ML12353A225

12Q0108.50-R-001, Rev. 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 LaSalle County Station, Unit 1, Part 1 of 15

ML12353A225
Person / Time
Site:	LaSalle
Issue date:	11/01/2012
From:	Delaney M Stevenson & Associates
To:	Exelon Generation Co, Office of Nuclear Reactor Regulation
References
RS-12-163 12Q0108.50-R-001, Rev 1
Download: ML12353A225 (161)

Text

U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 27, 2012 Page 4 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 LaSalle County Station, Unit 1, Report Number: 1200108.50-R-001, Revision 1 (938 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 LASALLE COUNTY GENERATING STATION UNIT 1 2601 North 21st Road, Marseilles, Illinois, 61341-9757 Facility Operating License No. NPF-11 NRC Docket No. 50-373 Correspondence No.: RS-12-163 140111111W ANNNOW ANOW-Exeton Exelon Generation Company, LLC (Exelon)PO Box 805398 Chicago, IL 60680-5398 Prepared by: Stevenson

& Associates 1661 Feehanvllle Drive, Suite 150 Mount Prospect, IL 60056 Report Number: 12Q0108.50-R-001, Rev. 1 Prned Name Sianature Date Preparer:

Marlene Delaney Reviewer:

Tony Perez Approver:

Tony Perez Peer Review Team Leader: Walter Djordjevic AM-11/1/2012 111112012 11/1/2012 11/1/2012 Lead Responsible Engineer: ,!a--! j-L L'I I- Ioia.Branch Manager: LUA/ /T Senior Manager Design Engineering:

__._,-Corporate Acceptance:

s. ci'V IF a 't. 04L4A -A/(- / 26, 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 LASALLE COUNTY GENERATING STATION UNIT 1 Document Type: Report Report Number: 12Q0108.50-R-001 Project Name: NTTF R2.3 Seismic Walkdowns for Exelon -LaSalle Job No.: 12Q0108.50 Eif"' Exeton.Client: e o This document has been prepared in accordance with the S&A Quality Assurance Program Manual, Revision 17 and project requirements:

Initial Issue (Rev. 0)Prepared by: Marlene Delaney Date: 10/31/2012 Reviewed by: Tony Perez "-zi Date: 10/31/2012 Approved by: Tony Perez ,- Date:10/31/2012 Revision Record: Revision Prepared by/ Reviewed by/ Approved by/ Description of Revision No. Date Date Date 1 Marlene Tony Perez Tony Perez Replaced pages 4-3, 5-8, 5-Delaney 11/1/2012 11/1/2012 10, and B-77 to B-81.11/1/2012 DOCUMENT CONTRACT NO.APPROVAL SHEET 12Q0108 Stvenson & Associates 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Contents L is t o f T a b le s .........................................................................................................

iii Executive Summary ................................................................................................

iv 1 Introduction

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1-1 1.1 Purpose ..........................................................................

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1-1 1.2 Background

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1-1 1.3 Plant Overview ..........................

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1-1 1 .4 A p p ro a c h .................................................................................................................

1-2 1 .5 C o n c lu s io n ..............................................................................................................

1-2 Seismic Licensing Basis ...........................................

2-2.1 Overiew...............................................2...

2 .1 O v e rv ie w ......................................................................

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... 2 -1 2.2 SAFE SHUTDOWN EARTHQUAKE (SSE) ...... ...... .................

..... 2-1 2.3 DESIGN OF SEISM IC CATEGORY I SSCS ...........................................................

2-1 2.3.1 Summary of Seismic Design .........................................................................

2-1 2.3.2 Summary of Codes and Standards

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2-2 3 Personnel Qualifications

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3-1 3.1 Overview ........................................................................

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3-1 3.2 Project Personnel

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3-1 3.2.1 Stevenson

& Associates Personnel

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3-2 3.2.2 Additional Personnel

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

4-4 .1 O v e rv ie w .................................................................................................................

4 -1 4.2 SW EL Development

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4-1 4.2.1 SWEL 1 -Sample of Required Items for the Five Safety Functions

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4-1 4.2.2 SW EL 2 Development

-Spent Fuel Pool Related Items ...............................

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

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

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

5-1 5.2.1 Adverse Anchorage Conditions

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5-2 5.2.2 Configuration Verification

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5-2 12QO108.50-R-o.1 Rev. 1 Correspondence No.: RS-12-163 5.2.3 Adverse Seismic Spatial Interactions

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5-3 5.2.4 Other Adverse Seismic Conditions

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5-4 5.2.5 Conditions Identification during Seismic Walkdowns

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5-4 5 .3 A rea W alk-B ys .......................................................................................................

5-4 5.3.1 Conditions Identification during Area Walk-bys ............................................

5-6 5.4 Supplemental Information on Electrical Cabinet Inspections

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5-6 6 Licensing Basis Evaluations

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

7-1 8 Peer R eview ....................................................................................................................

8-1 9 References

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9-1 Appendices A Project Personnel Resumes and SWE Certificates

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

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

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

D-1 E Plan for Future Seismic Walkdown of Inaccessible Equipment

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

F-I 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 List of Tables Table 2-1. List of Codes, Standards, and Specifications

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2-3 Table 3-1. P ersonnel R oles ...................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation

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5-3 Table 5-2. Conditions Identified during Seismic Walkdowns

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5-8 Table 5-3. Conditions Identified during Area Walk-Bys ............................................

ý.. 5-10 Table B-Ia. Base List la -Items Exclusive to Unit 1 ...................................................

B-3 Table B-lb. Base List lb -Items Common to Units 1 and 2 ..................

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B-59 T able B -2 .B ase List 2 ........................................................................................

B -76 T a ble B -3 .S W E L 1 .............................................................................................

B -77 Table B-4. SWEL 2 ...................................................

B-82 Table C-1. Summary of Seismic Walkdown Checklists

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C-2 Table D-1. Summary of Area Walk-By Checklists

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D-2 Table E-1. Inaccessible and Deferred Equipment

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E-2 Table E-2. Supplemental Cabinet Internal Inspection List ...... ...................

E-3 iii 12QO108.50-R-OO1 Rev. 1 Correspondence No.: RS-12-163 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. 6) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 6)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 21't 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. 7) 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. 6) 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 LaSalle County 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. 6) 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/LaSalle 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 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Seismic Licensinq Basis The Seismic Licensing Basis is briefly described in Section 2 of this report. The safe shutdown earthquake for the LaSalle County Station site is 0.20g horizontal ground acceleration and 0.133g vertical ground acceleration. (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* Major new or replacement equipment* A variety of types of equipment* A variety of environments v

12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 LaSalle Unit 1, the SWEL is comprised of:* SWEL 1 resulted with 114 items for walkdown." SWEL 2 resulted with 2 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 LaSalle Unit 1 were performed during the weeks of August 27, September 3, September 10, and September 17 2012. During the walkdown activities, the walkdown team consisted of two (2) Seismic Walkdown Engineers (SWEs), a station Equipment Operator, and various station personnel.

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.,)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:

vi 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163* 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 109 of the 116 components on the SWEL (comprised of SWEL 1 and SWEL 2). Walkdowns for seven (7) components were deferred due to accessibility issues such as being located in containment or energized equipment.

The seven (7) remaining items will be inspected during a unit outage or another time when the equipment is accessible, as required.

Anchorage verification was required for a minimum of 31 components. (Ref. 1) A total of 42 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 18 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 the LaSalle Unit 1 nine (9) Issue Reports (IRs) were issued. After evaluation through the corrective action program (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 CAP. In lieu of this process, Exelon/LaSalle utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/LaSalle 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 Checklists (SWCs), Area Walk-By Checklists (AWCs), and entered into the CAP. For those conditions that vii 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 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. 5) Further, no anomalies, outliers, findings, or plant improvements were identified as a result of the IPEEE program. (Ref. 3 & 5)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 LaSalle County 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 in 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 in no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).The Seismic Walkdowns identified nine (9) minor conditions.

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 seven (7) items deferred due to inaccessibility along viii 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 with supplemental inspections of 18 electrical cabinets.

Area Walk-Bys will be completed, as required, during these follow-on activities.

ix 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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. 6) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 6)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. 7) 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. 6) 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 LaSalle County 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. 6) 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/LaSalle has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1)1.3 PLANT OVERVIEW The LaSalle County Station consists of two operating boiling water reactor (BWR)generating units. The site is located in the agricultural area of Brookfield Township, LaSalle County, Illinois.

It is approximately 55 direct-line miles southwest of Chicago and 20 miles west of Dresden Nuclear Power Station. (Ref. 2 section 1.1)1-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 The station utilizes two single-cycle forced-circulation boiling water reactors, rated at 3546 MWt and designed for 3559 MWt. Both units' containment design employs the BWR Mark II concept of over-under pressure suppression with multiple downcomers connecting the reactor drywell to the water-filled pressure suppression chamber. The NSSS supplier was GE (Nuclear Energy Division).

The plant, except for the NSSS, was designed by Sargent & Lundy (S&L) Engineers. (Ref. 2 section 1.1)Unit 1 was authorized to commence power operation under license No. NPF-1 1 which was granted on April 17, 1982. Unit 2 was authorized to commence power operation under license No. NPF-18 which was granted on December 16, 1983. (Ref. 18 and 19)1.4 APPROACH The EPRI guidance document is used for the LaSalle County Generating Station Unit 1 engineering walkdowns and evaluations described in this report. In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:* Seismic Licensing Basis* Personnel Qualifications

• Selection of SSCs* Seismic Walkdowns and Area Walk-Bys* Licensing Basis Evaluations, as applicable

• IPEEE Vulnerabilities Resolution Report* Peer Review

1.5 CONCLUSION

Seismic walkdowns have been performed at the LaSalle County 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 in 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 in no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).The Seismic Walkdowns identified nine (9) minor conditions.

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 seven (7) items deferred due to inaccessibility along with supplemental inspections of 18 electrical cabinets.

Area Walk-Bys will be completed, as required, during these follow-on activities.

1-2 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the LaSalle County Station Unit 1 and Unit 2. 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 safe shutdown earthquake for the LaSalle County Station site is 0.20g horizontal ground acceleration and 0.133g vertical ground acceleration. (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 LaSalle County Station UFSAR sections:* 3.7 Seismic Design 0 3.8 Design of Category I Structures

• 3.9 Mechanical Systems and Components 0 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 Design Resoonse Spectra The site response spectra which are defined at the free field foundation level for the SSE and the operating basis earthquake (OBE) are presented in UFSAR Subsection 2.5.2 and are shown in UFSAR Figures 2.5-39 and 2.5-40. The maximum horizontal ground acceleration at the free field foundation level, corresponding to above site response spectra, is 20% gravity for SSE and 10% gravity for OBE. Vertical response spectra used are 2/3 of the horizontal response spectra. Earthquake history, site geology, and seismology are discussed in UFSAR Section 2.5. (Ref. 2 section 3.7)2-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Desigqn Time History In the design of the station, time-history response analyses are used to determine the seismic environment in which internal equipment systems and components must be designed to function.

The site response spectra cannot be used directly as the seismic load in the time-history analysis; rather, equivalent time-history forcing functions are used as the seismic load. (Ref. 2 section 3.7)Spectrum compatible time history is obtained by modifying an actual earthquake time-history record in such a way that its response spectrum matches closely with the given OBE spectrum.

The matching of the response spectrum is done such that the points which are higher are suppressed first. To suppress the response spectrum, the selected time-history motion is passed.through a two parameter frequency-suppression filter. The first parameter is a damping parameter that mainly controls the amount of suppression at the given period, and the second parameter controls the band width of suppression.

These two parameters are adjusted such that the desired suppression effect is obtained at a given period. After that, raising of response spectrum at required periods is done by adding sine waves of appropriate amplitude and phase lag. UFSAR Figures 3.7-1 and 3.7-2 illustrate the horizontal synthetic time histories in both N-S and E-W directions.

These two synthetic time histories are statistically independent.

The vertical synthetic time history is taken from the horizontal E-W synthetic time history with a 1/3 overall reduction in acceleration. (Ref. 2 section 3.7)Modified 1940 El Centro earthquake records for N-S and E-W components are used for these compatible time-history forcing functions.

Compatibility is verified by generating response spectra for 2% and 5% damping ratios as shown in UFSAR Figures 3.7-3 through 3.7-6. In generating these spectra, 72 period intervals from 0.02 to 2.0 seconds are considered.

The period intervals at which the response spectra are calculated are as follows: Period Range (sec) Increment (sec)0.02 -0.1 0.005 0.1-0.4 0.01 0.4 -0.5 0.02 0.5- 1.0 0.05 1.0-2.0. 0.1 (Ref. 2 section 3.7)2.3.2 Summary of Codes and Standards The information presented below has been extracted from the UFSAR Section 3.8. This section summarizes the codes, specifications, standards of practice, and other accepted industry guidelines which are adopted tothe extent applicable, in the design and construction of the following.

The specification reference(s)'associated with each item below are the applicable Codes, standards, and specifications listed in Table 2-1 of this report.* Concrete Containment

-specification reference numbers 1-13, 16-19, 21, 22, 24, 27-29, and 31* Steel pressure retaining components of the containment

-specification reference numbers 12, and 27-29* Drywell Floor -specification reference numbers 1-10, 16-19, 21, 22, 24, and 27-29 2-2 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Reactor Stabilizer Structure

-specification reference numbers 12, 16-19, 24, and 27-29 Reactor Pedestal -specification reference numbers 1-10, 16-19, 21, 22, 24, and 27-29 Reactor Shield -specification reference numbers 3-5, 8-10, 12, 16- 19, 24, and 27-29 Platforms, Galleries and Downcomer Bracing -specification reference numbers 12, 16-19, and 24 Other Seismic Category I Structures

-specification reference numbers 1-10, 12, and 14-31 Table 2-1. List of Codes, Standards, and Specifications UFSAR Table 3.8-2 List of Specifications, Codes, and Standards SPECIFICATION SPECIFICATION TITLE EDITION REMARKS REFERENCE OR STANDARD NUMBER DESIGNATION 1 AC1 318 Building Code 1963 Requirements for Reinforced Concrete 2 ACI 318 Building Code 1971 Requirements for Reinforced Concrete 3 AC1 214 Recommended Practice 1965 for Evaluation of Compression Test Results 4 AC1 301 Specifications for 1972 Exceptions are Structural Concrete for listed in Buildings UFSAR Appendix E 5 ACI 306 Recommended Practice 1966 Additions are for Cold Weather listed in Concreting UFSAR Appendix E 6 AC1 315 Manual of Standard 1957 Practice for Detailing Reinforced Concrete Structures 7 ACI 347 Recommended Practice 1968 for Concrete Formwork 2-3 12Q.108.50-R-.01 Rev. 1 Correspondence No.: RS-12-163 UFSAR Table 318-2 List of Specifications, Codes, and Standards SPECIFICATION SPECIFICATION TITLE EDITION REMARKS REFERENCE OR STANDARD NUMBER DESIGNATION 8 ACI 605 Recommended Practice 1959 Exceptions are for Hot Weather listed in Concreting UFSAR Appendix E 9 ACI 211.1 Recommended Practice 1970 Normal and for Selecting Proportions Heavyweight for Concrete 10 ACI-304 -73 Recommended Practice 1973 for Measuring, Mixing, and Placing Concrete 11 ACI-ASCE Tentative 1969 Recommendations for Concrete Members Pre-stressed with Unbonded Tendons (Committee 423)12 AISC Manual of Steel 1969 Construction 13 ANSI B31.1.0 Standard Code for 1967 Pressure Piping, Power Piping 14 ANSI Al 23.1 Standard Nomenclature 1967 for Steel Door and Steel Door Frames 15 AWS D1.0 Code for Welding in Addenda of Building Construction March 1965 16 AWS A3.0 Definitions for Welding and 1969 Cutting 17 AWS A5.1 Mild Steel Arc-Welding 1969 Electrodes 18 AWS A6.1 Recommended Safe 1966 Practice for Inert-Gas Metal-Arc Welding 19 AWS D12.1 Recommended Practice 1971 for Welding Reinforcing Steel 2-4 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 UFSAR Table 3.8-2 List of Specifications, Codes, and Standards SPECIFICATION SPECIFICATION TITLE EDITION REMARKS REFERENCE OR STANDARD NUMBER DESIGNATION 20 CRSI Manual of Standard 1970 Practice 21 CRSI Recommended Practice 1968 for Placing Reinforcing Bars 22 AISI Light Gage Cord-Formed 1962 Steel Design Manual 23 ASTM Annual Books of ASTM 1972 For applicable Standards ASTM Standards see UFSAR Appendix E 24 ASA B1.1 Unified Inch Screw 1960 Threads 25 ASA B18.2 Square and Hexagonal 1960 Bolts and Nuts 27 ASME ASME Boiler and Pressure Summer of Vessel Code,Section III 1972 and Section IX Addenda 28 ASME 1971 ASME Boiler & Summer of Pressure Vessel Code, 1972 Material Specifications, Addenda Section II 29 ASME ASME Boiler and Pressure 1974 Vessel Code, Section Xl, Edition"In Service Inspection of Summer of Nuclear Reactor Coolant 1975 System" Addenda 30 API Spec No 620 Specification for Welded February Steel Storage Tanks 1970 31 Standard Assoc of The use of Steel in 1981 Australia AS1250 Structures 2-5 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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.(Ref. 1) 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 Equipment Seismic L NSeint Plant Walkdown icensing IPEEE Peer Name Selection Basis Reiwr evwr Engineer Operations Engineer Review Reviewer Reviewer (SWE)A. Perez X K. Hull X T.K. Ram XM D. Carter X X M. Wodarcyk X X J. Griffith X X M. Etre X X T. Bacon X W. Djordjevic X(2)T. Dean (Exelon) X Jorge Sanchez X X (Exelon)Notes: 1. Peer Review Team member for SWEL review only.2. Peer Review Team Leader.3-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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.

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. 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 Inspections (CDBI), and with INPO in their biennial evaluations.

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.David Carter, P.E., S.E. Mr. Carter is a Senior Engineer III in the S&A Chicago, IL Office. He has a Bachelor of Science degree in civil engineering and has more than 30 years of experience in the nuclear power plant industry.

He is a licensed Structural 3-2 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Engineer in the State of Illinois and is a licensed Professional.

Engineering in several states. He is a SQUG Qualified Seismic Capability Engineer (SCE) and has completed the NTTF Recommendation 2.3 Training Course (SWE). In addition to his involvement in design and analysis of structures, systems, and components at nuclear power plants, he has performed SQUG walkdowns at various nuclear power plants. He has worked for over ten years as a Seismic Qualification Engineer at another utility performing seismic evaluations of plant equipment, input to procurement documents, and reviewing seismic qualification reports for new plant equipment.

Michael Wodarcyk, E.I.T. Mr. Wodarcyk is a Staff Engineer in the S&A Chicago, IL Office. He has a Master of Science Degree in Civil Engineering and has been working in the nuclear power plant industry for slightly more than one year. He has completed the NTTF Recommendation 2.3 Training Course (SWE). He has been involved in the design and analysis of rigging configurations, piping and pipe supports, and other various structures.-Jim Griffith, P.E. Mr. Griffith is a Senior Engineer III in the S&A Chicago, IL Office. He has a Bachelor of Science degree in civil engineering and has more than 25 years of experience in the nuclear power plant industry.

He is a licensed Professional Engineer in the State of Wisconsin.

He is a SQUG Qualified Seismic Capability Engineer (SCE)and has completed the NTTF Recommendation 2.3 Training Course (SWE). In addition to his involvement in design and analysis of structures, systems, and components at nuclear power plants, Mr. Griffith has many years of experience working at numerous nuclear power plants in support of construction, design, outage, and walkdown activities including SQUG walkdowns.

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.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 3-3

.12QO18.50-R-o-1 Rev. 1 Correspondence No.: RS-12-163 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).3.2.2 Additional Personnel Exelon plant Operations staff member Thomas Dean, reviewed the SWEL. Mr. Dean is the Manager of Operations Support at LaSalle County Station. He is currently a licensed SRO and has been since 2002. Mr. Dean has worked in the operations department for 12 years and 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.

Exelon Engineering staff member Mr. Jorge Sanchez performed the IPEEE Vulnerabilities Review based, in part, on the IPEEE submittal along with subsequent correspondence and station records. (Ref. 3) Mr. Sanchez is a Structural Engineer in the Exelon Engineering Department.

He has a Bachelor of Science degree in civil engineering and a Master of Science degree in structural engineering.

He has worked at LaSalle since 2010. He has successfully completed Seismic Evaluations Training and the Near-Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Training Course. Mr. Sanchez is a licensed Professional Engineer and Structural Engineer in the State of Illinois.3-4 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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" 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, was utilized to develop the SWEL for LaSalle County Generating Station Unit 1. (Ref. 1)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 4.2.1 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 composite list of Safety Related systems, structures, and components identified in the station master equipment list.This initial data set contained approximately 52, 831 items for LaSalle Unit 1, Unit 2, and common Unit. This data set was then screened based on the following four screens to identify the items to be included on the first Seismic Walkdown Equipment List (SWEL 1): 1. Screen #1 -Seismic Category I As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. Consistent with the LaSalle County Power Station UFSAR Chapter 3, SSCs identified as Safety-Related are also Seismic Category I.(Ref. 2) As such, all items on the initial data set are included for consideration to be added to SWEL 1.4-1 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 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 reduced the data set of any Class I Structures, Containment Penetrations, Class I Piping Systems, cable/conduit raceways and HVAC ductwork.

Major pieces of equipment in the Nuclear Steam Supply System (NSSS) located inside the containment were also removed from the data set.3. Screen #3 -Support for the Five Safety Functions This screen is intended to narrow 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.

This screen began as an effort to assign safety function(s) to each item in the data set. This was accomplished on a 'system' based effort by utilizing Reference 1 Appendix E: Systems to Support Safety Functions.

Reference 1 Appendix E provides guidance to identify systems that support each of the safety functions.

It is noted that items on SWEL 1 with a specific safety function(s) are considered frontline systems. Items with a safety function of 'Auxiliary

& Support', 'Electrical Systems', or 'Racks &' Panels' may be a frontline or support system. Items with a safety function of 'Auxiliary

& Support', 'Electrical Systems', or 'Racks & Panels'support at least one of the five safety functions however, the specific safety function(s) is not indicated as identification of the specific safety function(s) supported is not required by Reference 1.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. Screen #4- Sample Considerations This screen is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Category I equipment and systems to meet the objectives of the NRC 50.54(f) letter. The following attributes were considered in 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 multiple safety functions.

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

4-2 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 B. Major new and replacement equipment As described in Reference 1, the intent of this screening element is to ensure that equipment that has been modified or was not included as part of the seismic evaluations performed to address the Individual Plant Examination of External Events (IPEEE) program is included on the SWEL 1. However, based on References 3 and 5, seismic evaluations of SSCs were not conducted at the LaSalle County station as part of the IPEEE program.Instead, the licensee relied exclusively on the level III PRA developed to address the IPEEE program. Further, a review of Reference 4 Section 8 revealed that LaSalle specific equipment fragilities were limited to a very small population of equipment and that generic seismic equipment fragilities were relied on for most equipment.

This is an important point because it reveals an absence of extensive seismic evaluations of equipment generally necessary to develop equipment specific fragilities.

Because conducting seismic evaluations was not a major element of the IPEEE program at LaSalle, there is no need to identify equipment that has been modified or replaced since the completion of the IPEEE program.However, as a measure to meet the intent of this element, Reference 4, Table 8.2 LaSalle specific equipment fragilities, was reviewed and of the 39 items listed at least 12 were added to the SWEL 1. These items are not specifically 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. 1, #2, and #3 resulted in no equipment in the following classes:* 11. Chillers,* 13. Motor Generators.

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 No vulnerabilities or plant improvements were identified as a result of the IPEEE program. (Ref. 3 and 5)F. Contribution to risk In selecting items for SWEL I 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 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1. (Ref. 8)4.2.2 SWEL 2 Development-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 Only those items identified as Seismic Category I (having defined seismic licensing basis) are to be included on SWEL 2 with exception to the SFP structure.

As described in Reference 1, the adequacy of the SFP structure is assessed by analysis as a Seismic Category I 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.The review of design and licensing basis documentation for the SFP revealed there are SSCs that are Seismic Category I for LaSalle County Generating Station Unit 1.(Ref. 2) UFSAR Table 3.2-1 item XX indicates that the Spent Fuel Pool pumps, piping and valves are Seismic Category II. However, Note (18) of UFSAR Table 3.2-1 states, in part, piping which provides a flow path from the fuel pool skimmer surge tanks to the RHR system and back to the fuel pool up to and including the isolation valves, which provide pressure boundary for this mode of operation is Seismic Category I. Based on this Note, the indicated piping and valves were included for further selection of SSC for SWEL 2.It is noted the Spent Fuel Pool Emergency Make-Up Pumps, valves, and piping is Category I. However, this system piping terminates with a normally closed valve and capped end that does not communicate directly with the SFP or the SFP cooling system. This equipment was not included for consideration to be added to the SWEL 2.2. Screen #2- Equipment or Systems This screen considers only those items associated with the SFP that are appropriate for an equipment walkdown process. The only equipment identified for consideration to be added to SWEL 2 included piping and manual valves. Only the manual valves are considered appropriate for inclusion to SWEL 2.3. Screen #3- Sample Considerations This screen represents a process that is intended to result in a SWEL 2 that sufficiently represents a broad population of SFP Seismic Category I equipment and systems to meet the objectives of the NRC 50.54(f) letter. (Ref. 1) The following attributes were considered in the development of SWEL 2: A. A variety of types of systems The system is identified for each item on SWEL 2. The equipment included on SWEL 2 is to be a representative sample of the systems associated with the SFP and its cooling system. The only equipment considered for inclusion to SWEL 2 is within the Spent Fuel Pool Cooling system.4-4 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 B. Major new and replacement equipment The equipment included on SWEL 2 includes items that have been modified or replaced over the past several years. Each item on SWEL 2 that is new or replaced is identified.

There was no modified or replacement equipment identified.

C. 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 only equipment for consideration to be included on SWEL 2 is manual valves which are class (00) Other.D. A variety of environments The location for each item is identified on SWEL 2. The equipment included on SWEL 2 is a representative sample from a variety of environments (locations) for equipment associated with the SFP and its cooling system. The only equipment considered to be included on the SWEL 2 is located in the Reactor Building.4. 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 (having defined seismic licensing basis) items, but are 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the earthquake.

An assessment of the LaSalle County Generating Station Unit 1 spent fuel pools and their cooling systems was performed and found no SFP penetrations below 10 feet above the top of the fuel assemblies. (Ref. 2, 9, 10, 11, 12, 13, 14, 15, 16, &17) As such, and consistent with Reference 1, there is no potential for rapid drain-down and no items were added to SWEL 2.It is noted the isolation valve between the RHR system and the spent fuel pool return line is located upstream of the spent fuel pool return line siphon breaks. As such, these valves were not considered to be included on the SWEL 2. (Ref. 9)Two (2) items were identified to be included in the scope of SWEL 2 for LaSalle County Generating Station Unit 1.4-5 12Q.108.50-R-O1.

Rev. 1 Correspondence No.: RS-12-163 5 Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by two (2) person teams of trained Seismic Walkdown Engineers (SWEs) in accordance with the EPRI guidance document during the weeks of August 27, 2012, September 3, 2012, September 10, 2012, and September 17, 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 109 of the 116 total items identified on the LaSalle Unit 1 SWEL. The completed SWCs are provided in Appendix C of this report. 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 seven (7) items to a unit outage or another time when the equipment is accessible.

These items could not be walked down during the 180-day period following the issuance of the 1 0CFR50.54(f) letter due to their being inaccessible.

Inaccessibility of this equipment was either based on the location of 5-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 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 Configuration Verification 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.5-2 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Examples of documentation that was considered to verify that the anchorage installation configurations are consistent with the plant documentation include the following:

• Design drawings* 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 116 55 31 42 5.2.3 Adverse Seismic Spatial Interactions 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.

5-3 12Q0108:50-R-001 Rev. 1 Correspondence No.: RS-12-163 5.2.4 Other Adverse 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 the conditions identified during the equipment Seismic Walkdowns.

The equipment Seismic Walkdowns resulted in a total of four (4) conditions identified which were entered into the station's CAP. The conditions were assessed and it was concluded that the conditions would not prevent the associated equipment from performing its safety-related function(s).

The conditions identified by the SWEs during the equipment Seismic Walkdowns were concluded to not 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, elg., 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 44 AWCs were completed for LaSalle Unit 1. It is noted that additional AWCs will be completed as deferred and supplemental inspections are completed.

