully installed, tested, and placed in service; 3. Developed ETAP scenarios and performed load flow studies to successfully support the 2006 INPO evaluation; 4. Performed arc flash calculations per IEEE 1584 methodology for 4 kV, 480V Load Centers, and MCCs, enabling a justification of reduced arc flash rated clothing, thereby allowing conversion of OUTAGE PMs into ONLINE PMs and; 5. Performed single point system vulnerability analysis.

As a Consulting Lead Project Engineer, Mr. Ram was heavily involved in resolution of the USI A-46 for several plants. He performed an extensive review of dozens of control circuits for relay chattering issues. To replace bad relay actors, Mr. Ram developed and/or supervised the development of many modification packages including: selection of replacement relays (both protective and auxiliary);

preparation of relay testing specification with civil engineering input; working with and visiting seismic testing facilities for relay qualification and; developing pre and post installation instructions including test procedures. He worked closely with teams consisting of maintenance, operations, and work MGMT during the development and implementation of these projects. Besides the A-46 issue, Mr. Ram first developed and then was personally involved in the implementation of modification packages consisting of Cable, Conduit, Circuit Breaker and motor starter (contactor) replacements.

The following provides a list of USI A-46 resolution projects:

Northeast Utilities - Millstone Station Consumers Power Co. - Palisades Nuclear Station Boston Edison Co. - Pilgrim Nuclear Power Station Commonwealth Edison Company- Dresden Station, Quad Cities Station Tribhawan Ram Page 2 A-3

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 KIM L. HULL BACKGROUND

SUMMARY

Accomplished Lead Engineer/ Project Manager with significant experience in commercial nuclear power industry. Demonstrated ability to lead and contribute on cross-functional project teams. Possess strong analytical, problem resolution, collaboration, and communication skills when interacting with diverse audiences including regulatory inspectors, internal inspectors, management, and employees. Respected trainer with ability to develop and present information and measure effectiveness through evaluation techniques. Strengths include:

Project Management Design Modifications Plant Operational Support Procurement Management/Leadership Regulatory Compliance Training/Coaching Auditing Inspections KEY ACCOMPLISHMENTS

Served as KNPP Lead Engineer/ Project Supervisor for approximately 125 plant design changes.

Experienced in all aspects of nuclear power plant modification packages including development of calculations, design, engineering, and procurement specifications.

Thorough understanding of configuration control, management, and preparation of IOCFR50.59 analyses.

Participated in several regulatory and industry audits, including CDBI and INPO assessments.

Experienced as a Technical Specialist performing NUPIC Audits.

" Well-developed communication skills for preparing technical presentations including lesson plans, project reports, and meetings in support of regulatory activities and inspections.

" Qualified Shift Technical Advisor for KNPP Operations Group (1980s).

PROFESSIONAL EXPERIENCE STEVENSON & ASSOCIATES - Project Manager 2010 - Current National consulting engineering firm specializing in civil, structural and mechanical engineering for power, industrial and advanced technology facilities.

Project Manager

Development of plant specific Seismic Walkdown Equipment Lists for multiple Units in response to NRC 50.54(f) requirements regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3:

Seismic."

Onsite at Kewaunee Power Station Consultant support to resolve Q-list Open Items

On-site at Kewaunee Power Station Consultant support for Auxiliary Feedwater Flow Control Modification including preparation and review of design documentation.

WISCONSIN PUBLIC SERVICE RESOURCES / Nuclear Management Company DOMINION ENERGY - Kewaunee, WI 1982 to 2010 Senior Instructor (Maintenance) (2009 - 2010) 0 Developed lesson plans and taught Basic Systems and Continuing Training Topics for Engineering and Technical Support training program.

Engineer Ill/Principal Engineer (2004 - 2009)

Responsible for modifications and emergent issues including Steam Exclusion Boundaries, Fuel Transfer Carriage, Frazil Ice development on the KPS Circulating Water Intake, and NRC 96-06 Two Phase flow.

Member of Dominion Fleet Calculation Quality Review Team and Mentor for Calculation training.

Outage nightshift Lead Mechanical Design Engineer/Back-up Supervisor.

KPS Engineering representative on the Independent Review Team developed to address CDBI A-4

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 inspection findings. Assigned to review all calculations, modification packages, 10CFR 50.59 screenings, evaluations, and procurement packages.

Technical Instructor for Administrative Process training for new engineers.

Mechanical Design Supervisor (2002 - 2004)

Supervised nine engineers, analysts, and technicians assigned to the KNPP Mechanical Design Group.

" Provided Mechanical Design Oversight for all vendor activities impacting KNPP Mechanical Design Bases.

Provided support for emergent plant issues, NRC Inspections, and Physical Change Packages.

" Subject Matter Expert Instructor for 10CFR 50.59 process training for new engineers.

Principal Engineer (Analytical Group SGR Project) (1998 - 2002)

Contract Manager for Steam Generator Replacement (SGR).

" Responsible for coordination of SGE design, fabrication and installation contracts.

" Provided outage schedule development, coordination, and work process integration between Bechtel and KNPP.

Coordinated contractor mobilization, badging, and plant specific training.

Technical Specialist for Quality Assurance audits of vendors.

" SGR Shift Manager for night shift

" Responsible Engineer for SGR related Physical Change Packages.

" Responsible for SGR budget development up to 1998.

Prepared, reviewed, and awarded Bechtel Installation contract.

Participated in review and award of Ansaldo Fabrication contract.

Served on team to review and award Westinghouse Design contract.

" Selected to work at Arkansas Nuclear One for their steam generator installation.

Senior Engineer (Analytical Group) (1994-1998)

" Responsible Engineer for Physical Change Packages.

Member KNPP Engineering Reorganization Team.

" Recognized Technical Expert for KNPP systems.

Senior Project Supervisor (1992-1994)

" Provided project management and engineering services for KNPP DCR packages.

Supervisor of KNPP NPM Project Attendants responsible for modification package organization and close out.

Nuclear Services Supervisor (1991-1992)

Supervised initial Steam Generator replacement project effort.

0 Provided specification development for services and major plant components.

Prior to 1992 - Held engineering positions from Associate Engineer to Nuclear Design Engineering Supervisor.

EDUCATION Masters Program Coursework - Mechanical Engineering; Michigan State University - E. Lansing, MI B.S. - Mechanical Engineering - Michigan State University - E. Lansing, MI B.A. - Biology - Albion College - Albion, MI A-5

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 A-6

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Mark S. Etre EDUCATION:

MBA, Rensselaer Polytechnic Institute - Hartford Graduate Center, Hartford, CT MS, Mechanical Engineering, Rensselaer Polytechnic Institute - Hartford Graduate Center, Hartford, CT BS, Civil Engineering - Worcester Polytechnic Institute, Worcester, MA PROFESSIONAL HISTORY:

Stevenson & Associates, Inc., Woburn Massachusetts, Project Manager, 2009 - Present.

Pratt & Whitney Power Systems, East Hartford, CT, Project Manager, 2000 - 2009.

Northeast Utilities, Millstone, Waterford, CT, Engfineering Supervisor, 1981 - 2000.

Pratt & Whitney Aircraft, East Hartford, CT, Analytical Engineer, 1978 - 1981.

PROFESSIONAL EXPERIENCE:

Mr. Etre is a result oriented Manager with extensive experience working on the design basis reconstruction, evaluation and construction of nuclear power plants and assessment of components. Significant accomplishments in' the areas of licensing; engineering reviews, welding evaluations, quality program evaluation and implementation, project coordination, and ASME interpretation and training. He has testified as a witness before regulatory groups on topics such as design basis criteria, engineering analysis, fabrication techniques, material and welding applications, material control, and construction practices. Known for and have demonstrated skills and capabilities in:

Managing Resources Safety Analysis Erosion-corrosion criteria Project Management ASME Section III, IX, XI, B31.1 NRC GL 89-13 High Energy Line Break Seismic Assessments RESPONSIBILITIES AND ACCOMPLISHMENTS Stevenson & Associates, Woburn, MA Directorof Projects 2009 - Present Advises leadership and/or office managers at the highest levels about the project portfolio, status and resource planning for delivering strategic business Initiatives. Plans, directs, and ensures the successful management of designed business solutions utilizing the complete resources of the staff and assigned project management teams. Provides technical assistance in identifying, evaluating and developing methods and procedures that are efficient, effective and meet good business practice. Maintains communication with upper management both within and across organizations to ensure smooth running of all projects undertaken by team. Responsible for leading in a mature and organization-focused manner, providing help where necessary to project a professional image. Has expert experience in Project/Program Management and able to lead in the coaching and mentoring of team members to help them achieve individual expectations and deliverables. Assesses resource loads and makes appropriate individual assignments.

Pratt & Whitney Power Systems, Windsor, CT Project Manager 2000 - 2009 Mark S. Etre 5 4 A-7

12QO108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Responsible for the organization of proposal teams and the Project management function of a $56 million power plant. Coordinated the priorities of management and personnel to ensure goals.

Ensured customer satisfaction while maintaining high quality and controlling costs.

Managed the Engineering function of the design, analysis and manufacturing of rotating and static structures.

Demonstrated versatility, coordinated diverse activities, i.e., proposals, projects on through to job implementation.

Routinely oversee multiple proposals and projects.

Created and negotiated realistic proposals and schedules that satisfied customer requirements and resulted in accurate outcomes on time and within financial targets.

Northeast Utilities, Millstone, Waterford, CT Manager,EngineeringBacklog 1999-2000 Responsible for the Design Basis Reconstruction. ,

Managed turnaround of the Design Basis Reconstruction that resulted in a 30% increase in production.

Implemented a process to prioritize projects and other initiatives, which resulted in a 90% reduction in our design and calculations basis backlog while ensuring the documentation was current.

Created and negotiated realistic budgets and schedules, which satisfied NRC regulatory requirements and resulted in on-time completion within budget constraints.

Maintained a bottom line focus in scheduling and budgeting that allowed for the completion of backlog ahead of schedule.

Eliminated projects that had limited added value to the bottom-line performance.

EngineeringSupervisor 1992-1999 Managed the Mechanical/Civil engineering function at Millstone Unit 3 with a professional staff of 15.

Coordinated the priorities of management and personnel to ensure goals.

Ensured customer satisfaction while maintaining high quality and controlling costs.

Demonstrated versatility, coordinated diverse activities, i.e., construction, purchasing on through to job completion. Routinely oversaw multiple projects.

Managed the implementation of NRC GL 89-13, Erosion-corrosion assessments, Reg Guide 1.97 and USI A-46.

Senior Engineer 1981-1992 Various engineering assignments designed to enhance performance throughout manufacturing and power generation facilities.

Demonstrated track record for translating technical knowledge and leadership to bottom line results.

Reviewed and approved engineering documents such as calculations, specifications and drawings for adherence to regulatory and code requirements. This included design, analysis, fabrication, and erection of pressure vessels and piping components at several nuclear power plants.

Pratt& Whitney, East Harffiord, CT 1978-1981 Analytical Engineer Responsible for evaluation and improving jet engine designs.

Performed Critical Speed and Forced Response Analysis.

Conducted test demonstrations to ensure design compliance.

Mark S. Etre 5:4 A-8

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Certificate of Completion Mark Etre Successf*llih Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns

f *v*aj Date: 06/26/12 Bruce M. Lory - kistructor NTTF 2.3 Seismic Walkdown Course A-9

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 SETH BAKER 275 Mishawum Rd Suite 200 Woburn, MA 01801 sbaker@vecsa.com 781-932-9580 ext 105 EDUCATION 2012 Stanford University, MS, Civil/Structural Engineering 2008 Worcester Polytechnic Institute, BS, Civil Engineering PROFESSIONAL HISTORY 6/12 - pres Stevenson & Associates, Senior Engineer I Woburn, MA 5/08 - 6/10 Stevenson & Associates, Staff Engineer Woburn, MA Focus on structural engineering analysis & design, finite element analysis, structural mechanics evaluations, seismic qualification PROFESSIONAL PROJECTS Evaluation of underground utilities at the Cooper Nuclear Station for large overburden loads associated with the hauling of spent fuel casks to the independent spent fuel storage facility.

Evaluated concrete structures for the Salt Water Processing Facility at the Savannah River nuclear plant.

Performed a detailed seismic analysis of the service water building at the Ginna nuclear station. Development of GTSTRUDL 3D model and dynamic response analysis. Was also responsible for load and stress analysis of the steel structural members and connections.

Analyzed the washdown area for larger fuel casks at Cooper nuclear station. This work lead to design retrofits to locally strengthen the supporting floor beams and additionally brace the spent fuel cask.

Review and evaluation of seismic and tornado vulnerabilities associated with maintaining the component cooling water systems within the Turbine Building at Prairie Island nuclear plant.

Participated in on-site staff augmentation at Point Beach nuclear station for duration of 1.5 months. Authored a report that that analyzed and articulated the design of a flood relief louver system in the circulating water pump house.

Evaluating repair options for a personnel hatch containment penetration at Brunswick nuclear station. Design will involve placing a 10' concentric sleeve within the existing penetration sleeve. Extensive ASME work was performed.

A-10

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 PROFESSIONAL PROJECTS (cont.)

Seismic evaluation and redesign of equipment frames for Shaw/Areva Mixed Oxide facility using GTSTRUDL model.

Main Steam Line inspections at Cooper nuclear station to determine locations for additional dampers.

Design of equipment support frames to resist blast load at Palo Verde nuclear station MISC.

SOFTWARE GTSTRUDL, ETABS, ANSYS, MATLAB, AutoCAD, MathCAD, Revit Architecure CODES AISC 6 7th 9th, 1 3 th Editions, IBC A-11

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 f*

A"" W.

Mr, "M If ..

I/A KI is.

Certificate of Completion Seth Baker 47 SuccesJullj Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns "!-q AM, Date: 06/26/12 Bruce M. Loryinstructor NTTF 2.3 Seismic Walkdown Course V)

- /

I A-12

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 WING HO, P.E.

PROFESSIONAL EXPERIENCE Exelon Nuclear, Oyster Creek Nuclear Generating Station, NJ StructuralEngineer (2009 - present)

Designedplant modifications, defended plant design basis, specialized in seismic qualificationof nuclearpower plant equipment using SQUG-GIP,IEEE, STERI, NARE, SQURTS

" Modification design, for: Drywell penetration, main transformer foundation, conduit supports, pipe supports, boiler house, feed pump skid and feed pump motor foundation

" Seismic qualification of equipment

" Lead shield supports

Rigging and hauling

Scaffolding

" Structures monitoring

" Pipe stress analyses Di Stasio & Van Buren, Mountainside, NJ ProjectManager,(2004 - 2009)

Providedtechnicalsupport andproject managementfor parkinggarages,health care and researchfacilities,marine structures,bridges,paper mills and buildingprojects CUH2A, Princeton, NJ Directorof StructuralEngineering/SeniorAssociate, (1989 - 2003)

Led a group of 25 structuralengineers and CADD draftspersons Managed design teamsfor major buildingprojects, many over 1,000,000 squarefeet

Provided design services to Fortune 500 companies and government agencies such as Merck, Pfizer, Bristol Myers Squibb, Schering Plough, Procter and Gamble, Rorer, Astra Zeneca, US Department of Agriculture (USDA), National Institute of Health (NIH). Applied building codes and design standards flexibly to achieve optimum effects of construction budgets. Codes and standards included the New Jersey Uniform Construction Code (NJUCC), BOCA, UBC, IBC, OSHA, Factory Mutual (FM) Loss Prevention Data, American Institute of Steel Construction (AISC) and American Concrete Institute (ACI)

A-13

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Page 2 WING HO REGISTRATION & EDUCATION

" Professional Engineer: New Jersey, New York

" Master of Structural Engineering: University of Toronto, Toronto, Canada PUBLICATIONS

"Keeping Corrosion Contained", AISC Modern Steel Construction,Feb. 2009, on the rehabilitation of heavily corroded steel structures in harsh environment

AISC Modern Steel Construction,Oct. 2002, p.10, on seismic spatial interactions

" AISC Modern Steel Construction,Dec. 1999, p. 10, on steel moment frame design

" AISC Modern Steel Construction,Jan. 1998, p. 1 0, on design of columns with knee braces

" AISC Modern Steel Construction,Feb. 1997, p. 1 0, on structural steel end-plate connections

" American Concrete Institute (ACI), SP-63, p.497-513, on the design of concrete shear walls under seismic torsion

" Building & Environment,United Kingdom, Vol. 12, p. 199-204, on the design of concrete shear walls subjected to seismic bending A-14

Oyster Creek Generating Station Unit 1 1200108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 r 2l.

l-lI E,,CT,,C RESI ARCHPowER INSTITUTE Certificate of Completion Wing Ho Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns June 21, 2012 Date Robert K. Kassawars EPRI Manager Structural Reliability & Integrty A-15

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Stev'enson & Associates Antonio J. Perez, P.E.

SUMMARY

Mr. Perez has over 15 years of experience in project management, project engineering, equipment design, and mechanical systems layout for nuclear and industrial facilities.

EDUCATION B.S. - Mechanical Engineering Michigan Technological University, Houghton, MI Magna cum Laude LICENSES Professional Engineer, Wisconsin: September 2002 Minnesota: December 2010 PROFESSIONAL EXPERIENCE Stevenson & Associates, Green Bay, WI General Manager October 2010 - Present

Responsible for interfacing with clients with a focus on continuously improving relationships.

" Responsible for managing staff resources to meet or exceed clients' needs.

" Responsible for recruiting and hiring staff necessary to meet resource requirements while effectively increasing capacity.

Responsible for providing Engineering Consultation services to clients.

Project Manager March 2007 - October 2010

Performing Project Management tasks including development of project plans, identification of resource needs, estimating task durations, developing project schedules, and monitoring budgets.

Lead design team efforts at the Kewaunee Power Station on multiple projects that include two separate Auxiliary Feedwater flow control modifications, Auxiliary Feedwater flow monitoring instrumentation modifications, and Auxiliary Building roof modifications.

Supported the Calculation Reconstitution and Improvement Project at the Prairie Island Nuclear Generating Plant by mapping calculations associated with the RHR system.

Dominion Energy Kewaunee (formerly Nuclear Management Company 2001 - 2005)

Kewaunee Power Station, Kewaunee, WI Shift Technical Advisor (trainee) January 2006 - March 2007

Trainee in a Senior Reactor Operator Certificate training program.

Page 1 of 3 A-16

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Stev enson & Associates Antonio J. Perez, P.E.

Engineering Supervisor - ME/CE/SE Design May 2004 - January 2006

Supervised a. staff of 12 to 15 engineers (mechanical, civil, and structural design) who were charged with developing design changes, maintaining design and licensing basis documentation and supporting maintenance.

Integrated the civil/structural engineering group and the mechanical engineering group into a cohesive unit that resulted in gained efficiency and a net reduction of one full time equivalent engineer.

Substantially increased the quality of engineering products developed and published by the ME/CE/SE Design Engineering group through coaching and feedback as a result of increased supervisory oversight of engineering products.

Developed a work management system for the group that provided a means for prioritizing activities, estimating the level of effort, and scheduling of activities. This system allowed for an increased understanding of workload and became an invaluable tool for prioritizing work and managing resources.

Increased communications within the group by holding daily 15 minute meetings where station messages were delivered and where the group's resources were assessed and redirected as necessary to meet commitments. This resulted in an increase in morale and an increase in commitments met.

Increased communications with other departments by establishing a central point of contact for the group and by assuring that the ME/CE/SE Design Engineering group was represented at Planning and Scheduling meetings.

Motor Operated Valve Engineer June 2001 - May 2004

Established a project plan and led the implementation effort that re-organized the Motor-Operated Valve Program at KPS. This effort consisted of developing a Program Manual, developing controlled calculations, performing Design Basis Reviews, and compiling and/or establishing plant positions on known industry issues.

The result of this effort was a reduction of full time equivalent engineers, from 3 to 1, required to maintain the Program.

" Performed and reviewed MOV safety related calculations including Minimum Required Stem Thrust, Weak Link Analysis, and Available Margin.

Assisted in MOV testing by providing engineering support to maintenance personnel.

DISTRIBUTION PLANNING, INC., Grandville, MI Systems Mechanical Engineer 2000 -2001

Integrated mechanical systems and designed equipment for material handling systems.

Procured equipment and coordinated delivery schedules with vendors.

Page 2 of 3 A-17

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Stev'enson & Associates Antonio J. Perez, P.E.

SMS SANDMOLD SYSTEMS, INC., Newaygo, MI Project Engineer /Manager 1998 - 2000

Led multi-discipline project design teams for several projects that ranged in size from a few thousand dollars up to $2.2 million.

Coordinated efforts with engineering, manufacturing, and installation groups to establish and maintain project schedules that met or exceeded the client's expectations.

Procured equipment and coordinated delivery schedules with vendors.

" Acted as the company's liaison with clients to work through issues that arose during projects. Provided project status updates to clients and management.

" Designed equipment such as sand storage bins - up to 540-ton live load capacity, bucket elevators, belt conveyors, screw conveyors, and mixers. Most of this equipment was for handling of bulk solids (foundry sand).

Analyzed and designed structural support members for various types of equipment such as vibratory conveyors, mixers, and conveyors. Designed access structures such as stair towers, service platforms and catwalks.

Calculated foundation loads and point loads of equipment support points.

LIFT-TECH INTERNATIONAL, Muskegon, MI Project Engineer 1997-1998

Performed engineering analyses, wrote critiques, and recommended design modifications of structural members for the purpose of upgrading bridge cranes and hoists.

Implemented engineering design changes to enhance product development.

Page 3 of 3 A-18

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Zý IN ..........ýý Certificate of Completion Tony Perez S uccessfUlh Completedl Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns X

i

-/, m I ix PQ R )

Date: 06/26/12 Bruce M. LoiyiInstructor "

NTTF 2.3 Seismic Walkdown Course V

V V ~ ~ ~

A-19

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 275 Mishawurn Road, Suite 200, Woburn, MA1 01801 Tel (781) 932-9580 Fax (781) 933-4428 1invi. vecsa.coOn Stevenson &Associates EngineeringSolutionsfor Nuclear Power Todd A Bacon Education 1976 - 1980 University of Illinois - Urbana-Champaign Bachelor of Science - Civil Engineering Registration / Certification Professional Engineer: California License No. C-0336104 (Civil), Georgia License. No. 015562, Ohio License No. E-57497 Professional History 2012 - Present Stevenson & Associates, Charlotte, North Carolina, Senior Consultant and General Manager, Charlotte, NC Office 1980-2012 AREVA Inc., Charlotte, NC, Engineering Manager Professional Experience Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities as an Engineering Manager have included work from the conceptual design through to the installation support phases of projects. Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations. The efforts have also included significant client and/or regulatory interface, as required. These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed. In addition, he has extensive experience in proposal and report development, as well as personnel training activities.

Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities as an Engineering Manager have included work from the conceptual design through to the installation support phases of projects. Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations. The efforts have also included significant client and/or regulatory interface, as required. These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed. In addition, he has extensive experience in proposal and report development, as well as personnel training activities.

Mr. Bacon's work has involved extensive use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, including various piping system related committees, These have included the design group for the HDPE buried pipe group of Section III, and the Flaw Analysis group of Section XI.

Other Code experience includes the American Institute of Steel Construction (AISC), American Concrete BOSTONoCLEVELAND oCHICA GO oMINNEAPOL!SoPJHOENIX A-20

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 275 AMishawuni Road. Suite 200, Woburn, MA 01801 TeS (781) 932-9580 Fav (781) 933-4428 w1w1w1.

Vecsa. corn Stevenson & Associates EngineeringSolutionsfor Nuclear Power Institute (ACI), and ASME (ANSI) B31.1 and B31.3 codes. He serves on the AREVA College of Experts in the areas of structural and dynamic analysis and is also fluent in using numerous piping and finite element computer programs, as well as in typical frame analysis programs.

Engineering Manager, Civil and Layout Department AREVA NP Inc.

Mr. Bacon served as an Engineering Manager in the Civil and Layout Department in Charlotte, North Carolina. In this role he was responsible for the efforts involving work on the 3D model for an AREVA US EPR plant being designed for the Calvert Cliffs site in Maryland. His areas of responsibility also included the balance of plant piping system design efforts for the plant. In this role, he was involved with interfaces with numerous groups utilizing the 3D model information, as well as consortium partner Bechtel Power, and AREVA offices throughout the US and Europe who served as subcontractors for various portions of the overall project scope of work. This included coordinating the efforts of approximately fifty individuals for these efforts involving technical resolution of issues, manpower planning, personnel issues, and development of the group.

In addition to the managerial responsibilities, he was a member of the AREVA College of Experts in the area of mechanics and fluid mechanics. This group was comprised of approximately one percent of the company worldwide which served as the technical leaders for the company, sharing best practices and knowledge throughout the global organization.

In addition to the New Plants activities in the US, Mr. Bacon supported efforts involving current activities for the International Thermonuclear Experimental Reactor (ITER) effort in which AREVA had the responsibility for the Cooling System involving the piping system evaluations and development of Technical Guides and impact to the building resulting from the piping system.

He previously served as an Engineering Manager in the Structural and Engineering Mechanics Group, working on projects involving operating plants. As a Project Engineer and Manager, he helds responsibility for leading project teams in technical areas, as well as in budget and schedule item tracking functions.

Examples of typical projects include the following:

Mixed Oxide (MOX) Fuel FabricationFacility, Savannah River Site - Conducted third party review of overall project identifying ways to achieve efficiencies and improve production rates for the building design and construction effort. This resulted in numerous recommendations for the site to improve production in the areas of scheduling, group interfacing (engineering disciplines, construction, etc.),

procedural development as well as improvements through procedural revisions. This also included performing as the lead engineer on projects for the facility involving development of procedures for field routing of small bore piping systems, as well as conduit runs.

ECCS Debris Blockage Issue, Tokyo Electric Power Company (TEPCO) - Established contact and led proposal efforts to obtain contracts for ECCS suction strainer replacements for first plant performing this BOSTONoCLEVELAND oCHICA GO oMINNEAPOLISoPHOENIX A-21

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 275 Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fex (781) 933-4428 i ilr i)l.vee*SaT. coml Stevenson & Associates EngineeringSolutionsfor Nuclear Power scope in Japan. Subsequently won contracts for two additional TEPCO units as well, resulting in $ 8M in revenue for AREVA. This work involved extensive interface and oversight of the strainer hardware vendor during the design, fabrication and construction phases of the projects.

ASME BPVC Work, Various Facilities- Served in positions of increasing responsibility performing and reviewing ASME Boiler and Pressure Vessel Code work in the Structural and Engineering Mechanics Group. Work included Class 1 analyses of flued heads, mechanical equipment evaluations and numerous piping system analyses.

ECCS DebrisBlockage Issue, involving numerous US BWR clients - Served in various roles including Project Engineer, Project Manager, and Technical Consultant. Had a significant amount of involvement with this issue including involvement with the BWR Owner's Group for this issue spanning numerous years.

GL 96-06 Operabilityand Design Basis Resolution, Oconee Nuclear Station, Duke Power - Served as the Project Engineer for the Operability Evaluation for the Oconee Nuclear Station in an effort to show all three units operable under the additional loadings resulting from the USNRC Generic Letter. This assessment included evaluation of the LPSW system, including piping, supports, equipment nozzles, as well as structural platforms and associated components. In addition, operability guidelines were developed for Oconee during this effort.

Reactor Cavity DrainLine Modifications, PalisadesNuclear Power Plant,Consumers Power - Project Manager for the Reactor Cavity Drain Line modifications and letdown piping support modifications at the Palisades Plant. Work scopes included both engineering functions and the generation of modification package paperwork.

NRC Bulletin 79-14 Large-Bore PipingProjectEvaluation, D. C. Cook Nuclear PowerPlant, Indiana/MichiganPower - Work included serving as Project Engineer to evaluate the adequacy of D.C.

Cook's NRC Bulletin 79-14 Large-Bore Piping Project. The work scope involved supervising a project team performing piping and piping support evaluations. Conclusions drawn from this study have enabled the client to realize significant cost savings during recent maintenance outages through discrepancy trending and margin assessment studies.

Reactor Pressure Vessel Bottom Head DrainLine Unplugging Project,Dresden Nuclear Generating Station Units 2 & 3, Commonwealth Edison. Includedserving as Project Engineer responsible for unplugging reactor pressure vessel bottom head drain lines for Dresden Units 2 and 3. This project was successfully completed within schedule and budget constraints, and also was part of the Unit 2 critical path outage work.

HPCISystem SpargerModification, Quad Cities Nuclear GeneratingStation, CoinEd- Served as the Structural and Engineering Mechanics Project Engineer and Manager for Quad Cities Unit I and 2 high pressure coolant injection (HPCI) system modification, which resulted in the addition of a sparger assembly inside the torus. The project also included the addition of platforms to provide accessibility for personnel performing maintenance activities at both units.

Hardened Wetwell Vent Project Third PartyReviews, Dresden and Quad Cities Nuclear Generating BOSTON oCLEVELAND oCHICA GO oMINNEAPOLISoPHOENIX A-22

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 275 Mishawunm Road, Suite 200, Woburn,AMA' 01801 Tel (781) 932-9580 Fax (781) 933-4428 wwwt;.ivecsa. coin Stevenson & Associates EngineeringSolutionsfor Nuclear Power Stations, CornEd- Led the third party reviews of the hardened wetwell vent projects for the Dresden and Quad Cities stations. These projects involved the evaluation of existing, as well as new, piping and auxiliary steel. Design codes used for the mechanical work included ASME Section 111, Subsections NC, ND, NE and NF, as well as AISC and Uniform Building Code (UBC) standards for the structural evaluations.

Structural Projects, Various Facilities- Past projects have included extensive structural experience, such as the Hope Creek Nuclear Generating Station's drywell inner water seal plate analysis, and also Mark I piping and pipe support evaluations. Previous work also included extensive experience working on various mechanical and structural design projects.

Licensing and Special Projects, Comanche Peak Steam Electric Station, TU Electric - Involved in licensing and special studies projects for the Comanche Peak Station.

SSFIAudit Responses, CoinEd- Participated in responding to concerns raised during safety system functional inspection (SSFI) audits.

Project Summary Reports and OperabilityGuidelines, CoinEd and AEPSC - Wrote numerous project summary reports and operability guidelines for Commonwealth Edison (ComEd) and American Electric Power Company (AEPC).

Piping,Piping Support and HVAC Modifications, Various Facilities- Served as Project Engineer for piping, piping support and HVAC modification work for various nuclear plants, including Dresden Units 2 and 3, Quad Cities Units 1 and 2, D. C. Cook Units 1 and 2, and Duane Arnold. Project Engineer responsibilities included coordinating schedule and budget issues, as well as addressing technical questions as they arose.

Control Rod Drive Frame Analysis, Browns FerryNuclear PowerPlant, Tennessee Valley Authority (TVA) - Involved in the analysis of the control rod drive frames for the Browns Ferry Plant.

BOSTON oCLE VELA ND oCHICA GO oMINNEA POL IS oPHOENIX A-23

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Certificate of Completion Todd Bacon Successfulhj Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Date: 06/26/12 Bruce M .Lo-y- Instructor NTTF 2.3 Seismic Walkdown Course A-24

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Walter Djordjevic EDUCATION:

B.S. - Civil Engineering, University of Wisconsin at Madison, 1974 M.S, - Structural Engineering, Massachusetts Institute of Technology, 1976 PROFESSIONAL REGISTRATION:

State of California, State of Wisconsin, Commonwealth of Massachusetts, State of Michigan, State of Arizona, State of Missouri PROFESSIONAL HISTORY:

Stevenson & Associates, Inc., President 1996 - present; Vice President and General Manager of the Boston area office, 1983 - 1995 URS/John A. Blume & Associates, Engineers, Boston, Massachusetts, General Manager, 1980 - 1983; San Francisco, California, Supervisory Engineer, 1979 - 1980 Impell Corporation, San Francisco, California, Senior Engineer, 1976 - 1979 Stone & Webster Engineering Corporation, Boston, Massachusetts, Engineer, 1974 - 1976 PROFESSIONAL EXPERIENCE:

" Structural Engineering

Structural Dynamics

" Seismic Engineering

" Construction

Vibration Engineering

Expert Witness

" Committee Chairman Mr. Djordjevic founded the Stevenson & Associates Boston area office in 1983 and serves as President and General Manager. Mr. Djordjevic is expert in the field of structural engineering - more specifically, in the areas of structural vulnerabilities to the effects of seismic and other extreme loading phenomena.

As a structural dynamicist, Mr. Djordjevic also heads the Vibration Engineering Consultants corporate subsidiary of Stevenson & Associates for which he has overseen numerous designs of vibration sensitive microelectronics facilities for such clients as IBM, Intel, Motorola and Toshiba. He has personally been involved in such projects as resolving vibration problems due to construction activities for the Central Artery Project (Big Dig) in Boston for which he was retained by Massport. Finally, Mr.

Djordjevic has been personally retained as an Expert Witness a number of times relating to cases involving construction, structural and mechanical issues.

He has performed over a thousand hours of onsite seismic and other natural phenomena (including tornados, hurricanes, fire, and flooding) inspection walkdowns to assess structural soundness and vulnerabilities. He has inspected microelectronics fabrication facilities, power facilities, and hazardous material government and military reservations. He is one of the most experienced seismic walkdown A-25

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 inspection screening and verification engineers having personally participated in seismic walkdowns at over 50 U.S. nuclear units.

In recent years, he has concentrated on screening inspection walkdowns and assessments for resolution of the USI A-46 and seismic IPEEE issues, on numerous facilities. The following provides a partial list of recent projects:

American Electric Power - D.C. Cook Station Boston Edison Co. - Pilgrim Nuclear Power Station (SPRA)

Commonwealth Edison Company- Braidwood StationpM , Byron Station"M , Dresden StationpM , Quad Cities StationPM Consumers Power Co. - Palisades Nuclear StationPM Entergy - Arkansas Nuclear One Florida Power & Light - Turkey Point Station New York Power Authority - James A. Fitzpatrick Nuclear Power Plant Niagara Mohawk Power Corporation - Nine Mile Point Station PM Northern States Power Co. - Monticello Nuclear Generating Plant Northern States Power Co. - Prairie Island Nuclear Generating Plant Omaha Public Power District - Fort Calhoun Station (SPRA)

Public Service Electric & Gas - Salem Nuclear Station Rochester Gas & Electric - R.E. Ginna Station Wisconsin Electric - Point Beach Nuclear StationPM (SPRA)

Wisconsin Public Service - Kewaunee Nuclear Power PlantPM (SPRA)

PM Indicates projects where Mr. Djordjevic served as Project Manager Hanford Reservation Savannah River Plant Reservation Rocky Flats Reservation Tooele US Army Depot Anniston US Army Reservation Umatilla US Army Reservation Newport US Army Reservation Aberdeen US Army Reservation He is a member of the IEEE 344 Standards Committee, Chairman of the ASCE Working Group for Seismic Evaluation of Electrical Raceways, and Chairman of the IES Committee for Microelectronics Cleanroom Vibrations Representative projects include overseeing the SEP shake-table testing of electrical raceways, in-situ testing of control panels and instrumentation racks at various nuclear facilities, equipment anchorage walkdowns and evaluations at various nuclear facilities. He is the principal author of the CERTIVALVE software package to evaluate nuclear service valves, and contributing author in the development of the ANCHOR and EDASP software packages commercially distributed by S&A.

Mr. Djordjevic is expert in the area of seismic fragility analysis and dynamic qualification of electrical and mechanical equipment. He has participated in and managed over twenty major projects involving the evaluation and qualification of vibration sensitive equipment and seismic hardening of equipment.

As demonstrated by his committee work and publications, Mr. Djordjevic has participated in and contributed steadily to the development of equipment qualification and vibration hardening methodology.

Walter Djordjevic Page 2 A-26

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 PROFESSIONAL GROUPS Member, Institute of Electrical and Electronics Engineers, Nuclear Power Engineering Committee Working Group SC 2.5 (IEEE-344)

Chairman, American Society of Civil Engineers Nuclear Structures and Materials Committee, Working Group for the Analysis and Design of Electrical Cable Support Systems Member, American Society of Mechanical Engineers Operation, Application, and Components Committee on Valves, Working Group SC-5 Chairman. Institute of Environmental Sciences, Working Group foe Standardization of Reporting and Measuring Cleanroom Vibrations PARTIAL LIST OF PUBLICATIONS 1979 ASME PVP Conference, San Francisco, California, "Multi-Degree-of-Freedom Analysis of Power Actuated Valves", Paper No. 79-PVP-106.

1983 ASME PVP Conference, Portland, Oregon, "A Computer Code for Seismic Qualification of Nuclear Service Valves", Paper No. 83-PVP-81.

1983 ASME PVP Conference, Portland, Oregon, "Qualification of Electrical and Mechanical Equipment at Rocky Flats Reservation Using Prototype Analysis".

1984 ANS Conference, "Qualification of Class 1E Devices Using In-Situ Testing and Analysis."

1986 Testing of Lithography Components for Vibration Sensitivity, Microelectronics, Cahners Publishing 1990 Nuclear Power Plant Piping and Equipment Conference, "Development of Generic Amplification Factors for Benchboard and Relay Cabinet Assemblies", Paper No. 106, Structures and Components Symposium, held by North Carolina State University 1991 Electric Power Research Institute, "Development of In-Cabinet Response Spectra for Benchboards and Vertical Panels," EPRI Report NP-7146 Walter Djordjevic Page 3 A-27

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 A A A A A A A A A A A A A A

A A Ex M. -121 Ag 4 Certificate of Completion 4

4 Walter Djordjevic 4

4 Successfiulli Completed 4

Training on Near Term Task Force 4

Recommendation 2.3 - Plant Seismic Walkdowns .j 4

4

&I'0,0I) Date: 06/26/12 Bruce M. Lor#- Instructor 4 NTTF 2.3 Seismic Walkdown Course

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 B

Equipment Lists Appendix B contains the equipment lists that were developed during SWEL development.

The following contents are found in Appendix B:

SW EL Approval Signature Page ...................................................................... B-2 Table B-i, Base List 1.................................................................................. B-3 Table B-2, Base List 2 .................................................................................. B-83 Table B-3, SW EL 1..................................................................................... B-87 Table B-4, SW EL 2 ..................................................................................... B-93 B-I

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Stevenson & Associates Seismic Walkdown Interim Report, Rev. 2 In Response to NTTF Recommendation 2.3: SeismiC Oyster Creek Generating Station - Unit 1 TK Ram

-T-K 09/26/2012 Equipm.ent Selection Preparer date Kim Hall 09/27/2012 Equipment Selection Reviewer date Eric De M onch s 09/26/2012 Statio.dn.Opera tions Staff Member dlatei Refer to Attacmen 3for.synopsi ofStation Operitions role ahd responsibility.

B-2

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Table B-I. Base List 1 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION BATTERY BANK B VITAL BANK 'B' STATION BATTERY 735 OB 35 OCMOB 35' 125v BATTERY ROOM (LEAD ACID)

BATTERY BANK C VITAL BANK 'C' STATION BATTERY 735 TB 23 OCTB SOUTH MEZZANINE 4160 (LEAD ACID) _VOLT SWITCHGEAR ROOM DG-1 BATTERY DIESEL GENERATOR UNIT #1 741 DG 23 OCDIESEL GEN BLDG 23' 0" BANK STARTING BATTERIES 7 DG-2 BATTERY DIESEL GENERATOR UNIT #2 OCDIESEL GEN BLDG 23' 0" STARTING BATTERIES 741 DG 23 BANK BTCHG C1 'C' STATION BATTERY SOLID STATE 735 TB 23 OCTB SOUTH MEZZANINE 4160 STATIC CHARGER Cl _VOLT SWITCHGEAR ROOM BTCHG C2 'C' STATION BATTERY SOLID STATE TB 23 OC,TB SOUTH MEZZANINE 4160 STATIC CHARGER C2 VOLT SWITCHGEAR ROOM DG-1 BATTERY DIESEL GENERATOR UNIT #1 BATTERY 741 DG 23 OC,DIESEL GEN BLDG 23' 0" CHARGER CHARGER DG-2 BATTERY DIESEL GENERATOR UNIT #2 BATTERY 741 DG 23 OCDIESEL GEN BLDG 23' 0" CHARGER CHARGER STATIC CHGR

'A/B' STT STATION BATTERIES S OLID TTCCAGR735 OCMOB 35' 125v BATTERY ROOM STATE STATIC CHARGER OB 35 1A2-460V 480V UNIT SUBSTATION 1A2 FOR 732 RB 23 460V SWITCHGEAR ROOM REACTOR BLDG 1B2-460V 480V UNIT SUBSTATION 1B2 FOR 732 RB 23 460V SWITCHGEAR ROOM REACTOR BLDG FN-56-4 SWGR ROOM 'A' SUPPLY FAN 823 RB 23 OC,460V SWITCHGEAR ROOM FN-56-7 SWGR ROOM 'A' EXHAUST FAN 823 RB 23 OC,460V SWITCHGEAR ROOM FN-56-8 480V SWITCHGEAR ROOM "A"823 RB 23 OC,460V SWITCHGEAR ROOM ALTERNATE EXHAUST FAN FN-59-6 'C' BATTERY ROOM VENT FAN 1-1 732 RB 23 OC,460V SWITCHGEAR ROOM FN-59-7 480V BREAKER 'C' BATTERY ROOM 732 RB 23 OC,460V SWITCHGEAR ROOM VENT FAN 1-2 0- VMCC 1A2-(B06)

M-39-1 EMERGENCY DIESEL GENERATOR #1 741 DG 23 OCDIESEL GEN BLDG 23' 0" M-39-2 EMERGENCY DIESEL GENERATOR #2 741 DG 23 OCDIESEL GEN BLDG 23' 0" Table B-1 Page 1 of 80 B-3

Oyster Creek Generating Station Unit 1 1200108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION ROTARY AC GENERATOR FOR 120V AC SUPPLY 733 OB 35 OCMOB 35' 125v BATTERY ROOM INVERTER\AC FOR CIP-3 IN 120V AC SUPPLY FOR CIP-3 733 OB 35 OCOB 35'125v BATTERY ROOM 208/120V,3PH,4W 1A21-460V MCC 1A21 460V,3PH,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM TURBINE BUILDING MCC 1A21A 460V,3P,3W,60HZ FOR OC,RX 23' S. WALL ACCESS AREA -

1A21A-460V REACTOR BUILDING 732 RB 23 S. TORUS CTRL AREA - MCC 1AZ1A 1A21B-460V MCC 1A21 B 460V,3P,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING 1A23-460V MCC 1A23 460V,3PH,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING 1A24-460V MCC 1A24 460V,3PH,3W,60HZ FOR 732 HBH 23 OC,BOILER HOUSE 23' ALL AREAS STACK 1A2-460V 460V UNIT SUBSTATION 1A2 FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING ISOLATION VALVES MCC lAB2 OC,RX 23' OUTSIDE LABRYNTH 1AB2-460V 460V,3PH,3W,60HZ 732 RB 23 AREA-D/W PARTICULATE MONITOR-02 ANALY 1B21-460V MCC 1B21 460V,3PH,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING 1B21A-460V MCC 1B21A 460V,3P,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING 1 B21B-460V MCC 1B21B 460V,3P,3W,60HZ FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING 7 1B23-460V MCC 1 B23 460V,3PH,3W,60HZ FOR 732 HBH 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING MCC 1 B24 460V,3PH,3W,60HZ FOR OC,BOILER HOUSE 23' ALL AREAS 1B24-460V HEATING BOILER HOUSE 732 HBH 23 1B2-460V VITAL MCC 1B2 460V,3PH,3W 60HZ,FOR 732 RB 23 OC,460V SWITCHGEAR ROOM REACTOR BUILDING DC-1 125VDC 125VDC ISOLATION VALVES MOTOR 735 RB 23 OC, RX 23' SOUTHEAST ACCESS CONTROL CENTER I AREA - MCC DC-1 Table B-1 Page 2 of 80 B-4

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 125VDC MOTOR CONTROL CTR FOR OC,RX 75' EMRGNCY CONDENSER DC-2 125VDC REACTOR BUILDING 735 RB 23 RETURN VALVE AREA lC 4160V 1C BUS & EMERGENCY 731 TB 23 OCTB SOUTH MEZZANINE 4160 SWITCHGEAR I VOLT SWITCHGEAR ROOM 1D 4160V 1D BUS & EMERGENCY 731 TB 23 OCTB SOUTH MEZZANINE 4160 SWITCHGEAR VOLT SWITCHGEAR ROOM DG-1 SWGR DIESEL GENERATOR #1 UNIT 741 DG 23 DIESEL GENERATOR BUILDING SWITCHGEAR #1,NORTH WALL DG-2 SWGR DIESEL GENERATOR UNIT #2 741 DG 23 DIESEL GENERATOR BUILDING SWITCHGEAR #2,NORTH WALL 10F MAIN CONTROL ROOM AREA & 611 TB 46 MAIN CONTROL ROOM AREA EAST PROCESS RADIATION PANEL SIDE MAIN CONTROL ROOM PNL 1OR MAIN CONTROL ROOM AREA PROCESS INSTR EQUIPMENT NORTHWEST SIDE 1F MAIN CONTROL RM ISOLATION PANEL 611 TB 46 MAIN CONTROL ROOM AREA EAST SIDE MAIN CONTROL ROOM PNL 11R GAS MAIN CONTROL ROOM AREA TREATMENTNENTILATION NORTHWEST SIDE CONTROL ROOM PANEL 1IXR MAIN CONTROL ROOM AREA SW TELEMTR/GENERA PROTECTION CORNER MAIN CONTROL ROOM PNL 12R MAIN CONTROL ROOM AREA GENERATOR/XFMR PROTECTION SOUTHWEST SIDE MAIN CONTROL RM PNL 12XR MAIN CONTROL ROOM AREA TURBINE/AUX SYSTEM TEMP. NORTHWEST SIDE MAIN CONTROL AIR H2&02 ROOM PNL 16R CONT ANALYZING MAIN CONTROL ROOM AREASOUTHWEST CORNER MAIN CONTROL ROOM PNL 17R WIDE CONTROL ROOM SW CORNER ON 17R RANGE RX LEVEL 611 TB 46 WEST WALL MAIN CONTROL ROOM PNL 18R MAIN CONTROL ROOM REACTOR PROTECTION SYSTEM 6NORTHWEST CORNER MAIN CONTROL ROOM PNL 19R MAIN CONTROL ROOM REACTOR PROTECTION SYSTEM NORTHWEST CORNER 1F/2F MAIN CONTROL ROOM REACTOR & I11 TB OCMAIN CONTROL ROOM 64 46 DRYWELL COOLING PANEL Table B-1 Page 3 of 80 B-5

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 2R MAIN CONTROL ROOM AREA & 611 TB 46 OC,MAIN CONTROL ROOM RADIATION MONITOR PANEL MAIN CONTROL ROOM CLEANUP & 5 FEET NORTH OF SHIFT RECIRCULATION PANEL 6SUPERVISORS OFFICE MAIN CONTROL ROOM NEUTRON 5 FEET FROM SOUTH WALL MONITORS PANEL CONTROL MAIN CONTROL ROOM REACTOR 8 FEET SOUTHWEST OF RECORD CONTROL ROD PANEL &COMM DESK 4R MAIN CONTROL ROOM NEUTRON FLUX 611 TB 46 MAIN CONTROL ROOM AREA 5FT CALIBRATION PANEL FROM S WALL 5F/6F MAIN CONTROL ROOM PANEL 611 TB 46 OCMAIN CONTROL ROOM FEEDWATER & CONDENSATE MAIN CONTROL ROOM PNL 5R 5 FEET FROM SOUTH WALL NEUTRON MONITORS 6CONTROL ROOM MAIN CONTROL RM PANEL 6R MAIN CONTROL ROOM AREA SW REACTOR PROTECTION CH.1 OF COL.8A/FA MAIN CONTROL ROOM PNL 6XR MAIN CONTROL ROOM AREA PROTECT SYSTEM OPERATIONS SOUTHWEST SIDE MAIN CONTROL RM PANEL 7R MAIN CONTROL ROOM AREA REACTOR PROTECTION CH.2 WEST OF COL.8NAFA 8F/9F MAIN CONTROL ROOM PANEL 611 TB 46 OC,MAIN CONTROL ROOM GENERATOR & AUX POWER 8R MAIN CONTROL ROOM PNL 8R 611 TB 46 OC,MAIN CONTROL ROOM TEMPERATURE RECORDERS MAIN CONTROL ROOM PNL 9R MAIN CONTROL ROOM NW OF FEEDWATER & RECIRCULATION COLUMN 8AIFA ClP-3 CONTINUOUS INSTRUMENT PNL NO.3 733 RB 23 480V SWGR ROOM,SOUTH OF USS 208/120V,3PH,4W,60HZ 1A2-460V DC-B 125V 125VDC DISTRIBUTION PANEL 'B' 735 OB A/B BATTERY ROOM NORTH WALL DC-C 125V 125V DC DISTRIBUTION CENTER 'C' 735 TB 23 4160V SWITCHGEAR WL THIE RM SOUTH WALL (TE 91NE)

DCD 125VDC POWER PANEL'D' 73 5 ABN BATTERY ROOM NORTH WALL Table B-1 Page 4 of 80 B-6

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION DC-F 125VDC POWER PANEL DC-F 735 RB 23 480V SWGR ROOM,SOUTHEAST OF MCC 1A2-460V DG-1 GOV CONT DIESEL GENERATOR UNIT #1 AC 741 DG 23 INSIDE ELECTRICAL CONTROL PNL PANEL(GEN & GOV CONTR) CABINET DG-1 MASTER DIESEL GENERATOR UNIT #1 MASTER 741 DG 23 INSIDE ELECTRICAL CONTROL PANEL EXTRA PANEL CABINET DIESEL GENERATOR UNIT #1 INSIDE ELECTRICAL CONTROL DASEQ SEQUENCE CONTROL PANEL 741 DG 23 CABINET PANEL DIESEL GENERATOR UNIT #1 INSIDE ELECTRICAL CONTROL D ANG STARTING CONTROL PANEL 741 DG 23 CABINET PAN EL DG-1 UNIT PANEL DIESEL GENERATOR #1 UNIT EXTRA 741 DG 23 INSIDE ELECTRICAL CAIE CONTROL PANEL (DEADLINE) CABINET DG-2 GOV CONT DIESEL GENERATOR UNIT #2 AC INSIDE ELECTRICAL CONTROL PNL PANEL(GEN & GOV CONTR) CABINET DG-2 MASTER DIESEL GENERATOR UNIT #2 MASTER INSIDE ELECTRICAL CONTROL PANEL EXTRA PANEL CABINET DIESEL GENERATOR UNIT #2 INSIDE ELECTRICAL CONTROL D2SEQ SEQUENCE CONTROL PANEL 741 DG 23 CABINET PAN EL DIESEL GENERATOR UNIT #2 INSIDE ELECTRICAL CONTROL D ANG STARTING CONTROL PANEL 741 DG 23 CABINET PANEL DG-2 UNIT PANEL DIESEL GENERATOR UNIT #2 EXTRA 741 DG 23 INSIDE ELECTRICAL CONTROL PANEL (DEADLINE) CABUINET ER18A CORE SPRAY/AUTO DEPRESS'N 642 RB 23 480V SWGR ROOM,SOUTH OF USS SYSTEM RELAY LOGIC PANEL 1A2-460V ER18B CORE SPRAY/AUTO DEPRESS'N 642 RB 23 OC,460V SWITCHGEAR ROOM SYSTEM RELAY LOGIC PANEL AUXILIARY RELAY CABINET - CORE OC,RX 51 CORE SPRAY BOOSTER ER-642-112 SPRAY PS-RV0046A 642 RB 51 PUMPS NZ03A & NZ03C Table B-1 Page 5 of 80 B-7

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION AUXILIARY RELAY CABINET - CORE OC,RX 51' CORE SPRAY BOOSTER ER-642-113 SPRAY PS-RV0046B 642 RB 51 PUMPS NZ03A & NZ03C AUXILIARY RELAY CABINET - CORE OC,RX 51' CORE SPRAY BOOSTER ER-642-114 SPRAY PS-RV0046C 642 RB 51 PUMPS NZ03A & NZ03C AUXILIARY RELAY CABINET - CORE OC,RX 51' CORE SPRAY BOOSTER ER-642-115 SPRAY PS-RV0046D 642 RB 51 PUMPS NZ03A & NZ03C AUXILIARY RELAY PNL-ESAS NORTH OF STAIRWAY TO ACTUATION PS-RV0046A TO D PERSONNEL LOCK AUXILIARY RELAY PANEL FOR ADS OC,RX 23' SOUTH ACCESS ER-642-79 VALVES/INSTRUMENTS 642 RB 23 CORRIDOR (MOTOR GENERATOR ROOM)

ER7A FUSE PANEL GROUP I SCRAM PILOT 225 RB 23 OC,RX 23' NORTH WEST ACCESS SOLENOID VALVES AREA ER7B FUSE PANEL GROUP II SCRAM PILOT 225 RB 23 OC,RX 23' NORTH WEST ACCESS SOLENOID VALVES AREA FUSE PANEL GROUP 3 SCRAM PILOT OC, RX 23' NORTH WEST ACCESS SOLENOID VALVES AREA ER7D FUSE PANEL GROUP IV SCRAM PILOT 225 RB 23 OC,RX 23' NORTH WEST ACCESS SOLENOID VALVES 23 AREA FUSE PANEL GROUP I SCRAM PILOT OC,RX 23'S. WALL ACCESS AREA -

ER7E SOLENOID VALVES 225 RB 23 S. TORUS CTRL AREA - MCC 1AZIA FUSE PANEL GROUP IISCRAM PILOT OC,RX 23'S. WALL ACCESS AREA -

ER7F SOLENOID VALVES 225 RB 23 S. TORUS CTRL AREA - MCC 1AZIA FUSE PANEL GROUP 3 SCRAM PILOT OC,RX 23' S. WALL ACCESS AREA -

ER7G SOLENOID VALVES 225 RB 23 S. TORUS CTRL AREA - MCC 1AZIA FUSE PANEL GROUP IV SCRAM PILOT OC,RX 23' S. WALL ACCESS AREA -

ER7H SOLENOID VALVES 225 RB 23 S. TORUS CTRL AREA - MCC 1AZIA Table B-1 Page 6 of 80 B-8

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION ER8A CONTAINMENT SPRAY SYSTEM/ RELAY 642 RB 23 480V SWGR ROOM,SOUTH OF USS LOGIC PANEL 1A2-460V ER8B CONTAINMENT SPRAY SYSTEM/ RELAY 642 RB 23 480V SWGR ROOM,SOUTH OF USS LOGIC PANEL 1A2-460V IP-4 120VAC INSTRUMENT PANEL 4 - 733 RB 23 IN 480V SWGR RM,SOUTH OF USS 208/120V,3PH,4W 1A2-460V IP-4A 208/120VAC INSTRUMENT PNL 4A - 733 RB 23 480V SWGR ROOM,SOUTH OF USS 208/120V,3PH,4W,60HZ 1A2-460V IP-4B 208/120VAC INSTRUMENT PNL 4B - 733 RB 23 480V SWGR ROOM,SOUTH OF USS 208/120V,3PH,4W,60HZ 1A2-460V IP-4C 208/120VAC INSTRUMENT PNL 4C - 733 RB 23 480V SWGR ROOM,SOUTH OF USS 208/120V,3PH,4W,60HZ 1A2-460V LSP-1A2 LOCAL SHUTDOWN PANEL- USS 1A2 615 OB 23 480V SWGR RM, 4 FT WEST OF PUMP/BREAKER CONTROL 8USS 1A2-460V LOCAL SHUTDOWN PANEL FOR V OC,RX 23' OUTSIDE LABRYNTH LSP-1AB2 0054 & V-17-0019&54 615 RB 23 AREA-D/W PARTICULATE MONITOR-02 ANALY VACP- 120V VITAL AC POWER PANEL 733 RB 23 OC,460V SWITCHGEAR ROOM 208/120V,3PH,4W,60HZ 7 UA2-460VXF USS 1A2-460V TRANSFORMER 4160- 732 RB 23 OC,460V SWITCHGEAR ROOM 480V/277V 3PH 60HZ 1U2-460V XF USS 1B2-460V TRANSFORMER 4160- 732 RB 23 OC,460V SWITCHGEAR ROOM 480V/277V 3PH 60HZ DIESEL GENERATOR UNIT #2 OCDIESEL GEN BLDG 23' 0" CT5B TASOMR.741 TRANSFORMER________ DGB 23 IT-3 POTENTIAL TRANSFORMER FOR MCC 733 RB 23 OC,460V SWITCHGEAR ROOM 1A2-460V TO CIP-3 POTENTIAL AC TRANSFORMER FROM OC,460V SWITCHGEAR ROOM IT-4A MCC 1A2-460V TO IP-4733 RB 23 IT-4B POTENTIAL AC TRANSFORMER FROM 733 RB 23 OC,460V SWITCHGEAR ROOM MCC 1B2-460V TO IP-4 PS-1 480/120VAC TRANSFORMER TO 733 TB OC,OLD CABLE SPREADING ROOM PROTECTION SYS PANELS 1&2 VACP-1 XF 120V VITAL AC POWER PANEL 733 RB 23 OC,460V SWITCHGEAR ROOM VTRANSFORMER 480/208/120V Table B-1 Page 7 of 80 B-9

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\06-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\06-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\06-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\06-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\06-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\06-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\06-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\10-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\10-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\10-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 'ACCUMULATORS)

PI-305-131\10-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\10-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

Table B-1 Page 8 of 80 B-10

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\10-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\14-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\14-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

ACCUMULATORS GAS PRESSURE 23 OC,RX 23' N. BANK HCU'S (CRD PI-305-131\14-15 INDICATOR 225 RB ACCUMULATORS)

PI-305-131\14-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\14-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\14-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\14-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\14-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' N. BANK HCU'S (CRD PI-305-131\14-39 INDICATOR 225 RB 23 ACCUMULATORS)

PI-305-131\14-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-13t\14-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-03 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR

_(CRD ACCUMULATORS)

PI-305-131\18-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\18-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2 RACCUMULATORS)

Table B-1 Page 9 of 80 B-1 1

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\18-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\18-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\18-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\18-51 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\22-03 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\22-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR _ACCUMULATORS)

PI-305-131\22-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\22-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\22-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\22-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\22-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-113122-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131 \22-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

Table B-1 Page 10 of 80 B-12

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\.2-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-13122-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\2-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2 ACCUMULATORS)

PI-305-131\2-51 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\6-03 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\6-07. ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD INDICATOR 2 RCCUMULATORS)

PI-305-131\.6-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2CRD ACCUMULATORS)

PI-305-131\26-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\26-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR

_(CRD ACCUMULATORS)

PI-305-13116-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\6-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR CRD ACCUMULATORS)

PI-305-131\26-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\6-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR

_(CRD ACCUMULATORS)

PI-305-131\.6-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR 2ACCUMULATORS)

PI-305-131\.6-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR _(CRD ACCUMULATORS)

Pi-305-131\6-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

PI-305-131\6-51 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD INDICATOR ACCUMULATORS)

Table B-1 Page 11 of 80 B-1 3

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\30-03 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S PI-305-131\30-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\30-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23'SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\30-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' SOUTH BANK HCU'S PI-305-131\30- INDICATOR (CRD ACCUMULATORS)

INDICATOR 225____23 (CRD PI30-11\0-3ACCUMULATORS GAS PRESSURE. 2 B 2 OC,RXACCUMULATORS) 23' SOUTH BANK HCU'S ACCUMULATORS GAS PRESSURE RB 23 OC, RX 23' SOUTH BANK HCU'S PI-305-131\30-31 225 INDICATOR (CRD ACCUMULATORS)

PI-305-131\30-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S PI-305-131\30-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR "(CRD ACCUMULATORS)

INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' SOUTH BANK HCU'S PI-305-131\30-27 PI-305-131\30-31 INDICATOR 22___2 225 RB 23 (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\30-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR CRD ACCUMULATORS)

PI-305-131\340- ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' SOUTH BANK HCU'S PI-305-131\30 INDICATOR CRD ACCUMULATORS)

INDICATOR 225 RB 23 (CRD ACCUMULATORS)

OC,RX 23' SOUTH BANK HCU'S PI-305-131\34-07 ACCUMULATORS GAS PRESSURE PI-305-131\34-11 ACCUMULATORS GAS PRESSURE 225 RB OCRXACCUMULATORS) 23' SOUTH BANK HCU'S

_______INDICATOR _______(CRD 23 ACCUMULATORS IND R GAS PRESSURE) OCRX 23' N. BANK HCU'S Table B-1 Page 12 of 80 B-14

Oyster Creek Generating Station Unit I 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID PI-305-131\34-19 PI-305-131\34-23 PI-305-131 \34-27 PI-305-131\34-31 ACCUMULATORS GAS PRI OC,RX 23- SOUTH BANK HCU'S PI-305-131\34-35 INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OC,RX 23' SOUTH BANK HCU'S PI-305-131\34-39 INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE SOUTH BANK HCU'%

PI-305-131\34-43 INDICATOR PI-305-131\34-47 ACCUMULATORS GAS PRESSURE INDICATOR PI-305-131\34-51 ACCUMULATORS GAS PRESSURE 11 INDICATOR ýC ACCUMULATORS GAS PRESSURE OCRX PI-305- 31\38-07 INDICATOR (CRD A PRESSURE OC,RX 23' SOUTH BANK HCU'S P-305- 31\38-1 1 ACCUMULATORS GAS INDICATOR (CRD ACCUMULATORS)

PRESSURE OC,RX 23SOUTH BANK HCU'S P-305-131 \38-15 ACCUMULATORS GAS INDICATOR I(CRD ACCUMULATORS)

C,RX 23' SOUTH BANK HCU'S P-305-131 \38-19 ACCUMULATORS GAS PRESSURE

_INDICATOR 'RD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE 'SOUTH BANK PI-305-131\38-23 INDICATOR 'UMULATORS)

PI-305-131 \38-27 PI-305-131 \38-31 PI-305-131\38-35 Table B-1 Page 13 of 80 B-15

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\38-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\38-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 3 (CRD ACCUMULATORS)

PI-305-131\38-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\42-07 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR P(CRD ACCUMULATORS)

PI-305-131\42-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\2-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2 (CRD ACCUMULATORS)

PI-305-131\42-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\42-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\42-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\42-31 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\42-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2 R(CRD ACCUMULATORS)

PI-305-131\42-39 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\42-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\42-47 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\46-11 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\6-15 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\46-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2 R(CRD ACCUMULATORS)

Table B-1 Page 14 of 80 B-1 6

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION PI-305-131\46-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\46-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23'SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

ACCUMULATORS GAS PRESSURE OCRX 23' SOUTH BANK HCU'S PI-305-131\46-31 IC ATOR 225 RB 23 INDICATOR

_(CRD ACCUMULATORS)

PI-305-131\46-35 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR _(CRD ACCUMULATORS)

PI-305-131\46-3 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR 2(CRD ACCUMULATORS)

PI-305-131\46-43 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR _(CRD ACCUMULATORS)

PI-305-131\50-19 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR

_(CRD ACCUMULATORS)

PI-305-131\50-23 ACCUMULATORS GAS PRESSURE 225 RB 23 OCRX 23' SOUTH BANK HCU'S INDICATOR _(CRD ACCUMULATORS)

PI-305-131\50-27 ACCUMULATORS GAS PRESSURE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

PI-305-131\50-31 ACCUMULATORS GAS PRESSURE 225 RB 23 23' SOUTH BANK HCU'S OCRXACCUMULATORS)

__NDICATO__(CRD AI35115-5*CCUMULATORS GAS PRESSURE 25 R23 OCRX 23' SOUTH BANK HCU'S INDICATOR (CRD ACCUMULATORS)

REACTOR PROTECTION SYSTEM 1A,2A OC,RX 51' INSTRUMENT RACK RK-RK-1 INSTRUMENT RACK A,B 614 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

RK-2 REACTOR PROTECTION SYSTEM 1B,2B 614 RB 51 OCRX 51' INSTRUMENT RACK RK-INSTRUMENT RACK AB 02 RK-3 INSTRUMENT RACK RECIRC'N PUMP 614 RB 51 OCRX 51' INSTRUMENT RACK RK-REACTOR PROTECTION 03 AREA RK-4 INSTRUMENT RACK FOR RPS & 614 RB -1 OCRX -1' CONTROL ROD DRIVE RECIRC PUMP & NSS SYSTEMS SYSTEM PUMP (RK-04)

RK-411-1 MSIV'S SOLENOID AIR VALVE & 411 TB 23 OCTRUNION ROOM GENERAL ALL EQUIPMENT MOUNTING RACK AREAS DPIS-IB0005A1 EMERGENCY CONDENSER NE01A HIGH 211 RB 51 OCRX 51' INSTRUMENT RACK RK-SYSTEM FLOW SWITCH _ 03 AREA Table B-1 Page 15 of 80 B-1 7

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION DPIS-1B0005A2 EMERGENCY CONDENSER NE01A HIGH 211 RB 51 OC,RX 51' INSTRUMENT RACK RK-SYSTEM FLOW SWITCH 03 AREA DPIS-IB0005B1 EMERGENCY CONDENSER NE01 B HIGH 211 RB 51 OC,RX 51' INSTRUMENT RACK RK-SYSTEM FLOW SWITCH 03 AREA DPIS-IB0005B2 EMERGENCY CONDENSER NE01B HIGH 211 RB 51 OC, RX 51' INSTRUMENT RACK RK-SYSTEM FLOW SWITCH 03 AREA DPIS-IB0011A1 EMERGENCY CONDENSER NE01A HIGH 211 RB 51 OCRX 51' INSTRUMENT RACK RK-CONDENSATE LINE FLOW 03 AREA DPIS-IB0011A2 EMERGENCY CONDENSER NE01A HIGH 211 RB 51 OCRX 51' INSTRUMENT RACK RK-CONDENSATE LINE FLOW 03 AREA DPIS-IB30011B1 EMERGENCY CONDENSER NE01B HIGH 211 RB 51 OCRX 51' INSTRUMENT RACK RK-CONDENSATE LINE FLOW 03 AREA DPIS-IBO011B2 EMERGENCY CONDENSER NE01B HIGH 211 RB 51 OCRX 51' INSTRUMENT RACK RK-CONDENSATE LINE FLOW 03 AREA REACTOR VESSEL LOW LEVEL OC,RX 51' INSTRUMENT RACK RK-LIS-RE0018A INDICATING SWITCH 622 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

LIS-RE0018B REACTOR VESSEL LOW LEVEL 622 RB 51 OC,RX 51' INSTRUMENT RACK RK-INDICATING SWITCH 02 REACTOR VESSEL LOW LEVEL OC,RX 51' INSTRUMENT RACK RK-LIS-RE0018C INDICATING SWITCH 622 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