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

• 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)* Potentially adverse seismic interactions including those that could cause flooding, spray, and fires in the area 5-4 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163* Other housekeeping items that could cause adverse seismic interaction (including temporary installations and equipment storage)* Scaffold construction was inspected to meet Exelon Procedure NES-MS-04.1 Seismic Prequalified Scaffolds* Seismic housekeeping was examined to meet station procedure LAP-1 00-56, Equipment

/ Parts Storage in Plant Areas Containing Safety-Related Equipment 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.5-5 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 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* 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.

Six (6) 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 5-6 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 4. Transformers

14. Distribution Panels and Automatic Transfer Switches 16. Battery Chargers and Inverters 20. Instrumentation and Control Panels 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.

5-7 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Table 5-2. Conditions Identified during Seismic Walkdowns Actions Action Complete Item ID Description of Issue Request (Yes/No, ID (IR) See Notes 1 &2)1 C11 -DO01 001, During the performance of Fukushima 1 C11-D001089, Seismic Walkdowns on Unit One, it was 1C1 1-DO01093, noted that the S-hooks associated with the 1C11-D001182, chains holding fluorescent lighting fixtures 1C11-D2659-125, were not completely crimped closed. Two of 1C11-D2659-126, the areas noted were in the vicinity of the 1C1 1-D2659-127, Unit 1 North and South Hydraulic Control 1C1 1-D3003-125, Unit (HCU) banks in the Reactor Building 1406922 No 1C 11-D3003-126, (761' Elevation).

It should be noted that the 1 C11-D3003-127, S-hooks are closed enough such that they 1 C11-D3403-125, would not allow the fixture to become 1C11-D3403-126, disconnected during a seismic event;1 C11 -D3403-127, therefore, this is not a seismic issue per 1C1 1-D4259-125, Engineering.

However, these S-hooks 1C 11-D4259-126, should be completely crimped closed as per 1 C1l1-D4259-127 normal maintenance standards.

Rack 1 H22-P021 is in contact with existing pipe support RH11-1412G auxiliary steel.Both the rack frame member and the pipe support cantilevered member are relatively flexible at the point of contact. The instruments on the rack are mounted away from the point of contact and therefore any 1E12-N007B, impact energy imparted to the rack during a 1E12-NO7B, seismic event will significantly dissipate 1411614 Yes before reaching the instruments.

Margin between the horizontal seismic accelerations experienced by the rack during seismic qualification testing and the peak horizontal seismic accelerations expected during a design-basis sesmic event (per LaSalle Seismic Response Spectra) is large. Contact judged to be acceptable.

Hairline crack on face of instrument pressure 1E12-F051B gauge for the valve will not affect 1412094 Yes functionality of valve per Engineering.

5-8 1200108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Actions Action Complete Item ID Description of Issue Request (Yes/No, ID (IR) See Notes 1 &2)During the performance of Fukushima Seismic Walkdowns in the Unit 1 Diesel Generator Building, El. 736 ft., it was noted that a small portion of the grout under the base plate of 1VY05C "RHR ECCS Equipment Cooling Fan" is dried out. The grout provides moisture protection for the 1VY05C anchors and acts to transfer the equipment 1419071 No load to the floor slab through bearing. The small amount of grout missing does not adversely affect the overall functionality of the grout installation and the anchor's two nuts (one above the base plate and one below) serve to hold the whole assembly in place. Therefore, per Engineering, this is not a seismic concern.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 Corrective Action Program.5-9 12Q.108.50-R-O.1 Rev. 1 Correspondence No.: RS-12-163 Table 5-3. Conditions Identified during Area Walk-Bys Actions Item ID Action Complete (AWC- Description of Issue Request (Yes/No, U1-) ID (IR) See Notes 1 &2)During the performance of Fukushima Seismic Walkdowns on Unit One, it was noted that the S-hooks associated with the chains holding fluorescent lighting fixtures were not completely crimped closed. The areas noted were the Unit One Diesel Generator Penthouse, as 1-05,1- well as the Unit One Hydraulic Control Units (HCUs) in the Reactor Building (Elevation 761'). It should be noted 1406922 No that the S-hooks are closed enough such that they would not allow the fixture to become disconnected during a seismic event; therefore, this is not a seismic issue per Engineering.

However, these S-hooks should be completely crimped closed as per normal maintenance standards.

During the performance of Fukushima Seismic Walkdowns in the Unit One Reactor Building, it was noted that a floor plug located on the 786' Elevation (A&10) needed to be resealed.

Sealant is missing between the south plug and the center plug. Per Engineering and 3-02 LAP-300-44, Rev. 20, "Floor Plug Removal and 1410959 Yes Installation", this is not a seismic, flooding, or EQ issue with the sealant missing. It was verified with the Fire Marshall that this floor plug has no fire rating; therefore it is not a fire protection issue. This is a housekeeping issue only.During the performance of Fukushima Walkdowns in the Unit One Reactor Building, it was noted that there was a pipe clamp that was not installed on a short run of tube spanning between valves 1 B33-NO1 8B-RR and 1 B33-3-14 NN018B-UDV on RHR Instrument Panel 1H22-P021.

Per 1412069 No Engineering, this is not a seismic issue due to the fact the tube is relatively flexible and has a short unsupported span between the aforementioned valves. Therefore, functionality of the tube would not be affected during a seismic event.5-10 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Actions Item ID Action Complete (AWC- Description of Issue Request (Yes/No, Ul-) ID (IR) See Notes 1 & 2)During the performance of Fukushima Seismic Walkdowns in the Unit One Reactor Building, it was noted that 1 B33-SO01 B "1 B Reactor Recirculation Pump Low Frequency Motor Generator Set" motor termination 4-01 junction box had a loose bolt. The loose bolt is located on 1414865 Yes the north end, west side of the box. The loose bolt is one of several bolts that attach the cover plate to the junction box. The loose bolt has no significant effect on the junction box integrity, therefore per Engineering this is not a seismic issue.During the performance of Fukushima Seismic Walkdowns in the Unit One Reactor Building, it was noted that on two back panel doors the lower bolts on 1AP61E "480V MCC 133-1" were not engaging on the lower portion of the doors. The two doors are the second and fourth back panel doors coming from the north. The 4-03 bolts were tightened by Operations but are not holding 1414894 Yes properly.

The top bolt and the middle bolt on each of the above mentioned doors are secured properly, therefore the doors are closed and secure. Per Engineering, this is not a seismic issue due to the fact that the doors are adequately secured in their as-found condition and will not interact adversely with MCC 1AP61E during a seismic event.During the performance of Fukushima Seismic Walkdowns in Unit 1, the Unit 1 Main Control Room received an unexpected alarm for Reactor Building South Water Tight Door Open on 1 PM06J. Door 5, RHR Pumps B & C Pump Room to Basement Area Unit 1 was verified closed. All water tight door seals and room 3-14 penetration seals were verified operable and showed no 1411647 No signs of degradation, damage, or obstruction.

The water tight door met all requirements of LOP-PF-01 and TRM 3.5.a for operability at all times. The alarm limit switch/door switch for Door 5 appears degraded and it was not entirely made up when the Main Control Room alarm was received.

This is not a seismic issue.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 Corrective Action Program.5-11 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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/LaSalle utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/LaSalle 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.6-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 7 IPEEE Vulnerabilities Resolution Report A review of the LaSalle County Nuclear Power Station Individual Plant Examination of External Events (IPEEE) Submittal along with the NRC Staff Evaluation Report of the IPEEE found that no vulnerabilities were identified and no plant improvements resulted from the IPEEE program. (Ref. 3 and 5)7-1 12..108.50-R-O.1 Rev. 1 Correspondence No.: RS-12-163 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.8-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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. LaSalle County Power Station Updated Final Safety Analysis Report (UFSAR), Revision 19, April 2012 3. Nuclear Regulatory Commission letter to Mr. Oliver D. Kingsley, Commonwealth Edison Company, dated December 8, 2000,

Subject:

LaSalle County Station, Units 1 and 2 NRC Staff evaluation of the Individual Plant Examination of External Events (IPEEE) Submittal (TAC NOS. M83634 And M83635)4. NUREG/CR-4832, Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP), Vol. 8 5. Commonwealth Edison Letter from Gary G. Benes to U.S. Nuclear Regulatory Commission, dated December 12, 1994,

Subject:

LaSalle County Nuclear Power Station, Individual Plant Examination and Individual Plant Examination (External Events) Submittal, NRC Dockets 50-373 and 50-374 6. 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." 7. "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. ML111861807, July 12, 2011 8. Internal RM Document LS-MISC-16, Rev. 0, SWEL Risk Importance Input 9. Drawing M-98, Sheet 1 Rev. AO, P&ID Fuel Pool Cooing Filter & Demineralizing System 10. Drawing M-98, Sheet 2 Rev. X, P&ID Fuel Pool Cooing Filter & Demineralizing System 11. Drawing M-98, Sheet 3 Rev. K, P&ID Fuel Pool Cooing Filter & Demineralizing System 9-1 12Q.108.50-R-O.1 Rev. 1 Correspondence No.: RS-12-163 12. Drawing M-98, Sheet 4 Rev. N, P&ID Fuel Pool Cooing Filter & Demineralizing System 13. Drawing M-87, Sheet 1 Rev. BD, P&ID Core Standby Cooling System Equipment Cooling Water System 14. Drawing M-87, Sheet 2 Rev. AR, P&ID Core Standby Cooling System Equipment Cooling Water System 15. Drawing M-87, Sheet 3 Rev. 0, P&ID Core Standby Cooling System Equipment Cooling Water System 16. Drawing M-770, Sheet 9 Rev. G, Substructure Piping Unit 1 17. Drawing M-770, Sheet 10 Rev. F, Substructure Piping Unit 1 18. Exelon Generation Company, LLC, Docket No. 50-373, LaSalle County Station, Unit 1, Facility Operating License, License No. NPF-1 1 19. Exelon Generation Company, LLC, Docket No. 50-374, LaSalle County Station, Unit 2, Facility Operating License, License No. NPF-1 8 9-2 1200108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 A Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix A: A. Perez, Equipm ent Selection Engineer .........................................................

A-2 K. Hull, Equipm ent Selection Engineer ............................................................

A-6 J. Griffith, SWE, Licensing Basis Reviewer .......................................................

A-9 D. Carter, SWE, Licensing Basis Reviewer ......................................................

A-13 M. Etre, SWE, Licensing Basis Reviewer ........................................................

A-16 M. Wodarcyk, SWE, Licensing Basis Reviewer ...............................................

A-19 T. Ram , SW EL Peer Review er .....................................................................

A-21 T. Bacon, Peer Review er ............................................................................

A-23 W. Djordjevic, Peer Review Team Leader ..............................

A-28 Jorge Sanchez (Exelon), Licensing Basis Reviewer, IPEEE Reviewer ..................

A-32 A-1 Stev 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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-2 Ste%12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163& 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-3 Stev 12Q0108.50-R-OO1 Rev. 1 Correspondence No.: RS-12-163 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-4 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 A-5 12..108.50-R-O.1 Rev. I Correspondence No.: RS-12-163 KIM L. IULL 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)* 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-6 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 1OCFR 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.* 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-7 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 A-8 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 STEVENSON

& ASSOCIATES JAMES D. GRIFFITH QUALIFICATIONS Knowledgeable professional with over 23 years of diverse experience in structural engineering.

Thorough, results-oriented problem solver with excellent communication skills. Works well independently or as part of a team. Highly skilled in all project phases from design through construction and specializes in field problem resolution.

PROFESSIONAL EXPERIENCE Promect Engineer (Stevenson

& Associates, 2000 to present)Responsible for all aspects of civil structural design. Also provides interface between clients, vendors, constructors and Stevenson

& Associates.

Decommissioning Design Engineer (CoinEd, 1998 to 2000)Responsible for structural design work during conversion from generating to storage facility.

Gathered design information during conceptual field walkdowns and prepared design calculations and drawings.Provided field support during construction.

• Designed all component supports and concrete foundations for various new indoor equipment.

• Managed construction during installation of new roof-mounted HVAC system.* Designed structural steel support framing and access gallery for new outdoor cooling towers.Maintenance Engineer (CoinEd, 1995 to 1998)Responsible for the design of structural repairs to station equipment and facilities.

Interfaced with maintenance and construction personnel and performed evaluations of rigging, lead shielding, and scaffolding.

Investigated and developed solutions for structural problems in the field and provided field support during installation of modifications.

• Designed and supervised field installation of heavy-duty rigging apparatus for replacement of large overhead crane motor.* Performed conceptual design and supervised field construction of 60 foot high scaffold work platform for valve replacement.

• Prepared and reviewed calculations to justify structural acceptability of station equipment during successful completion of Seismic Qualification Utility Group (SQUG) evaluation program.* Acted as engineering liaison to other station departments (Maintenance, Operations, Radiation Protection, etc) to resolve emergent problems regarding:

• Rigging for lifting various plant equipment* Placement and support of temporary lead shielding* Storage of equipment in safety related seismic areas of the plant* Structural repairs and improvements to plant buildings and equipment Structural Engineer (Sargent and Lundy, 1983 to 1995)Responsible for design of structural modifications to various components of power generating facilities.

Prepared and reviewed design calculations and drawings* Designed numerous modifications to existing structural steel framing members and end connections.

1 A-9 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163" Supported field installation of modifications and provided solutions to problems encountered in the field." Designed and monitored field installation of new access galleries for various pieces of equipment.

EDUCATION B.S., Civil and Environmental Engineering, University of Wisconsin, Madison, Wisconsin Continuing Education"Concrete Evaluation and Repair Seminar", Portland Cement Association, Skokie, Illinois, 1996"STAAD III Program Training", Sargent and Lundy Engineers, Chicago, Illinois, 1995"Piping Design, Analysis and AUTOPIPE Training" Vectra Technologies, Inc., Zion, Illinois, 1995"SQUG Walkdown Screening and Seismic Evaluation Training Course", Seismic Qualification Utility Group through ComEd, Downers Grove, Illinois, 1994 PROFESSIONAL REGISTRATIONS Licensed Professional Engineer in State of Wisconsin 2 A-10 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Jim Griffith SuccessfUlll Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Ar er~ ~)Date: 06/26/12 Bruce M. L4 -Instructdr NTTF 2.3 Seismic Walkdown Course A-11 "12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SQUG fiT Vý,rrtif iratir of Ar~iiiutimrnt

~T~is is to (Trrtifij tl~nt 4as (TnMPIirtb the §'(QQ1Qs wallkbowu 4 Unb §'eismir Euuluaiiou cuiatinin 4 4 A,. 2.-q to& 11I9iYV Dateof Course -----7 4 4 SQUG RepresenLative Training Course A raor a a a a a a a a a A-12 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 Stevenson

& Associates DAVID N. CARTER PROFESSIONAL EXPERIENCE April, 1998-Present Wisconsin Electric, Point Beach Nuclear Plant (On loan from Stevenson

&Associates)

Point Beach Nuclear Plant is located in Wisconsin between Milwaukee and Green Bay on Lake Michigan.Worked as Seismic Qualification Engineer responsible for performing seismic evaluations of plant equipment as well as providing input to procurement documents and reviewing seismic qualification reports for new plant equipment.

Also worked as Design Engineer preparing and managing various plant modifications.

Modifications included reinforcement of RWST anchorage, new HELB barriers and vent paths, new firewall, platform and foundation modifications.

The modification preparations included preparing design change documents, 50.59 safety evaluations and calculations as well as assisting in resolution of installation problems.December, 1997-April, 1998 Stevenson

& Associates Stevenson

& Associates is a consulting engineering firm. Work includes design and analysis of building structures and components.

April, 1995-December, 1997 CornEd, Zion Station Zion Station is a nuclear power plant that is owned and operated by ComEd, an electric utility serving northern Illinois.

Member of design engineering group as a Senior Structural Engineer.

Work included the scoping, cost estimating, design and preparation of design documents for various plant modifications.

Prepared 50.59 safety evaluations for various plant modifications.

Member of the Zion Seismic Review Team that implemented the SQUG program. Performed SQUG walkdowns and assessments.

Proposed and implemented upgrades to SQUG outliers.

Attended and completed the SQUG SCE Training.April, 1984-April, 1995 Sargent & Lundy Engineers Sargent & Lundy is a consulting engineering firm that specializes in the design and modification of power plants. Work included the design and analysis of building structures and support components on fossil and nuclear power plants. Assignment highlights include the following:

• Member of modification design project team at Zion Station.* Member of Zion project team in Sargent and Lundy Chicago office for approximately two years.Worked on various modifications for Zion Station as a Senior Engineer in the Structural Engineering Division.

Design activities included preparation, review or approval of design calculations, design documents such as engineering change notices and design criteria documents.

Supervised up to four other engineers.

• Member of a design team working on the design of two new nuclear units located in Korea (Yonggwang 3&4). The design was done in the offices of Korea Power Engineering Corporation located in Seoul, Korea. Responsibilities included the design of the structural steel for the turbine building.

The assignment involved working with and providing guidance for engineers from the Korean engineering company. The work also involved the preparation of design procedures, procurement specifications, and design calculations as well as the review of design drawings and shop drawings.

The length of this assignment was approximately four years.1 A-13 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163* Member of a group Of engineers that worked on a weld evaluation program at Watts Bar Nuclear Power Station. The assignment included the evaluation of various weld discrepancies on structural steel connections and component supports.

This assignment lasted one year.* Member of various project teams which worked on the design of modifications for fossil and nuclear power plants. Projects include Dresden, Quad Cities, Byron, Braidwood Stations (Commonwealth Edison Co.), and Parish Station (Houston Lighting and Power). Work included the assessment of masonry walls, design of component supports, design of hot air ducts, evaluation of structural steel framing for final loads and preparation of study and design reports. Responsibilities also included the preparation and review of design documents, letters, supervising other engineers, and meeting with clients.September, 1980-March 1984 American Bridge Division -United States Steel Corp.American Bridge was a consulting engineering firm whose main client was U.S. Steel. They specialized in the design and modification of steel mill buildings.

Assignments included the following:

• Design of various modifications to blast furnaces." Member of group of engineers whose function was to inspect existing mill buildings, prepare a report of findings and recommend repairs. Included in this assignment was the preparation of design drawings showing the recommended repairs. This assignment lasted approximately one year." Loaned to Sargent and Lundy Engineers to assist in the design of component supports and the final load evaluation on Byron Nuclear Power Station. This assignment totaled approximately 16 months.EDUCATION Syracuse University, L. C. Smith College of Engineering; Bachelor of Science Degree in Civil Engineering.

Graduated Cum Laude.PROFESSIONAL AFFILIATIONS Licensed Professional Engineer in State of Minnesota Licensed Structural Engineer in State of Illinois Licensed Professional Engineer in State of Wisconsin 2 A-14 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Dave Carter Successfully Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. Lofy -Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-15 12Q.108.50-R-Oo1 Rev. 1 Correspondence No.: RS-12-163 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, Engineering 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 Director of 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 54 A-16 12QO108.50-R-OO1 Rev. 1 Correspondence No.: RS-12-163 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, Engineering Backlog 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.

Engineering Supervisor 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 Hartford, 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 S"4 A-17 LaSalle County Generating Station Unit 1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 A-18 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 MICHAEL WODARCYK EMPLOYMENT Stevenson

& Associates, Glenview, Illinois Staff Engineer June 2011 -present* Analysis and design of nuclear power plant structures and other assorted structures.

On-site engineering at plants during outage maintenance periods.ESCA Consultants, Urbana, Illinois Design Engineer September 2010 -June 2011* Structural design and hydraulic modeling of bridges for the Illinois Department of Transportation, Canadian National Railway, BNSF Railway, and others. Inspection of the production of precast structural elements for CN.Evans, Mechwart, Hambleton, & Tilton, Columbus, Ohio Intern May 2007 -August 2007, May 2008 -August 2008* Assisted in the design and drafting of site, stormwater, and utility plans for various projects using AutoCAD, including the headquarters tower and garage for Grange Insurance in downtown Columbus.D.E. Huddleston General Contractors, Columbus, Ohio Laborer May 2006 -August 2006* Constructed footing foundations and performed other miscellaneous tasks for two elementary schools under construction in the Columbus City Schools district.EDUCATION University of Illinois, Urbana-Champaign Master of Science, Civil Engineering Structural Engineering Concentration GPA: 3.66 (of 4.0)University of Notre Dame Bachelor of Science, Civil Engineering GPA: 3.47 (of 4.0)Urbana-Champaign, Illinois August 2010 Notre Dame, Indiana May 2009* Undergraduate Research, January 2009 -August 2009 Studied the effects that different structural systems have on the harmonic damping of a high-rise structure.

Modeled a case study high-rise building using SAP2000.* Big Beam Contest, August 2008 -February 2009 Led a team of four students that designed, built, and tested Notre Dame's entry for the Precast/Prestressed Concrete Institute's Big Beam reinforced-concrete beam contest, with all design considerations based upon ACI 318-08 and PCI 6th ed. codes and specifications.

This design won 2nd place in the contest's Zone 4 (Midwest).

CERTIFICATIONS Engineer-in-Training First Aid April 2009 August 2008 ORGANIZATIONS American Concrete Institute American Society of Civil Engineers A-19 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Mike Wodarcyk Success~ulhj Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Date: 06/26/12 Bruce M. Ley -Instructor NTTF 2.3 Seismic Walkdown Course A-20 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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

• Plant Systems Engineering

• Transformer and Relay(s) Spec Developer* Plant Modification Engineering

• Systems and Component Test Engineering 0 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-21 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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-6-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-22 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 C275 AMishawumn Road, Suite 200, Woburn, MA 01801 Tel (78!) 932-9580 Fax (781) 933-4428 www. vecsa. corn Stevenson

& Associates Engineering Solutions for 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-0336 104 (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 BOSTON &CLEVELAND oCHICA GO oMINNEA POLLS oPHOENIX A-23 12Q0108.50-R-001 Rev.Correspondence No.: RS-12-163 275 Mishawuni Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428.www. vecsa. com Stevenson

& Associates Engineering Solutions for 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 Managerin 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 Fabrication Facility, 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 BOSTON eCLEVELA ND oCHICA GO oMINNEA POLISoPHOENIX A-24 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 c A 275 Mishawurn Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa. corn Stevenson

& Associates Engineering Solutions for 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 Debris Blockage 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 Operability and 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 Drain Line Modifications, Palisades Nuclear 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 Piping Project Evaluation, D. C. Cook Nuclear Power Plant, Indiana/Michigan Power -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 Drain Line Unplugging Project, Dresden Nuclear Generating Station Units 2 & 3, Commonwealth Edison. Included serving 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.HPCI System Sparger Modification, Quad Cities Nuclear Generating Station, CoinEd -Served as the Structural and Engineering Mechanics Project Engineer and Manager for Quad Cities Unit 1 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 Party Reviews, Dresden and Quad Cities Nuclear Generating BOSTON aCLEVELAND

• CHICA GO oMINNEA POL IS oPHOENIX A-25 12Q.108.50-R-O.1 Rev. 1 Correspondence No.: RS-12-163 275 Mishawumn Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa. corn Stevenson

& Associates Engineering Solutions for 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 III, 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 Operability Guidelines, CornEd and AEPSC -Wrote numerous project summary reports and operability guidelines for Commonwealth Edison (CornEd) 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 I 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 Ferry Nuclear Power Plant, Tennessee Valley Authority (TVA) -Involved in the analysis of the control rod drive frames for the Browns Ferry Plant.BOSTON OCLEVELAND oCHICAGO eMINNEA POLLS oPHOENIX A-26 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Todd Bacon Success{fullh Completed Training on -Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. L Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-27 12Q.108.50-R-O.1 Rev. 1 Correspondence No.: RS-12-163 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-28 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 Stationp M , Byron StationPM, Dresden Stationp M , 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-29 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 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 1 E 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-30 "12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Walter Djordjevic Successfully Completed Training on Near Term T ask Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. Lorf- Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-31 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163" Exeton.JORGE L. SANCHEZ, S.E., P.E.EXPERIENCE

SUMMARY

Exelon Nuclear, LaSalle, IL 2010-present Civil/Structural Engineer" Responsible Engineer for numerous structural related modifications and projects including Reactor Building Upgrades to support Dry Cask Storage and Low Level Waste.* Responsible Engineer for the Structures Monitoring Program.* Structural/Seismic Engineering representative for the Fukushima Seismic Walkdown Project." Qualifications in Configuration Change Responsible Engineer, Engineering Reviewer, Calculations, and General Structural Activities

• General Seismic walkdown and scaffolding-qualification expert.Chamlin & Associates, Peru, IL 2000-2010 Structural Engineer, Professional Engineer" Responsible for a wide range of projects in all aspects and phases of design from proposal through final construction for industrial, commercial, institutional, municipal and state clients.* Experience includes the design and construction of structures of all types and materials including bridge and building foundations, wall framing, roof systems with steel, reinforced concrete, prestressed/precast concrete, masonry and timber as part of new construction and expansion to existing structures." Design equipment-specific supports under static and dynamic loading scenarios.

This experience includes overhead crane bay hoists, elevated walkways and equipment access platforms, shoring and temporary soil retention systems, above and under ground storage tanks and foundations, pipe rack supports, complete fall-protection system framing, temporary rigging and shoring for critical lifts using mobile cranes.* Further experience includes temporary rigging for major electrical transformer replacement projects." Investigate and analyze structural load capacity of existing structures, provide retrofit and remedial measure recommendations for substandard structures, and conduct root-cause failure determination investigations.

Illinois Department of Transportation, Ottawa, IL 1998-2000 Resident Engineer* Responsible for the construction oversight of various roadway improvements and bridge construction projects.* Specific responsibilities included construction layout, material testing and documentation and contractor coordination and oversight.

A-32 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 A Exelon.Duke Engineering and Services, Naperville, IL 1997-1998 Design Engineer" Responsible for piping analysis and support design for multiple systems at LaSalle and Dresden power plant stations.* All structural computations were prepared in accordance with NRC permit regulations and included static and dynamic loadings scenarios.

• Participated as part of design and analysis team for the ECCS strainer replacement projects.* Prepared computations to support qualifying existing structural components for proposed loadings from instrumentation components or additional piping.EDUCATION University of Illinois, Champaign

-Urbana, IL -Bachelor of Science in Civil Engineering, 1995 University of Illinois, Champaign

-Urbana, IL -Master of Science in Structural Engineering, 1997 QUALIFICATIONS AND TRAINING Registered Professional Engineer / Illinois -2002 Registered Structural Engineer / Illinois -2004 ACTIVITIES ASCE Member, Society of Hispanic Professional Engineers (SHPE)North American Young Generation in Nuclear (NA-YGN)Chi Epsilon Civil Engineering Honor Society American Society of Civil Engineers Illinois Society of Professional Engineers A-33 12Q0108.50-R-OO1 Rev. 1 ELECTRIC POWER RESEARCH INSTITUTE Certificate of Completion Jorge Sanchez Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 27, 2012 Date Robert K. Kassawara EPRI Manager, Structural Reliability

& Integrity A-J4 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 B Equipment Lists Appendix B contains the equipment lists that were developed during SWEL development.

Note that because no Rapid Drain-Down items existed for LaSalle County Generating Station Unit 1, there is no Rapid Drain-Down Equipment List.The following contents are found in Appendix B: SWEL Approval Signature Page ......................................................................

B-2 Table B-la. Base List la -Items Exclusive to Unit 1 ...........................................

B-3 Table B-lb. Base List lb -Items Common to Units 1 and 2 .................................

B-59 Table B -2 .B ase List 2 .................................................................................

B -76 T able B -3 .S W E L 1 ....................................................................................

B -77 T able B -4 .S W E L 2 ....................................................................................