LIS-RE0018D REACTOR VESSEL LOW LEVEL 622 RB 51 OC,RX 51' INSTRUMENT RACK RK-INDICATING SWITCH 02 LS-862-10B LO-LO LEVEL (START NORMAL PUMP) 862 DG 23 OC,DIESEL GEN BLDG 23' 0" ON TANK T-39-003 LS-862-10C HI-HI LEVEL(PUMP CUT-OFF) ON TANK 862 DG 23 OCDIESEL GEN BLDG 23' 0" T-39-003 LS-862-11A LO-LO LEVEL(START BACK-UP PUMP) 862 DG 23 OC,DIESEL GEN BLDG 23' 0" ON TANK T-39-004 LS-862-11B HIGH LEVEL (STOP PUMP) ON TANK T- 862 DG 23 OCDIESEL GEN BLDG 23' 0"39-004 LS-862-12B LO LEVEL(START NORM PUMP) ON 862 DG 23 OC,DIESEL GEN BLDG 23' 0" TANK T-39-004 8 D 2 Table B-1 Page 16 of 80 B-18

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION LS-862-12C HI-HI LEVEL(PUMP CUT-OFF) ON TANK 862 DG 23 OC,DIESEL GEN BLDG 23' 0" T-39-004 LS-862-9A LO-LO LEVEL(START BACK-UP 862 DG 23 OC, DIESEL GEN BLDG 23' 0" PUMP)ON TANK T-39-003 LS-862-9B HIGH LEVEL(STOP PUMP)FUEL OIL 862 DG 23 OC,DIESEL GEN BLDG 23' 0" TANK T-39-003 LS-IG0003A EMERGENCY CONDENSER NE01A 211 TB 46 OC,MAIN CONTROL ROOM LEVEL SWITCH(HI/LO ALARM) I LS-IG0003B EMERGENCY CONDENSER NE01 B 211 TB 46 OC,MAIN CONTROL ROOM LEVEL SWITCH(HI/LO ALARM)

NORTH SDIV LEVEL SWITCH (LEVEL HI- OC,RX 23' NW-NORTH SCRAM LS-RD0087C HI CH. I-SCRAM) 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS NORTH SDIV LEVEL SWITCH (LEVEL HI- OC,RX 23' NW-NORTH SCRAM LS-RD0088B HI CH.2-SCRAM) 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS LS-RD0091A SOUTH SDIV LEVEL SWITCH (LEVEL HI- 225 RB 23 OC,RX 23' SOUTH SCRAM HI CH2R-SCRAM) DISCHARGE VOLUME AREA LS-RD0092D SOUTH SDIV LEVEL SWITCH (LEVEL HI- 225 RB 23 OC,RX 23' SOUTH SCRAM HI CH.2-SCRAM) DISCHARGE VOLUME AREA PS-lA0083A EMRV NR108A HIGH PRESSURE 622 RB 51 OC,RX 51' GENERAL ALL AREAS SWITCH I PS-IA0083B EMRV NR108B HIGH PRESSURE 622 RB 51 OC,RX 51' NORTHWEST CONTROL SWITCH AREA PS-IA0083C EMRV NR108C HIGH PRESSURE 622 RB 51 OC,RX 51' INSTRUMENT RACK RK-SWITCH 02 PS-IA0083D EMRV NR108D HIGH PRESSURE 622 RB 51 OC,RX 51' EAST SWITCH _CORRIDOR/WALKWAY PS-IA0083E EMRV NR108E HIGH PRESSURE 622 RB 51 OC,RX 51' NORTHWEST CONTROL SWITCH AREA LOW REACTOR PRESS. SWITCH OC,RX 51' INSTRUMENT RACK RK-PS-RE0017A READIES CORE SPRAY VALVES 622 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

PS-RE0017B LOW REACTOR PRESS. SWITCH 622 RB 51 OC,RX 51' INSTRUMENT RACK RK-READIES CORE SPRAY VALVES 1 1 102 Table B-1 Page 17 of 80 B-19

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION LOW REACTOR PRESS. SWITCH OC,RX 51' INSTRUMENT RACK RK-PS-RE0017C READIES CORE SPRAY VALVES 622 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

PS-RE0017D LOW REACTOR PRESS. SWITCH 622 RB 51 OCRX 51' INSTRUMENT RACK RK-READIES CORE SPRAY VALVES 1 02 CS PUMP NZ01-A DISCHARGE OC,RX -19' CORE SPRAY PUMP PS-RV0029A PRESSURE SWITCH(SYSTEM I) 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

PS-RV0029B CS PUMP NZ01-B DISCHARGE 212 RB -19 OCRX -19' CORE SPRAY PUMP PRESSURE SWITCH(SYS.II) ROOM WEST (NZ01 B & NZ01 D)

CS PUMP NZ01-C DISCHARGE OC,RX -19' CORE SPRAY PUMP PS-RV0029C PRESSURE SWITCH(SYS.I) 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

PS-RV0029D CS PUMP NZ01-D DISCHARGE 212 RB -19 OCRX -19' CORE SPRAY PUMP PRESSURE SWITCH(SYS.II) IROOM WEST (NZ01 B & NZ01 D)

PS-RV0046A DRYWELL HIGH PRESSURE SWITCH- 243 RB 51 OCRX 51 INSTRUMENT RACK RK-AUTO STARTS PUMPS 103 AREA PS-RV0046B DRYWELL HIGH PRESSURE SWITCH- 243 RB 51 OC,RX 51' INSTRUMENT RACK RK-AUTO STARTS PUMPS 103 AREA PS-RV0046C DRYWELL HIGH PRESSURE SWITCH- 243 RB 51 OCRX 51' INSTRUMENT RACK RK-AUTO STARTS PUMPS _03 AREA PS-RV0046D DRYWELL HIGH PRESSURE SWITCH- 243 RB 51 OCRX 51' INSTRUMENT RACK RK-AUTO STARTS PUMPS 103 AREA DPT-5-1A0091A FUEL ZONE LEVEL'A' WIDE RANGE 622 RB 51 OCRX 51' INSTRUMENT RACK RK-LEVEL TRANSMITTER 103 AREA REACTOR FUEL ZONE LEVEL WIDE OC,RX 23' NW-NORTH SCRAM DPT-622-1009 RANGE IXMITR(CH.C) 622 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS REACTOR FUEL ZONE LEVEL WIDE OC,RX 23' NW-NORTH SCRAM DPT-622-1011 RANGE IXMITR(CH.D) 622 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS DPT-6-1A0091B FUEL ZONE LEVEL 'B' WIDE RANGE 622 RB 51 OC RX 51' INSTRUMENT RACK RK-LEVEL TRANSMITTER 03 AREA DPT-822-13 RX BUILDING DIFFERENTIAL 822 RB 119 OC, RX 119' WEST FLOOR AREA PRESSURE TRANSMITTER I Table B-1 Page 18 of 80 B-20

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION DPT-IA0050A RECIRCULATION PUMP NG01-A LOOP 223 RB 51 OC,RX 51' INSTRUMENT RACK RK-

'A' D/P TRANSMITTER 03 AREA DPT-IA0050B RECIRCULATION PUMP NG01-B LOOP 223 RB 51 OC, RX 51' INSTRUMENT RACK RK-

'B' D/P TRANSMITTER _03 AREA DPT-IA0050C RECIRCULATION PUMP NG01-C LOOP 223 RB 51 OCRX 51' INSTRUMENT RACK RK-

'C' D/P TRANSMITTER 03 AREA RECIRCULATION PUMP NG01-D LOOP OCRX 51' INSTRUMENT RACK RK-DPT__A0050D 'D' D/P TRANSMITTER 223____51 03 AREA DPT-IA0050E RECIRCULATION PUMP NG01-E LOOP 223 RB 51 OC,RX 51' INSTRUMENT RACK RK-

'E' D/P TRANSMITTER 03 AREA CONTAINMENT SPRAY HTEXCHG 1A OC,RX 23' NORTH BANK DPT-IP0005A ESW D/P TRANSMITTER 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

CONTAINMENT SPRAY HTEXCHG 1B OC,RX 23' NORTH BANK DPT-IP0005B ESW D/P TRANSMITTER 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

CONTAINMENT SPRAY HTEXCHG 1C OC,RX 23'. SOUTH BANK DPT-IP0005C ESW D/P TRANSMITTER 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-3 &1-4)

CONTAINMENT SPRAY HTEXCHG 1D OC,RX 23' SOUTH BANK DPT-IP0005D ESW D/P TRANSMITTER 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-3 &1-4)

CRD SYSTEM DRIVE WATER/RX OC,RX 23' CRD SYSTEM DPT-RD0004 VESSEL D/P TRANSMITTER 225 RB 23 FILTERNALVING AREA (FILTERS=NC06 A&B)

CRD SYSTEM COOLING WATER/ RX OC,RX 23' CRD SYSTEM DPT-RD0005 VESSEL D/P TRANSMITTER 225 RB 23 FILTERNALVING AREA (FILTERS=NC06 A&B)

REACTOR VESSEL LOW WATER LEVEL OC,RX 51' INSTRUMENT RACK RK-LT-RE0005A REACTOR SCRAM 622 RB 51 01 (ACCESS FROM RX-75' AREA RFG)

LT-RE0005B REACTOR VESSEL LOW WATER LEVEL 622 a1 51 OCRX 51' INSTRUMENT RACK RK-REACTOR SCRAM 02 EF-1-8 SBGTS

______________028) SYSTEM EXHAUST FAN (FN 822

_________ RB _____23 OC,RX 23' OUTSIDE SOUTH Table B-1 Page 19 of 80 B-21

Oyster Creek Generating Station Unit 1 12001 08.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION FN-732-1 USS 1A2-460V TRANSFORMER 732 RB 23 OC,460V SWITCHGEAR ROOM COOLING FAN FN-732-2 USS 1A2-460V TRANSFORMER 732 RB 23 OC,460V SWITCHGEAR ROOM COOLING FAN FN-732-3 USS 1A2-460V TRANSFORMER 732 RB 23 OC,460V SWITCHGEAR ROOM COOLING FAN FN-732-43 SS 1B2-460V TRANSFORMER 732 RB. 23 OC,460V SWITCHGEAR ROOM COOLING FAN FN-732-4 USS 1 B2-460V TRANSFORMER 732 RB 23 OC,460V SWITCHGEAR ROOM COOLING FAN FN-732-5 FNUSS 1B2-460V TRANSFORMER 732 RB 23 OC,460V SWITCHGEAR ROOM COOLING FAN CD-14-1A EMERGENCY CONDENSER NE01A 211 RB 95 OCRX 95' "A" EMERGENCY CONDENSER NE01-A CD-14-1B EMERGENCY CONDENSER NE01B 211 RB 95 OCRX 95' "B"EMERGENCY CONDENSER NE01-B CONTAINMENT SPRAY SYSTEM HEAT OC,RX 23' NORTH BANK H-21-1A EXCHANGER 1-1 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

CONTAINMENT SPRAY SYSTEM HEAT OC,RX 23' NORTH BANK H-21-1B EXCHANGER 1-2 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

CONTAINMENT SPRAY SYSTEM HEAT OC,RX 23' SOUTH BANK H-21-1C EXCHANGER 1-3 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-3 &1-4)

CONTAINMENT SPRAY SYSTEM HEAT OC,RX 23' SOUTH BANK H-21-1D EXCHANGER 1-4 241 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-3 &1-4)

H-39-1 M-39-1 OIL COOLER 861 DG 23 OC,DIESEL GEN BLDG 23' 0" H-39-2 M-39-2 OIL COOLER 861 DG 23 OCDIESEL GEN BLDG 23' 0" M-39-10 M-39-2 RADIATOR 'B' 861 DG 23 OC,DIESEL GEN BLDG 23' 0" M-39-7 M-39-1 RADIATOR 'A' 861 DG 23 OCDIESEL GEN BLDG 23' 0" M-39-8 M-39-1 RADIATOR 'B' 861 DG 23 OC,DIESEL GEN BLDG 23' 0" M-39-9 M-39-2 RADIATOR 'A' 861 DG 23 OC,DIESEL GEN BLDG 23' 0" Table B-1 Page 20 of 80 B-22

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CORE SPRAY PUMP NZ01-A OC,RX -19' CORE SPRAY PUMP P-20-1A 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

P-20-1B CORE SPRAY PUMP NZ01-B 212 RB -19 OCRX -19' CORE SPRAY PUMP I__

_ROOM WEST (NZ01 B & NZ01 D)

CORE SPRAY PUMP NZ01-C OC,RX -19' CORE SPRAY PUMP P-20-1 C 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

P-20-1 D CORE SPRAY PUMP NZ01-D 212 RB -19 OC,RX -19' CORE SPRAY PUMP ROOM WEST (NZ01 B & NZ01 D)

CORE SPRAY BOOSTER PUMP NZ03-A OC,RX 51' CORE SPRAY BOOSTER P-20-2A 212 RB 51 PUMPS NZ03A & NZ03C CORE SPRAY BOOSTER PUMP NZ03-B OC,RX 23' CORE SPRAY BOOSTER P-20-2B 212 RB 23 PUMPS NZ03B & BZ03D CORE SPRAY BOOSTER PUMP NZ03-C OC,RX 51' CORE SPRAY BOOSTER P-20-2C 212 RB 51 PUMPS NZ03A & NZ03C CORE SPRAY BOOSTER PUMP NZ03-D OC,RX 23' CORE SPRAY BOOSTER P-20-2D 212 RB 23 PUMPS NZ03B & BZ03D CONTAINMENT SPRAY PMP 1-1 (51A) OC,RX -19' CONTAINMENT SPRAY P-21-1A 241 RB -19 PUMP ROOM NORTH EAST (1-1 & 1-

___ ___ _______ __ ___ ___ 2)(1-6 SUMP CONTAINMENT SPRAY PMP 1-2 (51 B) OC,RX -19' CONTAINMENT SPRAY P-21-1B 241 RB -19 PUMP ROOM SOUTH EAST (1-3 & 1-4)(1-7 SUMP CONTAINMENT SPRAY PMP 1-3 (51C) OC,RX -19' CONTAINMENT SPRAY P-21-1C 241 RB -19 PUMP ROOM SOUTH EAST (1-3 & 1-4)(1-7 SUMP CONTAINMENT SPRAY PMP 1-4 (51D) OC,RX -19' CONTAINMENT SPRAY P-21-1D 241 RB -19 PUMP ROOM SOUTH EAST (1-3 & 1-I_ I_ 1_ 1 14)(1-7 SUMP Table B-1 Page 21 of 80 B-23

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION P-3-3A EMERGENCY SERVICE WATER PUMP 1- 532 IS 6 OC,INTAKE STRUCTURE 6 FT 1 (52A) ELEVATION P-3-3B EMERGENCY SERVICE WATER PUMP 1- 532 is 6 OCINTAKE STRUCTURE 6 FT 2 (52B) ELEVATION P-3-3C EMERGENCY SERVICE WATER PUMP 1- 532 Is 6 OCINTAKE STRUCTURE 6 FT 3 (52C) ELEVATION P-3-3D EMERGENCY SERVICE WATER PUMP 1- 532 is 6 OCINTAKE STRUCTURE 6 FT 4 (52D) ELEVATION P-39-13 FUEL OIL PUMP TO DAY TANK T-39-3 862 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-14 FUEL OIL PUMP TO DAY TANK T-39-3 862 DG 23 OC,DIESEL GEN BLDG 23' 0" P-39-15 FUEL OIL PUMP TO DAY TANK T-39-4 862 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-16 FUEL OIL PUMP TO DAY TANK T-39-4 862 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-17 DIESEL GENERATOR UNIT #1 ENGINE 862 DG 23 OC,DIESEL GEN BLDG 23'0" DRIVEN FUEL PUMP P-39-18 DIESEL GENERATOR UNIT #2 ENGINE 862 DG 23 OCDIESEL GEN BLDG 23' 0" DRIVEN FUEL PUMP P-39-19 M-39-1 LEFT BEARING COOLING 861 DG 23 OCDIESEL GEN BLDG 23' 0" WATER PUMP P-39-20 M-39-1 RIGHT BEARING COOLING 861 DG 23 OCDIESEL GEN BLDG 23' 0" WATER PUMP P-39-1 M-39-2 LEFT BEARING COOLING 861 DG 23 OC,DIESEL GEN BLDG 23'0" WATER PUMP M-39-2 RIGHT BEARING COOLING OCDIESEL GEN BLDG 23' 0" P-39-2 WATER PUMP861 DG 23 P-39-23 AC TURBO LUBE OIL PUMP 861 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-24 DC TURBO BACKUP LUBE OIL PUMP 861 DG 23 OC,DIESEL GEN BLDG 23' 0" P-39-25 AC TURBO LUBE OIL PUMP 861 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-26 DC TURBO BACKUP LUBE OIL PUMP 861 DG 23 OC,DIESEL GEN BLDG 23' 0" Table B-1 Page 22 of 80 B-24

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION P-39-3 M-39-1 LUBE OIL CIRCULATING PUMP 861 DG 23 OCDIESEL GEN BLDG 23' 0" P-39-4 M-39-2 LUBE OIL CIRCULATING PUMP 861 DG 23 OCDIESEL GEN BLDG 23' 0" 305-125\02-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\02-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\02-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

_ACCUMULATORS) 305-125\02-31 SCRAM ACCUMULATOR-H20. 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

_ACCUMULATORS) 305-125\02-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

-ACCUMULATORS) 305-125\06-11 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

-ACCUMULATORS) 305-125\06-39 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\06-43 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-07 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD I- ACCUMULATORS)

Table B-1 Page 23 of 80 B-25

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\10-11 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23- N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-43 SCRAM ACCUMULATOR-H-120 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\10-47 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-07 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-11 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-23 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\14-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 3 22 RACCUMULATORS)

Table B-1 Page 24 of 80 B-26

Oyster Creek Generating Station Unit 1 12Q0108.BO-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\14-35 ACCUMULATORS)

SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\14-39 ACCUMULATORS) 305-125\14-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS)

SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\14-47

.ACCUMULATORS) 305-125\18-03 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S

_(CRD ACCUMULATORS)

SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-07

_ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-11 SCRAM ACCUMULATOR-H20 ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-15 SCRAM ACCUMULATOR-H20 ACCUMULATORS) 225 RB 23 OCRX 23' N. BANK HCU'S (CRD 305-125\18-19 SCRAM ACCUMULATOR-H20 ACCUMULATORS) 305-125\18-23 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\18-27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-31 SCRAM ACCUMULATOR-H20 ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\1 8-35 SCRAM ACCUMULATOR-H20 ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-39 SCRAM ACCUMULATOR-H20 25 2 ACCUMULATORS) 305-125\18-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS)

SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD 305-125\18-47

_ACCUMULATORS)

SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 305-125\18-51

_ACCUMULATORS)

Table B-1 Page 25 of 80 B-27

Oyster Creek Generating Station Unit 1 1200108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\22-03 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S S2 R3 (CRD ACCUMULATORS) 305-125\22-07 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-11 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-23 SCRAM ACCUMULATOR.-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-31 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\22-43 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\2-47 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\2-51 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\26-03 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\26-07 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\26-11 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S 2(CRD ACCUMULATORS) 305-125\26-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD 2ACCUMULATORS)

Table B-1 Page 26 of 80 B-28

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\26-19 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\26-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\26-27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S

_(CRD ACCUMULATORS) 305-125\26-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

-ACCUMULATORS) 305-125\26-35 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\26-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\26-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S

_(CRD ACCUMULATORS) 305-125\26-47 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

_ACCUMULATORS) 305-125\26-51 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\30-03 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-07 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-11 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-15 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-31 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S I __(CRD ACCUMULATORS)

Table B-1 Page 27 of 80 B-29

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\30-35 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23- SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\3047 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\30-51 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23'N. BANK HCU'S (CRD ACCUMULATORS) 305-125\34-03 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-07 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S SCRD ACCUMULATORS) 305-125\34-11 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-15 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\34-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\3447 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S 3 22 R(CRD ACCUMULATORS)

Table B-1 Page 28 of 80 B-30

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\34-51 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS) 305-125\38-07 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-11 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-15 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-19 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-35 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-39 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-43 SCRAM ACC5MULATOR-H20 225 RB 23 OC,RX 23- SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\38-47 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-07 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-11 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-15 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-19 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-23 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S S(CRD ACCUMULATORS)

Table B-1 Page 29 of 80 B-31

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\42'27 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-31 SCRAM ACCUMULATOR-720 225 RB 23 OC,RX 23' SOUTH BANK HCU'S

_(CRD ACCUMULATORS) 305-125\42-35 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-39 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\42-47 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23'SOUTH BANK HCU'S I _(CRD ACCUMULATORS) 305-125\46-11 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-15 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23- SOUTH BANK HCU'S

_(CRD ACCUMULATORS) 305-125\46-19 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-23 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S I (CaD ACCUMULATORS) 305-125\46-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23'SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-31 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-35 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-39 305-125\50-19 SCRAM ACCUMULATOR-H20 225 225 RB RB 23 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\46-43 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

SCRAM ACCUMULATOR-H20 OC RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\50-23 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

Table B-1 Page 30 of 80 B-32

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 305-125\50-27 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SCRD ACCUMULATORS) 305-125\50-31 SCRAM ACCUMULATOR-H20 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS) 305-125\50-35 SCRAM ACCUMULATOR-H20 225 RB 23 OCRX 23' SOUTH BANK HCU'S

_ (CRD ACCUMULATORS)

CV-305-126\02-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS)

CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\02-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\02-27 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

_____________-7 _ 225_ _ 23_ ACCUMULATORS)

CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\02-31 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\02-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OCRX 23' NW-NORTH SCRAM CV-305-126\06-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-23 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1126\06-27 225 RB 23 DSCHRG VOL - TORUS TOP I_ I_ I ACCESS Table B-1 Page 31 of 80 B-33

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-31 225 ,RB .23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\06-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\10-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\10-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-31 225 RB 23 DSCHRG VOL - TORUS TOP I_ I_ I I ACCESS Table B-1 Page 32 of 80 B-34

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD INLET SCRAM VALVE. OC,RX 23' NW-NORTH SCRAM CV-305-126\10-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 0-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\14-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\14-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 4-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\14-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS)

CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\14-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 4-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\14-31 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' N. BANK HCU'S (CRD ACCUMULATORS)

CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\14-35 225 RB 23 DSCHRG VOL - TORUS TOP I _ACCESS Table B-1 Page 33 of 80 B-35

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 4-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 4-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\14-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\18-03 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OCRX 23' NW-NORTH SCRAM CV-305-126\18-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\18-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-23 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-31 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\18-35 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS Table B-1 Page 34 of 80 B-36