B -82 B-1 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Stevenson

& Associates Seismic Walkdown Interim Report, Rev-2 In Response to NTTF Recommendation 23: Seismic LaSalle County Generating Station -Unit I 09/12/2012 Tony Perez -Equipment Selection Preparer date KimLC -09/12/2012 Equim L #we S fiitn Ople/ations Staff Member' dateAttachment 3 for synopsis of Station Operations role and responsibility, B-2 12QO108.50-R-001 Rev. I Correspondence No.: RS-12-163 Table B-la. Items Exclusive to Unit 1 Eq Component Equipment Name System Building Column No Floor Tag EquipmentNameCode Elev 1AP01E 6.9KVSWGR 151 AP AB 12 N 710 1AP02E 6.9KV SWGR 152 AP AB .12 N 731 1AP03E 4160V SWGR 141X AP AB 10 N 710 1AP05E 4160V SWGR 142X AP AB 10 N 731 1AP06E DIV II 4160V SWGR 142Y AP AB 10 N 731 1AP06E-9 TRANSFORMER, 136X AP AB 10 L 731 1AP09E 6.9KV SWGR 152-1 AP RB 10 C 820 1AP11E 480VSWGR 131X AP AB 10 R 815 1AP12E 480V SWGR 131Y AP TB 01 V 731 1AP13E 480V SWGR 132X AP AB 11 L 786 1AP15E 480V SWGR 133 AP RB 13 C 786 1AP19E DIV I 480V SWGR 135X AP AB 10 L 710 1AP19E-102B TRANSFORMER, 135X AP AB 10L 710 1AP20E DIV I 480V SWGR 135Y AP AB 10 L 710 1AP21E DIV II 480V SWGR 136X AP AB 10 L 731 1AP22E DIV II 480V SWGR 136Y AP AB 11 L 731 1AP22E-402B TRANSFORMER, 136Y AP 1AP23E 480V SWGR 137X AP AB 07 N 794 1AP24E 480V SWGR 137Y AP AB 11 N 794 1AP25E 480V SWGR 138 AP AB 15 N 815 1AP31E 480V SWGR 133A AP AB 12 L 786 1AP33E 480V SWGR 134A AP AB 12 L 786 1AP44E 480V MCC 132B-1 AP AB 12 N 710 1AP50E 480 VAC MCC 133A-1 AP AB 11 N 786 1AP56E 480V MCC 131X-1 AP AB 11 R 815 1AP58E 480V MCC 132X-1 AP AB 10 L 815 1AP61E 480V MCC 133-1 AP RB 14 A 786 1AP62E 480V MCC 133-2 AP RB 15 E 740 1AP63E 480V POWER PANEL 133-3 AP RB 15 H 843 1AP64E 480V MCC 134X-1 AP RB 11 C 786 1AP65E 480V MCC 134X-2 AP RB 10:00 AM 740 1AP69E 480V POWER PANEL 134Y-3 AP RB 09 C 843 1AP70E 480V POWER PANEL 134Y-4 AP RB 11 C 786 1AP71E DIV I 480V MCC 135X-1 AP RB 14 A 761 480-120/208V DISTRIBUTION TRANSFORMER 1AP73E DIV I 480V MCC 135X-3 AP AB 11 L 710 IAP73E-E2 480-120/208V DISTRIBUTION AP TRANSFORMER 1AP75E DIV I 480V MCC 135Y-1 AP RB 15 D 740 1AP75E-A5 TRANSFORMER, 135Y AP 1AP78E DIV II 480V MCC 136X-1 AP RB 12 C 820 1AP79E. DIV III 480V MCC 143-1 AP AB 10 L 687 1AP79E-1A SYSTEM AUX TRANSFORMER 142 AP 1AP80E DIV II 480V MCC 136X-2 AP AB 10 L 731 Table B-la Page 1 of 56 B-3 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1AP81E DIV II 480V MCC 136X-3 AP AB 10 L 731 1AP82E-F6 TRANSFORMER, RAD/CHEM FACILITY AP 1AP83E DIV II 480V MCC 136Y-2 AP RB 10 J 740 1B21-503A ACTUATOR, A SJAS PCV B21 1B21-503B ACTUATOR, B SJAE PCV B21 1B21-A001A A INBD MSIV ACCUMULATOR B21 1B21-A001B B INBD MSIV ACCUMULATOR B21 1B21-A001C C INBD MSIV ACCUMULATOR B21 1B21-AO01D D INBD MSIV ACCUMULATOR B21 1 B21-A002A A OUTBOARD MSIV ACCUMULATOR B21 1B21-AO02B B OUTBOARD MSIV ACCUMULATOR B21 1B21-AO02C C OUTBOARD MSIV ACCUMULATOR B21 1B21-A002D D OUTBOARD MSIV ACCUMULATOR B21 1 B21-AO03C SRV 1 B21-F01 3C ADS ACCUMULATOR B21 1 B21-AO03D SRV 1 B21-F01 3D ADS ACCUMULATOR B21 1B21-A003E SRV 1B21-F013E ADS ACCUMULATOR B21 1B21-A003R SRV 1 B21-F01 3R ADS ACCUMULATOR B21 1B21-A003S SRV 1B21-F013S ADS ACCUMULATOR B21 1 B21-A003U SRV 1B21-F013U ADS ACCUMULATOR B21 1 B21 -A003V SRV 1 B21 -F01 3V ADS ACCUMULATOR B21 1B21-A004A SRV 1B21-F013A ACCUMULATOR B21 1 B21-AO04B SRV 1 B21-F01 3B ACCUMULATOR B21 1B21-A004C SRV 1B21-F013C ACCUMULATOR B21 DW 1B21-A004D SRV 1B21-F013D ACCUMULATOR B21 1B21-A004E SRV 1B21-FO13E ACCUMULATOR B21 1 B21 -A004F SRV 1 B21 -F01 3F ACCUMULATOR B21 1B21-AO04G SRV 1B21-F013G ACCUMULATOR B21 1B21-A004H SRV 1B21-F013H ACCUMULATOR B21 1B21-A004J SRV 1B21-F013J ACCUMULATOR B21 1B21-AO04K SRV 1B21-F013K ACCUMULATOR B21 1B21-A004L SRV 1B21-F013L ACCUMULATOR B21 1 B21-AO04M SRV 1B21-F013M ACCUMULATOR B21 1B21-A004N SRV 1B21-F013N ACCUMULATOR B21 1 B21-AO04P SRV 1 B21-FO1 3P ACCUMULATOR B21 1B21-AO04R SRV 1B21-F013R ACCUMULATOR B21 1 B21-A004S SRV 1 B21-F01 3S ACCUMULATOR B21 1B21-AO04U SRV 1B21-F013U ACCUMULATOR B21 1 B21-AO04V SRV 1 B21-F01 3V ACCUMULATOR B21 1B21-A005A ACCUMULATOR, FOR 1B21-F032A, B21 OUTBOARD CHECK 1B21-A005B ACCUMULATOR, FOR 1B21-F032B, B21 OUTBOARD CHECK 1B21-AO05P ACCUMULATOR, MSRV B21 1B21-C1V1 VALVE -HYDRAULIC OPERATED B21 1B21-C1V2 VALVE -HYDRAULIC OPERATED B21 1B21-C1V3 VALVE -HYDRAULIC OPERATED B21 1B21-C1V4 VALVE -HYDRAULIC OPERATED B21 Table B-Ia Page 2 of 56 B-4 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNeCode Eev 1B21-C1V5 VALVE -HYDRAULIC OPERATED B21 1B21-CIV6 VALVE -HYDRAULIC OPERATED B21 1B21-ERDV CUSTOM VALVE, SOLENOID OPERATOR B21 1B321-FO13A D MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13A-C SRVA -PILOT SOLENOID VALVE 'C' B21 1B321-FO13B3 A MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13B-C SRV B -PILOT SOLENOID VALVE 'C' B21 1B321-FOI3C C MAIN STEAM LINE SAFETY RELIEF B21 DW 783 VALVE 1B21-FO13C-A SRV C UMF-1 SOLENOID VALVE 'A' B21 DW 777 1B21-FO13C-B SRV C UMF-1 SOLENOID VALVE 'B' B21 1B21-FO13C-C SRV C UMF-1 SOLENOID VALVE 'C' B21 1B21-FOI3D B MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13D-A SRV D IMF-2 SOLENOID VALVE 'A' B21 1B21-FO13D-B SRV D IMF-2 SOLENOID VALVE 'B' B21 1B21-FO1 3D-C SRV D IMF-2 SOLENOID VALVE 'C' B21 1B21-FO13E C MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13E-A SRV E UMF-1 SOLENOID VALVE 'A' B21 1B21-F013E-B SRV E UMF-1 SOLENOID VALVE 'B' B21 1B21-FO13E-C SRV E UMF-1 SOLENOID VALVE 'C' B21 1B21-FO13F B MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13F-C SRV F IMF-2 SOLENOID VALVE 'C' B21 1B21-FOl3G D MAIN STEAM LINE SAFETY RELIEF B21 1B21-F013HG ANSEMLN AEYRLE B2.1 VALVE 1B21-F013H-C SRV G IMF-2 SOLENOID VALVE 'C' B21 D MAIN STEAM LINE SAFETY RELIEF 1B21-FO13H B21 VALVE 1B21-FO13J-C SRV J IMF-2 SOLENOID VALVE 'C' B21 1B21-F013K B MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13K-B SRV K IMF-2 SOLENOID VALVE 'B' B21 1B121-FOI 3K-C SRV K IMF-2 SOLENOID VALVE 'C' B21____C MAIN STEAM LINE SAFETY RELIEF 11321-F0131-VAV B21 VALVE______

__1B21-FO13L-C SRV L IMF-2 SOLENOID VALVE 'C' B21 1B21-FOI3M B MAIN STEAM LINE M SAFETY RELIEF B21 VALVE 1B21-FO13M-C SRV M IMF-2 SOLENOID VALVE 'C' B21 Table B-la Page 3 of 56 B-5 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor TagB Code Elev C MAIN STEAM LINE SAFETY RELIEF 1B21-F013N B2 1 VALVE 1B21-FO13N-C SRV N IMF-2 SOLENOID VALVE 'C' B21 1B21-FO13P A MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13P-B SRV P IMF-2 SOLENOID VALVE 'B' B21 1B21-FO13P-C SRV P IMF-2 SOLENOID VALVE 'C' B21 1B21-F013R C MAIN STEAM LINE SAFETY RELIEF B21____________

VALVE 1B21-F013R-A SRV R IMF-2 SOLENOID VALVE 'A' B21 1B21-FO13R-B SRV R IMF-2 SOLENOID VALVE 'B' B21 1B21-FO13R-C SRV R IMF-2 SOLENOID VALVE 'C' B21 11321-F7013S B MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-F013S-A SRV S IMF-2 SOLENOID VALVE 'A' B21 1B21-F013S-B SRV S IMF-2 SOLENOID VALVE 'B' B21 1B21-F013S-C SRV S IMF-2 SOLENOID VALVE 'C' B21 1B21-FO13U D MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13U-A SRV U UMF-1 SOLENOID VALVE 'A' B21 1B21-FO13U-B SRV U UMF-1 SOLENOID VALVE 'B' B21 1B21-FO13U-C SRV U UMF-1 SOLENOID VALVE 'C' B21 1B21-FOI3V A MAIN STEAM LINE SAFETY RELIEF B21 VALVE 1B21-FO13V-A SRV V UMF-1 SOLENOID VALVE 'A' B21 1B21-FO13V-B SRV V UMF-1 SOLENOID VALVE 'B' B21 1B21-FO13V-C SRV V UMF-1 SOLENOID VALVE 'C' B21 11321-F016 MS INBD ISOL VLVS DRN LINE INBD ISOL B21 DW 12 G 740 STOP 1B21-F019 MAIN STEAM INBD DRN LINE OTBD ISOL B21 RB 12 J 735 VLV 1B21-F022A A MS INBD ISOL B21 _1B21-F022A-P2 VALVE, SOLENOID, I/B MSIV B21 1B21-F022A-P3 VALVE, SOLENOID, I/B MSIV B21 1B21-F022B B MS INBD ISOL B21 DW 12 J 735 1B21-F022B-P2 VALVE, SOLENOID, I/B MSIV B21 I 1B21-F022B-P3 VALVE, SOLENOID, I/B MSIV B21 1B21-F022C C MS INBD ISOL B21 DW 12 J 735 1B21-F022C-P2 VALVE, SOLENOID, I/B MSIV B21 1B21-F022C-P3 VALVE, SOLENOID, I/B MSIV B21 1B21-F022D D MS INBD ISOL B21 DW 12 J 735 1B21-F022D-P2 VALVE, SOLENOID, I/B MSIV B21 1B21-F022D-P3 VALVE, SOLENOID, I/B MSIV B21 1B21-F028A A OTBD MAIN STEAM ISOLATION VALVE B21 RB 12 J 735 1B21-F028A-P2 VALVE, SOLENOID, O/B MSIV B21 1B21-F028A-P3 VALVE, SOLENOID, O/B MSIV B21 1B21-F028B B OTBD MAIN STEAM ISOLATION VALVE B21 RB 12 J 735 Table B-I a Page 4 of 56 B-6 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1B21-F028B-P2 VALVE, SOLENOID, O/B MSIV B21 1B21-F028B-P3 VALVE, SOLENOID, O/B MSIV B21 1B21-F028C C OTBD MAIN STEAM ISOLATION VALVE B21 RB 12 J 735 1B21-F028C-P2 VALVE, SOLENOID, O/B MSIV B21 RB 12J 736 1B21-F028C-P3 VALVE, SOLENOID, O/B MSIV B21 1B21-F028D D OTBD MAIN STEAM ISOLATION VALVE B21 RB 12 J 735 1B21-F028D-P2 VALVE, SOLENOID, O/B MSIV B21 1B21-F028D-P3 VALVE, SOLENOID, O/B MSIV B21 1B21-F032A SOLENOID VALVE B21 1B21-F032A-A ACTUATOR, FW CHECK CYLINDER A B21_1B21-F032A-AC VALVE, A CYL CLOSE FW CHECK B21 1B21-F032A-AO VALVE, A CYL OPEN FW CHECK B21 1B21-F032A-B ACTUATOR, FW CHECK CYLINDER B B21 1B21-F032A-BC VALVE, B CYL CLOSE FW CHECK B21 1B21-F032A-BO VALVE, B CYL OPEN FW CHECK B21 IB21-F032B B FEEDWATER LINE OTBD TESTABLE B21 RB 12 J 735 CHECK VALVE 1 B21-F032B-A ACTUATOR, FW CHECK CYLINDER A B21 1B21-F032B-AC VALVE, A CYL CLOSE FW CHECK B21 1B21-F032B-AO VALVE, A CYL OPEN FW CHECK B21 1B21-F032B-B ACTUATOR, FW CHECK CYLINDER B B21 1B21-F032B-BC VALVE, B CYL CLOSE FW CHECK B21 1B21-F032B-BO VALVE, B CYL OPEN FW CHECK B21 A FEEDWATER LINE OTBD ISOLATION 1 B21 -F065A VLEB21 RB 12 J 735 VALVE 1 B21 -F067 BA MAIN STEAM OTBD DRAIN LINE ISOL B21 RB 12 K 735 VALVE B MAIN STEAM OTBD DRAIN LINE ISOL 1B21-F067B 821 RB 12 K 735 VALVE 1 B21 -F067D C MAIN STEAM OTBD DRAIN LINE ISOL 821 RB 12 K 735 VALVE 1821 -F067D D MAIN STEAM OTBD DRAIN LINE ISOL B21'1B21-F067D

_ VALVE B21 _RB 12_K_ 735 1B21-F536C VLV 1 IN SOL GLOBE 821 _______1B21-F536D VALVE, GLOBE B21 1B21 -F536G VLV 1 IN SOL GLOBE B21 1B21-F536H VLV 1 IN SOL GLOBE B21 1B21-F536M VLV I IN SOL GLOBE B21 1B21-F536R VLV 1 IN SOL GLOBE B21 1 B33-F020 B RX RECIRC LOOP PROCESS SAMPLING 833 RB 11 B 740 OTBD ISOL VALVE 1C11-D001 ASSY -CONTROL UNIT CRD HYDRAULIC C11 G-F 9 lCl1-DO01001 CONTROL UNIT CRD HYDRAULIC 26-59 C11 RB SOT 761 SOUTH lC11-D001002 CONTROL UNIT CRD HYDRAULIC 22-59 C11 1Cll-D001003 CONTROL UNIT CRD HYDRAULIC 18-59 Cll lC11-D001004 CONTROL UNIT CRD HYDRAULIC 26-55 C11 Table B-Ia Page 5 of 56 B-7 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Code Elev lCll-DO01005 CONTROL UNIT CRD HYDRAULIC 22-55 C11 lCll-DO01006 CONTROL UNIT CRD HYDRAULIC 18-55 C11 ___lCl1-DO01007 CONTROL UNIT CRD HYDRAULIC 26-51 C11 lCll-DO01008 CONTROL UNIT CRD HYDRAULIC 22-51 Cllý1Cll-D001009 CONTROL UNIT CRD HYDRAULIC 18-51 Cll lCll-DO01010 CONTROL UNIT CRD HYDRAULIC 14-51 Cll IC11-DO01011 CONTROL UNIT CRD HYDRAULIC 10-51 C11 lCl1-DO01012 CONTROL UNIT CRD HYDRAULIC 14-55 C11 lCll-D001013 CONTROL UNIT CRD HYDRAULIC 26-47 C11 lCll-DO01014 CONTROL UNIT CRD HYDRAULIC-22-47 Cll lCll-DO01015 CONTROL UNIT CRD HYDRAULIC 18-47 Cll lCll-D001016 CONTROL UNIT CRD HYDRAULIC 14-47 Cll lCll-DO01017 CONTROL UNIT CRD HYDRAULIC 10-47 Cll lCll-D001018 CONTROL UNIT CRD HYDRAULIC 06-47 C11 1Cll-D001019 CONTROL UNIT CRD HYDRAULIC 26-43 C11 lCll-DO01020 CONTROL UNIT CRD HYDRAULIC 22-43 Cll lCll-DO01021 CONTROL UNIT CRD HYDRAULIC 18-43 Cll 1C11-D001022 CONTROL UNIT CRD HYDRAULIC 14-43 C11 1C11-D001023 CONTROL UNIT CRD HYDRAULIC 10-43 C11 lC11-D001024 CONTROL UNIT CRD HYDRAULIC 06-43 C11 lCll-DO01025 CONTROL UNIT CRD HYDRAULIC 02-43 C11 lCll-DO01026 CONTROL UNIT CRD HYDRAULIC 26-39 C11 1C11-D001027 CONTROL UNIT CRD HYDRAULIC 22-39 C11 1C11-D001028 CONTROL UNIT CRD HYDRAULIC 18-39 C11 lCll-DO01029 CONTROL UNIT CRD HYDRAULIC 14-39 Cl1 lCll-DO01030 CONTROL UNIT CRD HYDRAULIC 10-39 C11 lCll-DO01031 CONTROL UNIT CRD HYDRAULIC 06-39 C11 1Cll-D001032 CONTROL UNIT CRD HYDRAULIC 02-39' C11 lCl1-DO01033 CONTROL UNIT CRD HYDRAULIC 26-35 C11 lCll-DO01034 CONTROL UNIT CRD HYDRAULIC 22-35 C11 lCl1-DO01035 CONTROL UNIT CRD HYDRAULIC 18-35 C.1 1CIl-DO01036 CONTROL UNIT CRD HYDRAULIC 14-35 C11 1C11-D001037 CONTROL UNIT CRD HYDRAULIC 10-35 C11 1C11-D001038 CONTROL UNIT CRD HYDRAULIC 06-35 C11 1C11-D001039 CONTROL UNIT CRD HYDRAULIC 02-35 C11 1C11-D001040 CONTROL UNIT CRD HYDRAULIC 26-31 C11 lCll-D001041 CONTROL UNIT CRD HYDRAULIC 22-31 C11 lCll-D001042 CONTROL UNIT CRD HYDRAULIC 18-31 C11 iCll-D001043 CONTROL UNIT CRD HYDRAULIC 14-31 C11 lCll-D001044 CONTROL UNIT CRD HYDRAULIC 10-31 C11 lC1l-D001045 CONTROL UNIT CRD HYDRAULIC 06-31 C11 lCll-DO01046 CONTROL UNIT CRD HYDRAULIC 02-31 Cl1 lCll-DO01047 CONTROL UNIT CRD HYDRAULIC 30-27 C11 iCl1-DO01048 CONTROL UNIT CRD HYDRAULIC 26-27 C11I 1C1l-D001049 CONTROL UNIT CRD HYDRAULIC 22-27 C11 lCll-DO01050 CONTROL UNIT CRD HYDRAULIC 18-27 C11 lCll-DO01051 CONTROL UNIT CRD HYDRAULIC 14-27 Cl1 Table B-Ia Page 6 of 56 B-8 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Code Elev 1Cll-DO01052 CONTROL UNIT CRD HYDRAULIC 10-27 C11 lCll-D001053 CONTROL UNIT CRD HYDRAULIC 06-27 Cll lCl1-DO01054 CONTROL UNIT CRD HYDRAULIC 02-27 C11 lCl1-DO01055 CONTROL UNIT CRD HYDRAULIC 30-23 C11 lC11-D001056 CONTROL UNIT CRD HYDRAULIC 26-23 C11 lCll-DO01057 CONTROL UNIT CRD HYDRAULIC 22-23 Cll IC1 1-D001058 CONTROL UNIT CRD HYDRAULIC 18-23 C11 lCl1-D001059 CONTROL UNIT CRD HYDRAULIC 14-23 C11 lCl1-DO01060 CONTROL UNIT CRD HYDRAULIC 10-23 C11 1C11-D001061 CONTROL UNIT CRD HYDRAULIC 06-23 C11 lCll-D001062 CONTROL UNIT CRD HYDRAULIC 02-23 C11 lCll-DO01063 CONTROL UNIT CRD HYDRAULIC 30-19 C11 lCll-DO01064 CONTROL UNIT CRD HYDRAULIC 26-19 C11 lCll-D001065 CONTROL UNIT CRD HYDRAULIC 22-19 C11 lCll-DO01066 CONTROL UNIT CRD HYDRAULIC 18-19 C11 lCll-DO01067 CONTROL UNIT CRD HYDRAULIC 14-19 Cll lCl1-D001068 CONTROL UNIT CRD HYDRAULIC 10-19 C11 lCll-DO01069 CONTROL UNIT CRD HYDRAULIC 06-19 C11.lCl1-D001070 CONTROL UNIT CRD HYDRAULIC 02-19 C11 lCll-DO01071 CONTROL UNIT CRD HYDRAULIC 30-15 Cll lCll-D001072 CONTROL UNIT CRD HYDRAULIC 26-15 C11 lC11-D001073 CONTROL UNIT CRD HYDRAULIC 22-15 C11 lCll-DO01074 CONTROL UNIT CRD HYDRAULIC 18-15 Cll lCll-D001075 CONTROL UNIT CRD HYDRAULIC 14-15 Cll 1C11-D001076 CONTROL UNIT CRD HYDRAULIC 10-15 C11 lCll-DO01077 CONTROL UNIT CRD HYDRAULIC 06-15 C11 lCll-DO01078 CONTROL UNIT CRD HYDRAULIC 30-11 C11_lCll-DO01079 CONTROL UNIT CRD HYDRAULIC 26-11 Cll lCll-DO01080 CONTROL UNIT CRD HYDRAULIC 22-11 Cll lCl1-D001081 CONTROL UNIT CRD HYDRAULIC 18-11 Cll lCll-D001082 CONTROL UNIT CRD HYDRAULIC 14-11 Cll lCll-DO01083 CONTROL UNIT CRD HYDRAULIC 10-11 Cll lCll-DO01084 CONTROL UNIT CRD HYDRAULIC 14-07 C11 lCl1-D001085 CONTROL UNIT CRD HYDRAULIC 30-07 C11 lC11-D001086 CONTROL UNIT CRD HYDRAULIC 26-07 C11 lC11-D001087 CONTROL UNIT CRD HYDRAULIC 22-07 C11 lCll-D001088 CONTROL UNIT CRD HYDRAULIC 18-07 C11 C-D 9 1C11-D001089 CONTROL UNIT CRD HYDRAULIC 30-03 Cll RB SOUTH 761 1Cll-D001090 CONTROL UNIT CRD HYDRAULIC 26-03 Cll lCll-D001091 CONTROL UNIT CRD HYDRAULIC 22-03 Cl1 IC11-D001092 CONTROL UNIT CRD HYDRAULIC 18-03 C11 lCli-DO01093 CONTROL UNIT CRD HYDRAULIC 42-59 C11 RB G-F 14.5 761 NORTH lCll-DO01094 CONTROL UNIT CRD HYDRAULIC 38-59 Cll lCil-DO01095 CONTROL UNIT CRD HYDRAULIC 34-59 C11 iCll-DO01096 CONTROL UNIT CRD HYDRAULIC 30-59 C11 Table B-la Page 7 of 56 B-9 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 Eq Component Equipment Name System Building -Column No Floor Tag Code Elev 1Cll-D001097 CONTROL UNIT CRD HYDRAULIC 42-55 C11 lC11-D001098 CONTROL UNIT CRD HYDRAULIC 38-55 C11 1C11-D001099 CONTROL UNIT CRD HYDRAULIC 34-55 C11 lCll-DO01100 CONTROL UNIT CRD HYDRAULIC 30-55 Cll lCll-DO01101 HCU 46-55 Cll lCll-DO01102 HCU 50-51 Cll lCll-DO01103 HCU 46-51 Cll1 1Cll-D001104 HCU 42-51 Cll lCll-D001106 DELETE -DO NOT USE C11 1C11-D001108 CONTROL UNIT CRD HYDRAULIC 54-47 C11 1C11-D001109 CONTROL UNIT CRD HYDRAULIC 50-47 C11 1011-DO01110 CONTROL UNIT CRD HYDRAULIC 46-47 C11-1Cll-D001112 HCU 38-47 Clil lCll-D001114 CONTROL UNIT CRD HYDRAULIC 30-47 C11 lCll-DO01115 CONTROL UNIT CRD HYDRAULIC 58-43 C11 lC11-D001117 CONTROL UNIT CRD HYDRAULIC 50-43 C11 1Cl1-DO01118 CONTROL UNIT CRD HYDRAULIC 46-43 C11 ICll-DO01119 CONTROL UNIT CRD, HYDRAULIC 42-43 Cll I CII-DO01120 CONTROL UNIT CRD HYDRAULIC 38-43 C11 lC11-DO01121 CONTROL UNIT CRD HYDRAULIC 34-43 C11 1C11-D001122 CONTROL UNIT CRD HYDRAULIC 30-43 C11 1C11-D001123 CONTROL UNIT CRD HYDRAULIC 58-39 C11 lCll-D001124 CONTROL UNIT CRD HYDRAULIC 54-39 C11 lCl1-DO01125 CONTROL UNIT CRD HYDRAULIC 50-39 C11 lCll-D001126 SCRAM INLT VLV C11 lCll-D001127 SCRAM OTLT VLV Cli lCll-D001128 CONTROL UNIT CRD HYDRAULIC 38-39 C11 lCl1-DO01129 CONTROL UNIT CRD HYDRAULIC 34-39 C11 lCl1-DO01130 CONTROL UNIT CRD HYDRAULIC 30-39 C11 1Cl1-D001131 CONTROL UNIT CRD HYDRAULIC 58-35 C11 1Cl1-D001133 CONTROL UNIT CRD HYDRAULIC 50-35 C1 1 lCll-D001134 CONTROL UNIT CRD HYDRAULIC 46-35 Cll lCll-DO01135 CONTROL UNIT CRD HYDRAULIC 42-35 C11 lCll-D001136 CONTROL UNIT CRD HYDRAULIC 38-35 C11 1Cll-D001137 CONTROL UNIT CRD HYDRAULIC 34-35 C11 lC11-D001138 CONTROL UNIT CRD HYDRAULIC 30-35 C11 IC11-D001139 CONTROL UNIT CRD HYDRAULIC 58-31 Cll lCll-DO01140 CONTROL UNIT CRD HYDRAULIC 54-31 C11 lCll-DO01141 CONTROL UNIT CRD HYDRAULIC 50-31 C11 lCll-DO01142 CONTROL UNIT CRD HYDRAULIC 46-31 C11 lCll-D001143 CONTROL UNIT CRD HYDRAULIC 42-31 C11 lCll-DO01144 CONTROL UNIT CRD HYDRAULIC 38-31 C11 lCll-DO01145 CONTROL UNIT CRD HYDRAULIC 34-31 C11 iCli-DO01146 CONTROL UNIT CRD HYDRAULIC 30-31 C11 lCl1-DO01147 CONTROL UNIT CRD HYDRAULIC 58-27 C11 lCl1-DO01148 CONTROL UNIT CRD HYDRAULIC 54-27 Cii lCll-DO01149 CONTROL UNIT CRD HYDRAULIC 50-27 C11 TableB-1a Page 8 of 56 B-1 0 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Equipment eCode Elev 1011-D0001150 CONTROL UNIT CRD HYDRAULIC 46-27 C11 10C11-DO01151 CONTROL UNIT CRD HYDRAULIC 42-27 C11 1C11-D001152 CONTROL UNIT CRD HYDRAULIC 38-27 C11 1C11-D001153 CONTROL UNIT CRD HYDRAULIC 34-27 C11 1C11-D001154 CONTROL UNIT CRD HYDRAULIC 58-23 CI1 1C11-D001155-CONTROL UNIT CRD HYDRAULIC 54-23 C11 11C1-D001156 CONTROL UNIT CRD HYDRAULIC 50-23 C11 1C11-D001157 CONTROL UNIT CRD HYDRAULIC 46-23 C11 1C11-D001158 CONTROL UNIT CRD HYDRAULIC 42-23 C11 1C11-D001159 CONTROL UNIT CRD HYDRAULIC 38-23 C11 1C11-D001160 CONTROL UNIT CRD HYDRAULIC 34-23 C11i 1C11-D001161 CONTROL UNIT CRD HYDRAULIC 58-19 C1 1_lC11-D001162 CONTROL UNIT CRD HYDRAULIC 54-19 C11 1C11-D001163 CONTROL UNIT CRD HYDRAULIC 50-19 C11 1C11-D001164 CONTROL UNIT CRD HYDRAULIC 46-19 C11 1C11-D001165 CONTROL UNIT CRD HYDRAULIC 42-19 C11 1C11-D001166 CONTROL UNIT CRD HYDRAULIC 38-19 C11 1C0l-D001167 CONTROL UNIT CRD HYDRAULIC 34-19 Cll 1C11-D001168 CONTROL UNIT CRD HYDRAULIC 54-15 C11 01 C1-D001169 CONTROL UNIT CRD HYDRAULIC 50-15 C1t 01 C1-D001170 CONTROL UNIT CRD HYDRAULIC 46-15 C11 1C0l-D001171 CONTROL UNIT CRD HYDRAULIC 42-15 C11 1C11-D001172 CONTROL UNIT CRD HYDRAULIC 38-15 C11 1C11-D001173 CONTROL UNIT CRD HYDRAULIC 34-15 C11 1C11-D001174 CONTROL UNIT CRD HYDRAULIC 46-07 C11 1Cll-D001175 CONTROL UNIT CRD HYDRAULIC 50-11 Cll 1C11-D001176 CONTROL UNIT CRD HYDRAULIC 46-11 C11 1C11-D001177 CONTROL UNIT CRD HYDRAULIC 42-11 C11 1C11-D001178 CONTROL UNIT CRD HYDRAULIC 38-11 C11 1Cll-D001179 CONTROL UNIT CRD HYDRAULIC 34-11 Cll 1C11-D001180 CONTROL UNIT CRD HYDRAULIC 42-03 C11 1C11-D001181 CONTROL UNIT CRD HYDRAULIC 38-03 C11 1011-D001182 CONTROL UNIT CRD HYDRAULIC 34-03 C11 RB 0-0 14.5 761 NORTH 1Cll-D001183 CONTROL UNIT CRD HYDRAULIC 42-07 C11 1Cll-D001184 CONTROL UNIT CRD HYDRAULIC 38-07 C11 1C11-D001185 CONTROL UNIT CRD HYDRAULIC 34-07 C11 1011-00219 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 02-19 1C11-D0219-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D0219-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D0219-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D0223 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 02-23 10C1-D0223-125 CRD HCU SCRAM WATER ACCUMULATOR C0l Table B-Ia Page 9 of 56 B-11 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 tSystem Floor Tag Equipment Nasem Building Column No Elev 1CI1-D0223-126 CRD HCU SCRAM INLET VALVE Cod 1C11-D0223-127 CRD HCU SCRAM OUTLET VALVE Cll lCll-D0227 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 02-27 1 C11 -D0227-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0227-126 CRD HCU SCRAM INLET VALVE Cll 1CIl-D0227-127 CRD HCU SCRAM OUTLET VALVE C11 1Cll-D0231 CONTROL ROD DRIVE HYDRAULIC Cll CONTROL UNIT 02-31 lCll-D0231-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 1Cll-D0231-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D0231-127 CRD HCU SCRAM OUTLET VALVE C11 lCll-D0235 CONTROL ROD DRIVE HYDRAULIC Cll CONTROL UNIT 02-35 1C11-D0235-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D0235-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D0235-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC 1lCll-D0239 CONTROL UNIT 02-39 C1 t1 1C11-D0239-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0239-126 CRD HCU SCRAM INLET VALVE Cll 1 1C11-D0239-127 CRD HCU SCRAM OUTLET VALVE C11l lCll-D0243 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 02-43 I C11 -D0243-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0243-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D0243-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC lCll-D0615 C11 CONTROL UNIT 06-15 1 C11 -D0615-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0615-126 CRD HCU SCRAM INLET VALVE Cli 1 C1 1-D0615-127 CRD HCU SCRAM OUTLET VALVE Cll 1 C1 -D0619 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-19 1 C11 -D0619-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lCll-D0619-126 CRD HCU SCRAM INLET VALVE Cli 1C11-D0619-127 CRD HCU SCRAM OUTLET VALVE Cll lClli-D0623 CONTROL ROD DRIVE HYDRAULIC Cli_CONTROL UNIT 06-23 Table B-la Page 10 of 56 B-1 2 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component ESystem Floor Tag Equipment Namestdem Building Column No Elev Tag qimetNm Code _____Ee 1 C11 -D0623-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0623-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D0623-127 CRD HCU SCRAM OUTLET VALVE C11 lCll-D0627 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-27 1C11-D0627-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D0627-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D0627-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 06-31 ___1CIl-D0631-125 CRD HCU SCRAM WATER ACCUMULATOR Cli lC11-D0631-126 CRD HCU SCRAM INLET VALVE C11 ICll-D0631-127 CRD HCU SCRAM OUTLET VALVE Cll lCIll-D0635 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 06-35 1 C11 -D0635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D0635-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D0635-127 CRD HCU SCRAM OUTLET VALVE C11 lCIll-D0639 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-39 1C11-D0639-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1C-D0639-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D0639-127 CRD HCU SCRAM OUTLET VALVE Cll lCll1-D0643 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-43 1C11-D0643-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D0643-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D0643-127 CRD HCU SCRAM OUTLET VALVE C11l CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 06-47 1C 11-D0647-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D0647-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D0647-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D1011 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 10-11 lCll-DlOll-125 CRD HCU SCRAM WATER ACCUMULATOR Cii lCll-DlOll-126 CRD HCU SCRAM INLET VALVE C11 1CIl-DlOll-127 CRD HCU SCRAM OUTLET VALVE C11 Table B-i a Page 11 of 56 B-1 3 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 SystemFloor Eq Component Eqimn aeSystem Building Column No Floor EqCopoen Equipment Name Code Tag Code uldn ClmnN Elev CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 10-15 1C1-D1015-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1015-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1015-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-Dl0i9 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 10-19 1 C11-D1019-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D1019-126 CRD HCU SCRAM INLET VALVE Cll IC1l-D1019-127 CRD HCU SCRAM OUTLET VALVE Cll iC11-D1023 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-23 tC11-D1023-125 CRD HCU SCRAM WATER ACCUMULATOR C11.1C11-D1023-126 CRD HCU SCRAM INLET VALVE Cll 1C1C-D1023-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D1027 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-27 1C11-D1027-125 CRD HCU SCRAM WATER ACCUMULATOR Cll IC11-D1027-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1027-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D1031 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-31 1 C11-D1031-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC11-D1031-126 CRD HCU SCRAM INLET VALVE Cll IC11-D1031-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D1035 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 10-35 1C11-D1035-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC1l-D1035-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1035-127 CRD HCU SCRAM OUTLET VALVE C11 IC11-D1039 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-39 IC11-D1039-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC11-D1039-126 CRD HCU SCRAM INLET VALVE C11 1Cil-D1039-127 CRD HCU SCRAM OUTLET VALVE C11 ICii-D1043 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-43 1C11-D1043-125 CRD HCU SCRAM WATER ACCUMULATOR C11 ICll-D1043-126 CRD HCU SCRAM INLET VALVE Cll Table B-i a Page 12 of 56 B-14 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Code Elev 1C11 -D1 043-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D1047 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 10-47 1C11-D1047-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC11-D1047-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D1047-127 CRD HCU SCRAM OUTLET VALVE Cll iCli-DiO5i CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 10-51 1C11 -D1051-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D1051-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1051-127 CRD HCU SCRAM OUTLET VALVE C11 C1Cll-DI407 CONTROL ROD DRIVE HYDRAULIC Cll CONTROL UNIT 14-07 1C11-D1407-125 CRD HCU SCRAM WATER ACCUMULATOR Cll ICll-D1407-126 CRD HCU SCRAM INLET VALVE Cll 1CI1-D1407-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D1411 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 14-11 1Cll-D1411-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1411-126 CRD HCU SCRAM INLET VALVE C11_1C11-D1411-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D1415 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 14-15 1C11-D1415-125 CRD HCU SCRAM WATER ACCUMULATOR C11 C1C1-D1415-126 CRD HCU SCRAM INLET VALVE Cll 1C1 1-D1415-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D1419 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 14-19 Cll lC11-D1419-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D1419-126 CRD HCU SCRAM INLET VALVE Cll iC11-D1419-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC____________