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\1 8-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\22-03 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-07 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS -

CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-31 225 RB 23 DSCHRG VOL -TORUS TOP ACCESS Table B-1 Page 35 of 80 B-37

Oyster Creek Generating Station Unit 1 1200108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1126\22-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1126\22-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\22-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\26-03 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\26-11 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\26-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\26-27 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-31 225 RB 23 DSCHRG VOL - TORUS TOP I _ACCESS Table B-1 Page 36 of 80 B-38

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-126\.6-35 CRD INLET SCRAM VALVE 225 RB 23 OC, RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\.6-43 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\26-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\30-03 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-07 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-11 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM 225 RB 23. DISCHARGE OC,RX VOLUME 23' SOUTH SCRAMAREA CV-305-126\30-15 CRD INLET SCRAM VALVE DISCHARGE VOLUME AREA CV-305-126\30-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-23 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-27 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-31 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

CV-305-126\30-35 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-1'26\30-39 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\30-43 CRD INLET SCRAM VALVE 225 RB 23 OC, RX 23' SOUTH SCRAM I DISCHARGE VOLUME AREA Table B-1 Page 37 of 80 B-39

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-126\30-47 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1126\30-51 225 RB 23 DSCHRG VOL - TORUS TOP I_ ACCESS CV-305-126\34-03 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-07 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

CV-305-126\34-11 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-15 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-23 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-27 CRD INLET SCRAM VALVE 225 RB 23 OC,RXACCUMULATORS) 23' SOUTH BANK HCU'S C(CRD CV-305-126\34-31 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-35 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-39 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-43 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\34-47 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-126\34-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-126\38-07 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA Table B-1 Page 38 of 80 B-40

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-126\38-11 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-15 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-19 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-23 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-27 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-31 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM

.. __DISCHARGE VOLUME AREA CV-305-126\38-35 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-39 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-43 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\38-47 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-07 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-11 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\,2-15 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-23 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-27 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM

. DISCHARGE VOLUME AREA CV-305-126\42-31 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM III_ DISCHARGE VOLUME AREA Table B-1 Page 39 of 80 B-41

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-126\42-35 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME SCRAMAREA CV-305-126\42-39 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23'SOUTH DISCHARGE VOLUME AREA CV-305-126\42-43 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\42-47 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM

_DISCHARGE VOLUME AREA CV-305-126\6-11 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-15 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-19 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-23 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM CV-305-126\46-27 225 RB 23 DISCHARGE VOLUME AREA CRD INLET SCRAM VALVE OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-31 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-35 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-39 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\46-43 CRD INLET SCRAMVALVE 225 RB 23 OC,RX 23- SOUTH SCRAM

,DISCHARGE VOLUME AREA CV-305-126\50-19 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\50-23 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\50-27 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-126\50-31 CRD INLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA Table B-1 Page 40 of 80 B-42

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-126\50-35 CRD INLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1127\02-19 225 RB 23 DSCHRG VOL - TORUS TOP I_ ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\02-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\02-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\02-31 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\02-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-31 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS Table B-1 Page 41 of 80 B-43

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\06-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\10-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\10-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OCRX 23' NW-NORTH SCRAM CV-305-127\1 0-31 225 RB 23 DSCHRG VOL - TORUS TOP I_ _ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-35 225 RB 23 DSCHRG VOL - TORUS TOP I_ I_ ACCESS Table B-1 Page 42 of 80 B-44

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-43 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 0-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 4-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\14-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OCRX 23' NW-NORTH SCRAM CV-305-127\14-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 4-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\114-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 4-27 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CV-305-127\14-31 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD CACCUMULATORS)

CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\14-35 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 4-39 225 RB 23 DSCHRG VOL - TORUS TOP I ._ 1ACCESS Table B-1 Page 43 of 80 B-45

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\14-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\14-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-03 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\18-11 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-31 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\18-35 225 RB 23 DSCHRG VOL - TORUS TOP

___ ___ ___ ___ ___ ___ ___ __ ___ ___ACCESS Table B-1 Page 44 of 80 B-46

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\1 8-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-127\18-51 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD ACCUMULATORS)

CV-305-127\22-03 CRD OUTLET SCRAM VALVE 225 RB 23 OC, RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-07 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-11 225 RB 23 DSCHRG VOL - TORUS TOP I _ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-19 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-27 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-31 225 RB 23 DSCHRG VOL - TORUS TOP I__*CCESS Table B-1 Page 45 of 80 B-47

Oyster Creek Generating Station Unit 1 12QO108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1127\22-35 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-39 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-43 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1127\22-47 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\22-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-127\26-03 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-07 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CV-305-127\.6-11 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-15 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-127\.6-19 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-1127\26-23 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-127\26-27 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-31 225 RB 23 DSCHRG VOL - TORUS TOP I _ACCESS I_

Table B-1 Page 46 of 80 B-48

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-127\26-35 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM D__DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-39 225 RB 23 DSCHRG VOL - TORUS TOP I_ ACCESS CV-305-127\26-43 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-47 225 RB .23 DSCHRG VOL - TORUS TOP ACCESS CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\26-51 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS CV-305-127\30-03 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM

_DISCHARGE VOLUME AREA CV-305-127\30-07 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM

_DISCHARGE VOLUME AREA CV-305-127\30-11 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-15 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-19 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-23 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-27 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-31 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-35 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-39 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\30-43 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM I I_DISCHARGE VOLUME AREA Table B-1 Page 47 of 80 B-49

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION 225 RB 23 OC,RX 23' SOUTH SCRAM CV-305-127\30-47 CRD OUTLET SCRAM VALVE DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\30-51 225 RB 23 DSCHRG VOL - TORUS TOP I _ACCESS CV-305-127\34-03 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-07 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-11 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM

_DISCHARGE VOLUME AREA CV-305-127\34-15 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-19 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

CV-305-1 27\34-23 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-27 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-31 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-35 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\34-39 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CRD OUTLET SCRAM VALVE OCRX 23' SOUTH SCRAM CV-305-127\34-43 225 _____ RB

_____DISCHARGE 23 VOLUME AREA CV-305-127\34-47 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

CRD OUTLET SCRAM VALVE OC,RX 23' NW-NORTH SCRAM CV-305-127\34-51 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS CV-305-127\38-07 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM I _DISCHARGE VOLUME AREA Table B-1 Page 48 of 80 B-50

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-127\38-11 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-15 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-19 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-23 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-27 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-31 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-35 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-39 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-43 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\38-47 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-07 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-11 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-15 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-19 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-23 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-27 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-31 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM

_DISCHARGE VOLUME AREA Table B-1 Page 49 of 80 B-51

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-127\42-35 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-39 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-43 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\42-47 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-11 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-15 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

CV-305-127\46-19 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-23 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-27 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-31 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-35 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23'SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-39 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\46-43 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\50-19 CRD OUTLET SCRAM VALVE 225 RB 23 OC,RX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\50-23 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\50-27 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA CV-305-127\50-31 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH SCRAM DISCHARGE VOLUME AREA Table B-1 Page 50 of 80 B-52

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CV-305-127\50-35 CRD OUTLET SCRAM VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S (CRD ACCUMULATORS)

T-39-2 DIESEL GENERATOR FUEL OIL 862 DG 18 OCDIESEL GEN BLDG 18' 4" STORAGE TANK 8 T-39-3 DIESEL GENERATOR UNIT #1 FUEL OIL 862 DG 23 OC,DIESEL GEN BLDG 23' 0" DAY TAN K T-39-4 DIESEL GENERATOR UNIT #2 FUEL OIL 862 DG 23 OC,DIESEL GEN BLDG 23' 0" DAY TANK T-39-5 M-39-1 COOLING WATER TANK 861 DG 23 OC,DIESEL GEN BLDG 23' 0" T-39-6 M-39-2 COOLING WATER TANK 861 DG 23 OC,DIESEL GEN BLDG 23' 0" EMRV ELECTROMATIC RELIEF VALVE SERIAL 212 DW 46 OC,DRYWELL 46' ELEVATION NO. BY8791 GENERAL EMRV\BY8791 ELECTROMATIC RELIEF VALVE SERIAL 212 DW 46 OC,DRYWELL 46' ELEVATION NO. BY8791 GENERAL SO-305-117\06-11 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 1) ACCUMULATORS)

SO-305-11.7\06-15 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 4) ACCUMULATORS)

SO-305-117\06-19 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 2) ACCUMULATORS)

SO-305-117\06-23 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 3) ACCUMULATORS)

SO-305-117\06-27 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 1) ACCUMULATORS)

SO-305-117\06-31 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 4) ACCUMULATORS)

SO-305-117\06-35 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 2) ACCUMULATORS)

SO-305-1117X06-39 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SO-35-17\_6-3 SOLENOID VALVE(GROUP 3) 225 RB 23 ACCUMULATORS)

SO-305-117\06-43 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 4) ACCUMULATORS)

SO-305-117\30-03 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 2) 1 1 (CRD ACCUMULATORS)

Table B-1 Page 51 of 80 B-53

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-117\30-07 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 3) (CRD ACCUMULATORS)

SO-305-117\30-11 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 1) (CRD ACCUMULATORS)

SO-305-1 17\30-15 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 4) (CRD ACCUMULATORS)

SO-305-1 17\30-19 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 2) (CRD ACCUMULATORS)

SO-305-117\30-23 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 3) (CRD ACCUMULATORS)

SO-305-117\30-27 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23'SOUTH BANK HCU'S SOLENOID VALVE(GROUP 1) (CRD ACCUMULATORS)

SO-305-117\30-31 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 4) (CRD ACCUMULATORS)

SO-305-117\30-35 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 2) (CRD ACCUMULATORS)

SO-305-117\30-39 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 3) (CRD ACCUMULATORS)

SO-305-117\30-43 CHANNEL I SCRAM AIR PILOT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 1) (CRD ACCUMULATORS)

SO-305-117\30-47 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE(GROUP 4) (CRD ACCUMULATORS)

SO-305-117\30-51 CHANNEL I SCRAM AIR PILOT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE(GROUP 2) ACCUMULATORS)

SO-305-11 SO \0-1 9WITHDRAW DIRECTIONAL FLOW CONTROL 2)

SOLENOID VALVE 225 RB RB 23 23 OC,RX 23' N.

ACCUMULATORS)

BANK HCU'S (CRD SO-305-120\02-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\02-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\02-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\02-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

Table B-1 Page 52 of 80 B-54

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\06-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\06-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\06-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

Table B-1 Page 53 of 80 B-55

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\10-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\10-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

S 2 DIRECTIONAL FLOW CONTROL OC,RX 23' N. BANK HCU'S (CRD SO-305-120\14-19 WITHDRAW SOLENOID VALVE 225 RB 23 ACCUMULATORS)

SO-305-120\14-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\14-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD S0-305-120\14-39 WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\14-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD S 2 WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\14-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\18-03 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\18-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

Table B-1 Page 54 of 80 B-56

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\18-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE _ACCUMULATORS)

SO-305-120\18-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD.

WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

DIRECTIONAL FLOW CONTROL SO-305-120\18-43 WITHDRAW 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-120\18-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SO-305-120\18-51 WITHDRAW SOLENOID VALVE DIRECTIONAL FLOW CONTROL _ACCUMULATORS) 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\22-03 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\22-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\22-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\22-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\22-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\.2-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\.2-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

Table B-1 Page 55 of 80 B-57

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\22-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\22-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE _ACCUMULATORS)

SO-305-120\22-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\22-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE 2ACCUMULATORS)

SO-305-120\22-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE _ACCUMULATORS)

SO-305-120\22-51 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\.6-03 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\26-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\26-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\26-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\6-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\6-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\26-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\26-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\6-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTHBANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\6-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\6-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S

_WITHDRAW SOLENOID VALVE I T (CRD ACCUMULATORS)

Table B-1 Page 56 of 80 B-58

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\26-7 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\26-51 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\30-03 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23 SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\30-51 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23'N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\34-03 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE I I (CRD ACCUMULATORS)

Table B-1 Page 57 of 80 B-59

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\34-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRID ACCUMULATORS)

SO-305-120\34-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23'SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-120\34-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-1 20\34-21 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE CRD ACCUMULATORS)

SO-305-120\34-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-120\34-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\34-51 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-120\38-07 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE 2CRD ACCUMULATORS)

SO-305-120\38-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRID ACCUMULATORS)

SO-305-120\38-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE _(CRD ACCUMULATORS)

Table B-1 Page 58 of 80 B-60

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\38-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC, RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23'SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S

'WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-43 DIRECTIONAL FLOWCONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\38-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\ DIRECTIONAL FLOW CONTROL WITHDRAW SOLENOID VALVE 25 RBCRD 23' SOUTH BANK HCU'S OCRXACCUMULATORS)

SO-305-120\42-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE I(CRD ACCUMULATORS)

SO-305-120\42-35 DIRECTIONAL FLOW CONTROL 225 RB 23 C,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23'SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\42-47 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\46-11 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE I (CRD ACCUMULATORS)

Table B-1 Page 59 of 80 B-61

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-120\46-15 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\46-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC, RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

DIRECTIONAL SO-305-120\46-23 WITHDRAW FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\46-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-120\46-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

DIRECTIONAL FLOW CONTROL OCRX 23' SOUTH BANK HCU'S SO-305-12046-3WITHDRAW SOLENOID VALVE 2 23 WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\46-39 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\46-43 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\50-19 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE 2(CRD ACCUMULATORS)

SO-305-120\50-23 DIRECTIONAL FLOW CONTROL 225 RB 23 OC, RX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-120\50-27 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S SO-305-120\50-31 DIRECTIONAL FLOW CONTROL 225 RB 23 OC,RX 23'SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE CR CUULATORS)

WITHDRAW SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-1200-35 DIRECTIONAL FLOW CONTROL 225 RB 23 OCRX 23' SOUTH BANK HCU'S WITHDRAW SOLENOID VALVE ACCUMULATORS)

SO-305-121\02-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N BANK HCU'S (CRD SO35110-3DIRECTIONAL FLOW CONTROL ISR 2 B 2 OCR.X 23' SOUT BANK HCU'S (R SOLENOID VALVE ACCUMULATORS)

WIHRWSOLENOID VALVE _______(R ACCUMULATORS)

SO-305-121\02-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\02-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD

_SOLENOID VALVE I I ACCUMULATORS)

Table B-1 Page 60 of 80 B-62

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\02-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23'N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SO-305-121\06-3SOLENOID VALVE ACCUMULATORS SO-305-121\06-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\06-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCUS (CRD SOLENOID VALVE ACCUMULATORS SO-305-121\10-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

SO-305-121\10-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE I I ACCUMULATORS)

Table B-1 Page 61 of 80 B-63

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\10-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-1211\10-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\10-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

SO-305-121\14-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23'N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-31 DIRECTIONAL FLOW.CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\14-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-03 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

Table B-1 Page 62 of 80 B-64

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\18-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

SO-305-121\18-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

SO-305-121\18-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC, RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\18-51 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\22-03 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\.2-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121 \22-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-12122-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX'23' N. BANK HCU'S (CRD SOLENOID VALVE _ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE 225 _ _ 23 ACCUMULATORS)

SO-305-121\22-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE I I _ACCUMULATORS)

Table B-1 Page 63 of 80 B-65

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID SO-305-121\22-27 SO-305-121\22-31 SO-305-121 \22-35

'T1 N. BANK HCU'S (CRD SO-305-121\22-39 DI ATORS)

DIRECTIONAL FLOW CONTROL INSERT X 23' N. BANK HCU'S (CRD SSOLENOID VALVE JMULATORS)

DIRECTIONAL FLOW CONTROL INSERT ,RX 23' N.

SO-305-12122-47SOLENOID VALVE DIRECTIONAL FLOW CONTROL INSERT SO-305-121 \22-51_ SOLENOID VALVE SO-305-121\26-03 DIRECTIONAL FLOW CONTROL INSERT SOLENOID VALVE DIRECTIONAL FLOW CONTROL INSERT ,RX 23' N. BANK HCU'S (CRD SO-305-12126-0SOLINOID VALVE CUMULATORS)

SO-051212611DIRECTIONAL FLOW CONTROL INSERT ,RX 23' SOUTH BANK HCU'S SOLENOID VALVE

.D ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT ,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE CUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT ,RX 23' N.

SO-305-12126-23SOLENOID VALVE SO-305-121 \26-27 (CRD SO-305-121 \26-31 CONTROL INSERT ,RX 23' SOUTH BANK HCU'S SO-305-121\26-35 0D ACCUMULATORS)

SO-305-121\26-39 DIRECTIONAL FLOW CONTROL INSERT ;,RX 23' N. BANK HCU'S (CRD Table B-1 Page 64 of 80 B-66

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO_305-.121\26-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\26-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121T6-51 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\30-03 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\30-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\30-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _ (CRD ACCUMULATORS)

SO-305-121\30-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE CRD ACCUMULATORS)

SO-305-121\30-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC, RX 23' SOUTH BANK HCU'S SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\30-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE __(CRD ACCUMULATORS)

SO-305-121\30-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID

_(CRD VALVE ACCUMULATORS)

SO-305-121\30-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\30-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121 DIRECTIONAL SOLENOID FLOW CONTROL INSERT VALVE 225 RB 23 OCRX 23' SOUTH BANK HCU'S CRD ACCUMULATORS)

SO-305-121\30-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\30-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\30-51 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' N. BANK HCU'S (CRD SOLENOID VALVE ACCUMULATORS)

SO-305-121\34-03 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE I (CRD ACCUMULATORS)

Table B-1 Page 65 of 80 B-67

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\34-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121 \34-1 5 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\34-1 9 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE 2CRD ACCUMULATORS)

SO-305-121\34 .-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23'SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

OEOI SO-305-121\34-27 DIRECTIONAL AVFLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE _ (CRD ACCUMULATORS)

SO-305-121\34-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\34-51 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\34-51 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

Table B-1 Page 66 of 80 B-68

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\38-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\38-47 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-07 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\42-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE 2(CRD ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT OC,RX 23' SOUTH BANK HCU'S SO-305-121\42-39 SOLENOID VALVE (CRD ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

DIRECTIONAL FLOW CONTROL INSERT OC,RX 23' SOUTH BANK HCU'S SSOLENOID VALVE 2 R 2 (CRD ACCUMULATORS)

Table B-1 Page 67 of 80 B-69

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SO-305-121\46-11 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _ (CRD ACCUMULATORS)

SO-305-121\46-15 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\46-39 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\46-43 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S

'SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\50-19 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _(CRD ACCUMULATORS)

SO-305-121\50-23 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\50-27 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE _CRD ACCUMULATORS)

SO-305-121\50-31 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OC,RX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

SO-305-121\50-35 DIRECTIONAL FLOW CONTROL INSERT 225 RB 23 OCRX 23' SOUTH BANK HCU'S SOLENOID VALVE (CRD ACCUMULATORS)

MAIN STEAM LINE'B' OUTLET OCTRUNION ROOM MAIN STEAM V-1-10 ISOLATION VALVE(NS04-B) 411 TB 23 ISOLATION VALVE (MSIV) NS-04B V-1-106 MAIN STEAM LINE 'A' DRAIN VALVE 411 DW 23 OC DRYWELL 23' GENERAL ALL AREAS V-1-107 MAIN STEAM LINE 'B' DRAIN VALVE 411 DW 23 OC,DRYWELL 23' GENERAL ALL I _AREAS Table B-1 Page 68 of 80 B-70

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-1-110 MAIN STEAM LINE DRAIN VALVE 411 TB 23 OC,TRUNION ROOM GENERAL ALL AREAS V-1-160 SAFETY RELIEF VALVE NR28D (SOUTH 411 DW 46 OC,DRYWELL 46' ELEVATION

_HEADER) GENERAL SAFETY RELIEF VALVE NR28E (SOUTH OCDRYWELL 46' ELEVATION V--161 ADER)411 DW 46 GENERAL V-1-162 SAFETY RELIEF VALVE NR28F (SOUTH 411 DW 46 OC,DRYWELL 46' ELEVATION HEADER) GENERAL V-1-163 SAFETY RELIEF VALVE NR28G (SOUTH 411 DW 46 OCDRYWELL 46' ELEVATION HEADER) GENERAL V-1-164 SAFETY RELIEF VALVE NR28H (NORTH 411 DW 46 OC,DRYWELL 46' ELEVATION HEADER) GENERAL V-1-165 SAFETY RELIEF VALVE NR28J (NORTH 411 DW 46 OCDRYWELL 46' ELEVATION HEADER) GENERAL V-1-166 SAFETY RELIEF VALVE NR28K (NORTH 411 DW 46 OC,DRYWELL 46' ELEVATION HEADER) GENERAL V-1-167 SAFETY RELIEF VALVE NR28L (NORTH 411 DW 46 OC,DRYWELL 46' ELEVATION HEADER) GENERAL V-i-167 V-1-168 HEADER)RELIEF VALVE NR28M (NORTH SAFETY 411 411 DW_DW 46 OC,DRYWELL GENERAL 46' ELEVATION V-1-173 ELECTROMATIC RELIEF VALVE NR108- 212 DW 46 OC,DRYWELL 46' ELEVATION HEADER)

A(SOUTH GENERAL V-1-174 V-1-174 ELECTROMATIC B(SOUTH HEADER)RELIEF VALVE NR108- 212 212 DW_DW 46 4 OC,DRYWELL GENERAL 46' ELEVATION V-1-175 ELECTROMATIC RELIEF VALVE NR108- 212 DW 46 OC,DRYWELL 46' ELEVATION C(NORTH HEADER) GENERAL V-1-176 ELECTROMATIC RELIEF VALVE NR108- 212 DW 46 OCDRYWELL 46' ELEVATION D(NORTH HEADER) GENERAL V-1-177 ELECTROMATIC RELIEF VALVE NR108- 212 DW 46 OCDRYWELL 46' ELEVATION E(SOUTH HEADER) _GENERAL NORTH SCRAM DISCHARGE HDR VENT OC,RX 23' NW-NORTH SCRAM V-15-119 VALVE(NC51-A) 225 RB 23 DSCHRG VOL - TORUS TOP

_ACCESS V-1 5-120 SOUTH SCRAM DISCHARGE HDR VENT 225 RB 23 OC,RX 23' SOUTH SCRAM VALVE(NC53-A) _DISCHARGE VOLUME AREA Table B-1 Page 69 of 80 B-71

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-15-121 SOUTH SCRAM DISCHG VOLUME 225 RB 23 OCRX 23' SOUTH SCRAM DRAIN VALVE(NC50-A) DISCHARGE VOLUME AREA NORTH SCRAM DISCHG VOLUME OC,RX 23' NW-NORTH SCRAM V-15-133 DRAIN VALVE(NC52-A) 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS V-15-134 SOUTH SCRAM DISCHG VOLUME 225 RB 23 OC,RX 23' SOUTH SCRAM DRAIN VALVE(NC50-B) I DISCHARGE VOLUME AREA NORTH SCRAM DISCHG VOLUME OC,RX 23' NW-NORTH SCRAM V-15-135 DRAIN VALVE(NC52-B) 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS NORTH SCRAM DISCHARGE HDR VENT OC,RX 23' NW-NORTH SCRAM V-1 5-136 VALVE(NC51-B) 225 RB 23 DSCHRG VOL - TORUS TOP ACCESS V-15-137 SOUTH SCRAM DISCHARGE HDR VENT 225 RB 23 OC,RX 23' SOUTH SCRAM VALVE(NC53-B) DISCHARGE VOLUME AREA V-16-1 CU INLET ISOLATION VALVE FROM 215 DW 46 OC,DRYWELL 46' ELEVATION REACTOR VESSEL _GENERAL V-16-133 V-16-1 TEST BARRIER VALVE 215 DW 46 OCDRYWELL 46' ELEVATION GENERAL V-16-134 DRAIN VALVE TO HEADER 'A' (L.C.) 215 DW 46 OC,DRYWELL 46' ELEVATION GENERAL V-16-135 DRAIN VALVE TO HEADERA' 215 DW 46 OC,DRYWELL 46' ELEVATION GENERAL V-16-136 TEST CONNECTION FOR VALVE V 215 DW 46 OC,DRYWELL 46' ELEVATION 1(L.C.) GENERAL V-16-137 TEST CONNECTION FOR VALVE V-16-1 215 DW 46 OCDRYWELL 46' ELEVATION GENERAL V-16-14 CLEAN-UP INLET ISOLATION VALVE 215 RB 51 OCRX 51' CLEANUP SYSTEM

,VALVE NEST (ELEV = 64)

V-16-140 TEST VALVE INSIDE DRYWELL 215 DW 46 OCDRYWELL 46' ELEVATION

_GENERAL V-16-141 TEST VALVE INSIDE DRYWELL 215 DW 46 OCDRYWELL 46' ELEVATION

_GENERAL V-16-142 DRAIN TO HEADER A' 215 DW 23 OC, DRYWELL 23' GENERAL ALL

_AREAS Table B-1 Page 70 of 80 B-72

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-16-143 DRAIN TO HEADER A'215 DW 23 OC,DRYWELL 23' GENERAL ALL AREAS V-16-144 INLET VALVE TO V-16-0030 215 RB 51 OCRX 51' SAMPLE SINK AREA V-16-145 DRAIN AND TEST VALVE FOR V-16-0030 215 RB 51 OCRX 51' SAMPLE SINK AREA V-16-2 INLET ISOLATION VALVE TO CLEANUP 215 RB 51 OCRX 51' CLEANUP SYSTEM AUXILIARY PUMP VALVE NEST (ELEV = 64)

V-16-221 H.P. VENT VALVE AND T.C. 215 RB 51 OCRX 51' CLEANUP SYSTEM VALVE NEST (ELEV = 64)

V-16-222 H.P. VENT VALVE AND T.C. 215 RB 51 OCRX 51' CLEANUP SYSTEM VALVE NEST (ELEV = 64)

V-16-223 H.P. VENT VALVE AND T.C. (LOCKED 215 RB 51 OC,RX 51' CLEANUP SYSTEM CLOSED) VALVE NEST (ELEV = 64)

V-16-224 VENT VALVE 215 RB 51 OCRX 51' SAMPLE SINK AREA V-16-287 RW CLEANUP CHEMICAL FLUSH 215 DW 23 OCDRYWELL 23' GENERAL ALL CONNECTION OUTLET VALVE AREAS V-16-288 RW CLEANUP CHEMICAL FLUSH 215 DW 23 OCDRYWELL 23' GENERAL ALL CONNECTION OUTLET VALVE AREAS V-16-289 RW CLEANUP CHEMICAL FLUSH 215 DW 46 OCDRYWELL 46' ELEVATION CONNECTION INLET VALVE GENERAL V-16-290 RW CLEANUP CHEMICAL FLUSH 215 DW 46 OCDRYWELL 46' ELEVATION CONNECTION INLET VALVE GENERAL V-16-3 AUXILIARY PUMP LINE DRAIN VALVE 215 RB 51 OCRX 51' CLEANUP SYSTEM ON 6-ND-1 TO RBEDT VALVE NEST (ELEV = 64)

V-16-30 RELIEF TO TORUS TELL-TALE DRAIN 215 RB 51 OCRX 51' CLEANUP FILTER VALVE SLUDGE PUMP HALLWAY ND-12 V-16-319 ISOL'N VALVE OFF CLEAN-UP RELIEF 215 RB -19 OCRX -19' TOP OF TORUS SAN LINE TO TORUS V-16-320 ISOL'N VALVE OFF CLEAN-UP RELIEF 215 RB -19 OC, RX -19' TOP OF TORUS S/W LINE TO TORUS V-16-4 AUXILIARY PUMP LINE DRAIN VALVE 215 RB 51 OC,RX 51' CLEANUP SYSTEM ON 6-ND-1 TO RBEDT VALVE NEST (ELEV = 64)

V-16-61 REGENERATIVE HT EXCHANGER 215 RB 51 OCRX 51' CLEANUP SYSTEM OUTLET TO REACTOR VESSEL I _VALVE NEST (ELEV = 64)

Table B-1 Page 71 of 80 B-73

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-16-62 CLEANUP DEMINERALIZER SYS 215 DW 46 OCDRYWELL 46' ELEVATION RETURN CHECK VALVE GENERAL V-16-63 REGENERATIVE HT EXCHANGER 215 DW 23 OCDRYWELL 23' GENERAL ALL OUTLET TO REACTOR (L.O.) AREAS REGENERATIVE HT EXCHANGER OC,RX 51' CLEANUP SYSTEM HEAT V-16-64 OUTLET LINE DRAIN VALVE 215 RB 51 EXCHANGER RM (REGEN=ND03 NON-REGEN=ND04)

REGENERATIVE HT EXCHANGER OC,RX 51' CLEANUP SYSTEM HEAT V-16-65 OUTLET LINE DRAIN(L.C.) 215 RB 51 EXCHANGER RM (REGEN=ND03 NON-REGEN=ND04)

DEMINERALIZER LINE RELIEF VALVE OC,RX 51' CLEANUP SYSTEM V-16-76 TO SUPPRESSION POOL 215 RB 51 PUMP AREA (ND02A & ND02B +

AUX PUMP)

V-16-84 CHECK VALVE DISCHARGE TO 215 RB 51 OCRX 51' GENERAL ALL AREAS SUPPRESSION POOL V-1-7 MAIN STEAM LINE'A' OUTLET 411 DW 23 OCDRYWELL 23' GENERAL ALL ISOLATION VALVE(NS03-A) AREAS V-17-1 SDC LOOP 'A' PUMP SUCTION VALVE 214 RB 38 OCRX 38' SHUTDOWN COOLING PUMP ROOM EAST V-17-19 SHUTDOWN COOLING DRYWELL INLET 214 DW 46 OC,DRYWELL 46' ELEVATION ISOLATION VALVE GENERAL V-17-2 SDC LOOP 'B' PUMP SUCTION VALVE 214 RB 38 OCRX 38' SHUTDOWN COOLING PUMP ROOM EAST V-17-20 INLET HEADER DRAIN VALVE TO 214 RB 38 OCRX 38' SHUTDOWN COOLING RBEDT PUMP ROOM EAST SHUTDOWN COOLING LOOP 'A' OC,RX 51' S/D COOLING HEAT V-1 7-205 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

SHUTDOWN COOLING LOOP 'B' OC,RX 51' S/D COOLING HEAT V-17-206 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

Table B-1 Page 72 of 80 B-74

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SHUTDOWN COOLING LOOP 'C' OC,RX 51' S/D COOLING HEAT V-1 7-207 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

SDC LOOP'C' OUTLET HEADER VENT OC,RX 51' S/D COOLING HEAT V-1 7-208 VALVE(L.C.) 214 RB 51 EXCHANGER RM (NU01A & NUO1C)

SDC LOOP'C' OUTLET HEADER VENT OC,RX 51' S/D COOLING HEAT V-17-209 VALVE(L.C.) 214 RB 51 EXCHANGER RM (NU01A & NUOIC)

V-17-21 INLET HEADER CONDENSATE 214 RB 38 OC,RX 38' SHUTDOWN COOLING FILL/DRAIN TO RBEDT PUMP ROOM EAST SDC LOOP'B' OUTLET HEADER VENT OCRX 51' S/D COOLING HEAT V-17-210 VALVE(L.C.) 214 RB 51 EXCHANGER RM (NU01A & NUO1C)

SDC LOOP'B' OUTLET HEADER VENT OC,RX 51' S/D COOLING HEAT V-17-211 VALVE(L.C.) 214 RB 51 EXCHANGER RM (NU01A & NU01C)

SDC LOOPA' OUTLET HEADER VENT OC,RX 51' S/D COOLING HEAT V-17-212 VALVE 214 RB 51 EXCHANGER RM (NU01A & NU0IC)

SDC LOOP'A' OUTLET HEADER VENT OC,RX 51' S/D COOLING HEAT V-17-213 VALVE(L.C) 214 RB 51 EXCHANGER RM (NU01A & NU0IC)

V-17-54 SHUTDOWN COOLING DRYWELL 214 DW 46 OC,DRYWELL 46' ELEVATION OUTLET ISOLATION VALVE GENERAL SHUTDOWN COOLING LOOP 'A' OC,RX 51' S/D COOLING HEAT V-17-55 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

SHUTDOWN COOLING LOOP 'B' OC,RX 51' S/D COOLING HEAT V-17-56 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

SHUTDOWN COOLING LOOP 'C' OC,RX 51' S/D COOLING HEAT V-17-57 OUTLET ISOLATION VALVE 214 RB 51 EXCHANGER RM (NU01A & NU01C)

Table B-1 Page 73 of 80 B-75

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-1-8 MAIN STEAM LINE'B' OUTLET 411 DW 23 OCDRYWELL 23' GENERAL ALL ISOLATION VALVE(NS03-B) AREAS MAIN STEAM LINE'A' OUTLET OCTRUNION ROOM MAIN STEAM V-1-9 ISOLATION VALVE(NS04-A) 411 TB 23 ISOLATION VALVE(MSIV) NS-04A CORE SPRAY SYSTEM OC,RX -19' CORE SPRAY PUMP V-20-1 COND.STORAGE TANK SUPPLY 212 RB -19 ROOM NORTH WEST (NZ01A &

ISOLATION VALVE NZ01C)

V-20-12 CORE SPRAY PUMP DISCHARGE 212 RB 51 OCRX 51' INSTRUMENT RACK RK-VALVE(SYSTEM I) _03 AREA V-20-15 CORE SPRAY SYS.I PARALLEL 212 RB 51 OC,RX 51' INSTRUMENT RACK RK-ISOLATION VALVE 03 AREA V-20-17 CORE SPRAY SYS1 ISOLATION VALVE 212 DW 46 OC,DRYWELL 46' ELEVATION (INSIDE DRYWELL) GENERAL V-20-2 CONDENSATE TRANSFER VALVE TO 212 RB -19 OCRX -19' CORE SPRAY PUMP NZ01-B SUCTION(L.C.) ROOM WEST (NZ01 B & NZ01 D)

V-20-21 CORE.SPRAY SYS.2 PARALLEL 212 RB 75 OCRX 75' CLEANUP CONTROL ISOLATION VALVE _PRECOAT TANK AREA V-20-23 CORE SPRAY SYS2 ISOLATION VALVE 212 DW 75 OCDRYWELL 75' GENERAL ALL (INSIDE DRYWELL) _AREAS V-20-250 CS PUMP NZ01-C SEAL WATER VENT 212 RB -19 OCRX -19' CORE SPRAY PUMP VALVE _ROOM WEST (NZ01 B & NZ01 D)

V-20-251 CORE SPRAY SYSTEM II FLOW 212 RB 75 OCRX 75' CLEANUP CONTROL REGULATING THRU ORIFICE PRECOAT TANK AREA V-20-252 CORE SPRAY SYS.II RECIRC. LINE 212 RB 75 OCRX 75' CLEANUP CONTROL ISOLATION VALVE PRECOAT TANK AREA PUMP NZ01-A SUCTION VALVE FROM OC,RX -19' CORE SPRAY PUMP V-20-3 TORUS 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

MAIN PUMP NZ01-C SUCTION VALVE OC,RX -19' CORE SPRAY PUMP V-20-32 FROM TORUS 212 RB -19 ROOM NORTH WEST (NZ01A &

I NZ01C)

PUMP NZ01-D SUCTION VALVE FROM OC,RX -19' CORE SPRAY PUMP V-20-33 TORUS 212 RB -19 ROOM WEST (NZ01 B & NZ01 D)

Table B-1 Page 74 of 80 B-76

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CONDENSATE TRANSFER SUPPLY TO OC,RX -19' CORE SPRAY PUMP V-20-34 NZ01-C MAIN PUMP ISOLATION 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

V-20-35 CONDENSATE TRANSFER TO PUMP 212 RB 19 OCRX -19' CORE SPRAY PUMP NZ01-D SUCTION(L.C.) I ROOM WEST (NZ01 B & NZ01 D)

V-20-4 PUMP NZ01-B SUCTION VALVE FROM 212 RB -19 OCRX -19' CORE SPRAY PUMP TORUS ROOM WEST (NZ01 B & NZ01 D)

V-20-40 CORE SPRAY SYS.I PARALLEL 212 RB 51 OC,RX 51' INSTRUMENT RACK RK-ISOLATION VALVE 03 AREA V-2041 CORE SPRAY SYS.2 PARALLEL 212 RB 75 OCRX 75' CLEANUP CONTROL ISOLATION VALVE _PRECOAT TANK AREA CST SUPPLY TO MAIN PUMP NZ01-A OC,RX -19' CORE SPRAY PUMP V-20-5 ISOLATION VALVE 212 RB -19 ROOM NORTH WEST (NZ01A &

NZ01C)

CONTAINMENT SPRAY SYS 2 DRYWELL OC,RX 23' AREA WEST OF V-21-5 SPRAY DISCHARGE VALVE 241 RB 23 RAILROAD AIRLOCK CONTAINMENT SPRAY SYS 1 PUMP 51B OC,RX -19' CONTAINMENT SPRAY V-21-7 SUCTION VALVE 241 RB -19 PUMP ROOM NORTH EAST (1-1 & 1-2)(1-6 SUMP CONTAINMENT ISOLATION FOR TORUS OC,RX -19' CONTAINMENT SPRAY V-21-75 WATER CLEAN-UP 241 RB -19 PUMP ROOM SOUTH EAST (1-3 & 1-4)(1-7 SUMP CONTAINMENT ISOLATION FOR TORUS OC,RX -19' CONTAINMENT SPRAY V-21-76 WATER CLEAN-UP 241 RB -19 PUMP ROOM SOUTH EAST (1-3 & 1-4)(1-7 SUMP V-21-77 CONTAINMENT ISOLATION FOR TORUS 241 RB 23 OC,RX 23' SOUTHEAST ACCESS WATER CLEAN-UP AREA - MCC DC-1 V-21-78 CONTAINMENT ISOLATION FOR TORUS 241 RB 23 OC, RX 23' SOUTHEAST ACCESS WATER CLEAN-UP I AREA - MCC DC-1 V-23-258 ISOLATION FOR N2 MAKE-UP TO 242 RB 75 OCRX 75' WEST CONTROL AREA DRYWELL I V-23-259 ISOLATION VLV FOR V-23-16 TORUS N2 242 RB 23 OC,RX 23' SOUTH SCRAM

_MAKEUP DISCHARGE VOLUME AREA Table B-1 Page 75 of 80 B-77

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION N2 PURGE HEADER TRAP Y-23-2 INLET OC,RX -19' CONTAINMENT SPRAY V-23-263 VALVE 242 RB -19 PUMP ROOM NORTH EAST (1-1 & 1-2)(1-6 SUMP NITORGEN SUPPLY VALVE TO OC,RX 51' NE ACCESS CORRIDOR V-23-264 SHUTDOWN COOLING HX ROOM 242 RB 51 QA/QC EQUIPMENT STORAGE CAGE NITROGEN SUPPLY VALVE TO SDC OC,RX 51' S/D COOLING HEAT V-23-265 HEAT EXCHANGER ROOM ISOL. VALVE 242 RB 51 EXCHANGER RM (NU01A & NU01C)

V-2-35 FEEDWATER SYSTEM REACTOR 422 DW 23 OC,DRYWELL 23' GENERAL ALL ISOLATION VALVE AREAS V-2-36 FEEDWATER SYSTEM REACTOR 422 DW 23 OCDRYWELL 23' GENERAL ALL ISOLATION VALVE AREAS V-23-70 N2 SOLENOID VALVE FOR TIP PURGE 242 RB 33 OC,RX 33' TIP SHIELD RM #3 & #4 TO INDEXERS SHIELD AREA V-25-21 REACTOR HEAD VENT VALVE 221 DW 95 OC,DRYWELL 95'GENERAL ALL AREAS V-25-22 REACTOR HEAD VENT VALVE 221 DW 95 OC,DRYWELL 95' GENERAL ALL

_AREAS V-25-23 REACTOR HEAD VENT VALVE 221 DW 95 DRYWELL 95'GENERAL ALL

____ ____ ___ _ __ _______ ___AREAS V-26-1 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS ES/E BREAKER (NORTH SIDE ACCESS HATCH)

V-26-10 TORUS TO DRYWELL VACUUM 243 RB -19 OC,RX -19' TOP OF TORUS WN/W BREAKER I V-26-11 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS N/W BREAKER V-26-12 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS NAN BREAKER V-26-13 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS N/E BREAKER V-26-14 TORUS TO DRYWELL VACUUM 243 RB -19 OC,RX -19' TOP OF TORUS N/E BREAKER V-26-15 TORUS TO REACTOR BUILDING 243 RB 23 OCRX 23' TORUS TO RX BLDG

-VACUUM BREAKER VALVE I_ IVACUUM BREAKERS AREA Table B-1 Page 76 of 80 B-78

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-26-16 RX BUILDING TO TORUS AIR 243 RB 23 OCRX 23' TORUS TO RX BLDG OPERATED VACUUM BREAKER VACUUM BREAKERS AREA V-26-17 TORUS TO REACTOR BUILDING 243 RB 23 OC,RX 23' TORUS TO RX BLDG

_VACUUM BREAKER VALVE VACUUM BREAKERS AREA V-26-18 RX BUILDING TO TORUS AIR 243 RB 23 OCRX 23' TORUS TO RX BLDG OPERATED VACUUM BREAKER VACUUM BREAKERS AREA V-26-2 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS ES/E BREAKER (NORTH SIDE ACCESS HATCH)

V-26-3 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS S/E BREAKER V-26-4 TORUS TO DRYWELL VACUUM 243 RB -19 OCRX -19' TOP OF TORUS S/E BREAKER V-26-5 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS SiW BREAKER V-26-6 TORUS TO DRYWELL VACUUM 243 RB -19 OC,RX -19' TOP OF TORUS S/V BREAKER TORUS TO DRYWELL VACUUM OC, RX -19' TOP OF TORUS S/W V-26-7 BREAKER 243 RB -19 (SOUTH SIDE ACCESS HATCH)

TORUS TO DRYWELL VACUUM OC,RX -19' TOP OF TORUS WSIW V-26-8 BREAKER 243 RB -19 (SOUTH SIDE ACCESS HATCH)

V-26-9 TORUS TO DRYWELL VACUUM 243 RB -19 OC, RX -19' TOP OF TORUS WNIW BREAKER FEEDWATER ISOLATION CHECK VALVE OCTRUNION ROOM FEEDWATER V-2-71 TO REACTOR 422 TB 23 CHECK VALVE V-2-71 AREA V-27-1 R.B. DRYWELL VENTILATION 822 RB -19 OC,RX -19' TOP OF TORUS EN/E ISOLATION VALVE V-27-2 R.B. DRYWELL VENTILATION 822 RB -19 OC,RX -19' TOP OF TORUS EN/E ISOLATION.VALVE V-27-3 DRYWELL PURGE ISOLATION VALVE 822 RB 75 C RX 75' WEST CONTROL AREA V-27-4 DRYWELL PURGE ISOLATION VALVE 822 RB 75 OC,RX 75'WEST CONTROL AREA Table B-1 Page 77 of 80 B-79

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V-28-1 RB VENTILATION ISOLATION VALVE TO 822 RB 119 OC,RX 119' WEST FLOOR AREA EL.119-3 V-28-10 RB VENTILATION ISOLATION VALVE TO 822 RB 75 OC,RX 75' CLEANUP VALVE AISLE EL.75-3 ESW SYSTEM 1 ISOLATION AT CSHX OC,RX 23' NORTH BANK V-3-1119 532 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

ESW I/SERVICE WATER CROSS- OC,RX 23' NORTH BANK V-3-1120 CONNECT ISOLATION VLV 532 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

AIR-OPERATED REACTOR HEAD OC,RX 75' EMRGNCY CONDENSER V-31-2 COOLING ISOLATION VALVE 216 RB 75 RETURN VALVE AREA V-31-5 REACTOR HEAD COOLING FLOW INLET 216 RB 119 OC,RX 119' CAVITY VALVE TO REACTOR REACTOR HEAD COOLING SUPPLY TO OC,RX 75' EMRGNCY CONDENSER V-31-6 RX ISOLATION VALVE 216 RB 75 RETURN VALVE AREA V-36-47 ALTERNATE SUPPLY TO DG NO.1 ISOL 862 DG 23 OC,DIESEL GEN BLDG 23' 0" VALVE V-36-48 ALTERNATE SUPPLY TO DG NO.2 562 DG 23 OC,DIESEL GEN BLDG 23' 0" ISOLATION VALVE V-3-65 ESW PUMP 1-4 (52D) DISCHARGE 532 Is 6 OCINTAKE STRUCTURE 6 FT CHECK VALVE ELEVATION V-3-66 ESW PUMP 1-3 (52C) DISCHARGE 532 Is 6 OCINTAKE STRUCTURE 6 FT CHECK VALVE I 6 ELEVATION V-3-67 ESW PUMP 1-2 (52B) DISCHARGE 532 is 6 OCINTAKE STRUCTURE 6 FT CHECK VALVE ELEVATION V-3-68 ESW PUMP 1-1 (52A) DISCHARGE 532 is 6 OC,INTAKE STRUCTURE 6 FT CHECK VALVE ELEVATION FT-IA0060AFT-IA006OA1 HI PRESSURE OC,RX 23' NW-NORTH SCRAM V-37-1 SIDE ROOT VALVE 223 RB 23 DSCHRG VOL - TORUS TOP ACCESS Table B-1 Page 78 of 80 B-80