CONTROL UNIT 14-23 __ _1Cll-D1423-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D1423-126 CRD HCU SCRAM INLET VALVE Cll 1Cli-D1423-127 CRD HCU SCRAM OUTLET VALVE C11 1C1i-D1427 CONTROL ROD DRIVE HYDRAULIC C1i 1Cll-D1427_

CONTROL UNIT 14-27 C!1 1C11-D1427-125 CRD HCU SCRAM WATER ACCUMULATOR Cli Table B-i a Page 13 of 56 B-15 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component System ' Floor EquimentNameBuilding Column No Tag Code Elev 1C1l-D1427-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1427-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D1431 CONTROL ROD DRIVE HYDRAULIC'CONTROL UNIT 14-31 1C1l-D1431-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1431-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D1431-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D1435

.CONTROL ROD DRIVE HYDRAULIC Cli_CONTROL UNIT 14-35 1C11-D1435-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1435-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D1435-127 CRD HCU SCRAM OUTLET VALVE Cll iC11-D1439 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 14-39 1C1l-D1439-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1439-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1439-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D1443 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-43 1C11-D1443-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D1443-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1443-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D1447 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-47 1C11-D1447-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D1447-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D1447-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D1451 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-51 1Cll-D1451-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 1C11-D1451-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D1451-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D1455 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 14-55 1C1l-D1455-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 1Cll-D1455-126 CRD HCU SCRAM INLET VALVE C11 1C1l-D1455-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC_ _ _ _ _ _ _ _ _ _ _ IC O N T R O L U N IT 1 8 -0 3 ___Table B-la Page 14 of 56 B-16 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1Cl1-D1803-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1803-126 CRD HCU SCRAM INLET VALVE Cll 1CII-D1803-127 CRD HCU SCRAM OUTLET VALVE C1l 1CII-D1807 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 18-07 1Cl1-D1807-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D1807-126 CRD HCU SCRAM INLET VALVE Cl1 1CIl-D1807-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 18-11 1Cl1-D1811-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1811-126 CRD HCU SCRAM INLET VALVE C11 1C11-D1811-127 CRD HCU SCRAM OUTLET VALVE C1l 1CII-D1815 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 18-15 1Cll-D1815-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C1C-D1815-126 CRD HCU SCRAM INLET VALVE Cll 1 C11-D1815-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 18-19 1C11-D1819-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1819-126 CRD HCU SCRAM INLET VALVE C11l 1C11-D1819-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 18-23 1C11-D1823-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D1823-126 CRD HCU SCRAM INLET VALVE Cll lCll-D1823-127 CRD HCU SCRAM OUTLET VALVE C11l IC11-D1827 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 18-27 1Cll-D1827-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1827-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1827-127 CRD HCU SCRAM OUTLET VALVE C11 ICii-D1831 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 18-31 1 C11 -D1831-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lCll-D1831-126 CRD HCU SCRAM INLET VALVE Cii 1 C11 -D1 831-127 CRD HCU SCRAM OUTLET VALVE C11 Table B-i a Page 15 of 56 B-1 7 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev CONTROL ROD DRIVE HYDRAULIC 1CII-D1835 CONTROL UNIT 18-35 CII 1Cll-D1835-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1835-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D1835-127 CRD HCU SCRAM OUTLET VALVE Cll ICII-D1839 CONTROL ROD DRIVE HYDRAULIC Cl1 1C11-D1839_

CONTROL UNIT 18-39 _ll 1C11-D1839-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D1839-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1839-127 CRD HCU SCRAM OUTLET VALVE C11 ICII-D1843 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 18-43 1 C11 -D1 843-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D1843-126 CRD HCU SCRAM INLET VALVE C11 1 C11 -D1 843-127 CRD HCU SCRAM OUTLET VALVE, C11 CONTROL ROD DRIVE HYDRAULIC l___________

CONTROL UNIT 18-47 __ _1Cl1-D1847-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 1C11-D1847-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D1847-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC 1Cll-D1851_

CONTROL UNIT 18-51 1ClI-D1851-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D1851-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D1851-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC___________

CONTROL UNIT 18-55 _ _ _1C11-D1855-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D1855-126 CRD HCU SCRAM INLET VALVE Cl1 1C11-D1855-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC 1Cll-D1859_

CONTROL UNIT 18-59 Cll iC11-D1859-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cl1-D1859-126 CRD HCU SCRAM INLET VALVE C111 1Cl1-D1859-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D2203 CONTROL ROD DRIVE HYDRAULIC Cll___________

CONTROL UNIT 22-03 __1 1C11-D2203-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2203-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 16 of 56 B-1 8 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component ESystem Floor Eq Component Sys Building Column No Tag EquipmentNameCode Elev 1 Cll -D2203-127 CRD HCU SCRAM OUTLET VALVE Cll lClI-D2207 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-07 1C11-D2207-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2207-126 CRD HCU SCRAM INLET VALVE Cll 101 1-D2207-127 CRD HCU SCRAM OUTLET VALVE C11 lCll-D2211 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-11 1C1l-D2211-125 CRD HCU SCRAM WATER ACCUMULATOR Cll iC11-D2211-126 CRD HCU SCRAM INLET VALVE C11 1C11-D2211-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D2215 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-15 1 C11 -D2215-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2215-126 CRD HCU SCRAM INLET VALVE C11 1Cl1-D2215-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D2219 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-19 1C11-D2219-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2219-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2219-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D2223 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 22-23 1C11-D2223-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2223-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D2223-127 CRD HCU SCRAM OUTLET VALVE Cll iCII-D2227 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 22-27 1 C11 -D2227-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2227-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D2227-127 CRD HCU SCRAM OUTLET VALVE Cll IC1I-D2231 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-31 1 C11 -D2231-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2231-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D2231-127 CRD HCU SCRAM OUTLET VALVE Cll ICiI-D2235 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 22-35 1 C11 -D2235-125 CRD HCU SCRAM WATER ACCUMULATOR C11 Table B-la Page 17 of 56 B-19 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component EquipmentSystem Building Column No Floor Tag Equipment' Blg lNCode Elev 1C11-D2235-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2235-127 CRD HCU SCRAM OUTLET VALVE Cll 1Cll-D2239 ICONTROL ROD DRIVE HYDRAULIC Cll___________

CONTROL UNIT 22-39 __ _1C11-D2239-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2239-126 CRD HCU SCRAM INLET VALVE Cll 1C ll-D2239-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC____________

CONTROL UNIT 22-43 __ _1 C11 -D2243-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cl1-D2243-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2243-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D2247 CONTROL ROD DRIVE HYDRAULIC C 11 CONTROL UNIT 22-47 1C1 1-D2247-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D2247-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2247-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D2251 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 22-51 1C11-D2251-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2251-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D2251-127 CRD HCU SCRAM OUTLET VALVE Cll IC1I-D2255 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 22-55 1Cl1-D2255-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2255-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D2255-127 CRD HCU SCRAM OUTLET VALVE Cll iCI1-D2259 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 22-59 1C11-D2259-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2259-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2259-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D2603 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 26-03 1C11-D2603-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2603-126 CRD HCU SCRAM INLET VALVE Cii 1Cil-D2603-127 CRD HCU SCRAM OUTLET VALVE C11l CONTROL ROD DRIVE HYDRAULIC CCONTROL UNIT 26-07 Table B-la Page 18 of 56 B-20 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column No Floor Tag Equipment Name Code Elev 1C11-D2607-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2607-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D2607-127 CRD HCU SCRAM OUTLET VALVE C11 ICI 1-D2611 -CONTROL ROD DRIVE HYDRAULIC Ci CONTROL UNIT 26-11 1C11-D2611-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1CII-D2611-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2611-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D2615 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-15 1C11-D2615-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2615-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D2615-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D2619 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 26-19 C1 1C-D2619-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 1C11-D2619-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2619-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 26-23 1C11-D2623-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2623-126 CRD HCU SCRAM INLET VALVE Cll C1C1-D2623-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 26-27 C1 1C-D2627-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2627-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2627-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 26-31 1C11-D2631-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2631-126 CRD HCU SCRAM INLET VALVE CI 1 1C11-D2631-127 CRD HCU SCRAM OUTLET VALVE C11 1Cii-02635 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 26-35 1C11-D2635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2635-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D2635-127 CRD HCU SCRAM OUTLET VALVE Cll Table B-la Page 19 of 56 B-21 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component ESystem Floor Tag Equipment Namestdem Building Column No Elev Tagl Equipment__________Name

__ Code _____Ee 1Cll-D2639 CONTROL ROD DRIVE HYDRAULIC____________

CONTROL UNIT 26-39 dii C1 1C-D2639-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cl1-D2639-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D2639-127 CRD HCU SCRAM OUTLET VALVE Cll iCi i-D2643 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-43 1C11-D2643-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2643-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D2643-127 CRD HCU SCRAM OUTLET VALVE C11 IC1I-D2647 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-47 1 C11 -D2647-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2647-126 CRD HCU SCRAM INLET VALVE C11 1C11-D2647-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D2651 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 26-51 1C11-D2651-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D2651-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2651-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D2655 CONTROL ROD DRIVE HYDRAULIC Cii 1Cll-D2655_

CONTROL UNIT 26-55 1C11-D2655-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D2655-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D2655-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC___________

CONTROL UNIT 26-59 ___G-F 9 1C11-D2659-125 CRD HCU SCRAM WATER ACCUMULATOR C11 RB SOT 761 SOUTH 1Cll-D2659-126 CRD HCU SCRAM INLET VALVE Cll RB G-F 761 SOUTH G-F 9 1C11-D2659-127 CRD HCU SCRAM OUTLET VALVE C11 RB SOUTH 761 ICI 1-D3003 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 30-03 1C11-D3003-125 CRD HCU SCRAM WATER ACCUMULATOR C11 RB C-D 9 761 SOUTH C-D 9 1Cll-D3003-126 CRD HCU SCRAM INLET VALVE Cll RB SOT 761 SOUTH 1C11-D3003-127 CRD HCU SCRAM OUTLET VALVE C11 RB C-D 9 761 1 1 SOUTH Table B-la Page 20 of 56 B-22 4.

12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 30-07 1C 11-D3007-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3007-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D3007-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D3011 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 30-11 1Cll-D3011-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D3011-126 CRD HCU SCRAM INLET VALVE C11 1C11-D3011-127 CRD HCU SCRAM OUTLET VALVE C11 IC1i-D3015 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-15 1Cll-D3015-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 1Cll-D3015-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3015-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D3019 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 30-19 1CII-D3019-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3019-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D3019-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D3023 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-23 1 C11 -D3023-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC1 1-D3023-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3023-127 CRD HCU SCRAM OUTLET VALVE Cll iCi1-D3027 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-27 C11 1 C11 -D3027-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3027-126 CRD HCU SCRAM INLET VALVE Cll 1Cli-D3027-127 CRD HCU SCRAM OUTLET VALVE Cll iCI 1-03031 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 30-31 1C11-D3031-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3031-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3031-127 CRD HCU SCRAM OUTLET VALVE C11 iCI 1-03035 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-35 1C11-D3035-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3035-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 21 of 56 B-23 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column No Floor Tag Equipment Name Code Elev 1Cll-D3035-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D3039 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-39 1C1 1-D3039-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3039-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3039-127 CRD HCU SCRAM OUTLET VALVE C11 IC11-D3043 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-43 1 C11 -D3043-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D3043-126 CRD HCU SCRAM INLET VALVE C1_1 1 C11 -D3043-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC 1C11-D3047 C11 CONTROL UNIT 30-47 1 C11 -D3047-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3047-126 CRD HCU SCRAM INLET VALVE Cil 1 C11 -D3047-127 CRD HCU SCRAM OUTLET VALVE C1l ICII-D3051 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-51 1C11-D3051-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3051-126 CRD HCU SCRAM INLET VALVE Cli lCl-D3051-127 CRD HCU SCRAM OUTLET VALVE Cli 1C11-D3055 CONTROL ROD DRIVE HYDRAULIC Cll CONTROL UNIT 30-55 ___1C11-D3055-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3055-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3055-127 CRD HCU SCRAM OUTLET VALVE Cll I CII -D3059 CONTROL ROD DRIVE HYDRAULIC

.C1 CONTROL UNIT 30-59 1C1 1-D3059-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3059-126 CRD HCU SCRAM INLET VALVE Cll 1C1C-D3059-127 CRD HCU SCRAM OUTLET VALVE C1"1 IC.11-D3403 CONTROL ROD DRIVE HYDRAULIC C11 1Cll-D3403__

CONTROL UNIT 34-03 1C11-D3403-125 CRD HCU SCRAM WATER ACCUMULATOR C11 RB C-D 14.5 761 NORTH 1C11-D3403-126 CRD HCU SCRAM INLET VALVE C11 RB C-D 14.5 761 NORTH 1C11-D3403-127 CRD HCU SCRAM OUTLET VALVE C11 RB C-D 14.5 761___ ___ ___ ___ __ ___ ___ ___ ___ __ __ ___ __ __ NORTH ICll-D3407 CONTROL ROD DRIVE HYDRAULIC Ci_CONTROL UNIT 34-07 Table B-I a Page 22 of 56 B-24 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor_ Tag Code Elev 1 C11 -D3407-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1'C11-D3407-126 CRD HCU SCRAM INLET VALVE Cli 1 C11 -D3407-127 CRD HCU SCRAM OUTLET VALVE C11 ICII-D3411 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 34-11 1C11-D3411-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3411-126 CRD HCU SCRAM INLET VALVE C11 1C11-D3411-127 CRD HCU SCRAM OUTLET VALVE C11 1C1i-D3415 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 34-15 iC11-D3415-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC11-D3415-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3415-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D3419 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-19 1C11-D3419-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3419-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3419-127 CRD HCU SCRAM OUTLET VALVE Cll iCI-D 3423 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-23 1C11-D3423-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3423-126 CRD HCU SCRAM INLET VALVE Cll ,1C11-D3423-127 CRD HCU SCRAM OUTLET VALVE Cll ICI 1-D3427 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-27 1 C11 -D3427-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3427-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3427-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D3431 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-31 I C11-D3431-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3431-126 CRD HCU SCRAM INLET VALVE C11 IC11-D3431-127 CRD HCU SCRAM OUTLET VALVE C11 iCii-D3435 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-35 1 C11 -D3435-125 CRD HCU SCRAM WATER ACCUMULATOR C11 iC11-D3435-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3435-127 CRD HCU SCRAM OUTLET VALVE Cll Table B-i a Page 23 of 56 B-25 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor Eq Component Equipment Name System Building Column No Flev Tag Codem Elev.CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 34-39 1C11-D3439-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3439-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3439-127 CRD HCU SCRAM OUTLET VALVE Cll ICi 1-D3443 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 34-43 C11 C1 1C-D3443-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 C1C1-D3443-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3443-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D3447 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 34-47 1Cl1-D3447-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3447-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D3447-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D3451 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 34-51 C1 1C-D3451-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C1l-D3451-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3451-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D3455 CONTROL ROD DRIVE HYDRAULIC C11 1_C11-D3455 CONTROL UNIT 34-55 C11 1 C11 -D3455-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3455-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D3455-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D3459 CONTROL ROD DRIVE HYDRAULIC Cli 1C11-D3459__

CONTROL UNIT 34-59 1 C11 -D3459-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3459-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D3459-127 CRD HCU SCRAM OUTLET VALVE C11 iCll-D3803 CONTROL ROD DRIVE HYDRAULIC Cli 1C11-D3803_

CONTROL UNIT 38-03 1C11-D3803-125 CRD HCU SCRAM WATER ACCUMULATOR Ci1 1C1I-D3803-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3803-127 CRD HCU SCRAM OUTLET VALVE C11 ICi 1-D3807 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-07 1C11 -D3807-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cil-D3807-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 24 of 56 B-26 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Equipment eCode Elev 1 C11 -D3807-127 CRD HCU SCRAM OUTLET VALVE Cli1 1C1 1-D3811 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-11 1 C11 -D3811-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 1C11-D3811-126 CRD HCU SCRAM INLET VALVE Cl1 1C11-D3811-127 CRD HCU SCRAM OUTLET VALVE Cl 1 ICl1-D3815 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-15 1C11-D3815-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3815-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D3815-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC 1C11-D3819 CONTROL UNIT 38-19 C11 1C11-D3819-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3819-126 CRD HCU SCRAM INLET VALVE Cl1 1C11-D3819-127 CRD HCU SCRAM OUTLET VALVE C1l ICI1-D3823 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 38-23 1C11-D3823-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3823-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3823-127 CRD HCU SCRAM OUTLET VALVE Cll ICII-D3827 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-27 1C1 1-D3827-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D3827-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D3827-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC 1Cll-D3831 CONTROL UNIT 38-31 Cll 1C11-D3831-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3831-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D3831-127 CRD HCU SCRAM OUTLET VALVE Cil 1CII-D3835 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-35 1C 11-D3835-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3835-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3835-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D3839 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-39 1 C11 -D3839-125 CRD HCU SCRAM WATER ACCUMULATOR C11 Table B-la Page 25 of 56 B-27 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column Floor Tag Equipment.Name Code Elev 1Cll-D3839-126 CRD HCU SCRAM INLET VALVE Cll 1C1C-D3839-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D3843 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-43 1C1 1-D3843-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3843-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D3843-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D3847 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 38-47 1Cl1-D3847-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3847-126 CRD HCU SCRAM INLET VALVE C11 1C11-D3847-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D3851 CONTROL ROD DRIVE HYDRAULIC Cli 1Cll-D3851_

CONTROL UNIT 38-51 Cll 1C1 1-D3851-125 CRD HCU SCRAM WATER ACCUMULATOR.