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION CONTAINMENT SPRAY HTEXCHG 1-1 & OC,RX 23' NORTH BANK V-3-88 1-2 OUTLET VALVE 532 RB 23 CONTAINMENT SPRAY HEAT EXCHANGERS (1-1 &1-2)

V-39-10 FUEL OIL TRANSFER PUMPS SUCTION 862 DG 23 OCDIESEL GEN BLDG 23' 0" VALVE V-39-106 FUEL OIL SUPPLY ISOLATION VALVE 862 DG 23 OC,DIESEL GEN BLDG 23' 0" V-39-107 #2 DG FUEL OIL SYSTEM NORMAL 862 DG 23 OC,DIESEL GEN BLDG 23' 0" SUPPLY ISOLATION VALVE V-39-109 EDG1 PRIMING PUMP SUCTION VALVE 861 DG 23 OCDIESEL GEN BLDG 23' 0" V-39-11 FUEL PUMP (P-39-18) SUCTION 862 DG 23 OC,DIESEL GEN BLDG 23' 0" EMERGENCY SHUTOFF VALVE V-39-110 EDG1 PRIMING PUMP DISCHARGE 861 DG 23 OCDIESEL GEN BLDG 23' 0" VALVE V-39-111 EDG2 PRIMING PUMP SUCTION VALVE 861 DG 23 OCDIESEL GEN BLDG 23' 0" V-39-14 CIRC, TURBO & TURBO BACKUP 861 DG 23 OC,DIESEL GEN BLDG 23' 0"

.PUMPS SUCTION VALVE V-39-16 AIR BOX DRAIN VALVE 861 DG 23 OC,DIESEL GEN BLDG 23' 0" V-39-17 EXTERNAL SUPPLY SHUTOFF VALVE 862 DG 18 OCDIESEL GEN BLDG 18' 4" V-39-18 EXTERNAL SUPPLY SHUTOFF VALVE 862 DG 18 OCDIESEL GEN BLDG 18' 4" V-39-19 EXTERNAL OIL SUPPLY CHECK VALVE 862 DG 18 OCDIESEL GEN BLDG 18' 4" V-39-2 ISOLATION VALVE FOR TANK T-39-002 862 DG 18 OC,DIESEL GEN BLDG 18' 4" OUTLET V-39-20 EXTERNAL OIL SUPPLY CHECK VALVE 862 DG 18 OC,DIESEL GEN BLDG 18' 4" V-39-3 FUEL OIL TRANSFER PUMPS SUCTION 862 DG 23 OC,DIESEL GEN BLDG 23' 0" VALVE _

V-39-41 DG FUEL DAY TANK TRANSFER PUMP 862 DG 23 OC,DIESEL GEN BLDG 23' 0" P-39-016 DISCHARGE I Table B-1 Page 79 of 80 B-81

Oyster Creek Generating Station Unit 1 12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION DF FUEL DAY TANK TRANSFER PUMP P 862 DG 23 OC, DIESEL GEN BLDG 23' 0" V-39-42 39-015 DISCHARGE Table B-1 Page 80 of 80 B-82

12QO108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Table B-2. Base List 2 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SPENT FUEL POOL WATER NORTH FLOOR AREA IN0010 HI TEMPERATURE 251 RB 119 NORTH WALL (RH11811)

CONTROLLER I MEASURE FLOW TO FUEL NORTHWEST SIDE FE-3A POOL CLEANUP RETURN 251 RB 75 DIFFUSERS MEASURE FLOW TO FUEL ENTRANCE TO FI-3A POOL CLEANUP RETURN 251 RB 75 INSTRUMENT RACK DIFFUSERS RK01 LI SPENT FUEL STORAGE NORTH OF FUEL POOL 169 POOL LEVEL INDICATOR L118 SKIMMER SURGE NORTH OF FUEL POOL 17 TANK'A'FUEL POOL LEVEL 251 RB 119 INDICATOR I SPENT FUEL POOL HI NORTH FLOOR AREA LWATER LEVEL SWITCH (RH11811)

SPENT FUEL POOL LOW NORTH FLOOR AREA WATER LEVEL SWITCH (RH11811)

SKIMMER SURGE TANK NORTH FLOOR AREA LS-55A WATER LEVEL LOW 251 RB 119 PANEL ER9 (RHl1811)

SWITCH SKIMMER SURGE TANK LO- NORTH FLOOR AREA LS-55B LO WATER LEVEL SWITCH 251 RB 119 PANEL ER9 (RH1 1811)

SKIMMER SURGE TANK NORTH FLOOR AREA LSH-54 WATER LEVEL HIGH 251 RB 119 PANEL ER9 (RHl1811)

SWITCH AUGMENTED SPENT FUEL ASFP HEAT H-18-1C POOL HEAT 251 RB 75 EXCHANGERS/PUMPS EXCHANGER(NN02-C) I AREA(RFJ18HM)

SPENT FUEL POOL FUEL POOL HEAT P-18-1A COOLING PUMP (NN01-A) 251 RB 75 EXCHANGERS/PUMPS(

RFH18PM)

SPENT FUEL POOL FUEL POOL HEAT P-18-1B COOLING PUMP (NN01-B) 251 RB 75 EXCHANGERS/PUMPS(

I I_ RFH18PM)

SPENT SPENT FUEL STORAGE NORTH OF REACTOR FUEL POOL (SEE SYSTEM 161) 251 RB 119 CAVITY (RHB18TM)

POOL SKIMMER SURGE TANK'A' NORTH SIDE OF FUEL T-18-1A FOR SPENT FUEL 251 RB 119 POOL (RHH18TM)

,STORAGE POOL SKIMMER SURGE TANK'B' NORTH SIDE OF FUEL T-18-1B FOR SPENT FUEL 251 RB 119 POOL (RHI18TM)

STORAGE POOL Table B-2 Page 1 of 4 B-83

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION SPENT FUEL POOL SPENT FUEL POOL COOLING SYSTEM-PIPING COOLING SKIMMER SURGE TANK ASFP HEAT V-18-1 DRAIN VALVE 'A' 251 RB 75 EXCHANGERS/PUMPS I AREA(RFJ 18VM)

V FUEL POOL CLG TO AUG 251 RB 75 WEST CONTROL AREA 116 SYS ISOLATION VALVE (RFG 18VM)

V FE-0003A LINE DRAIN 251 RB 75 NORTHWEST SIDE V FE-0003A LINE DRAIN 251 RB 75 NORTHWEST SIDE 1202 VALVE V FE-0003A LINE DRAIN NORTHWEST SIDE 1203 VALVE V FE-0003A LINE DRAIN 251 RB 75 NORTHWEST SIDE 1204 VALVE V FI-0003A HIGH SIDE BLOCK 251 RB 75 NORTHWEST SIDE 1205 VALVE ______ _ _ _ _ _ _ _ _

V FI-0003A CROSS CONNECT RBNORTHWEST SIDE 1206 VALVE V FI-0003A LOW SIDE BLOCK 251 RB 75 NORTHWEST SIDE 1207 VALVE V FI-0003A LO PRESSURE 251 RB 75 NORTHWEST SIDE 1215 SIDE ISOLATION VALVE V FI-0003A HI SIDE ISOLATION NORTHWEST SIDE 1216 VALVE AUGMENTED SPENT FUEL ASEP HEAT V-18-2 POOL SYSTEM INLET 251 RB 75 EXCHANGERS/PUMPS VALVEIEAREA(RFJ18VM)

V-18-24 FUEL STORAGE POOL 251 RB 75 NORTHWEST SIDE 1RECIRC. VALVE251B 7 RECIRC VALVE TO FUEL FUEL POOL HEAT V-18-25 POOL RE__POLCHECK VALVE

DIFFUSERM 251 __ RB 75 EXCHANGERS/PUMPS(

VLEAE(F18RFH18VM)

SPENTFUEL STORAGE NORTH SIDE OF FUEL V-1 8-26 251 RB 75 POOL RECIRC VALVE TO FUEL FUEL POOL HEAT V-18-27 POOL DIFFUSER'B' 251 RB 75 EXCHANGERS/PUMPS(

.___I_ I RFH18VM)

V-18-28 SPENT FUEL STORAGE 251 RB 75 NORTH SIDE POOL CHECK VALVE POOL SFP COOLING PUMP (NNFU FUEL POOL HEAT V-18-3 A) SUCTION ISOLATION 251 RB 75 EXCHANGERS/PUMPS(

VALVE RFH18VM)

SFP COOLING PUMP (NNO1 FUEL POOL HEAT V-18-4 B) SUCTION ISOLATION 251 RB 75 EXCHANGERS/PUMPS(

I VALVE I I _RFH18VM)

Table B-2 Page 2 of 4 B-84

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION DRAIN FROM REACTOR FUEL POOL HEAT V-18-47 WELL BACK TO FUEL 251 RB 75 EXCHANGERS/PUMPS(

POOL PUMPS I RFH18VM)

AUGMENTED SPENT FUEL ASFP HEAT P-18-1C POOL PUMP (NNO1-C) 255 RB 75 EXCHANGERS/PUMPS CONTROL SWITCH AREA(RFJ18PM)

AUGMENTED SPENT FUEL ASFP HEAT P-18-1D POOL PUMP (NNO1-D) 255 RB 75 EXCHANGERS/PUMPS

,CONTROL SWITCH AREA(RFJ18PM)

AUGMENTED SPENT FUEL ASFP HEAT P1-18-81 PUMP NN01-C,D SUCTION 255 RB 75 EXCHANGERS/PUMPS PRESSURE AREA(RFJ1811)

AUGMENTED SFP ASFP HEAT P1-18-82 COOLING PMP NN01-C 255 RB 75 EXCHANGERS/PUMPS

,DISCHARGE PRESSURE AREA(RFJ1811)

AUGMENTED SFP ASFP HEAT P1-1 8-88 COOLING PMP NNO1-D 255 RB 75 EXCHANGERS/PUMPS DISCHARGE PRESSURE AREA(RFJ1811)

ASFP COOLING HT ASFP HEAT P1-18-89 EXCHANGER NN02-C 255 RB 75 EXCHANGERS/PUMPS INLET PRESSURE AREA(RFJ1811)

ASFP COOLING HT ASFP HEAT P1-18-90 EXCHANGER NN02-C 255 RB 75 EXCHANGERS/PUMPS OUTLET PRESSURE AREA(RFJ1811)

ASFP HEAT EXCHANGER ASFP HEAT T67 NN02C OUTLET 255 RB 75 EXCHANGERS/PUMPS TEMPERATURE AREA(RFJ1811)

ASFP HEAT EXCHANGER ASFP HEAT TX1 NN02C INLET 255 RB 75 EXCHANGERS/PUMPS TEMPERATURE WELL AREA(RFJ18XM)

PS18 ASFP COOLING PUMP ASFP HEAT 79 NNO1-C LOW SUCTION 255 RB 75 EXCHANGERS/PUMPS PRESSURE TRIP AREA(RFJ1811)

PS18 ASFP COOLING PUMP ASFP HEAT NNO1-D LOW SUCTION 255 RB 75 EXCHANGERS/PUMPS PRESSURE TRIP AREA(RFJ1811)

AUGMENTED SPENT FUEL ASFP HEAT P-18-1C POOL PUMP (NN01-C) 255 RB 75 EXCHANGERS/PUMPS I I AREA(RFJ18PM)

AUGMENTED SPENT FUEL ASFP HEAT P-18-1D POOL PUMP (NN01-D) 255 RB 75 EXCHANGERS/PUMPS AREA(RFJ 8PM)

V18 ASFP COOLING PUMP ASFP HEAT

-l- NN01-C CASING VENT 255 RB 75 EXCHANGERS/PUMPS VALVE AREA(RFJ 18VM)

V-l8- ASFP COOLING PUMP ASFP HEAT NN01-D CASING VENT 255 RB 75 EXCHANGERS/PUMPS VALVE AREA(RFJ 18VM)

Table B-2 Page 3 of 4 B-85

12Q0108.80-R-001, Rev. I Correspondence No.: RS-12-177 ID DESCRIPTION SYSTEM BUILDING ELEVATION LOCATION V FUEL POOL MAKEUP 255 RB 75 NORTHWEST 1266 ISOLATION VALVE QUADRANT OF 75' V FUEL POOL MAKEUP 255 RB 75 NORTHWEST 1267 CHECK VALVE QUADRANT OF 75' PS-1 8-0079 TEST ASFP HEAT 179 ISOLATION VALVE 255 RB 75 EXCHANGERS/PUMPS 179 AREA(RFJ18VM)

AUGMENTED FUEL POOL NORTHWEST SIDE VCOOLING OUTLET VALVE AUGMENTE FUEL POOL ASFP HEAT V-18-74 CLG PUMP NN01-D 255 RB 75 EXCHANGERS/PUMPS DISCHARGE VALVE AREA(RFJ 1 8VM)

P-18-001C DISCHARGE ASFP HEAT V-18-77 CHECK VALVE 255 RB 75 EXCHANGERS/PUMPS I_ _ _AREA(RFJ1 8VM)

AUGMENTED SPENT FUEL ASFP HEAT V-18-78 POOL PUMP(NN01- 255 RB 75 EXCHANGERS/PUMPS D)SUCTION VALVE AREA(RFJ18VM)

AUGMENTED SPENT FUEL ASFP HEAT V-18-79 POOL PUMP(NN01- 255 RB 75 EXCHANGERS/PUMPS C)SUCTION VALVE AREA(RFJ1 8VM)

V-18-80 P1-18-88 ISOLATION VALVE 255 RB 75 NORTHWEST SIDE V-18-81 PS-18-0080 ISOLATION 255 RB 75 NORTHWEST QARN ROOT VALVE QUADRANT PS-18-0079 ISOLATION V-i18-82 ROTVLE255 RB 75 NORTHWEST SIDE ROOT VALVE V-18-83 P1-18-82 ISOLATION VALVE 255 RB 75 NORTHWEST SIDE V-18-86 P1-i18-89 ISOLATION VALVE 255 RB 75 NORTHWEST QARN QUADRANT V-i18-87 P1-18-90 ISOLATION VALVE 255 RB 75 NORTHWEST UDRN QUADRANT AUGMENTED FPC SYSTEM ASFP HEAT V-18-88 VENT VALVE 255 RB 75 EXCHANGERS/PUMPS AREA(RFJ18VM)

AUG FUEL POOL CLG SYS NORTHWEST V-18-89 OUTLET LINE DRAIN 255 RB 75 QUADRANT VALVE 255 RB 75 WEST SIDE V-i8-92 AUGMENTED FUEL POOL CLG THROTTLE VALVE I I Table B-2 Page 4 of 4 B-86

Oyster Creek Genefatng staton Unt 1 1200108s.8-R-001, R.v. 1 CorreSsondenOe No, RS-12-177 Table B-3. SWEL 1 IPEEE ID DESCRIPTION CLASS Building Elevation Location SYSTEM Seismic Safety New or Enhance- Comments Cat 1? Function(s) Replace? menht?

1A21-460V MCC 1A21 460V,3PH,3W,60HZ (1) MCCs RB 23 480V SWGR ROOMEAST WALL 460VAC Y SSAC FOR TURBINE BUILDING __)_MCsRB NEAR DOOR MCC 1A21A 460V,3P,3W,60HZ S. WALL ACCESS AREA - S.

1A21A-460V FOR REACTOR BUILDING (1) MCCs RB 23' TORUS CTRL AREA - MCC 460VAC Y SSAC 1AZIA MCC 1A21B 460V,3P,3W,B0HZ 460V SW'TCHGEAR ROOM; 1A21B-460V FOR REACTOR BUILDING (1) MCCs RB 23' SOUTHEAST QUADRANT NEAR 460VAC Y SSAC COLRB/R3 IA234V MCC 1A23 460V,3PH,3W,60HZ (1) MCCs RB 23' SOUTHEAST CORNER 480V FOR REACTOR BUILDING SWTCHGEAR ROOM 460VAC Y SSAC 1A2-460V 460V UNIT SUBSTATION 1A2 FOR (2) Low Voltage RB 23' 460V SWTCHGEAR ROOM, 480VAC Y SSAC REACTOR BUILDING Switchgear ___23__NEAR COL.RG/R6 1A2-460V XF USS 1A2460V TRANSFORMER (4) Transformers RB 23' 480V SWGR RMUSS 1A2-4W0V 460VAC Y SSAC 4160-480V/277V 3PH 60HZ 031B 1C 4160V BUS 1C SWVTCHGEAR (3) Medium Voltage, TB 23' SOUTH MEZZANINE 4160 VOLT 4KV Y SSAC F-V = 3.67E - 03 Metal-Clad Switchgear SWITCHGEAR ROOM 305-125\06-15 SCRAM ACCUMULATOR-H20 (21) Tanks and Heat RB 23' NORTH BANK CRD CRD Y RRC See VM-OC-0226 Rev. 12 Exchangers ACCUMULATORS SYSTEM 305-125\06-19 SCRAM ACCUMULATOR-H20 (21) Tanks and Heat NORTH BANK CRD Y RC See VM-OC-0226 Rev. 12 ACCUMULATORS SYSTEM Exchangers 305-125\26-11 SCRAM ACCUMULATOR-H20 (21) Tanks and Heat RB 23' SOUTH BANK CRD CRD Y RRC See VM-OC-0226 Rev. 12 Exchangers ACCUMULATORS SYSTEM 305-125\26-19 SCRAM ACCUMULATOR-H20 (21) Tanks and Heat RB 23' SOUTH BANK CRD CRD Y RRC Sea VM-OC-0226 Rev. 12 Exchangers ACCUMULATORS SYSTEM MAIN 6R MAIN CONTROL RM PANEL 6R (20) Instrumentation and MMAIN CONTROL ROOM, SWOF RPS Y RCPC REACTOR PROTECTION CH1 Control Panels CONTROL COL.BAFA ROOM MAIN MAIN CONTROL RM PANEL 7R (20) Instrumentation and MON MAIN CONTROL ROOM, WEST 7R REACTOR PROTECTION CH.2 Control Panels CONTROL OF COL8A/FA RPS Y RCPC ROOM VITAL BANK 'C' STATION C BATTERY ROOM, SOUTH 125V0C BATTERY BATTERY (LEAD ACID) SMEZZANINE 4160RVOLT BATTERY Y SSDC F-V 5.32E - 02 BANK C

'C' STATION BATTERY SOLID (16) Battery Chargers SOUTH MEZZANINE 4160 VOLT 125VDC BTCHGC STTCTTClHRE STATE STATIC CHARGER C1l an Inverters and netr TB 23' S'rTCHGEAR ROOM WEST WALLER BATTERY Y SSDC IWALL CONTINUOUS INSTRUMENT PNL 480V SWGR ROOM, SOUTH OF 208/120VA Y SSAC CIP-3 NO.3 208/120V,3PH,4W,60HZ (14) Distribution Panels RB 23' USS 1A2-460V C C-31 31 -ICRD INLET SCRAM VALVE (North) Valves (07) Fluid-Operated RB 23' - TORUSSCRAM NW-NORTH VOL DSCHRG TOP ACCESS CRD SYSTEM Y RRC See VM-OC-0226 Rev. 12 CV-305-126\1 0-CRD INLET SCRAM VALVE (North) (07) Fluid-Operated RB 23! NW-NORTH SCRAM DSCHRG CRD Y RRC See VM-OC-0226 Rev. 12 39 eValves VOL - TORUS TOP ACCESS SYSTEM Table B-3 Page 1 of 6 B-87

Oyster Creek Generating Station Unit1 12Q0108.80-R-O001 Rov. 1 Correspondence No.: RS-12-t77 I IPEEE Seismic Safety New or Enhance- Comments ID DESCRIPTION CLASS Building Elevation Location SYSTEM Cat 1? Function(s) Replace? ment?

CV-305-1263- IL(07) Fluid-Operated SOUTH SCRAM DISCHARGE CRD See VM-OC-0226 Rev. 12 03V CR0 INLET SCRAM VALVE (Sooth) Valves VOLUME AREA SYSTEM CV-305-126\30- (07) Fluid-Operated SOUTH SCRAM DISCHARGE CRD See VM-OC-0226 Rev. 12 07 CRD INLET SCRAM VALVE (South) Valves RB 23 VOLUME AREA SYSTEM CV-305-127\06- CRD OUTLET SCRAM VALVE (07) Fluid-Operated NW-NORTH SCRAM DSCHRG CRD (North) Valves RB 23 VOL - TORUS TOP ACCESS SYSTEM Y RRC See VM-OC-0226 Rev. 12 15 .