Cll 1Cl1-D3851-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D3851-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC C11 1C1_1-D3855 CONTROL UNIT 38-55 C__1 1C1 1-D3855-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3855-126 CRD HCU SCRAM INLET VALVE Cll 1 Cl -D3855-127 CRD HCU SCRAM OUTLET VALVE Cii lCli-D3859 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-59 1C11-D3859-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D3859-126 CRD HCU SCRAM INLET VALVE C11 ilCl1-D3859-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-D4203 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 42-03 1 C11 -D4203-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4203-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4203-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D4207 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-07 1C11 -D4207-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cii-D4207-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4207-127 CRD HCU SCRAM OUTLET VALVE C11 iCii-D4211 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-11 Table B-la Page 26 of 56 B-28 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev 1Cll-D4211-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C1I-D4211-126 CRD HCU SCRAM INLET VALVE C11 1C11-D4211-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D4215 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 42-15 1C11-D4215-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D4215-126 CRD HCU SCRAM INLET VALVE Cll 1Cl1-D4215-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1 II-D4219 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-19 1Cll-D4219-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cll-D4219-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D4219-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D4223 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-23 1C11-D4223-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1C-D4223-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4223-127 CRD HCU SCRAM OUTLET VALVE C11 IC1I-;D4227 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-27 1C11-D4227-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4227-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4227-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC___________

CONTROL UNIT 42-31 __ _1C11-D4231-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1C-D4231-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4231-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D4235 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-35 1 C11 -D4235-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 1C1C-D4235-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4235-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 42-39 ICi1-D4239-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1C-D4239-126 CRD HCU SCRAM INLET VALVE C11 iC1 I-D4239-127 CRD HCU SCRAM OUTLET VALVE Cli Table B-i a Page 27 of 56 B-29 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column No loor Tag Equipment Name Code Elev CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 42-43 1 Cl 1-D4243-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D4243-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D4243-127 CRD HCU SCRAM OUTLET VALVE Cll iCi 1-D4247 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-47 1Cll-D4247-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lC11-D4247-126 CRD HCU SCRAM INLET VALVE Cil 1 C11 -D4247-127 CRD HCU SCRAM OUTLET VALVE C11 iC1I-D4251 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 42-51 1C11 -D4251-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D4251-126 CRD HCU SCRAM INLET VALVE C11 C1 1-D4251-127 CRD HCU SCRAM OUTLET VALVE Cli IC1 1 -D4255 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-55 IC11-D4255-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D4255-126 CRD HCU SCRAM INLET VALVE C1l lCli-D4255-127 CRD HCU SCRAM OUTLET VALVE Ci_iCi 1-D4259 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-59 lC11-D4259-125 CRD HCU SCRAM WATER ACCUMULATOR C(11 RB C-D 14.5 761 NORTH 1C11-D4259-126 CRD HCU SCRAM INLET VALVE C11 RB C-D 14.5 761 NORTH 1C11-D4259-127 CRD HCU SCRAM OUTLET VALVE C11 RB C-D 14.5 761 NORTH ICI 1-D4607 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 46-07 lCl1-D4607-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4607-126 CRD HCU SCRAM INLET VALVE Cll lC11-D4607-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D4611 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 46-11 1C11-D4611-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lC11-D4611-126 CRD HCU SCRAM INLET VALVE Cll 1Cil-D4611-127 CRD HCU SCRAM OUTLET VALVE C11 iCI1-D4615 CONTROL ROD DRIVE HYDRAULIC Cii_CONTROL UNIT 46-15 Table B-I a Page 28 of 56 B-30 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Eq t Name System Building Column No Floor Tag quipmen Code Elev 1 Cl 1-D4615-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lC11-D4615-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4615-127 CRD HCU SCRAM OUTLET VALVE Cll 1C1I-D4619 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 46-19 lC11-D4619-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4619-126 CRD HCU SCRAM INLET VALVE C11 1C11-D4619-127 CRD HCU SCRAM OUTLET VALVE C11 1CII-04623 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 46-23 1 C11 -D4623-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D4623-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D4623-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D4627 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 46-27 i1CI1-D4627-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1C-D4627-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4627-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC l1 C11-D4631 CONTROL UNIT 46-31 C11 1C11-D4631-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4631-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4631-127 CRD HCU SCRAM OUTLET VALVE C11 11C11-D4635 CONTROL ROD DRIVE HYDRAULIC C11 CCONTROL UNIT 46-35 1C11-D4635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4635-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D4635-127 CRD HCU SCRAM OUTLET VALVE C11 1CONTROL ROD DRIVE HYDRAULIC 1 Ci-04639 !CONTROL UNIT 46-39 C11 ilC11-D4639-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D4639-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D4639-127 CRD HCU SCRAM OUTLET VALVE C11 ICii-D4643 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 46-43 1C11-D4643-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D4643-126 CRD HCU SCRAM INLET VALVE Cl 1.1C11-D4643-127 CRD HCU SCRAM OUTLET VALVE C11 Table B-I a Page 29 of 56 B-31 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor BuildngpCoumnnN Tag Code Elev CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 46-47 lC11-D4647-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 lC11-D4647-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D4647-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 46-51 IC11-D4651-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cll-D4651-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D4651-127 CRD HCU SCRAM OUTLET VALVE Cll iCI 1-D4655 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 46-55 lCl1-D4655-125 CRD HCU SCRAM WATER ACCUMULATOR C11 lC11-D4655-126 CRD HCU SCRAM INLET VALVE Cll 1 C 1-D4655-127 CRD HCU SCRAM OUTLET VALVE C 1 iCII-D5011 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-11 1CI -D5011-125 CRD HCU SCRAM WATER ACCUMULATOR C11 IC11-D5011-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5011-127 CRD HCU SCRAM OUTLET VALVE CI1 IC11 -D5015 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 50-15 1Cli-D5015-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5015-126 CRD HCU SCRAM INLET VALVE C11 1 C11 -D5015-127 CRD HCU SCRAM OUTLET VALVE CI 1 1C11-D5019 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-19 1C11-D5019-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D5019-126 CRD HCU SCRAM INLET VALVE Cll lC11-D5019-127 CRD HCU SCRAM OUTLET VALVE Cll ICI-D5023 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 50-23 1C1C-D5023-125 CRD HCU SCRAM WATER ACCUMULATOR Cll lC11-D5023-126 CRD HCU SCRAM INLET VALVE Cll iC1 1-D5023-127 CRD HCU SCRAM OUTLET VALVE Cll iCi I-D5027 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-27 1C11-D5027-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cl1-D5027-126 CRD HCU SCRAM INLET VALVE Cl1 L Table B-I a Page 30 of 56 B-32 12Q0108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev 1C11-D5027-127 CRD HCU SCRAM OUTLET VALVE C11 1C11-D5031 CONTROL ROD DRIVE HYDRAULIC C11___________

CONTROL UNIT 50-31 _ _ _1C1C-D5031-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cll-D5031-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5031-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D5035 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-35 1C11-D5035-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cll-D5035-126 CRD HCU SCRAM INLET VALVE Cl1 1Cll-D5035-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D5039 CONTROL ROD DRIVE HYDRAULIC Cl1 CONTROL UNIT 50-39 IC11-D5039-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5039-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D5039-127 CRD HCU SCRAM OUTLET VALVE C11 ICII-D5043 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 50-43 1CIl-D5043-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5043-126 CRD HCU SCRAM INLET VALVE Cll 1 C11 -D5043-127 CRD HCU SCRAM OUTLET VALVE C11 1Cii-D5047 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 50-47 1C11-D5047-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D5047-126 CRD HCU SCRAM INLET VALVE Cil 1C11-D5047-127 CRD HCU SCRAM OUTLET VALVE C11I 1C11-D5051 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 50-51 1C1 1-D5051-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D5051-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5051-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D5415 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 54-15 1Cll-D5415-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D5415-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D5415-127 CRD HCU SCRAM OUTLET VALVE Cii 1iC11-D5419 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 54-19 1C11-D5419-125 CRD HCU SCRAM WATER ACCUMULATOR Cii Table B-la Page 31 of 56 B-33 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1C1C-D5419-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D5419-127 CRD HCU SCRAM OUTLET VALVE C11 iCi 1-D5423 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 54-23 1C11-D5423-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5423-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5423-127 CRD HCU SCRAM OUTLET VALVE Cll iCi i-D5427 CONTROL ROD DRIVE HYDRAULIC CII 1C11-D5427__

CONTROL UNIT 54-27 C11 1 C11 -D5427-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5427-126 CRD HCU SCRAM INLET VALVE C11 1C11-D5427-127 CRD HCU SCRAM OUTLET VALVE C11 1CI1-D5431 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 54-31 1C11-D5431-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5431-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D5431-127 CRD HCU SCRAM OUTLET VALVE Cll iCI i-D5435 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 54-35 1 C11 -D5435-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D5435-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5435-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-D5439 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 54-39 '1 C11 -D5439-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5439-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5439-127 CRD HCU SCRAM OUTLET VALVE Cll 1C11-D5443 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 54-43 1C11-D5443-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5443-126 CRD HCU SCRAM INLET VALVE Cll 1C1l-D5443-127 CRD HCU SCRAM OUTLET VALVE Cll ICI-D5447 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 54-47 1 C11 -D5447-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5447-126 CRD HCU SCRAM INLET VALVE C11 1 C11 -D5447-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC___________

CONTROL UNIT 58-19 ___Table B-1 a Page 32 of 56 B-34 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1C1l-D5819-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1Cll-D5819-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D5819-127 CRD HCU SCRAM OUTLET VALVE Cll IC11-05823 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 58-23 ICll-D5823-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 1C11-D5823-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5823-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D5827 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 58-27 1C11-D5827-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5827-126 CRD HCU SCRAM INLET VALVE C11 1C1l-D5827-127 CRD HCU SCRAM OUTLET VALVE Cll 1CII-D5831 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 58-31 I C11-D5831-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1Cll-D5831-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5831-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 58-35 1Cl1-D5835-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C1l-D5835-126 CRD HCU SCRAM INLET VALVE Cll 1Cll-D5835-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 58-39 1 C11 -D5839-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5839-126 CRD HCU SCRAM INLET VALVE Cll 1C11-D5839-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC 1CII-D5843 CONTROL UNIT 58-43 Cli 1 C11 -D5843-125 CRD HCU SCRAM WATER ACCUMULATOR C11 1C11-D5843-126 CRD HCU SCRAM INLET VALVE C11 1Cll-D5843-127 CRD HCU SCRAM OUTLET VALVE Cll 1Cl1-F380 VALVE, SCRAM DISCH VOL VENT C11 1C11-F381 VALVE, AIR SCRAM DISCH VOL VENT C11 1C11-F388 VALVE, SOLENOID OPERATED SDV VENT C11 VLV 1C11 -F389 VALVE, AIR SCRAM DISCH VOL VENT C11 iCii-P002 LOCAL FLOW STATION RACK FOR COND Cii_CHAMBER 1B21-D004A Table B-la Page 33 of 56 B-35 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component, System Floor Tag Equipment Name Code BulinoumoIElev LOCAL FLOW STATION RACK FOR COND CHAMBER 1B21-D004B 1C1I-P004 LOCAL FLOW STATION RACK FOR COND C11 CHAMBER 1B21-DO04C IC1I-P005 LOCAL FLOW STATION RACK FOR COND Cli CHAMBER B21-D004D (RVWLIS)LOCAL FLOW STATION RACK FOR COND CHAMBER 1B21-D367 I Cli -P007 LOCAL FLOW STATION RACK FOR COND Cli CHAMBER B21-D368 (RVWLIS)1C41-A001 STANDBY LIQUID CONTROL SOLUTION C41 RB 10 C 820 TANK C41 RB1__2 1C41-C001A A STANDBY LIQUID CONTROL PUMP C41 RB 11 C 820 1C41-C001B B STANDBY LIQUID CONTROL PUMP C41 RB 11 C 820 1C61-P001 ASSY -PANEL, REMOTE S/D INSTR C61 1CM017A SUP CHBR / DW 02 MONITOR INLET CM UPSTRM ISOL VALVE TRITIUM GRAB SAMPLE STATION INLET UPSTRM ISOL VALVE 1CM018A SUP CHBR / DW 02 MONITOR INLET CM DWNST ISOL VALVE 1CM018B TRITIUM GRAB SAMPLE STATION INLET CM DWNST ISOL VALVE SUP CHBR / DW 02 MONITOR OUTLET UPSTRM ISOL VALVE 1CM019B TRITIUM GRAB SAMPLE STATION OUTLET CM UPSTRM ISOL VALVE 1 CMO02OA SUP CHBR / DW 02 MONITOR OUTLET CM DWNST ISOL VALVE TRITIUM GRAB SAMPLE STATION OUTLET DWNST ISOL VALVE 1 CM021 B B POST LOCA H2/02 CNMT MONITOR CM PANEL DW SAMPLE ISOL VALVE 1 CM022A A POST LOCA H2/02 CNMT MONITOR CM PANEL DW SAMPLE ISOL VALVE 1 CM023B B POST LOCA H2/02 CNMT MONITOR PANEL SUP CHBR SAMPLE ISOL VALVE 1 CM024A A POST LOCA H2/02 CNMT MONITOR PANEL SUP CHBR SAMPLE ISOL VALVE A POST LOCA H2/02 MONITOR PANEL SUP CHBR RETURN VALVE 1CM026B B POST LOCA H2/02 MONITOR PANEL CM SUP CHBR RETURN VALVE 1 CM027 PRI CNMT CAM SUP CHBR INLET UPSTRM CM ISOL VALVE 1 CM028 PRI CNMT CAM SUP CHBR INLET DWNST CM_ISOL VALVE I _Table B-i a Page 34 of 56 B-36 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag EquipmentNameCode Elev PRI CNMT CAM DW INLET UPSTRM ISOL 1 CM029 VLECM VALVE 1 CM030 PRI CNMT CAM DW INLET DWNST ISOL CM VALVE 1iCM031 PRI CNMT 24 POINT CAM INLET UPSTRM CM ISOL VALVE PRI CNMT 24 POINT CAM INLET DWNST 1CM032 ISLVLECM ISOL VALVE 1 CM033 PRI CNMT CAM SAMPLE PANEL OUTLET CM UPSTRM VALVE PRI CNMT CAM SAMPLE PANEL OUTLET 1 CM034 CM DWNST VALVE 1 CM03PA A POST LOCA H2/02 CNMT MONITOR CM RB 11 C 786 SAMPLE PUMP 1 CM03PB PRI CNMT H2-02 POST LOCA MONITOR CM RB 11 B 786 PMP U1 CNMT AIR SAMPLE HRSS UPSTRM 1CM085 CM STOP VALVE 1 CM086 Ul CNMT AIR SAMPLE HRSS DWNST CM STOP VALVE 1 CM089 UU CNMT AIR SAMPLE HRSS RETURN CM UPSTRM STOP VALVE Ul CNMT AIR SAMPLE HRSS RETURN 1 CM090 DWNST STOP VALVE CM 1DC001E 250V DC BAT DC 1 DC003E 250V DC BATTERY CHARGER NO. 1 DC AB 9J 710 1 DC005E 250V MCC DC AB 10 L 710 1DC006E MOTOR CONT CENTER BUS 121Y DC 1DC007E 125V DC BATTERY NO. 1A DC 1DC009E 125V DC BATTERY CHARGER NO. 1A DC lDC010E 125V DIST PNL DC 1DC011E DISTRIBUTION PNLNO 111Y DC lDC012E 125V DIST PNL DC lDC013E DISTRIBUTION PNLNO 112Y DC 1DC014E 125V DC BATTERY NO. 1B DC 1DC017E BAD RECORD ***USE EQUIPMENT TAG DC 1DC17E***1DC018E 125V BATTERY DIV.3 DC lDC019E 125V DC BATTERY CHARGER NO. 1C DC 1DC01E 250VDC BATTERY DC AB 9J 710 1DC02E DIV I 250VDC DISTRIBUTION BUS 1 DC AB 10 L 710 1 DCQ2E-2A TRIP UNIT- 121X FEED FROM 250V DC DC BUS #1 I DCO2E-2B TRIP UNIT- 121Y FEED FROM 250V DC DC BUS #1 1 DC031 E 24V BATTERY DC 1 DC032E 24V BATTERY DC Table B-i a Page 35 of 56 B-37 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System BFuilding Column No lor Tag EquipmentNameCode Elev 1DC033E 24V BATTERY DC 1DC034E 24V BATTERY DC 1DC035E 24V BATTERY CHARGER DC 1 DC036E 24V BATTERY CHARGER DC 1 DC037E 24V BATTERY CHARGER DC 1DC038E 24V BATTERY CHARGER DC 1DC039E 48/24V DIST PNL DC 1DC03E 250VDC BATTERY CHARGER DC 1 DC040E 48/24V DIST PNL DC 1DC05E 250VDC MCC 121X DC AB 10 L 710 1DC06E DIVI 250VDC MCC 121Y DC RB 14 B 694 1 DC06E-1 D TRIP UNIT -UNIT TIE TO 2DC06E (221Y) DC 1 DC07E DIV I 125VDC BATTERY DC 1DC08E DIV I 125VDC DISTRIBUTION BUS 1A DC AB 12 L 710 1IDC08E-3A TRIP UNIT- 111X FEED FROM 125VDC D-1 DC BUS 1A 1 DC08E-3B TRIP UNIT- 111Y FEED FROM 125VDC D-1 DC BUS 1A 1DC09E DIV 1 125VDC BATTERY CHARGER (1AA) DC 1DC10E 125VDC DISTRIBUTION PANEL 111X DC AB 12 L 710 1DC11E DIV I 125VDC DISTRIBUTION PANEL 111Y DC AB 12 L 710 1DC12E 125VDC DISTRIBUTION PANEL 112X DC AB 12 L 731 lDC14E DIV II 125VDC BATTERY DC AB L-N 12-13 731 lDC15E DIV II 125VDC DISTRIBUTION BUS 1B DC AB 12 L 731 IDC15E-3A TRIP UNIT- 1DC15ECKT3A FEED TO DC 112X (1DC12E)1DC15E-3B TRIP UNIT -1DC1 5E CKT 3B FEED TO 112Y DC (1DC13E)1DC16E 125V DC BATTERY CHARGER NO. 1B DC AB L-N 11-12 731 lDC16E DIV 2 125VDC BATTERY CHARGER (1BB) DC 1DC17E DIV 2 125VDC BATTERY CHARGER (IBA) DC 1DC18E DIV III 125VDC BATTERY DC" lDC19E DIV III 125VDC BATTERY CHARGER DC 1DC23E DIV 1 125VDC BATTERY CHARGER (lAB) DC 1DC31E 24/48VDC BATTERY 1A DC AB 12 N 749 lDC32E 24 / 48VDC BATTERY 1 B DC AB 12 N 749 1DC33E 24 / 48VDC BATTERY 1 C DC AB 11 N 749 IDC34E 24 / 48VDC BATTERY 1 D DC AB 11 N 749 1DC39E 48/24VDC DISTRIBUTION PANEL 1A DC AB 10 N 749 1DC40E 48/24VDC DISTRIBUTION PANEL 1B DC AB 10 N 749 1 DG01 1 1A DG COOLING WTR STRAINER DG DG J-H 8-9 674 BACKWASH VALVE lDG01A 1A DG COOLER DG DG J 7-8 710 lDG01D SILENCER, DG ENGINE DG lDG01F 1A DG COOLING WATER STRAINER DG DG J 9 674 lDG01K 1A DIESEL GENERATOR DG DG J 7-8 710 1DG01 K-1 FILTER, AIR INTAKE DG Table B-la Page 36 of 56.B-38 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag EquipmentNameCode Elev 1 DG01 K-A PUMP, AC TURBO SOAKBACK (B7A) DG 1 DG01 K-B PUMP, DC TURBO SOAKBACK DG 1DGO1K-C PUMP, AC LUBE OIL CIRC (B7) DG 1DG01K-D PUMP, SCAVENGING OIL DG 1DG01K-E FILTER, TURBOCHARGER OIL DG 1DG01K-F FILTER, FUEL ASSEMBLY DG 1 DG01 K-G PUMP, RIGHT BANK WTR DG 1DG01K-H PUMP, LEFT BANK WTR DG 1DG01K-I PUMP, MAIN LUBE OIL DG 1DG01K-J PUMP, PISTON COOL DG 1DG01 K-K PUMP, ENGINE DRIVEN FUEL DG 1DG01K-L PUMP, ELECT MTR DRIVEN FUEL DG 1DG01K-M TRAP, TYPE EXH SCREEN DG 1DG01 K-N HEAT EXCHANGER, DG COOLING WTR DG 1DG01K-O DIESEL ENGINE COOLER DG IDG01P 1A DG COOLING WATER PUMP DG AB J 674 lDG01S 1A DG STARTING AIR COMPRESSOR DG DG L-J 7-8 PACKAGE 1DG01SA ASSY -DG AIR TANK VESSEL DG lDG01SB ASSY -DG AIR TANK VESSEL DG lDG02F FILTER, DG AIR INTAKE SILENCER DG 1DG02JA 1A DG A GENERATOR CONTROL PANEL DG DG L 8-9 710 1DG02JB 1A DG B GENERATOR CONTROL PANEL DG 1 DG034 1A DG COOLER OUTLET HEADER RELIEF DG VALVE LPCS PUMP MOTOR COOLER UPSTRM 1 DG035 ILTVVEDG RB 14B 694_____ _____INLET VALVE___1DG03J 1A DG ENGINE CONTROL PANEL DG DG L 8-9 710 1DG04J ASSY -PANEL, TRANSFORMER DG I DG055A 1A DG A STARTING AIR RECEIVER DG RELIEF VALVE 1IDG055B 1A DG B STARTING AIR RECEIVER DG RELIEF VALVE lDG061A ASSY -VALVE, 1A D/G BANK A STARTER DG DG L-J 7-8 710 AIR SUPPLY 1DG061B ASSY -VALVE, 1A D/G BANK B STARTER DG AIR SUPPLY 1IDG062A 1A DG A/C STARTING AIR MOTORS DG PINION SUPPLY SOLENOID VALVE 1 DG062B 1A DG B/D STARTING AIR MOTORS DG PINION SUPPLY SOLENOID VALVE lDG08TA 1A DG A STARTING AIR RECEIVER DG lDG08TB 1A DG B STARTING AIR RECEIVER DG lDG10TA 1A DG A AUX AIR ACCUMULATOR DG 1DG10TB 1A DG B AUX AIR ACCUMULATOR DG 1DG15MA 1A DG A STARTING AIR STRAINER DG 1DG15MB 1A DG B STARTING AIR STRAINER DG Table B-1 a Page 37 of 56 B-39 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev 1DG18MA ASSY -DG AIR COMPRESSOR TANK DG 1DG18MB ASSY -DG AIR COMPRESSOR TANK DG 1 DG23M 1B DG LUBE OIL SOAK BACK PUMPS DG DISCHARGE STRAINER 1 DG24M 16B DG LUBE OIL CIRC PUMP DSCH DG STRAINER 1A DG LUBE OIL SOAK BACK PUMPS DSCH STRAINER 1 DG26M 1A DG LUBE OIL CIRC PUMP DSCH DG STRAINER 1DO001T DG 1A FUEL STGE TK DO 1D0002P PUMP, DIESEL OILTRANSFER DO 1DO002T DG 1B FUEL STGE TK DO 1DO003P DIESEL FIRE FUELTRANSFER PUMP DO 1D0004 D/G 1AFUEL TRAN PMP SO DSCH STOP DO 1 DO004T DG 1B DAY TK DO 1DO005T DG 1A DAY TK DO DG J-H 5-7 710 VLV 2B DIESEL GEN FUEL OIL XFR SOL 1 DO014 DO VLV 1DO01P PUMP, DIESEL OILTRANSFER DO AB 6 J 674 1DO01P 1A DG FUEL TRANSFER PUMP DO AB H 674 IDO01T 1A DG FUEL STORAGE TANK DO 1 D0024 DIESEL FIRE PUMP FUEL TRANSFER DO PUMP SUCT VALVE 1DO02P 1B DG OIL FUEL TRANSFER PUMP DO 1DO02T 1B DG FUEL STORAGE TANK DO 1DO04T 1B DG DAY TANK DO IDO05T 1A DG DAY TANK DO 1 B DG FUEL TRANSFER PUMP SUCT 1IDO09M DO STRNR 1iD01IOM 1A DG FUEL TRANSFER PUMP SUCT DO STRNR 1 D024M Y-TYPE STRNR 150LB.C.S.

BODY DO NO.20S.S.MESH 1D025M 1B DG FUEL STORAGE TANK FILL STRNR DO 1E12-B001A A RHR HEAT EXCHANGER E12 1E12-B001B B RHR HEAT EXCHANGER E12 RB A-B 9-10 694 1E12-CO02A A RHR PUMP E12 RB 14 F 673 1E12-C002B 1B RESIDUAL HEAT REMOVAL PMP E12 RB C 673 1E12-CO02C 1C RESIDUAL HEAT REMOVAL PMP E12 RB 10 B 673 1E12-C003 B/C RHR WATER LEG PUMP E12 RB 10:00 AM 673 1E12-C300A A RHR SERVICE WATER PUMP E12 1E12-C300B B RHR SERVICE WATER PUMP E12 RB 16B 673 1E12-C300C C RHR SERVICE WATER PUMP E12 1E12-C300D D RHR SERVICE WATER PUMP E12 1E12-D300A A RHR SERVICE WATER STRAINER E12 Table B-la Page 38 of 56 B-40 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev 1E12-D300B B RHR SERVICE WATER STRAINER E12 DG J 9 674 1E12-D301A STRAINER E12 1E12-D301B STRAINER E12 1E12-D301C STRAINER E12 1E12-D314A CONDENSING CHAMBER E12 1E12-D314B CONDENSING CHAMBER E12 1E12-D315A CONDENSING CHAMBER E12 1E12-D315B CONDENSING CHAMBER E12 1E12-D322A PULSATION DAMPENER E12 1E12-D322B PULSATION DAMPENER E12 1E12-D322C PULSATION DAMPENER E12 1E12-D322D PULSATION DAMPENER E12 1E12-D323A PULSATION DAMPENER E12.1E12-D323B PULSATON DAMPENER E12 1El2-D323C PULSATION DAMPENER E12 1E12-D323D PULSATION DAMPENER E12 1E12-F003A A RHR HX OUTLET VALVE E12 RB 14 H 694 1E12-F003B B RHR HX OUTLET VALVE E12 RB A-B 9 694 1 El 2-FO04A A RHR PUMP SUP POOL SUCT ISOL E12 RB 13 G 673___ __ ___ __VALVE _ _ _ _ _ _1E12-F004B B RHR PUMP SUP POOL SUCT ISOL E12 RB 10 C 673 VALVE 1E12-FOO4C C RHR PUMP SUP POOL SUCT ISOL E12 VALVE 1E12-F005 RHR SDC SUCT HEADER RELIEF VALVE E12 1E12-FO06A A RHR PUMP SDC SUCT VALVE E12 RB 14 G 673 1E12-F006B B RHR PUMP SDC SUCT VALVE E12 RHR SDC SUCT HEADER OTBD ISOL 1E12-F008 VLEE12 VALVE RHR SDC SUCT HEADER INBD ISOL 1E12-F009E12 VALVE E1 lEl2-F0llA A RHR HX STEAM CONDENSING SUP E12 RB 15 G 694 POOL RETURN ISOL VALVE _ I 1E12-FOIIB B RHR HX STEAM CONDENSING SUP E12 RB 694 POOL RETURN ISOL VALVE 1E12-FOI6A A RHR CONTAINMENT SPRAY UPSTRM E12 RB 13 C 761 ISOL VALVE 1E12-F0l6B B RHR CONTAINMENT SPRAY UPSTRM E12 RB 11 G 761 ISOL VALVE 1E12-FOI7A A RHR CONTAINMENT SPRAY DWNST E12 RB 13 C 777 ISOL VALVE 1E12-F0l7B B RHR CONTAINMENT SPRAY DWNST E12 RB 11 G 761 ISOL VALVE 1E12-F021 C RHR PUMP FULL FLOW TEST ISOL E12 RB 11 G 761 VALVE 1E12-F023 A RHR RX HEAD SPRAY OTBD ISOL VALVE E12 RB 13 H 740 Table B-la Page 39 of 56 B-41 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag! Equipment__________Name__

Code ____Ee 1E12-FT4ag A RHR PUMP FULL FLOW TEST ISOL Eod R 1H 7 1E12-F024A VLEE12 RB 14 H 710___ ___ ___VALVE_

_ _1E12-F024B B RHR PUMP FULL FLOW TEST ISOL E12 RB C 710 VALVE 1E12-F025A A RHR PUMP DSCH RELIEF VALVE E12 1E12-F025B B RHR PUMP DSCH RELIEF VALVE E12 1E12-F025C C RHR PUMP DSCH RELIEF VALVE E12 1 El12-F026A A RHR HX STEAM CONDENSING RCIC E12 RB 14 H 694 RETURN VALVE 1E12-F026B B RHR HX STEAM CONDENSING RCIC E12 RB 10:00 AM 694 RETURN VALVE 1E12-F027A A RHR SUP CHBR SPRAY ISOL VALVE E12 RB 14 G 710 1E12-F027B B RHR SUP CHBR SPRAY ISOL VALVE E12 RB 10 B 710 1E12-F030 RHR PUMPS DRAIN HEADER RELIEF E12 VALVE 1E12-F036A A RHR HX STEAM CONDENSING RCIC E12 RETURN HDR RELIEF VALVE B RHR HX STEAM CONDENSING RCIC 1 E12-F036B RETURN HDR RELIEF VALVE E12 RB 694 1E12-FO4OA A RHR HX BLOWDOWN DWNST ISOL 12 RB 13 H 694 VALVE 1E12-F040B B RHR HX BLOWDOWN DWNST ISOL E12 RB 10:00 AM 694 VALVE 1E12-F040C ASSY -VALVE, GLOBE E12 1E12-F041A A RHR LPCI TESTABLE CHECK VALVE E12 DW 13 D 777 1E12-F041B B RHR LPCI TESTABLE CHECK VALVE E12 DW 13 E 777 1E12-F041C C RHR LPCI TESTABLE CHECK VALVE E12 1E12-F042A A RHR LPCI INJECTION LINE ISOL VALVE E12 1E12-F042B B RHR LPCI INJECTION LINE ISOL VALVE E12 RB 12 H 761 1E12-F042C C RHR LPCI INJECTION LINE ISOL VALVE E12 RB 12 H 761 1E12-F047A A RHR HX INLET VALVE E12 RB 14 H 710 1E12-F047B B RHR HX INLET VALVE E12 1E12-F048A A RHR HX BYPASS VALVE E12 RB 14 H 710 1E12-F048B B RHR HX BYPASS VALVE E12 RB C 694 1E12-F049A A RHR HX BLOWDOWN UPSTRM ISOL E12 RB 14 H 694 VALVE 1E12-F049B B RHR HX BLOWDOWN UPSTRM ISOL E12 RB A 694 VALVE A RHR SDC RETURN TESTABLE CHECK 1E12-F050A VLEE12 DW' 13 F 710__________VALVE

___1E12-FO5OB B RHR SDC RETURN TESTABLE CHECK E12 DW 11 D 740 VALVE A RHR HX RCIC STEAM INLET PRESS 1E12-F051A COTVLEE12_________CONT VALVE __ __1 El 2-F051 B B RHR HX RCIC STEAM INLET PRESS E12 RB A-B 8-9 710_CONT VALVE 1E12-F052A A RHR HX RCIC STEAM INLET VALVE E12 RB 14 G 710 Table B-i a Page 40 of 56 B-42 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag EquipmentNameCode Elev 1E12-F052B B RHR HX RCIC STEAM INLET VALVE E12 RB C 710 1E12-F053A A RHR SDC RETURN ISOL VALVE E12 1E12-F053B B RHR SDC RETURN ISOL VALVE E12 RB 10 C 740 1 El 2-FO55A A RHR HX RCIC STEAM INLET HEADER E12 RELIEF VALVE B RHR HX RCIC STEAM INLET HEADER 1E12-F055B RELIEF VALVE E12 RB 694 1 El 2-F060A A RHR HX OUTLET PROCESS SAMPLE E12 UPSTRM ISOL VALVE 1E12-F060B B RHR HX OUTLET PROCESS SAMPLE E12 UPSTRM ISOL VALVE 1E12-F064A A RHR PUMP MIN FLOW ISOL VALVE E12 RB 14 G 673 1E12-F064B B RHR PUMP MIN FLOW ISOL VALVE E12 RB C 673 1E12-F064C C RHR PUMP MIN FLOW ISOL VALVE E12 RB 10 B 673 1E12-F065A A RHR HX STEAM CONDENSING LEVEL E12 CONTROL VALVE B RHR HX STEAM CONDENSING LEVEL 1E12-F065B E12 CONTROL VALVE 1 El 2-F068A A RHR HX SERVICE WATER OUTLET E12 RB 12.8A 673 VALVE B RHR HX SERVICE WATER OUTLET E12-F068B AE12 RB 13 A 673 1E12-F073A A RHR HX SHELL SIDE DWNST VENT E12 RB 14 H 710 VALVE B RHR HX SHELL SIDE DWNST VENT 1E12-F073A AV E12 RB 14B 710 1E12-F074A A RHR HX SHELL SIDE UPSTRM VENT E12 RB 14 G 710 VALVE I 1E12-F074B B RHR HX SHELL SIDE UPSTRM VENT E12 RB B 710 VALVE AWS RH XSHELVLVSIEUPTMVN 1E12-F075A A RHR HX OUTLET PROCESS SAMPLE E12]DWVTAL LVAVEVE_1 El12-F075B B RHR HX OUTLET PROCESS SAMPLE E12 DWNST ISOL VALVE 1E12-F087A ARHRHXRCICSTEAMINLETPCV E12 RB 14 G 710 BYPASS VALVE 1E12-F087B B RHR HX RCIC STEAM INLET PCV E12 RB C 710 BYPASS VALVE 1E12-F088A A RHR PUMP SUCT RELIEF VALVE E12 1E12-F088B B RHR PUMP SUCT RELIEF VALVE E12 1E12-F088C C RHR PUMP SUCT RELIEF VALVE E12 1 El 2-F093 B RHR FUEL POOL EMER MU SUPPLY E12 RB C 694 DWNST VALVE 1E12-F094 B RHR FUEL POOL EMER MU SUPPLY E12 RB C 694 UPSTRM VALVE 1 El1 2-F097 B RHR FUEL POOL EMER MAKE UP E12_SUPPLY DRAIN VALVE Table B-la Page 41 of 56 B-43 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev A RHR SDC RETURN TESTABLE CHECK 1 El12-F099A E12 DW 13 D 740 BYPASS VALVE 1E12-F099B B RHR SDC RETURN TESTABLE CHECK El2 DW 11 E 740 BYPASS VALVE 1E12-F311A A RHR HX SHELL SIDE RELIEF VALVE E12 1E12-F311B B RHR HX SHELL SIDE RELIEF VALVE E12 U2 H2 RECOMBINER 2HG01A 1A RHR CLG 1E12-F312A WATER SUPPLY UPSTRM VALVE E12 RB 14 H 710 1E12-F312B UI H2 RECOMBINER 1HGOIA 1B RHR CLG E12 RB B 710 WATER SUPPLY VALVE 1E12-F313A A RHR HX TUBE SIDE RELIEF VALVE E12 1E12-F313B B RHR HX TUBE SIDE RELIEF VALVE E12 lEl2-F336A A RHR SERVICE WATER STRAINER E12 BACKWASH VALVE 1E12-F336B B RHR SERVICE WATER STRAINER E12 BACKWASH VALVE RHR SDC SUCT HEADER CNMT PENETRATION RELIEF VALVE 1E12-FB04A VALVE, GATE E12 1E12-FB04B VALVE, GATE E12 1E12-K300C 1C RHR SW PUMP SHORTING RELAY E12 AB 731'SE12-N005A A RHR HX SERVICE WATER DSCH TEMP E12 ELEMENT B RHR HX SERVICE WATER DSCH TEMP 1 El2-N005B E12 RB Bi10 694 ELEMENT 1E12-N007A A RHR HX SERVICE WATER INLET FLOW E12 1E12-N007B B RHR HX SERVICE WATER INLET FLOW E12 RB C 9 673 1E12-N015A A RHR FLOW E12 I 1E12-N015B B RHR FLOW E12 RB C9 673 1E12-N015C C RHR FLOW E12 1 El 2-N027A A RHR HX OUTLET TEMPERATURE E12 ELEMENT 1 E12-N027B B RHR HX OUTLET TEMPERATURE E12 RB A10 694 ELEMENT 1E12-N034A A RHR PUMP DSCH PRESS E12 1E12-N034B B RHR PUMP DSCH PRESS E12 1E12-N034C C RHR PUMP DSCH PRESS E12 1E12-N510 RHR HEAT EXCHANGER 1A EFFLUENT E12 1E21A-M1 AMMETER E21 1 E21-COO1 LPCS PUMP E21 RB 20 A 673 1E21-C002 LPCS WATER LEG PUMP E21 RB 14 B 673 1E21-D302 SUCTION STRAINER E21 1E21-F001 LPCS PUMP SUCT ISOL VALVE E21 RB 14 B 673 1E21-F005 LPCS INJECTION ISOL VALVE E21 RB 13 C 761 LPCS INJECTION TESTABLE CHECK 1 E21 -F006 VLEE21 VALVE__ _ ______ __1E21-F011 LPCS PUMP MIN FLOW ISOL VALVE E21 RB 14 B 673 Table B-I a Page 42 of 56 B-44 12Q.108.50-R-O.1 Rev. I Correspondence No.: RS-12-163 Eq Component Equipment Name System Floor TagBuilding Column NoElev 1E21-F012 LPCS FULL FLOW TEST BYP E21 RB 12:00 AM 710 1E21-F018 LPCS PUMP DSCH RELIEF VALVE E21 1E21-F031 LPCS PUMP SUCT RELIEF VALVE E21 1E21-F333 ASSY -VALVE, CONTROL E21 1E21-N003 LPCS PP DISCH FLOW XMITTER E21 RB 14 A 673 1E22-C001 PMP HI PRESS CORE SPRAY E22 RB F 673 1 E22-C002 1B DG COOLING WATER PUMP E22 1 E22-C003 PMP HI PRESS CORE SPRAY WTR LEG E22 RB F 673 1E22-D300 1B DG COOLING WATER STRAINER E22 1E22-D302 STRAINER, SUCTION E22 1E22-D315 FILTER, INTAKE E22 1E22-D317A lB DG A STARTING AIR STRAINER E22 1E22-D317B 1B DG B STARTING AIR STRAINER E22 1E22-F004 HPCS INJECTION ISOL VALVE E22 RB 10 C 761 21 HPCS DSCH CST UPSTRM FULL FLOW 1E22-F010 TEST VALVE E22 1 E22-FOl 1 HPCS DSCH CST DWNST FULL FLOW E22 TEST VALVE 1E22-F012 HPCS PUMP MIN FLOW ISOL VALVE E22 1E22-F014 HPCS PUMP SUCT RELIEF VALVE E22 1E22-F015 HPCS PUMP SUP POOL SUCT ISOL VALVE E22 RB 10 F 673 1E22-F023 HPCS FULL FLOW TEST ISOL VALVE E22 RB 10 D 694 1E22-F035 HPCS PUMP DSCH RELIEF VALVE E22 1 E22-F301 B ASSY -PANEL, DG GEN/ENG CONTROL E22 1 E22-17319 1B DG COOLING WATER STRAINER E22 BACKWASH VALVE 1 E22-F345 1B DG COOLER INLET HEADER RELIEF E22 VALVE 1E22-F354 ASSY -VALVE, CONTROL E22 1 E22-F369A 1B DG A STARTING AIR RECEIVER E22 RELIEF VALVE 1B DG B STARTING AIR RECEIVER 1 E22-F369B E22 RELIEF VALVE 1 E22-F370A 1B DG C STARTING AIR RECEIVER E22 RELIEF VALVE 1 E22-F370B 1B DG D STARTING AIR RECEIVER E22 RELIEF VALVE 1 E22-F381 A 1B DG A/C STARTING AIR MOTORS E22 SUPPLY CONTROL VALVE 1B DG BID STARTING AIR MOTORS SUPPLY CONTROL VALVE 1 E22-F382A 1B DG A/C STARTING AIR MOTORS E22 PINION SUPPLY SOLENOID VALVE 1 E22-F382B 1B DG B/D STARTING AIR MOTORS E22 PINION SUPPLY SOLENOID VALVE 1 E22-K001 HPCS DG AMPS E22 Table B-1 a Page 43 of 56 B-45 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag EquipmentNameCode Elev 1E22-M001 1 B DG GENERATOR AC VOLTAGE E22 1 E22-M002 1 B DG GENERATOR OUTPUT FREQUENCY E22 1 E22-M004 METER, WATT, 1 E22P301B E22 1 E22-M005 1 B DG GENERATOR AC AMPS E22 1E22-M006 4160V SWGR 1AP07E (143) BUS E22 FREQUENCY 1E22-M007 SWGR 1AP07E (143) VOLTAGE E22 1E22-M008 1B DG EXCITER FIELD AMPS E22 1 E22-M009 1 B DG EXCITER FIELD VOLTAGE E22 1E22-M010 1B DG SYNCHROSCOPE E22 1E22-M012 SAT 1AP91E (TR 142) VOLTAGE E22 1E22-M100 1B DG DC BUS VOLTAGE E22 1E22-N004 HPCS PUMP DSCH PRESS E22 RB 9 F 673 1E22-N005 HPCS PUMP DSCH FLOW E22 RB 9 G 673 1E22-N530 1B DG SOAK BACK LUBE OIL PRESS E22 1 E22-13301A 1B DG GROUNDING TRANSFORMERS AND E22 AB 08 N 710 BUS 113 DISTRIBUTION PANEL 1E22-P301B 1B DG AUXILIARY CONTROL PANEL E22 1 E22-S300 1B DG STARTING AIR COMPRESSOR E22 DG 710 PACKAGE 1E32-F001A ABANDONED IN PLACE E32 RB 12 J 740 1E32-FOO1E ABANDONED IN PLACE E32 RB 12 J 740 C LINE INBD LCS UPSTRM BLEED VLV -OB i1E32-F001J MIROME32 RB 12 J 740 MSIV ROOM__________

1E32-FOOlN VALVE, MSIV LCS I/B-ABANDONED IN E32 RB 12 J 740 PLACE E32 RB 12 J _74 1E32-FO02A VALVE, MSIV LCS I-ABANDONED IN PLACE E32 RB 12 J 740 1 E32-F002E VALVE, MSIV/LCS I/B-ABANDONED IN 1_E32-F_02E

_PLACE E32 RB 12 J 740 1E32-F002J VALVE, MSIV LCS I/B-ABANDONED IN E32 RB. 12 J 740 PLACE E32 RB_ 12 J _74 1 E32-FO02N VALVE, MSIV LCS I/B-ABANDONED IN E32 RB 12 J 740 PLACE E32 RB 12 J _74 1 E32-F003A VALVE, MSIV LCS I/B-ABANDONED IN 1_E32-F_03A

_PLACE E32 TB 12 L 687 1 E32-FO03E VALVE, MSIV LCS I/B-ABANDONED IN E32 TB 12 L 687 PLACE E32 TB 12 L _68 1 E32-FO03J VALVE, MSIV LCS I/B-ABANDONED IN E32 TB 12 L 687 PLACE E32 TB 12 L _68 1E32-FO03N VALVE, MSIC LCS I/B-ABANDONED IN E32 TB 12 L 687 PLACE E32 TB 12 L _8 1E32-F006 VALVE, MSIV LCS O/B -BLEEDABANDONED E32 RB 12 J 740 IN PLACE E32 RB 12_J_ 740 1E32-F007 VALVE, MSIV LCS O/B BLEED-ABANDONED E32 RB 12 J 740 IN PLACE E32 RB 12 J _4 Table B-la Page 44 of 56 B-46 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor Eq Component EquipmentSystem Building Column No rElev Tag EquipmentBuiCm Code 1E32-F008 VALVE, MSIV LCS 0/B-ABANDONED IN E32 RB 12 J 740 PLACE VALVE, MSIV LCS O/B 1E32-F009 DEPRESSURIZATION-ABANDONED IN E32 RB 12 J 740 PLACE 1E32-N050 ABANDONED IN PLACE E32 1E51-COO1 RCIC PUMP E51 RB 14 A 673 1E51-C003 RCIC WATER LEG PUMP E51 RB 14 C 694 1E51-D314 DAMPER, PULSATION E51 1E51-D315A DAMPER, PULSATION E51 1 E51 -D315B DAMPER, PULSATION E51 1 E51 -D319 RCIC TURBINE TRIP / THROTTLE VALVE E51 LEAKOFF DRAIN STRAINER 1E51-F008 RCIC STEAM SUPPLY OTBD ISOL VALVE E51 RB 13 C 740 1E51-F010 RCIC PUMP CYCLED CST SUCT VALVE E51 RB 14 A 694 1E51-F013 RCIC INJECTION OTBD ISOL VALVE E51 RB 13 G 740 1 E5i -F0l 5 RCIC LUBE OIL COOLER INLET PRESS E51 CONT VALVE 1E51-F017 RCIC PUMP SUCT RELIEF VALVE E51 1E51-F019 RCIC PUMP MIN FLOW ISOL VALVE E51 RB 14 B 673 1E51-F022 RCIC FULL FLOW TEST UPSTRM VALVE E51 RB 14 A 694 1 E51 -F025 RCIC STEAM SUPPLY DRAIN POT UPSTRM E51 RB 14 A 673 OUTLET VALVE 1 E51 -F026 RCIC STEAM SUPPLY DRAIN POT DWNST E51 RB 14 A 673 OUTLET VALVE 1E51-F031 RCIC PUMP SUP POOL SUCT ISOL VALVE E51 RB 13 C 673 1E51-F045 RCIC TURBINE STEAM SUPPLY VALVE E51 RB 14 B 673 1 E51 -F046 RCIC TURBINE LUBE OIL COOLER INLET E51 RB 14 A 673 VALVE 1E51-F059 RCIC FULL FLOW TEST DWNST VALVE E51 RB 14 A 694 1E51-F063 RCIC STEAM SUPPLY INBD ISOL VALVE E51 1 E51 -17064 RCIC STEAM INLET RHR HX SUPPLY ISOL E51 RB 740 VALVE 1E51-F065 VALVE, AIR RI TESTABLE CHK VLV E51 1 E51 -17066 RCIC INJECTION INBD TESTABLE CHECK E51 DW VALVE 1E51-F068 RCIC TURBINE EXHAUST ISOL VALVE E51 RB 13 B 694 1E51-F069 RCIC CNDSR VACUUM PUMP DSCH ISOL E51 RB 13 B 694 VALVE 1 E51 -F076 RCIC STEAM SUPPLY INBD ISOL E51 BYPASS/WARMUP VALVE I1E51 -17080 RCIC TURBINE EXHAUST VACUUM BKR E51 RB 14 D 694 DWNST ISOL VALVE 1 E51 -F086 RCIC TURBINE EXHAUST VACUUM BKR E51 UPSTRM ISOL VALVE 1E51-F387 NEW RCIC VALVE E51 RB 13 G 740 Table B-Ia Page 45 of 56 B-47 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1E51-N004 RCIC PUMP DSCH PRESS E51 RB 14 C 673 1IFI-HG022 HYDROGEN RECOMBINER INLET FLOW HG (FI-1) HG 1 FI-HG023 HYDROGEN RECOMBINER TOTAL FLOW HG (FI-2)A POST LOCA H2 RECOMB INLET FLOW 1 FT-HG022 TASIERHG TRANSMITTER 1 FT-HG023 A POST LOCA H2 RECOMB TOTAL FLOW HG TRANSMITTER 1G33-F001 RWCU INBD ISOL VLV G33 DW 11 F 740 1G33-F004 RWCU OTBD ISOL VALVE G33 RB 13 D 774 1 G33-F040 RWCU DSCH HDR STOP OTBD MSIV G33 RB 12 J 740 ROOM 1G33-F100 RWCU SUCT STOP FROM A RECIRC LINE G33 DW 13 D 740 1H13-P601 ASSY -PANEL, EMERG CORE COOL SYST H13 MCR --1H13-P602 ASSY -PANEL, RWCU/RX RECIRC H13 MCR --CONTROL 1H13-P604 ASSY_-_PANEL, PROCESS RAD MONITOR H13 CR 14 J 768 INSTR _1H13-P610 ASSY_-_PANEL, CONTROL ROD TEST H13 CR 12.8L 768 INSTR 1H13-P614 ASSY_--PANEL, NSSS TEMP RECORDER H13 CR 14 J 768 1H13-P624 ASSY_-_PANEL, AREA RAD COMMON H13 CR 15 J 768 MONITOR 1H22-P001 LPCS INSTRUMENT PANEL H22 RB 673 REACTOR WATER CLEAN UP i1H22-P002 INTUETPNLH22 RB 761 INSTRUMENT PANEL I H22-P004 REACTOR VESSEL LEVEL AND PRESSURE H22 RB 761 PANEL A 1 H22-P005 REACTOR VESSEL LEVEL AND PRESSURE H22 PANEL C___1 H22-P006 A REACTOR RECIRC PUMP INSTRUMENT H22 RB 710 PANEL 1H22-P007 CRD & RX VESSEL TEMP RECORDR PNL H22 CR 768 1H22-P009 JET PUMP INSTRUMENT PANEL B H22 RB 710 1H22-P010 JET PUMP INSTRUMENT PANEL A H22 RB 14 F 710 1 H22-P0l15 MAIN STEAM FLOW INSTRUMENT PANEL H22 RB 710 A 1H22-P017 RCIC INSTRUMENT PANEL A H22 1H22-P018 A RHR INSTRUMENT PANEL H22 RB 673 1H22-P021 B/C RHR INSTRUMENT PANEL H22 RB 673 1 H22-P022 B REACTOR RECIRC PUMP INSTRUMENT H22_PANEL 1 H22-P024 HPCS INSTRUMENT PANEL H22 RB 673 Table B-1 a Page 46 of 56 B-48 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Code Elev 1 H22-P025 MAIN STEAM FLOW INSTRUMENT PANEL H22 RB 710 D REACTOR VESSEL LEVEL AND PRESSURE 1 H22-P026 PNLDH22 PANEL D ___1 H22-P027 REACTOR VESSEL LEVEL AND PRESSURE H22 PANEL B 1 H22-P028 1B DG PROTECTION RELAY CABINET H22 1H22-P029 RCIC INSTRUMENT PANEL B H22 RB 673 1H22-P030 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 740 ENCLOSURE A-1 1H22-P031 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 740 ENCLOSURE B-1 1 H22-P032 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 740 ENCLOSURE A-2 1H22-P033 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 740 ENCLOSURE B-2 1 H22-P073 ASSY -PANEL, MSIV LEAKAGE CONTROL H22 DIV-1I 1 H22-P074 ASSY--_PANEL, MSIV LEAKAGE CONTROL H22 RB 673 DIV-2 I1H22-P075 LOW LOW SET/SAFETY RELIEF VALVE DIV H22 I INSTRUMENT PANEL 1H22-P076 LOW LOW SET/SAFETY RELIEF VALVE DIV H22 1H22-P076_

II INSTRUMENT PANEL 1HG001A H2 RECOMB 1HG01A U-1 DW SUCT. VLV HG RB 11 C 786 1HGO01B H2 RECOMB 1HGO1A U-1 DW SUCT VLV HG RB 14 E 786 1HGO02A H2 RECOMB 1HGO1A U-1 DW SUCT VLV HG RB 11 C 786 1HGO02B H2 RECOMB 2HG01A U-1 DW SUCT VLV HG RB 14 E 786 1HGO03 U-1 SUP POOL RTN ISOL HG RB 10 B 761 1 HGO05A H2 RECOMB 1HG01A U-1 SUP POOL DIS HG RB 11 B 710 VLV 1 HGO05B H2 RECOMB 2HG01A U-1 SUP POOL DIS HG RB 13 B 710 VLV I HGO06A H2 RECOMB 1HG01A U-1 SUP POOL DIS HG RB 11 B 710 VLV 1 HGO06B H2 RECOMB 2HG01A U-1 SUP POOL DIS HG RB 13 B 710 VLV 1HG009 U-2 SUP POOL RTN ISOL HG RB 10 B 761 1HG018 U-2 CLG WTR X-TIE ISOL HG RB 10 B 761 1HG01A ASSY- BLOWER, H2 RECOMBINER HG RB 10 B 786 1 HG025 ASSY -VALVE, GLOBE HG 1HG026 ASSY -VALVE, GLOBE HG 1 HG027 ASSY -VALVE, HG IHGFV1 U-1 H2 RECOMB INLT VLV HG 1HGFV2 U-1 H2 RECOMB RECIRC VLV HG 1HT02E ASSY -PANEL, HEAT TRACE/HEATER HT AB 10 N 731 Table B-Ia Page 47 of 56 B-49 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev DRYWELL INST N2 SUCTION HEADER IlNO01A UPSTRM ISOLATION SOV-DW SUCT IN RB 14 F 740 UPSTRM ISOL DRYWELL INST N2 SUCTION HEADER 1 IN001 B DWNST ISOLATION SOV-DW SUCT IN RB 14 F 740 DWNST ISOL!11N017 DW INST N2 REGULATED HDR DRYWELL IN RB .14 F 740 SUPPLY-DW PNEUMATIC TO DW 1 IN02HA ADS N2 EMERG PRESSURIZATION IN BOTTLE STORAGE RACK NORTH ADS N2 EMERG PRESSIZATION 1IN02HB BOTTLE STORAGE BANK STORAGE RACK IN 1 IN031 DRYWELL INST N2 TIP INDEXER PURGE IN VLV 11N045 A N2 MANIFOLD RELIEF VALVE IN 11N046 B N2 MANIFOLD RELIEF VALVE IN DW INST N2 DRYER PURGE S11N074 DOWNSTREAM OUTLET VALVE-DW IN RB 14 F 740 PNEUMATIC DRYER DWNST PURGE OTLT DW INST N2 DRYER PURGE UPSTREAM 1 IN075' OUTLET VALVE-DW.

PNEUMATIC DRYER IN RB 14 F 740 UPSTRM PURGE OTLT " iIN100 A ADS ACCUM UNREGULATED N2 IN'HEADER DW ISOL VALVE 1IN101 B ADS ACCUM UNREGULATED N2 IN HEADER DW ISOL VALVE ASSY_-_TRANSDUCER/SENSOR POWER 1PA05J --PA AB 14 L-: 731 SUPPLY CABINET ASSY -PANEL, ANNUNCIATOR VISUAL PA 1_PA08JA

• LOGIC PA HYDROGEN RECOMBINER CONTROL 1 PAl12J 'PA PANEL 1PA13J DIV I NSSS AUX RELAY CABINET PA AB 731 1PA14J DIV II NSSS AUX RELAY CABINET PA AB 731 1PA17J STANDBY GAS TREATMENT PANEL PA 1PI-DG055A 1A DG LUBE OIL.FILTER PRESS DG IPI-DG055B 1A DG LUBE OIL FILTER PRESS DG I 1PI-DG056 1A DG MAIN LUBE OIL PRESS DG 1PI-DG057A 1A DG FUEL OIL PRESS DG 1PI-DG057B 1A DG FUEL OIL PRESS DG 1 PI-DG059 1A DG FUEL OIL PRESS DG 1PI-DG060A 1A DG FUEL OIL PRESS DG 1PI-DG060B 1A DG FUEL OIL PRESS DG 1PI-DG063 1A DG ENGINE COOLING WATER PRESS DG Table B-i a Page 48 of 56 B 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component, Equipment Name System Building Column No Floor Tag EquipmentNameCode Elev 1PI-DG086 1A DG SCAVENGING AIR PRESS DG 1PI-DG094 1A DG A AIR RECEIVER DG DG J 7-8 710 1 PI-DG095 1A DG B AIR RECEIVER DG 1PI-DG098A 1A DG A BANK STARTER AIR SUPPLY DG IPI-DG098B 1A DG B BANK STARTER AIR SUPPLY DG 1PI-DG121 1A DG SOAK BACK LUBE OIL DG 1PI-DG122 1A DG CRANKCASE PRESS DG STANDBY GAS TREATMENT CONTROL 1 PL1 7J PNLPL RB 12 B 820 PANEL _______1PL24J ASSY -PANEL, DG ROOM VENT SYST DIV- PL 3 1PL25J ASSY -PANEL, DG ROOM VENT SYST DIV- PL 2 PL 1PL26J ASSY -PANEL, AUX BLDG MISC VENT PL AB 09 L 815 1PL27JA ASSY -PANEL, REACTOR BLDG PL VENTILATION DIV-1 1PL27JB ASSY -PANEL, REACTOR BUILDING PL VENTILATION DIV-1 PL29J ASSY -PANEL, SWGR HEAT RMVL DIV-1 PL 1 PL30J ASSY -PANEL, SWGR HEAT RMVL DIV-2 PL 1PL31J ASSY -PANEL, M/G SET ROOM VENT PL 1PL32J HPCS PUMP ROOM VENTILATION PANEL PL 1PL33J- B/C RHR PUMP ROOM VENTILATION PL DG -736 PANEL 1PL34J A RHR PUMP ROOM VENTILATION PANEL PL RB 13 H 694 1PL35J LPCS PUMP ROOM VENTILATION PANEL PL RB 13 B 694 1PL38JB ASSY -PANEL, CONDENSER TUBE PL CLEANING CONTROL 1PL69J ASSY -PANEL, BATT ROOM VENT PL 1 PL73J ASSY -PANEL, RHR SERV WTR PP A/B PL ROOM VENT 1 PL74J ASSY -PANEL, RHR SERV WTR PP C/D PL ROOM VENT " 1PL76J ASSY -PANEL, A P/C HYDROGEN/OXYGEN PL MONITORING PL 1PL77J ASSY_-_PANEL, B P/C PL RB 761 HYDROGEN/OXYGEN MONITORING 1PL78J ASSY_-_PANEL, SC/DW OXYGEN PL RB 12 B 786 MONITORING PANEL 1PL86J ASSY -PANEL, RX BLDG HEATING PL 1PL87J TURBINE BLDG. HEATING PL 1PL99J RX BUILDING VENTCONS AIR MONITOR PL AB 13 L 786 I PLA8J .A PRI CNMT CHILLER 1VP01CA MOTOR PL STARTER AND AUXILIARY PANEL 1 PLA9 B PRI CNMT CHILLER 1VP01CB MOTOR PL_STARTER AND AUXILIARY PANEL Table B-ila Page 49 of 56 B-51 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1PLB8J ASSY -PANEL, CONDENSATE SYST PL 1PLD9J ASSY_-_PANEL, RX BLDG CLOSED COOL PL RB 09 B 786 WTR 1PLF3J ASSY -PANEL, H2 RECOMBINER LOCAL PL 1PLF5J ASSY_-_CABINET, S-POOL TEMP PL RB 761 MONITORING POWER 1PLF6J ASSY_-_CABINET, S-POOL TEMP PL RB 761 MONITORING POWER 1PLG1J ASSY -PANEL, CONT MONIT VLV AUX PL RELAY DIV-1 1PLG2J ASSY -PANEL, CONT MONIT VLV AUX PL RELAY DIV-2 1PLH2J DIV III 125VDC INST PANEL PL 1IPLH6J COND BSTR PUMP MIN FLOW CONTROL PL PANEL AUTOMATIC STRAINER BACKWASH 1__________CONTROL PANEL PL 1PLH9J 1HGO1A STARTER CABINET PL IPM01IJ ASSY -PANEL, ELECT CONTROL PM 1PM03J ASSY_-_PANEL, PM CR 13 L 768 FEEDWATER/CONDENSATE IPM05J ASSY -PANEL, HVAC CONSOLE. PM 1PM06J ASSY -PANEL, HVAC CONSOLE PM 1 PM07J ASSY -PANEL, STANDBY GAS PM TREATMENT SYST 1PM13J ASSY -PANEL, CONTAIN MONITOR/LEAK PM lPM13J____