CV-305-127\22- CRD OUTLET SCRAM VALVE (07) Fluid-Operated RB 2V NW-NORTH SCRAM DSCHRG CRD Y RRC See VM-OC-0226 Rev. 12 31 (North) . Valves RVOL - TORUS TOP ACCESS SYSTEMW CV-305-127\30- CRD OUTLET SCRAM VALVE (07) Fluid-Operated RB 23' SOUTH SCRAM DISCHARGE CRD Y RRC See VM-OC-0226 Rev. 12 03 (South) Valves RVOLUME AREA SYSTEM CV-305-127\30- CRD OUTLET SCRAM VALVE (07) Fluid-Operated SOUTH SCRAM DISCHARGE CRD See VM-OC-0226 Rev. 12 07 DC-C 125V (South)

DC-C 125V 125VDC POWER PANEL DC-C Valves (14) Distribution Panels RB TB 23' 23'

~~~~~416OV VOLUMEAREA SWlTCHGEAR WL RM SYSTEM 12VC 1OUH Y

Y RRC SCF-=15E3 STHESDC F-V =1.95E -3 SOUTH WALL EHNE)

CENTER 'C' 480V SWGR DC-F 12SVDC POWER PANEL DC-F (14) Distribution Panels RB 23' ROOM,SOUTHEAST OF MCC 125VDC Y SSDC 1A2-460V

- D L G 2 ' D N T # 1D 120VDC G Y S D B AT TE R SE L G E N ERA TO R U N IT # 1 D I Eý (1 ) Bt e y r c s D LG 2'D NT#1START Y SD BANKER STARTING BATTERIES (1)Bteyrcs BATTERY DG-1120VDC BATTERY DIESEL GENERATOR UNIT #1 (16) Battery Chargers DG BLDG 23' DG UNIT # 1 DG Y SSDC CHARGER BATTERY CHARGER and Inverters START BATTERY DG-1 SWGR DIESEL GENERATOR #1 UNIT (20) Instrumentation and DG BLDG 23' DG UNIT # 1 EMER Y SSAC SWITCHGEAR Control Panels PWR EMERGENCY CONDENSER RX 51' INSTRUMENT RACK RK- SOLATIO DPIS-IB0005A1 NE01A HIGH SYSTEM FLOW (18) Instrument racks RB 51' REA CSNDEN Y DHR SVWITCH 03 AREA .ONDENS ER DPT-6-1A0091B FUEL ZONELLEVELTWIDE (18) Instrument racks RB 51' RXR51' INSTRUMENT RACK RK-RANGE LEVEL TRANSMITTER 03 AREA RVLIS Y RCIC ER18A CORE SPRAY/AUTO DEPRESS'N (20) Instrumentation and 460V SWITCHGEAR ROOM CORE SYSTEM RELAY LOGIC PANEL Control Panels RB 23' SOUTH OF USS 1A2-460V SPRAY/A Y RRIC/RCPC DS 460V SWI*TCHGEAR ROOM, FN-56-4 "A" 480 SWGR RM SUPPLY FAN (9) Fans RB 23' NEAR COLUMN.RGTR6 R HVAC Y SSHVAC USS 1A2-460V TRANSFORMER (9) Fans RB 23' 480V SWGR ROOM, USS 1A2-COOLING FAN 460VCOMPT 031B 40VAC Y SSAC USS 1A2-460V TRANSFORMER (9)

( Fuss RB 23' 46V6OMT039AC__

480V SWGR ROOM, USS 1A2- 460VAC Y Y SSAC SSAC ___

FN-732-2 COOLING FAN I _I_460V COMPT 031_B FN-732-3 USS 1A2-460V TRANSFORMER (9) Fans RB 23' 480V SWGR ROOM, USS 1A2-FN-732-3 COOLING FAN (9)_Fans _ RB 23' 460V COMPT 031B ,60VAC Y SSAC Table B-3 Page 2 of 6 B-88

Oyster Creek Generatng Station Unit1 12Q0108.80-R-001,Rev. 1 Correspondence No, RS-12-177 CLASS Building Elevation Location SYSTEM Seismic Safety New or IPEEE ID DESCRIPTION Cat 1? Function(s) Replace? Enhance- Comments meent?

CONTAINMENT SPRAY SYS HEAT (21) Heat Exchangers RB 2V NORTH BANK CTMT SPRAY HT CTMT H-2A EXCHANGER 1-1 EXCHANGERS SPRAY Y DHR/UHS 120VAC INSTRUMENT PANEL 4 -(14) Distribution Panels RB 2 IN 480V SWGR RMSOUTH OF

_P-4 _ 08/120V,3PH,4W (D oa R USS 1A2-460V 120VAC Y SSAC IT-4A TRANSFORMER FROM MCC 12- (4) Transformers RB 2 480V SWITCHGEAR Y SSAC

_T-__ _.480V TO IP-4 .ToeB ROOM,SOUTH SIDE REACTOR VESSEL LOW LEVEL RX 51' INSTRUMENT RACK RK-LIS-RE0018A NDICATING SWSTCH (18) Instrument racks RB 51 01(ACCESS FROM RX-75' AREA RVLIS Y RCPC/DHR INDICTINGWITC RFG)

LI-R018 EACTOR VESSEL LOW LEVEL RX 51' INSTRUMENT RACK RK-LIS-RE0018C NDICATING SWSTCH (18) Instrument racks RB 51 01 (ACCESS FROM RX-75' AREA RVVUS Y RCPC/DHR L862IB LO-LO LEVEL (START NORMAL DG BLDG 23- DO UNIT# 1 DG OIL Y SSAC PUMP) ON TANK T-39-003 (0) other SYSTEM LS--8-1OC(0)

HI-HI LEVEL(PUMP CUT-OFF) ON other (DGOIL DG BLDG 23' OG UNIT#1STE__________ Y SSAC

__-8_2-10 TANK T-39-003 T SYSTEM LSP-1A2 LOCAL SHUTDOWN PANEL- USS (20) Instrumentation and OB 2S 480V SWGR RM, 4 FT WEST OF LSP Y SSAC 1A2 PUMP/BREAKER CONTROL S Control Panels 2 USS 1A2-460V REACTOR VESSEL LOW WATER LT-RE0005B .EVEL REACTOR SCRAM (18) Instrument racks RB 51' INSTRUMENT RACK RK-02 RVUS Y RCPC M-39-1 LMERGENCY DIESEL (17) Engine Generators DG BLDG 23' DG UNIT# 1 DG Y SSAC

______GENERATOR #1I P-20-1A CORE SPRAY PUMP NZ01-A (5) Horizontal Pumps RB 19 CORE SPRAY PUMP ROOM CORE RCIC/DHRSee Dwg. 4074-5 sheet 2 rev.

I NORTH WEST SPRAY 5 P-20-1A CORE SPRAY PUMP ROOM CORE (NZ01A) CORE SPRAY PUMP "A" - SYS. I (5) Horizontal Pumps RB 19 NORTH WEST SPRAY Y RCIC/DHR F-V = 1.10E - 03 P-20-2A CORE SPRAY BOOSTER PUMP (5) Horizontal Pumps RB 51, CORE SPRAY BOOSTER CORE F-V = 1.02E - 03; See Dwg.

NZ03-A PUMPS AREA SPRAY)Y RCIC/DHR 4074-5 sheet 2 rev. 5 P-3-3A _____ LMERGENCY SERVICE WATER UMP 1-1 (52.A) (6) Vertical Pumps IS &' NW SIDE OF IS ESW Y UHS P-39-13 FUEL OIL PUMP TO DAY TANK T- DG OIL Y SSAC

__39-13 39-3 (5) Horizontal Pumps DG BLDG 23 DG UNIT# 1 SYSTEM YSSAC DIESEL 1 GENERATOR UNIT #1 )Hozontal Pumps DG BLDG 23! DG UNIT# 1 DG OIL Y SSAC

-39-17 ENGINE DRIVEN FUEL PUMP (5) SYSTEM M-39-1 LEFT BEARING COOLING (5) Horizontal Pumps DG BLDG 23 DG UNIT# DG P-319 WATER PUMP DBD 23 DGNT#1COOLING

_5oznlPus Y SSAC DG OIL P-39-25 AC TURBO LUBE OIL PUMP (5) Horizontal Pumps DG BLDG 23' DG UNIT # 2 SYSTEM Y SSAC PI-305-131X06- ACCUMULATORS GAS (0) other RB 23' RX 23' N. BANK HCU'S (CRD CRD0 15 PRESSURE INDICATOR ACCUMULATORS) SYSTEM Y RRC See VM-OC-0228 Rev. 12 PI-305-131L)6- ACCUMULATORS GAS RX 23' SOUTH BANK HCU'S CRD 03 PRESSURE INDICATOR (0) other RB 23' 'CR0 ACCUMULATORS) SYSTEM Y RRC See VM-OC-0226 Rev 12 480/120VAC TRANSFORMER TO 4TOLD CABLE SPREADING ROOM 208/120VA Y SSAC PS-1 _PROTECTION SYS PANELS 1&2 (4) Transformers TB 3' EL36-0 C______

Table B-3 Page 3 of 8 B-89

Oyster Creek Generatngstation Urut 1 12Q010880 -Oo1,Rev 1 Corrapond-nce No: RS-12-177 Seismic Safety New or IPEEE ID DESCRIPTION CLASS Building Elevation Location SYSTEM Cat 17 Function(s) Replace? Enhance- Comments ment?

PS-IA0083A EMRV NR108A HIGH PRESSURE (18) Instrument racks RB 51' INSTRUMENT RACK RK1 ADS Y RCPC/DHR SWITCH NORTHWEST QUADRANT ADS Y ______

S,-IA0083C 0EMRV NR108C HIGH PRESSURE (WTH18)

Instrument racks RB 51' RX 51' INSTRUMENT RACK RK-02 ADS AS Y RCPC/DHR RPIH SWITCH 0 PS-RE0017A LOW REACTOR PRESS. SWITCH OC.RX 51' INSTRUMENT RACK CORE READIES CORE SPRAY VALVES (18) Instrument racks RB 51 RK-01 (ACCESS FROM RX-75' Y RCICSDHR AREA RFG) SPRAY RX 51 INSTRUMENT RACK RK- CORE DRYWELL HIGH PRESSURE PS-RV0046A SWITCH-AUTO STARTS PUMPS (18) Instrument racks RB 51' 03 AREA SPRAY/A Y RCIC/DHR DS REACTOR PROTECTION SYSTEM INSTRUMENT RACK RK-01 RK-1 1A,2A INSTRUMENT RACK A,B (18) Instrument racks RB 51' EL66-6 (ACCESS FROM RX-75' RPS Y RCPC AREA RFG)

RK-3 INSTRUMENT RACK RECIRCN RX 51' INSTRUMENT RACK RK- RPS Y RCPC PUMP REACTOR PROTECTION 03 AREA MSIVtS SOLENOID AIR VALVE & TRUNION ROOM EL23-8 Nuclear RK-411-1 EQUIPMENT MOUNTING RACK (18) Instrument racks TB 23 GENERAL ALL AREAS Boiler Y RCIC System ROTARY AC GENERATOR FOR 120V AC (13) Motor Generators OB 35 125VDC BATTERY ROOM 120VAC Y SSAC INVERTER\AC SUPPLY FOR CIP-3 SOUTHWEST CORNER (08) Motor-Operated and N BANK HCU'S (CR0 CR0 SO-305-117W0&- CHANNEL I SCRAM AIR PILOT 15 SOLENOID VALVE(GROUP 1) Solenoid-Operated RB 23T ACCUMUL S SYSTEM Y RRC See VM-OC-0226 Rev. 12 Valves ACCUMULATORS) SYSTEM (North) 50-305-117\06- CHANNEL I SCRAM AIR PILOT (08) Motor-Operated and N. BANK HCU'S (CRD CRD SOLENOID VALVE(GROUP 2) Solenoid-Operated RB 23 Y RRC See VM-OC-0226 Rev. 12 19 (North) Valves ACCUMULATORS) SYSTEM CHANNEL I SCRAM AIR PILOT (08) Motor-Operated and SOUTH BANK HCU'S (CR0 CR0 03 SOLENOID VALVE(GROUP 2) Solenoid-Operated RB 23' ACCUMULATORS) SYSTEM Y RRC See VM-OC-0228 Rev. 12 03 ISouth) Valves (08) Motor-Operated and SOUTH BANK HCUS (CR0 CR0 SO-305-117%30- CHANNEL I SCRAM AIR PILOT SOLENOID VALVE(GROUP 3) Solenoid-Operated RB 23 ACCUMULATORS) SYSTEM Y RRC l)South) Valves 12 SO-305-120IO- DIRECTIONAL FLOW CONTROL (08) Motor-Operated and N. BANK HCUS (CR0 s WITHDRAW SOLENOID VALVE (Nrh5Vle Solenoid-Operated RB 23' HCU DIRECTIONAL CONTROL HCUMDRETONA CONT SYSTEM STE Y RRC See VM-OC-0228 Rev. 12 (North) Valves UI UNIT DIRECTIONAL FLOW CONTROL (08) Motor-Operated and SOUTH BANK HCU'S (CR0 CR0 SO-305-120\3 D- WITHDRAW SOLENOID VALVE Solenoid-Operated RB 23' ACULATORS SYTE 033 (ot)Vle ACCUMULATORS) SYSTEM Y RRC See VM-OC-0226 Rev. 12 ISouth) Valves (08) Motor-Operated and N. BANK HCU'S (CRD O-305-12106- DIRECTIONAL FLOWCONTROL SoACCUMULATORS); N. BANK CRD 15 INSERT SOLENOID VALVE (North) Solenoid-Operated RB 23 HCU DIRECTIONAL CONTROL SYSTEM Y RRC See VM-OC-0228 Rev. 12 ValvesUNIT Table B-3 Page 4 of 6 B-90

Oyster Creek Generating Station Unit 1 1200108.8o-R-001, Rev. 1 Correspondence No.: RS-12-177 IPEEE ID DESCRIPTION CLASS Building Elevation Location SYSTEM Seismic Safety New or Enhance- Comments Cat 1? Function(s) Replace? ment?

SO-305-121\06- DIRECTIONAL FLOW CONTROL (08) Motor-Operated and OC RX 23' N. BANK HCU'S (CRD CRD INSERT SOLENOID VALVE (South) Solenoid-Operated RB 23' ACCUMULATORS) SYSTEM Y RRC See VM-OC-0228 Rev. 12 19 Valves T-30,2 DIESEL GENERATOR FUEL OIL (21) Tanks and Heat DG BLDG 18' DG BLDG 18' 4", NORTH WALL DG OIL Y SSAC F-V = 1.20E - 02; RAW=

TSTORAGE TANK Exchangers D TANK CELL SYSTEM Y 11150 T-39-3 DIESEL GENERATOR UNIT #1 (21) Tanks and Heat DGBLDG 23' DOUNIT#1 DGOIL Y SSAC 9FUEL OIL DAY TANK Exchangers SYSTEM YSSAC T-39-5 M-39-1 COOLING WATER TANK 21) Tanks and Heat DG BLDG 23' DG UNIT # 1 EMER Y SSAC Exchangers PWR (07) Fluid-Operated TRUNION ROOM EL27.0; MAIN Nuclear 0 MAINSTEAM LINEB'OUTLET V-1-10 MAION S ISOLATION AMLINE0B' VALVE(NS04-B) Valves Valves TB 23' STEAM iSV ISOLATION S0BSse VALVE Boiler Y RRC _________

(MSIV) NS-04B System _

MAIN STEAM LINE 'A' DRAIN Nuclear ECR 09-V-1-106 VALVE (0) other DW 23' DW NORTH WEST EL.27' Boiler Y CF System 00484 Noclear (07) Fluid-Operated DW 46' DRYWELL SOUTHWEST EL.51-3 Boiler Y RCPC V- 1-160 SAFETY RELIEF VALVE NR28D (SOUTH HEADER) Valves 46_____SUHWS_____Bier System Y__

Nuclear 48' DRYWELL NORTHWEST EL.51-3 Boiler Y RCPC (07) Fluid-Operated DW V-1-164 SAFETY RELIEF VALVE NR28H System Y__

(NORTH HEADER) Valves 4_____NRHET____Bie V-1-173 ELECTROMATIC RELIEF VALVE (07) Fluid-Operated DW 46' DRYWELL SOUTHWEST EL.51-3 ADS Y DHRIRCPC NR108-A(SOUTH HEADER) Valves V-1-175 ELECTROMATIC RELIEF VALVE (07) Fluid-Operated DW 46' DW51-03, NORTHWEST ADS Y DHR/RCPC NR108-C(NORTH HEADER) Valves (ICA01VM)

V-1-177 ELECTROMATIC RELIEF VALVE (07) Fluid-Operated DW 46' DRYWELL SOUTHWEST EL51-3 ADS Y RCPC/DHR F-V = 3.62E - 02 NR108-EISOUTH HEADER) Valves V-15-120 SOUTH SCRAM DISCHARGE HDR (07) Fluid-Operated RB 2& RX 23' SOUTH SCRAM CRD Y RRC Valves DISCHARGE VOLUME AREA SYSTEM VENT VALVE(NC53-A)

NORTH SCRAM DISCHG VOLUME (08) Motor-Operated and RX 23' NW-NORTH SCRAM CRD 133 DRAIN VALVE(NC52-A) Solenoid-Operated RB 23' DSCHRG VOL - TORUS TOP SYSTEM Y RRC DRI VLE)C2-) Valves ACCESSYSE (08) Motor-Operated and DRYWELL EL.4-3 AZ 80 CU INLET ISOLATION VALVE V-16-1 FROM REACTOR VESSEL Solenoid-Operated DW 46' DEGREES RWCU Y CF Valves Nuclear (07) Fluid-Operated DW 23' DRYWELL WEST SIDE EL27-0 Boiler Y CF V-1-7 MAIN STEAM LINEA' OUTLET System ISOLATION VALVE(NS03-A) Valves SDC LOOP'PUMP SUCTION (08) Motor-Operated and SHUTDOWN COOLING PUMP SDC Y DHR V-17-1 VALVE Solenoid-Operated SDC 38' ROOM EAST Valves SDC LOOPW'A'OUTLET HEADER (08) Motor-Operated and RX 51' S/D COOLING HEAT V17-212 VENT VALVE Solenoid-Operated SDC 51' EXCHANGER RM SDC Y CF/DHR Valves I Table B-3 Page 5 of 6 B-91

Oyster Creek GenerOng Station Unit1 12Q0108.80-R-001,ReW1 Corresponde-ne No. RS-12-177 ID DESCRIPTION CLASS Building Elevation Location SYSTEM Sersmic SaFeti Nwos Enhance- Comments Cat 17 Function(s) Reacement?

CORE SPRAY PUMP DISCHARGE (08) Motor-Operated and RX 51' INSTRUMENT RACK RK- CORE V-20-12 VALVE(SYSTEM I) Solenoid-Operated RB 51' 03 AREA SPRAY Y RCIC/DHR VLESSE1)Valves 03__AREA__SPRAY_

"A"CONTAINMENT ISO. VALVE - Motor-Operated RS 51 INSTRUMENT I RACK RK-03 CORE V-20-15 SYS. I (0)Mtr-prd__5'AREA SPRAYY__F CORE SPRAY PUMP ROOM CORE RCICIDHR/C CORE SPRAY PUMP "A SUCTION (08) Motor-Operated and VALVE FROM TORUS Solenoid-Operated RB 19 NORTH WEST SPRAY Y F (08) Motor-Operated and CONTAINMENT SPRAY PUMP TORUS CONTAINMENT ISOLATION FOR V-21-5 TORUS WATER CLEAN-UP Solenoid-Operated RB 19 ROOM SOUTH EAST (1-3 & 1- WTR Y CF Valves 4)(1-7 SUMP CLEANUP ECR 03-(0) other DG BLDG 23' DG UNIT # 1 DG Y SSAC ECR 03-V-39-109 EDG1PRIMING PUMP SUCTION VALVE EDG1 PRIMING PUMP ___________00731 _________

PUMP (0) other DG BLDG 23' DG UNIT # 1 DG Y SSAC 031 V-39-110 DISCHRG DISCHARGE VALVE ____________ .00731___

V-39-2 ISOLATION VALVE FOR TANK T- (0) other DG BLDG 18 FO TANK T-39-002 VAULT DG Y SDAC RAW= 1060 39-002 OUTLET _________ I__________

VACP-1 120V VITAL AC POWER PANEL 208/124Vi3PH,4WiRHZ (14) Distribution Panels RB 23' 460V SW1TCHGEAR SOUTHWEST CORNER ROOM, 208/120VA C Y SSAC VACP-1 XF 120V VITAL AC POWER PANEL (4) Transformers RB 23' OC,460V SWITCHGEAR ROOM, 208/120VA Y SSAC TRANSFORMER 480/208/120V SOUTHWEST CORNER C Table B-3 Page 6 of 6 B-92

Oyster Creek Generaing Staten Unit1 12Q0108.80*R-001,Rew. I Correspondence No,: RS-12-177 Table B-4. SWEL 2 Associated ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Seismic with Rapid Comments Call? Draindown H-18-IC AUGMENTED SPENT FUEL POOL HEAT (21) Heat exchanger RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N

____EXCHANGER(NN02-C)

LI-18-170SKIMMER SURGE TANKA'FUEL POOL LEVEL (18) Instrument on Rack RB 119' NORTH FLOOR AREA FC Y N INDICATOR LS-53B SPENT FUEL POOL LOW WATER LEVEL SWITCH 118) Instrument on Rack RB 119' NORTH FLOOR AREA FC Y N P-1l-1A Or SPENT FUEL POOL COOLING PUMP (NN01-B) (05) Horizontal Pumps RB 75' RX 75' OLD SFP HX & PUMP AREA FC Y N P-18-1C AUGMENTED SPENT FUEL POOL PUMP (NN01-C) (05) Horizontal Pumps RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N P1-18-82 AUGMENTED SFP COOLING PMP NN01-C DISCHARGE (18) Instrument on Rack RB 75' RX 75'AUGMENTED SFP HX & PUMPS FC Y N PRESSURE PS-18-79 ASFP COOLINGPUMPNN0-CLOWSUCTION (19) Temperature Sensers RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N TI-18-267 ASFP HEAT EXCHANGER NN02C OUTLET TEMPERATURE V-18-112 ASFP COOLING PUMP NN01-D CASING VENT VALVE (00) other RB 75' RX 75'AUGMENTED SFP HX & PUMPS FC Y N V-18-1266 FUEL POOL MAKEUP ISOLATION VALVE (00) other RB 75' RX 75'OLD SFP HX & PUMP AREA FC Y N ECR 08-01114 V-18-19 AUGMENTED FUEL POOL COOLING OUTLET VALVE (00) other RB 75' NX75'OLDSFPHX&PUMPAREA; SC E N NORTHWEST SIDE V-18-2 1AUGMENTED SPENT FUEL POOL SYSTEM INLET VALVE (00) Other RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N VSFP COOLING PUMP (NN01-A) SUCTION ISOLATION (00) Other RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N V"18"-3 VALVE V-18-47 DRAIN FROM REACTOR WELL BACK TO FUEL POOL (00) Other RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N VPUMPS V-18-74 AUGMENTE FUEL POOL CLG PUMP NN01-D DISCHARGE (00) other RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N VALVE V-18-80 P1-18-88 ISOLATION VALVE (00) other RB 75' RX 75' OLD SFP HX & PUMP AREA; FC Y N NORTHWEST SIDE V-18-81 PS-1a-0080 ISOLATION ROOT VALVE (00) other RB 75' IFC Y N V-18-88 AUGMENTED FPC SYSTEM VENT VALVE (00) other RB 75' RX 75' AUGMENTED SFP HX & PUMPS FC Y N V-18-92 AUGMENTED FUEL POOL CLG THROTTLE VALVE (00) other RE 75' RX 75'WEST CONTROL AREA FC Y N B-93

ML12359A008

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1.2 BACKGROUND

1.5 CONCLUSION

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Subject:

SUMMARY

SUMMARY

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