DETECTION 1PM16J ASSY -PANEL, P/C MONITOR/LEAK PM DETECTION A POST LOCA H2 RECOMB INLET PRESS 1 PT-HG023 TASIERHG__________TRANSMITTER 1RE024 DWEDS PUMP SUCT HDR UPSTRM VALVE RE 1RE025 DWEDS PUMP SUCT HDR DWNST VALVE RE 1RE026 DWEDS RECIRC DWNST VALVE RE 1RE029 DWEDS RECIRC UPSTRM VALVE RE 1RF012 DWFDS PUMP SUCT HDR UPSTRM VALVE RF RB 11 H 710 1RF013 DWFDS PUMP SUCT HDR DWNST VALVE RF 1SI-DG028 METER, FREQUENCY 1PM01J A DG DG 1SI-DG067 1A DG FREQUENCY METER DG 1TE-HGO14A HYDROGEN RECOMBINER GAS INLET (TE- HG 1A)1TE-HGO14B HYDROGEN RECOMBINER GAS INLET HG_SPARE(TEl B__Table B-i a Page 50 of 56 B-52 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag! Equipment_________Name___

Code ____Ee ITEaHgI HYDROGEN RECOMBINER BLWR INL GAS HG RB1 7 1 TE-HG0 15A (E2)HG RB B 10 786____________(TE-2A) 1TE-HGO15B SPARE TC BLWR INL GAS (TE-2B) HG 1 TE-HGOI 6A HYDROGEN RECOMBINER HEATER GAS HG (TE-4A)1TE-HGO16B SPARE TC HEATER GAS (TE-4B) HG HYDROGEN RECOMBINER HTR OUTLT 1TE-HG017A GA T-AHG GAS (TE-EA 1TE-HGO17B SPARE TC HTR GAS OUT (TE-5B) HG 1TE-HGO1 8A HYDROGEN RECOMBINER HEATER WALL HG (TE-6A)1TE-HGO18B SPARE TC HEATER WALL (TE-6B) HG 1 TE-HGO19A HYDROGEN RECOMBINER REAL CHMBR HG GAS(TE-7A 1TE-HGO19B SPARE TC REAC CHMBR GAS(TE-7B HG 1TE-HG020A H2 RECOMB REACTION CHAMB SHELL (TE HG 8A)SPARE TC REACTION CHAMBER SHELL 1TE-HG020B (T-B HG (TE-aB 1TE-HG021A HYDROGEN RECOMBINER RETURN HG GAS(TE-9A) 1TE-HGO21 B SPARE H2 HYDRO RECOMRETURN HG GAS(TE-9B) 1TE-VD003 E22S001 ROOM TEMP CONT SENSOR VD 1TE-VD005 E22S001 ROOM TEMP IND/ALM VD 1TE-VD008 1DG01K ROOM MOD DMPR TEMP CONT VD 1TE-VD013 1E22S001 ROOM MOD DMPR TEMP CONT VD 1 B HPCS DG COOLING WTR PP ROOM 1TE-VD015___

VENT RTN TEMP ELEMENT VD ITE-VX007 RESISTANCE TEMP DETECTOR VX 1TE-VX008 RESISTANCE TEMP DETECTOR VX 1ITE-VX009 SWGR HEAT RMVL DIV-1 AREA RET AIR TEMP 1TE-VY023 RHR WS PP A/B T/CONT DMPR VY 1TE-VY024 RHR WS PP C/D T/CONT DMPR VY ITI-DG054 1A DG MAIN LUBE OIL TEMP DG 1TI-DG058 1A DG FUEL OIL TEMP DG 1TI-DG061 DG ENGINE RAW COOLING WTR TEMP DG 1TI-DG062 1A DG ENGINE JACKET WATER TEMP DG 1TI-VX010 RX BLDG MG SET VENT SYST TEMP/IND VX 1TI-VX01 1 SWGR HEAT RMVL DIV-2 TEMP/IND VX 1TI-VX012 SWGR HEAT RMVL DIV-1 TEMP/IND VX 1VD01C FAN, HPCS DG ROOM VENT VD 1VD01F DIESEL GEN ROOM VENT SPLY VD 1VD01J TIME DELAY PANEL VD AB 674 IVD01YA DAMPER, VD Table B-la Page 51 of 56 B-53 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1VD01YB DAMPER, VD 1VD02C ASSY -FAN, HPCS DG FUEL STOR TANK VD ROOM VENT 1VD02F DIESEL GEN ROOM VENT SPLY VD IlVD02J TIME DELAY PANEL VD AB 674 1VD02YA DAMPER VD 1VD02YB DAMPER VD 1VD03C FAN, DG ROOM VENT SUPPLY VD 1VD03YA DAMPER, VD 1VD03YAB DAMPER, DG ROOM VENT VD 1VD03YB DAMPER, VD 1VD04C FAN, DG FUEL STOR TANK ROOM VENT VD 1VD04Y DAMPER, DG ROOM VENT VD 1VD05C ASSY -DIV 3 SWGR ROOM/CSCS PUMP VD ROOM SUPPLY FAN 1VD05C 1VD05Y DAMPER, DG ROOM VENT VD 1VD06C FAN, HPCS SWGR BATT ROOM EXH VD 1VD06Y DAMPER, DG ROOM VENT VD 1VD07C FAN, HPCS DG COOL WTR PP ROOM VD RETURN 1VD07Y DAMPER, DG ROOM VENT VD 1VD08Y DAMPER, DG ROOM VENT VD 1VD09YA DAMPER, VD 1VD09YB DAMPER, VD 1VD10YA DAMPER, VD 1VD10YB DAMPER, VD 1VD11YA DAMPER, VD 1VD11YAB DAMPER, DG ROOM VENT MODUL VD_____OPPOSED 1VD11YB DAMPER, VD 1VD12Y DAMPER, DG ROOM VENT VD 1VD13Y DAMPER, DG ROOM VENT VD 1VD14Y DAMPER, DG ROOM VENT VD 1VD15Y DAMPER, DG ROOM VENT VD 1A DG FUEL STORAGE TANK ROOM FAN DISCHARGE DAMPER 1VD17Y DAMPER, AMERICAN VD WARMINGNENTILATING 1VD18Y DAMPER, VD 1VD19Y DAMPER, VD 1VD20Y DAMPER, DG ROOM VENT VD 1VD21Y DAMPER, DG ROOM VENT ISOL FIRE VD I1VD22Y DAMPER, DG ROOM VENT VD 1VD23Y DAMPER, DG ROOM VENT VD 1VD24Y DAMPER, DG ROOM VENT VD IVD25Y DAMPER, DG ROOM VENT VD IVD26Y DAMPER, DG ROOM VENT VD Table B-I a Page 52 of 56 B-54 12QO108.50-R-O01 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No loor Tag Code EupnNmCEdev 1VD27Y DAMPER, DG ROOM VENT VD 1VD29Y DAMPER, DG ROOM VENT VD 1VD30Y DAMPER, DG ROOM VENT VD 1VD31Y DAMPER, DG ROOM VENT VD 1VD40Y DAMPER, DG ROOM VENT VD 1VD41Y DAMPER, DG ROOM VENT VD 1VD42Y DAMPER, DG ROOM VENT VD 1VD43Y DAMPER, DG ROOM VENT VD 1VD44Y DAMPER, GD ROOM VENT VD 1VG001 SBGT SUCT FROM RX BLDG VG RB 11:00 AM 820 ATMOSPHERE 1VG003 SBGT TRAIN OTLT DMPR VG RB 11:00 AM 820 1VP053A A DW COOLER OUTLET OTBD ISOL VALVE VP RB 12 G 761 1VP053B B DW COOLER OUTLET OTBD ISOL VALVE VP RB 12 G 761 1VP063A A DW COOLER INLET OTBD ISOL VALVE VP RB 12 G 761 1VP063B B DW COOLER INLET OTBD ISOL VALVE VP RB 12 G 761 1VP113A A DW COOLER INLET INBD ISOL VALVE VP DW 11 D 761 1VP113B B PCCW LOOP SPLY TO DW COOLER VP DW 11 D 761 INBDISOL A PCCW LOOP RTN FROM DW COOLER 1VP114A VP DW 11 D 761 INBDISOL IVPI 14B B PCCW LOOP RTN FROM DW COOLER VP DW 11 D 761 INBD ISOL 1VP197A A DW COOLER OUTLET RELIEF VALVE VP IVP197B B DW COOLER OUTLET RELIEF VALVE VP 1VP198A A DW COOLER INLET RELIEF VALVE VP 1VP198B B DW COOLER INLET RELIEF VALVE VP SUP POOL VENT/PURGE FROM RXBLDG 1VQ026 VQ RB 11- H 710 UPSTRM ISOL 1VQ027 SUP POOL VENT/PURGE FROM RXBLDG VQ RB 11 H 710__1V __027 _ DWNST ISOL V R1 7 DW VENT/PURGE FROM RX BLDG 1VQ029 VQ RB I11H 740 UPSTRM ISOL 1VQ030 DW VENT/PURGE INLET DWNST ISOL VQ RB 11 H 740 VALVE SUP POOL VENT/PURGE OTLT UPSTRM 1VQ031 ISLVQ RB 14 E 710 ISOL ___ ____1VQ032 SUP POOL VENT/PURGE OTLT UPSTRM VQ RB 14 E 710 ISOL BYP-20 FT.OVHD 1VQ034 DW VENT/PURGE OTLT UPSTRM ISOL VQ RB 13 G 807 1VQ035 DW VENT/PURGE OTLT UPSTRM ISOL VQ RB 13 G 807 1V_035 _BYP I 1VQ036 DW VENT/PURGE OTLT DWNST ISOL VQ RB 13 G 807 1VQ037 PRI CNMT VENT/PURGE TO FILT UNIT VQ AB 13 J 786 UPSTRM ISOL Table B-la Page 53 of 56 B-55 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component ESystem Floor EqTCompont Equipment Name Stem Building Column No Elev Tag! Code _________

Ee 1VQ038 VALVE, SECONDARY CONTAINMENT VQ 1VQ038____

ISOLATION

__1VQ040 SUP CHBR VENT/PURGE OUTLET DWNST VQ RB 14 E 710 ISOL VALVE 1VQ041 VALVE, BUTTERFLY VQ 1VQ042 SUP POOL N-2 INRTG LINE ISOL VQ RB 11 H 7.10 1VQ043 SUP POOL N-2 INRTG LINE ISOL VQ RB 11 H 710 mVQ047 DW N-2 MU LINE DWNST ISOL VQ RB 11 H 740 1VQ048 DW N-2 MU LINE UPSTRM ISOL VQ RB 11 H 740 1VQ050 SUP POOL N-2 MU LINE DWNST ISOL VQ RB 11 H 710 1VQ051 SUP POOL N-2 MU LINE UPSTRM ISOL VQ RB 11 H 710 1VQ068 DW VENT/PURGE OTLT DWNST ISOL BYP VQ RB 13 G 807 1VR04YA DAMPER, VR ISOLATION VR 1VR04YB DAMPER, VR ISOLATION VR 1VR05YA DAMPER, VR ISOLATION VR 1VR05YB DAMPER, VR ISOLATION VR 1VR08Y DAMPER, 30 INCH CHECK VR 1VR09Y DAMPER, 30 INCH CHECK VR 1VR10Y DAMPER, 54 INCH CHECK VR 1VR11Y DAMPER, 42 INCH CHECK VR 1VR12Y DAMPER, 42 INCH CHECK VR 1VR13Y DAMPER, 42 INCH CHECK VR 1VR14Y DAMPER, 42 INCH CHECK VR 1VR65YA DAMPER, RB VENT BALANCING OPPOSED VR 1VR65YB DAMPER, RB VENT BALANCING OPPOSED VR 1VR66Y DAMPER, RB VENT BALANCING OPPOSED VR 1VR90Y DAMPER, HELB IN MAIN STEAM TUNNEL VR U1 VR EXHAUST PLENUM 1VR91Y RB VENT SYS EXCESS FLOW CHECK VR DAMPER 1VX01C FAN, ESS SWGR DIV-1 VENT SUPPLY VX 1VX01F FILT ESS SWITCHGEAR DIV 1 VENT SPLY 'A AIR 1VX01Y DAMPER, SWGR HEAT RMVL VX 1VX02C FAN, ESS SWGR DIV-1 BATT ROOM EXH VX FILT ESS SWITCHGEAR DIV 2 VENT SPLY 1VX02F AIR VX 1VX02Y DAMPER, VX 1VX03C FAN, ESS SWGR DIV-1 BATT ROOM EXH VX 1VX03F FILT RX PROT MG SET RM 1 SPLY AIR VX 1VX03Y DAMPER, SWGR HEAT RMVL MODUL VX 1VX03Y____[OPPOSED VX 1VX04C FAN, ESS SWGR DIV-2 VENT SUPPLY VX AB 10 L 731 Table B-I a Page 54 of 56 B-56 12QO108.50-R-O01 Rev. I Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag *_EquipmentNameCode

_ Elev IVX04Y DAMPER, SWGR HEAT RMVL VX 1VX05C FAN, ESS SWGR DIV-2 BATT ROOM EXH VX AB 10 L 731 1VX05Y DAMPER, SWGR HEAT RMVL VX 1VX06C FAN, RX PROT MG SET ROOM 1 BATT VX ROOM EXH 1VX06Y DAMPER, SWGR HEAT RMVL ISOL FIRE VX IVX07C FAN, RX PROT MG SET ROOM 1 VENT VX SUPPLY 1VX07Y DAMPER, VX 1VX08C FAN, RX PROT MG SET ROOM 1 BATT Vx ROOM EXH *IVX08Y DAMPER, VX 1VX09Y DAMPER, SWGR HEAT RMVL VX 1VX10Y DAMPER, SWGR HEAT RMVL VX 1VX11Y DAMPER, SWGR HEAT RMVL VX 1VX12Y DAMPER, SWGR HEAT RMVL VX 1VX14Y DAMPER, VX 1VX15Y DAMPER, SWGR HEAT RMVL VX 1VX16Y DAMPER, SWGR HEAT RMVL VX 1VX17Y DAMPER, SWGR HEAT RMVL VX 1VX19YA DAMPER, DIV-1 HEAT RMVL ACTUATOR VX 1VX22Y DAMPER, SWGR HEAT RMVL VX 1VX26Y DAMPER, DIV-1 SWGR COOL VX 1VX30Y DAMPER, SWGR HEAT RMVL VX 1 VX31Y DAMPER, SWGR HEAT RMVL VX 1VX32Y DAMPER, SWGR HEAT RMVL VX 1VX33Y DAMPER, SWGR HEAT RMVL VX 1VX34Y DAMPER, SWGR HEAT RMVL VX 1VX35Y DAMPER, SWGR HEAT RMVL VX 1VX36Y DAMPER, SWGR HEAT RMVL VX 1VX37Y DAMPER, SWGR HEAT RMVL VX 1VX38Y DAMPER, SWGR HEAT RMVL VX 1VX39Y DAMPER, SWGR HEAT RMVL VX 1VX41Y DAMPER, SWGR HEAT RMVL VX 1VX42Y DAMPER, SWGR HEAT RMVL VX 1VX43Y DAMPER, SWGR HEAT RMVL ISOL FIRE VX 1VX44Y DAMPER, SWGR HEAT RMVL VX 1VX45Y DAMPER, SWGR HEAT RMVL VX 1VX46Y DAMPER, SWGR HEAT RMVL VX 1VX50Y DAMPER, SWGR HEAT RMVL VX 1VX51Y DAMPER, SWGR HEAT RMVL VX 1VX52Y DAMPER, SWGR HEAT RMVL VX 1VX53Y DAMPER, SWGR HEAT RMVL VX 1VX54Y DAMPER, SWGR HEAT RMVL VX 1VX55Y DAMPER, SWGR HEAT RMVL VX 1VX56Y DAMPER, SWGR HEAT RMVL VX 1VX57Y DAMPER, SWGR HEAT RMVL VX Table B-I a Page 55 of 56 B-57 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column No Floor Tag Code Elev 1VX58Y DAMPER, SWGR HEAT RMVL VX 1VX59Y DAMPER, SWGR HEAT RMVL VX 1VX60Y DAMPER, SWGR HEAT RMVL VX 1VY01A A RHR PUMP ROOM COOLER VY 1VY01C ASSY--_FAN, RHR PUMP A ROOM VY RB 15 E 694 COOLING 1VY01Y DAMPER, VY 1VY02A HPCS PUMP ROOM COOLER VY 1VY02C HPCS PUMP ROOM COOLER VENT FAN VY RB 8.9 E 694 1VY02Y DAMPER, VY 1VY03A B / C RHR PUMP ROOM COOLER VY 1VY03C ASSY_-_FAN, RHR PUMP B/C ROOM VY RB 09 D 694 COOLING FAN 1VYO3Y DIV I CSCS PUMP ROOM VENT EXHAUST DAMPER 1VY04A LPCS PUMP ROOM COOLER VY 1VY04C ASSY_-_FAN, LPCS PUMP ROOM VY RB 15 D 694 COOLING V R 1D 6 IVY04Y DAMPER, VY 1VY05C ASSY -FAN, RHR WS PP A-1B CUBE VY DG 7 H 736 SUPPLY 1VY05Y DAMPER, VY 1VY06C ASSY -FAN, RHR WS PP A-1B CUBE VY DG 7H 736 SUPPLY 1VY06Y DAMPER, VY 1WR029 DW EQUIP RBCCW SUPPLY OTBD ISOL WR RB 13 B 740 VALVE 1WR040 DW EQUIP RBCCW RTN OTBD ISOL WR RB 11 C 786 VALVE 1WR179 RBCCW DW INLET INBD ISOL STOP WR DW 12 B 740 1WR180 RBCCW DW OUTELT INBD ISOL STOP WR DW C 786 1WR225 DW EQUIP RBCCW SUPPLY RELIEF WR VALVE DW EQUIP RBCCW RETURN RELIEF I _1WR226 WVALVE _R Table B-la Page 56 of 56 B-58 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Table B-l b. Base List lb -Items Common to Units 1 and 2 SystemFloor Eq Component Tag Equipment Name Code Building Column No Eleo 0AE-VC090A CONT ROOM A/C A CHLOR MON A VC 0AE-VC090B CONT ROOM A/C A CHLOR MON A VC OAP08E RSH AUX PWR XFMR AP OC11-F002A VALVE, AO C11 0DC04E BATTERY CHARGER 250 VDC SPARE DC 0DC17E BATTERY CHARGER 125 VDC SPARE DC ODC23E BATTERY CHARGER 125 VDC SPARE DC ODC36E BATTERY CHARGER 24/48 VDC DC 0 DG COOLING WATER STRAINER ODG009 DG BACKWASH VALVE _0 DG COOLER INLET HEADER RELIEF ODG014 VALVE DG ODG01A 0 DG COOLER DG ODG01D SILENCER, DG ENGINE DG ODG01F 0 DG COOLING WATER STRAINER DG ODG01K 0 DIESEL GENERATOR DG ODG01 K-1 FILTER, AIR INTAKE DG ODG01K-A PUMP, AC TURBO SOAKBACK DG ODG01 K-B PUMP, DC TURBO SOAKBACK DG ODG01 K-C PUMP, AC LUBE OIL CIRC DG ODG01K-D PUMP, SCAVENGING OIL DG ODG01K-DG01K-EXC 0 DG EXCITER DG ODG01K-E FILTER, TURBOCHARGER OIL DG ODG01 K-F FILTER, FUEL ASSEMBLY DG ODG01K-G PUMP, RIGHT BANK WTR DG ODG01 K-H PUMP, LEFT BANK WTR DG ODG01 K-I PUMP, MAIN LUBE OIL DG 0DG01K-J PUMP, PISTON COOL DG ODG01K-K PUMP, ENGINE DRIVEN FUEL DG ODG01K-L PUMP, ELECT MTR DRIVEN FUEL DG 0DG01K-M TRAP, TYPE EXH SCREEN DG ODG01K-N HEAT EXCHANGER, DG COOLING DG VWTR ODG01P 0 DG COOLING WATER PUMP DG AB 09 G 674 0 DG STARTING AIR COMPRESSOR 0DG01S DG PACKAGE ODG01SA ASSY -TANK, DG AIR VESSEL DG ODG01SB ASSY -TANK, DG AIR VESSEL DG ODG029A 0 DG A STARTING AIR RECEIVER DG RELIEF VALVE 0 DG B STARTING AIR RECEIVER 0DG029B DG RELIEF VALVE ODG02F FILTER/SILENCER, DG AIR INTAKE DG ODG02JA 0 DG A GENERATOR CONTROL PANEL DG Table B-1 b Page 1 of 17 B-59 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Building Cuel 0DG02JB 0 DG B GENERATOR CONTROL PANEL DG ODG035A ASSY -VALVE, 0 DIG BANK A DG STARTER AIR SUPPLY ODG035B ASSY -VALVE, 0 D/G BANK B DG STARTER AIR SUPPLY 0 DG A/C STARTING AIR MOTORS PINION SUPPLY SOLENOID VALVE ODG036B 0 DG B/D STARTING AIR MOTORS PINION SUPPLY SOLENOID VALVE ODG03J 0 DG ENGINE CONTROL PANEL DG 0DG049 RELIEF CHECK VALVE DG 0DG04J PANEL, DG TRANSFORMER DG ODG050 0 DG LUBE OIL SOAK BACK PUMPS DC DSCH RELIEF CHECK VALVE ODG08M SS MESH .255AX 080 TYPE304, 301N DG 30OUT ODG08TA 0 DG A STARTING AIR RECEIVER DG ODG08TB 0 DG B STARTING AIR RECEIVER DG ODG09K FILTER, TSC DIESEL GENERATOR DG ENGINE OIL ODG10TA 0 DG A AUXILIARY AIR ACCUMULATOR DG 0DG10TB" 0 DG B AUXILIARY AIR ACCUMULATOR DG ODG12MA 0 DG A STARTING AIR STRAINER DG ODG12MB 0 DG B STARTING AIR STRAINER DG ODG20MA ASSY -TANK, DG AIR VESSEL DG 0DG20MB ASSY -TANK, DG AIR VESSEL DG 0DG23MA FILTER, AIR DG ODG23MB FILTER, AIR DG I ODG25M 0 DG LUBE OIL SOAK BACK PUMPS DC DSCH STRAINER 0 DG LUBE OIL CIRC PUMP DSCH 0DG26M DC STRAINER ODGT4 TRANSFORMER, ODG02J PHASE DG SHIFTING ODO001 P ASSY -PUMP, DG FUEL XFER DO ODO001T ASSY -TANK, 0 DG FUEL STORAGE DO 0D0004 0 DG FUEL OIL XFR PMP MU VLV DO 0DO01P 0 DG FUEL TRANSFER PUMP DO ODO01T 0 DG FUEL STORAGE TANK DO ODO02T 0 DG DAY TANK DO ODO03P PUMP, FP FUEL OIL XFER DO OD004M 0 DG FUEL TRANSFER PUMP SUCT DO STRNR Table B-lb Page 2 of 17 B-60 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code No Fleo D01DO1M 0 DG FUEL STORAGE TANK FILL DO STRNR OFI-VE027 AEER M/U SUPPLY AIR SY A VE OFI-VE067 AEER EMERG M/U SUPPLY AIR SYST B VE OPA09J ASSY -PANEL, AUX EQUIP ROOM A/C PA SYST A 0PA1OJ ASSY -PANEL, AUX EQUIP ROOM A/C PA SYST B OPDS-VC137HM INSTRUMENT PULSATION DAMPENER VC OPDS-VC137LM INSTRUMENT PULSATION DAMPENER VC OPDS-VC177HM INSTRUMENT PULSATION DAMPENER VC OPDS-VC177LM INSTRUMENT PULSATION DAMPENER VC OPDS-VE106HM INSTRUMENT PULSATION DAMPENER VE OPDS-VE106LM INSTRUMENT PULSATION DAMPENER VE OPDS-VE146HM INSTRUMENT PULSATION DAMPENER VE OPDS-VE146LM INSTRUMENT PULSATION DAMPENER VE OPI-DG055A 0 DG LUBE OIL FILTER PRESS DG OPI-DG055B 0 DG LUBE OIL FILTER PRESS DG OPI-DG056 0 DG MAIN LUBE OIL PRESS DG OPI-DG057A 0 DG FUEL OIL PRESS DG OPI-DG057B 0 DG FUEL OIL PRESS DG OPI-DG059 0 DG FUEL OIL PRESS DG 0PI-DG060A 0 DG FUEL OIL PRESS DG OPI-DG060B 0 DG FUEL OIL PRESS DG 0 DG ENGINE COOLING WATER 0PI-DG063 PESDG PRESS OPI-DG080 FUEL D/P DG OPI-DG081 FUEL D/P DG OPI-DG082 FUEL PRESS ENG PP DG 0PI-DG083 OIL D/P DG OPI-DG084 OIL D/P DG OPI-DG085 DG MAIN OIL PRESS DG OPI-DG086 0 DG SCAVENGING AIR PRESS DG 0PI-DG087 JACKET WTR PRESS DG OPI-DG094 0 DG A AIR RECEIVER DG 0PI-DG095 0 DG B AIR RECEIVER DG OPI-DG098A 0 DG A BANK STARTER AIR SUPPLY DG OPI-DG098B 0 DG B BANK STARTER AIR SUPPLY DG Table B-lb Page 3 of 17 B-61 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 System BuligClm oFloor Eq Component Tag Equipment Name Code Building Column No Elev OPI-DG121 0 DG SOAK BACK LUBE OIL DG 0PI-DG122 0 DG CRANKCASE PRESS DG 0PI-DG60A DG 0 FUEL OIL PRESS DG 0PI-DG60B DG 0 FUEL OIL PRESS DG 0PI-DG63 DG ENGINE COOLING WTR PRESS DG OPI-VC133 VC COMPRESSOR A LO SUCTION VC PRESS 0PI-VC134 VC COMPRESSOR A LO OIL PRESS VC OPI-VC135 VC COMPRESSOR A HI DISCH PRESS VC OPI-VC173 VC COMPRESSOR B LO SUCTION VC PRESS 0PI-VC174 VC COMPRESSOR B LO OIL PRESS VC 0PI-VC175 VC COMPRESSOR B HI DISCH PRESS VC 0PI-VE102 COMPRESSOR, OVE04CA LOW VE SUCTION PRESSURE COMPRESSOR, OVE04CA LOW OIL OPI-VE103 PRESSURE VE COMPRESSOR, 0VE04CA HI DISCH OPI-VE104 PRESSURE VE B AEER HVAC REFRIGERATION UNIT OPI___VE142

__ LOW SUCT PRESS INDICATOR

__B AEER HVAC REFRIGERATION UNIT LOW OIL PRESS INDICATOR OPI-VE144 B AEER HVAC REFRIGERATION UNIT VE HIGH DSCH PRESS INDICATOR 0PL100J ASSY -PANEL, 480V. POWER PANEL PL AT INTAKE STRUCTURE 0PL14J ASSY -PANEL, AUX BLDG/LAB HVAC PL 0PL14JA CONTROL PANEL PL AB 17 N 815 0PL14JB CONTROL PANEL PL AB 17 N 815 0PL15J ASSY -PANEL, CR HVAC SYST A PL OPL16J ASSY -PANEL, CR HVAC SYST B PL OPL17J ASSY -PANEL, DG VENT FAN PL 0PL42J ASSY -PANEL, AEER HVAC SYST A PL 0PL43J ASSY -PANEL, AEER HVAC SYST B PL 0PLB2J MONITOR, AIR, R/W VENT CONSTANT PL TB 710 0PLB5J ASSY -PANEL, RBCCW SYST PL RB 9:00 AM 786 0PLB9JA ASSY -PNL, VCNENG FLTR TRAIN A PL POWER SUPPLY 0PLB9JB ASSY -PANEL, VCNENG FLTR TRAIN PL___________

B POWER SUPPL PL OPLC9J ASSY_-_PANEL, HRSS VLV CONTROL PL AB 17 L 694 Table B-lb Page 4 of 17 B-62 12Qo108.50-R-No 1 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding iColumn No Ee Eq Component Tag Equipment Name Code Fleo OPLD1J ASSY -PANEL, SBGT VENT SAMPLE PL CONDITIONER OPLD2J ASSY -PANEL, SBGT WIDE RANGE PL GAS MONITOR OPLD3J ASSY -PANEL, SBGT VENT GAS PL MONTITOR MICROPRO OPLE6J ASSY -PANEL, STACK WRGM SYST PL LOCAL CONTROL OPLE7J ASSY- PANEL PL OPLF3J GENERAL ENGINEERING CORP. PL OPLF4J GENERAL ENGINEERING CORP. PL OPLF5J GENERAL ENGINEERING CORP. PL OPLF6J GENERAL ENGINEERING CORP. PL OPLF9J SH LOOP GLYCOL PUMP CONTROL PL PANEL OPLHP-1 PANEL, IRSF HTR CONT PL OPM11J ASSY_-_PANEL,-SWITCHYARD PM AB 15 L 768 CONTROL CONSOLE OPM14J ASSY -PANEL, RAD MONITORING PM AB 768 OPM15J ASSY -PANEL, RAD MONITORING PM AB 768 OPS-VC136M INSTRUMENT PULSATION DAMPENER VC OPS-VC138M INSTRUMENT PULSATION DAMPENER VC OPS-VC139M INSTRUMENT PULSATION DAMPENER VC OPS-VC176M INSTRUMENT PULSATION DAMPENER VC OPS-VC178M INSTRUMENT PULSATION DAMPENER VC OPS-VC179M INSTRUMENT PULSATION DAMPENER VC OPS-VE105M INSTRUMENT PULSATION DAMPENER VE OPS-VE107M INSTRUMENT PULSATION DAMPENER VE OPS-VE108M INSTRUMENT PULSATION DAMPENER VE OPS-VE145M INSTRUMENT PULSATION DAMPENER VE OPS-VE147M INSTRUMENT PULSATION DAMPENER VE OPS-VE148M INSTRUMENT PULSATION DAMPENER VE REFRIGERANT LIQUID LINE SOLENOID___________

IVALVE FOR OVC02AA __Table B-1 b Page 5 of 17 B-63 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 System Floor Eq Component Tag Equipment Name Code Building Column No Elev ORGO15B REFRIGERANT LIQUID LINE SOLENOID RG VALVE FOR OVC02AA ORGO16A VALVE, RG ORGO16B VALVE, RG ORGO34A VALVE,REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VC ORGO34B VALVE,REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VC I ORGO53A REFRIGERANT LIQUID LINE SOLENOID RG VALVE FOR OVE01AA REFRIGERANT LIQUID LINE SOLENOID VALVE FOR OVE01AA ORGO72A VALVE, REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VE ORGO72B VALVE, REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VE 0RG183 VALVE, RG'A' VE REFRIGERANT SUPPLY TO OIL RCOOLER SOLENOID VALVE ORGi 95B 'B' VE REFRIGERANT SUPPLY TO OIL RG COOLER SOLENOID VALVE'A' VC REFRIGERANT SUPPLY TO OIL ORG199A COOLER SOLENOID ISOLATION RG VALVE'B' VC REFRIGERANT SUPPLY TO OIL ORG199B COOLER SOLENOID ISOLATION RG VALVE OSI-DG028A DG 0 FREQUENCY METER DG 0SI-DG028B DG 0 FREQUENCY METER DG 0SI-DG067 0 DG FREQUENCY METER DG OTE-VC002 CONT RM HVAC ZONE MIX DMPR 16YA VC TEMP OTE-VC003 CONT RM HVAC ZONE MIX DMPR 19YA VC TEMP CONT RM HVAC ZONE MIX DMPR 22YA 0TE-VC004 VC TEMP OTE-VC005 CONT RM HVAC ZONE MIX DMPR 25YA VC TEMP OTE-VC006 CONT RM HVAC ZONE MIX DMPR 28YA VC TEMP CONT RM HVAC ZONE MIX DMPR 16YB 0TE-VC042 VC REHTR CONT CONT RM HVAC ZONE MIX DMPR 19YB OTE-VC043 VTEMP _C CONT RM HVAC ZONE MIX DMPR 22YB OTE-VC044 ITEMP ELEMENT __Table B-l b Page 6 of 17 B-64 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code No Fleo OTE-VC045 CONT RM HVAC ZONE MIX DMPR 25YB VC TEMP ELEMENT OTE-VC046 CONT RM HVAC ZONE MIX DMPR 28YB VC TEMP ELEMENT OTE-VC105 TRAIN OVC015A INLET TEMP VC OTE-VC106 TRAIN OVC01SA OUT TEMP VC OTE-VC145 TRAIN OVC01SB INLET TEMP VC OTE-VC146 TRAIN 0VC01SB OUTLET TEMP VC OTE-VD003 ODG01K ROOM TEMP CONT MOD MTR VD OTE-VE002 AEER A/C MIX DMPR REHTR CONT VE OTE-VE003 AUX EQUIP RM MIX DAMPER REHEAT VE CONTROL TEMP ELEMENT (UNIT 1)OTE-VE004 AUX EQUIP RM MIX DAMPER REHEAT VE CONTROL TEMP ELEMENT (UNIT 1)AEER A/C MIX DMPR REHTR CONT OTE-VE033 TEMP VE OTE-VE042 AEER A/C RT DET DMPR VE OTE-VE043 AUX EQUIP RM A/C SYS MIX DAMPER VE REHEAT CONTROL TEMP ELEMENT OTE-VE044 B AUX ELEC EQUIP RM MIX DMPR VE REHEAT CONTROL TEMP ELEMENT OTE-VE917 COMPUTER RM TEMP SENSOR VE OTE-VE918 COMPUTER RM TEMP SENSOR VE OTI-DG005A DG ODG01 K ROOM AREA AIR TEMP DG OTI-DG054 0 DG MAIN LUBE OIL TEMP DG OTI-DG058 0 DG FUEL OIL TEMP DG OTI-DG061 DG ENGINE RAW COOLING WTR DG TEMP OTI-DG062 0 DG ENGINE JACKET WATER TEMP DG_0TI-DG064A 0 DG ENGINE COOLING WATER DG OUTLET TEMP DG OTI-DG092 DG CYLINDER WALL TEMP DG 0TI-DG100 DG ODG01K COOLING WTR TEMP DG OTI-DG101 DG ODG01K JACKET WTR TEMP IN DG DG ENGINE RAW COOLING WTR 0TI-DG61 DG TEMP OTI-DG64A DG ENGINE COOLING WTR OUT TEMP DG OTI-DG64B DG ENGINE COOLING WTR IN TEMP DG DG ENGINE COOLING WTR TO OIL OTI-DG64C CORDG COOLR___ __ _ __ _ _OTI-VC103 HEATER IN TEMP TRAIN OVC01SA VC OTI-VC104 HEATER OUT TEMP TRAIN OVC01SA VC OTI-VC105 FLTR TRAIN A IN TEMP VC Table B-1 b Page 7 of 17 B-65 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No FElev GTI-VC106 FLTR TRAIN A OUT TEMP VC GTI-VC143 HEATER IN TEMP TRAIN OVC01SB VC OTI-VC144 HEATER OUT TEMP TRAIN OVC01SB VC OTI-VC145 FLTR TRAIN OVC01SB IN TEMP VC GTI-VC146 FLTR TRAIN OVC01SR OUT TEMP VC OTI-VE002 AEER A/C SY MIX DMPR REHTR VE OTI-VE003 AEER A/C SY MIX DMPR REHTR VE OTI-VE004 AEER A/C SY MIX DMPR REHTR VE OTI-VE042 AEER A/C MIX DMPR REHTR CONT VE GTI-VE043 AEER A/C ZONE MIX DMPR REHTR VE CON OTI-VE044 AEER A/C ZONE MIX DMPR REHTR VE CON OTI-VE081 AEER A/C SYST MIX AIR TEMP/IND VE GTI-VE082 AEER A/C SYST MIX AIR TEMP/IND VE OVC005CA ASSY- POWER PNL VC OVC01CA ASSY -FAN, CR HVAC SUPPLY OA VC AB 13 N 786 OVC01CB ASSY -FAN, CR HVAC SUPPLY GB VC OVC01FA FILTER, UNIT CR HVAC SUPPLY AIR VC OVC01FB FILT UNIT CONT ROOM HVAC SPLY VC AB 16 N 786 AIR OVC01SA FILT UNIT CONT RM HVAC EMER MU VC AIR FILT UNIT CONT RM HVAC EMER MU OVC01SB VC_____ ____ ____ AIR_ _ __ _ _ _ _ _0VC01YA DAMPER, CR A/C SYST A TORNADO VC DMPR OVC01YB DAMPER, CR A/C SYST B TORNADO VC DMPR OVC02CA ASSY -FAN, CR HVAC RETURN GA VC OVC02CB ASSY -FAN, CR HVAC RETURN GB VC OVC02SA GENERATOR, STEAM CR HVAC VC ELECTRIC OVC02SB GENERATOR, STEAM CR HVAC VC ELECTRIC OVC02YA A EMER MU TRAIN INLT VC OVC02YB B EMER MU TRAIN INLT VC OVC033A SOLENOID VALVE VC OVC033B SOLENOID VALVE VC OVC03CA ASSY -FAN, CR HVAC EMERG M/U AIR VC AB R 18 802 OA OVC03CB ASSY -FAN, CR HVAC EMERG M/U AIR VC 0B OVC03YA A EMER MU TRAIN OTLT VC OVC03YB B EMER MU TRAIN OTLT VC OVC04CA ASSY -FAN, CR HVAC AIR COOLED VC CONDENSER GA Table B-lb Page 8 of 17 B-66 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163.SystemFlo Eq Component Tag Equipment Name Code Building Column No FIoorev OVC04CB ASSY -FAN, CR HVAC AIR COOLED VC CONDENSER OB OVC04YA A CONTROL ROOM HVAC BALANCING VC DAMPER B CONTROL ROOM HVAC BALANCING 0VC04YB VC DAMPER OVC05CA PANEL, INSTR CONTROL HVAC VC REFRIGERATION 0VC05CB PANEL, INSTR CONTROL HVAC VC REFRIGERATION

__OVC05TA RECEIVER R-22 LIQUID VC AB 13 N 786 OVC05TB RECIEVER R-22 LIQUID VC AB 16 N 786 OVC05YA DAMPER, MINIMUM OUTSIDE AIR VC UPSTREAM B VC/VE MINIMUM OUTSIDE AIR UPSTREAM ISOLATION DAMPER OVC06A A' VC OIL COOLER VC OVC06B B' VC OIL COOLER VC OVC06C CONTROL ROOM TOILET EXHAUST VC FAN OVC06YA A CONTROL ROOM HVAC OUTSIDE VC AIR BALANCING DAMPER B CONTROL ROOM HVAC OUTSIDE AIR BALANCING DAMPER OVC07YA A CONTROL ROOM HVAC AEER VC BALANCING DAMPER OVC07YB B CONTROL ROOM HVAC AEER VC BALANCING DAMPER A CONTROL ROOM HVAC PURGE AIR DWNST ISOL DAMPER OVC08YB B CONTROL ROOM HVAC PURGE AIR VC DWNST ISOL DAMPER OVC093AA VLV 2 IN SOL GLOBE VC OVC093AB VLV 2 IN SOL GLOBE VC OVC09YA A CONTROL ROOM HVAC BALANCING VC DAMPER OVC09YB B CONTROL ROOM HVAC BALANCING VC DAMPER 0' A CONTROL ROOM HVAC ISOL 0VC 10YA VC DAMPER OVC10YB B CONTROL ROOM HVAC ISOL VC DAMPER OVC11YA A CHARCOAL FILT INLT VC OVCl1YB B CHARCOAL FILT INLT VC OVC12YA A CHARCOAL FILT OTLT VC OVC12YB B CHARCOAL FILT OTLT VC OVC13YA A CHARCOAL FILT BYP VC Table B-lb Page 9 of 17 B-67 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 System Floor CoeBuilding Column NoFlo Eq Component Tag Equipment Name Code Elev OVC13YB B CHARCOAL FILT BYP VC A CONTROL'ROOM HVAC RETURN FAN DSCH DAMPER __OVC14YB B CONTROL ROOM HVAC RETURN VC FAN DSCH DAMPER A CONTROL ROOM HVAC RETURN 0VC 1 5YA VC FAN SUCT DAMPER VC B CONTROL ROOM HVAC RETURN 0VC 15Y B VC FAN SUCT DAMPER OVC16YA DAMPER, CR A/C SYST A MIX VCO OVC16YB DAMPER, CR A/C SYST B MIX VC A CONTROL ROOM ZONE HEATING COIL OVC04AA OUTLET DAMPER __B CONTROL ROOM ZONE HEATING OVCIY COIL OVC04AB OUTLET DAMPER VC OVC18YA DAMPER, CR A/C SYST VC OVC18YB DAMPER, CR A/C SYST VC OVC19YA DAMPER, CR A/C MIX A VC OVC19YB DAMPER, CR A/C MIX B VC A CONTROL ROOM ZONE HEATING V 0VC20YA_____COIL OVC05AA OUTLET DAMPER VC OVC20YB B CONTROL ROOM ZONE HEATING VC COIL OVC05AB OUTLET DAMPER VC OVC21YA DAMPER, CR A/C MIX VC OVC21YB DAMPER, CONTROL ROOM STOP VC OVC22YA DAMPER, CR HVAC ZONE MIX VC OVC22YB DAMPER, CR A/C ZONE MIX VC A CR SECURITY CENTER ZONE OVC23YA HEATING COIL OVC06AA OUTLET VC DAMPER B CR SECURITY CENTER ZONE OVC23YB HEATING COIL OVC06AB OUTLET VC DAMPER OVC24YA DAMPER, CR A/C SYST VC B CR SECURITY CENTER ZONE OVC24YB HEATING COIL OVC06AB INLET, VC DAMPER OVC25YA DAMPER, CR HVAC ZONE MIX VC OVC25YB DAMPER, CR A/C SYST ZONE MIX VC A CABLE SPREADING ROOM ZONE OVC26YA HEATING COIL OVC07AA OUTLET VC DAMPER B CABLE SPREADING ROOM ZONE OVC26YB HEATING COIL OVC07AB OUTLET VC DAMPER OVC27YA DAMPER, CR A/C SYST VC OVC27YB DAMPER, CR A/C SYST VC Table'B-lb Page 10 of 17 B-68 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Eq Component Tag Equipment Name System Floor CodeBuilding Column NoElev EVC28YA DAMPER, CR A/C SYST ZONE MIX VC OVC28YB DAMPER, CR A/C SYST ZONE MIX VC A CR SECURITY CENTER ZONE OVC29YA HEATING COIL OVC08AA OUTLET VC DAMPER B CR SECURITY CENTER ZONE OVC29YB HEATING COIL OVC08AB OUTLET VC DAMPER OVC30YA DAMPER, CR A/C SYST VC OVC30YB DAMPER, CR A/C SYST VC UNIT 1 CONTROL ROOM HVAC RETURN BALANCING DAMPER UNIT 2 CONTROL ROOM HVAC 0VC32Y RETURN BALANCING DAMPER VC CR MAIN SECURITY CONTROL OVC34Y CENTER HVAC RETURN BALANCING VC DAMPER OVC35Y CONTROL ROOM EAST AREA HVAC VC RETURN BALANCING DAMPER CR MAIN SECURITY CONTROL OVC36Y CENTER HVAC RETURN BALANCING VC DAMPER OVC43Y A CONTROL ROOM HVAC AIR COOLED VC CONDENSER DSCH CHECK DAMPER OVC45Y B CONTROL ROOM HVAC AIR COOLED VC CONDENSER DSCH CHECK DAMPER OVC46Y CR MAIN SECURITY CONTROL CENTER HVAC RETURN FIRE DAMPER OVC47Y CR MAIN SECURITY CONTROL CENTER HVAC SUPPLY FIRE DAMPER OVC48Y DAMPER, CONTROL ROOM HVAC VC OVC49Y CR MAIN SECURITY CONTROL CENTER HVAC RETURN FIRE DAMPER OVC50Y CR MAIN SECURITY CONTROL CENTER HVAC RETURN FIRE DAMPER OVC51Y CR MAIN SECURITY CONTROL CENTER HVAC SUPPLY FIRE DAMPER OVC52YA DAMPER, MIN OUTSIDE AIR VC_ISOLATION I I I _ I Table B-1 b Page 11 of 17 B-69 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code No Eleo OVC52YB B VCNE MINIMUM OUTSIDE AIR DOWNSTREAM ISOLATION DAMPER OVC53YA A CONTROL ROOM HVAC MAXIMUM VC OUTSIDE AIR ISOL DAMPER OVC53YB B CONTROL ROOM HVAC MAXIMUM VC OUTSIDE AIR ISOL DAMPER OVC54YA A CONTROL ROOM HVAC MINIMUM VC OUTSIDE AIR BALANCING DAMPER ______VC54YB CONTROL ROOM HVAC MINIMUM VC OUTSIDE AIR BALANCING DAMPER A CONTROL ROOM HVAC MINIMUM OUTSIDE AIR BALANCING DAMPER B CONTROL ROOM HVAC MINIMUM OUTSIDE AIR BALANCING DAMPER OVC60Y DAMPER, CONTROL ROOM HVAC VC OVC61Y DAMPER, CONTROL ROOM HVAC ISOL VC FIRE VC SUPPLY TO EAST AREA OF OVC62Y CONTROL ROOM FIRE DAMPER VC OVC63Y VC RETURN FROM EAST AREA OF VC CONTROL ROOM FIRE DAMPER OVC64Y DAMPER, CONTROL ROOM HVAC VC OVC65Y DAMPER, CONTROL ROOM HVAC VC OVC66Y DAMPER, CONTROL ROOM HVAC VC OVC67Y DAMPER, CONTROL ROOM HVAC VC OVC68Y DAMPER, CONTROL ROOM HVAC VC OVC69Y DAMPER, CONTROL ROOM HVAC VC OVC70YA DAMPER, CONTROL ROOM HVAC VC B CONTROL ROOM HVAC GRAVITY 0VC70YB VC DAMPER OVC71YA A VC RETURN FAN SUCTION VC MAINTENANCE DAMPER OVC71YB B VC RETURN FAN SUCTION VC MAINTENANCE DAMPER OVC72YA BALANCING DAMPER, MANUAL, VC HORIZ, OPPOSED BLADE OVC72YB BALANCING DAMPER, MANUAL, VC HORIZ, OPPOSED BLADE OVC73YA DAMPER VC OVC73YB DAMPER VC OVD01C ASSY -FAN, DG ROOM VENT VD OVD01F DIESEL GEN ROOM VENT SPLY VD OVD01J TIME DELAY PANEL VD AB 674 OVD01YA DAMPER DG RM VENT VD 0VD01YAB DAMPER, DG ROOM VENT MODUL VD_OPPOSED OVD01YB DAMPER DG RM VENT VD I Table B-1 b Page 12 of 17 B-70 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No FElev OVD02C ASSY -FAN, 0 DG FUEL STOR TANK VD ROOM VENT OVD02YA DAMPER DG RM VENT VD OVD02YAB DAMPER, DG ROOM VENT VD OVD02YB DAMPER DG RM VENT VD OVD03YA DAMPER DG RM VENT VD OVD03YAB DAMPER, DG ROOM VENT VD OVD03YB DAMPER DG RM VENT VD OVD04Y DAMPER, DG ROOM VENT VD OVD05Y DAMPER, DG ROOM VENT VD OVD06Y DAMPER, DG ROOM VENT VD OVD07Y DAMPER, DG ROOM VENT. VD OVD08Y DAMPER, DG ROOM VENT VD OVD28Y DAMPER, DG ROOM VENT VD OVD40Y DAMPER, DG ROOM VENT VD OVD41Y DAMPER, DG ROOM VENT VD BOILER AUX ELECTRIC ROOM 0VE015B VE COOLING STM OVE01AA COIL AUX ELEC EQUIP RM HVAC SPLY VE D-X OVE01AB COIL AUX ELEC EQUIP ROOM HVAC VE OVE01CA ASSY_-_AUX EQUIPMENT ROOM VE AB 786 HVAC SUPPLY FAN OVE01CA I OVE01CB ASSY -FAN, HVAC SUPPLY VE 0VE01FA FILT UNIT AUX ELEC EQUIP RM HVAC VE SPLY AIR __OVEOIFB FILT UNIT AUX ELEC EQUIP RM HVAC VE SPLY AIR GEN AUX EL EQUIP RM HVAC ELEC 0VE01ISA SMVE STM OVE01SB GEN AUX EL EQUIP RM HVAC ELEC VE STM OVE01TA ASSY -VESSEL, REFRIGERANT VE RECEIVER 0VE01TB ASSY -VESSEL, REFRIGERANT VE RECEIVER OVE01YA A AEER HVAC SUPPLY BALANCING VE DAMPER OVEOIYB B AEER HVAC SUPPLY BALANCING VE DAMPER OVE02AA CNDSR COIL AUX EL EQUIP RM AIR VE COOLED OVE02AB CNDSR COIL AUX EL EQUIP RM AIR VE_COOLED OVE02CA ASSY -FAN, HVAC RETURN AIR VE OVE02CB ASSY -FAN, HVAC RETURN AIR O/B VE Table B-1 b Page 13 of 17 B-71 12QO108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Building Cuel A AEER HVAC SUPPLY BALANCING 0VE02YA DAPRVE DAMPER OVE02YB B AEER HVAC SUPPLY BALANCING VE DAMPER OVE03CA AUX ELEC EQUIP RM AIR COOLED VE CONDENSER FAN GA OVE03CB B AEER HVAC AIR COOLED CNDSR VE FAN A AEER HVAC MANUAL PURGE AIR OVE03YA ___ CONTROL DAMPER _ _OVE03YB B AEER HVAC MANUAL PURGE AIR VE CONTROL DAMPER OVE04CA REFRG COMP AUX EL EQUIP RM SPLY VE SYS OVE04CB B AEER HVAC REFRIGERATION UNIT VE OVE04TA RECEIVER R-22 LIQUID VE AB 13 N 802 OVE04TB RECEIVER R-22 LIQUID VE AB 16 N 802 A AEER HVAC MANUAL PURGE AIR OVE04YA CONTROL DAMPER VE OVE04YB B AEER HVAC MANUAL PURGE AIR VE CONTROL DAMPER OVE05YA A AEER HVAC MAXIMUM OUTSIDE AIR VE ISOLATION DAMPER B AEER HVAC MAXIMUM OUTSIDE AIR ISOLATION DAMPER OVE06A A' VE OIL COOLER VE OVE06B B' VE OIL COOLER VE OVE06YA A AEER HVAC RETURN AIR ISOLATION VE DAMPER B AEER HVAC RETURN AIR ISOLATION 0VE06YB VE DAMPER OVE07YA DAMPER, HVAC SYST 0V301 FA VE OVE07YB DAMPER, HVAC SYST OVE01 FB VE OVE08YA DAMPER, HVAC SYST FILTER BYPASS VE OVE08YB DAMPER, HVAC SYST FILTER BYPASS VE OVE09YA DAMPER, HVAC SYST OVE01 FA VE OVE09YB DAMPER, HVAC SYST OVE01 FB VE OVE10YA DAMPER, A/C SYST ZONE MIXING VE 0VE10YB DAMPER, A/C SYST ZONE MIXING VE OVE11YA DAMPER, A/C SYST ZONE MIXING VE OVE11YB DAMPER, A/C SYST ZONE MIXING VE OVE12YA DAMPER, A/C SYST ZONE MIXING VE OVE12YB DAMPER, A/C SYST ZONE MIXING VE OVE13YA A AEER HVAC SUPPLY AIR VE BALANCING DAMPER Table B-lb Page 14 of 17 B-72 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 System Floor Eq Component Tag Equipment Name Code Building Column No Elev OVE13YB B AEER HVAC SUPPLY AIR VE BALANCING DAMPER OVE14YA A AEER HVAC SUPPLY AIR VE BALANCING DAMPER OVE14YB B AEER HVAC SUPPLY AIR VE BALANCING DAMPER OVE15YA A AEER HVAC SUPPLY AIR VE BALANCING DAMPER OVE15YB DAMPER, AEER ROOM HVAC VE AUX EQUIP ROOM HVAC SPLY TO COMPUTER ROOM -20' ABOVE FLR AUX EQUIP ROOM HVAC SPLY TO COMPUTER ROOM -20' ABOVE FLR OVE17YA DAMPER, HVAC ISOLATION VE OVE17YB DAMPER, HVAC ISOLATION VE OVE18YA DAMPER, HVAC ISOLATION VE OVE18YB DAMPER, HVAC ISOLATION VE A AEER HVAC COMPUTER ROOM RETURN BALANCING DAMPER OVE22Y AEER HVAC PROCESS COMPUTER VE ROOM SUPPLY AIR FIRE DAMPER OVE23Y DAMPER, AEER ROOM HVAC VE OVE24Y DAMPER, AEER ROOM HVAC VE OVE25Y AEER HVAC PROCESS COMPUTER VE ROOM RETURN AIR FIRE DAMPER A AEER HVAC AIR COOLED OVE27Y CONDENSER FAN DISCHARGE VE DAMPER B AEER HVAC AIR COOLED 0VE29Y CONDENSER FAN DISCHARGE VE DAMPER OVE30YA A AEER HVAC MAXIMUM OUTSIDE AIR VE ISOLATION DAMPER OVE30YB B AEER HVAC MAXIMUM OUTSIDE AIR VE ISOLATION DAMPER OVE31Y DAMPER, AEER ROOM HVAC VE OVE32Y DAMPER, AEER ROOM HVAC VE OVE33Y AEER HVAC UNIT 1 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 1 AIR RETURN FIRE 0VE34Y VE DAMPER OVE35Y AEER HVAC UNIT I AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 1 AIR RETURN FIRE I0OVE36Y VDAMPER I _E Table B-1 b Page 15 of 17 B-73 12Q0108.50-R-001 Rev. I Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No Floor Code Elev AEER HVAC UNIT 1 AIR SUPPLY FIRE 0VE37Y VE DAMPER 0VE38Y AEER HVAC UNIT 1 AIR SUPPLY FIRE VE OVE38Y ____ DAMPER __OVE39Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 2 AIR RETURN FIRE OVE40Y VE___ ___ ___ ___DAMPER_

_ _ _ _ __ _ _ _ _OVE41IY AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER OVE42Y AEER HVAC UNIT 2 AIR RETURN FIRE VE DAMPER OVE43Y DAMPER, AEER ROOM HVAC VE OVE44Y DAMPER, AEER ROOM HVAC VE OVE45Y AEER HVAC UNIT 2 AIR RETURN FIRE VE DAMPER OVE46Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER OVE47Y DAMPER, AEER ROOM HVAC VE OVE48Y DAMPER, AEER ROOM HVAC VE OVE49Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 2 AIR SUPPLY FIRE.0VE50Y VE DAMPER OVE51 Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER OVE52Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 2 AIR RETURN FIRE 0VE53Y VE DAMPER OVE60Y AEER HVAC PROCESS COMPUTER VE ROOM SUPPLY AIR FIRE DAMPER OVE61Y DAMPER, OPPOSED BLADE, HORIZ VE SHAFT VE A AEER HVAC RETURN AIR ISOL MAINTENANCE DAMPER OVE66YB B AEER HVAC RETURN AIR ISOL VE MAINTENANCE DAMPER A AEER HVAC COOLER CNDSR FAN RECIRC DAMPER __B AEER HVAC COOLER CNDSR FAN RECIRC DAMPER OVE68Y FIRE DAMPER VE OVE69Y FIRE DAMPER VE OVE70Y FIRE DAMPER VE OVE71Y FIRE DAMPER VE OVE72Y FIRE DAMPER VE Table B-1 b Page 16 of 17 B-74 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Column No Fleo OVE73Y FIRE DAMPER VE OVE74Y FIRE DAMPER VE OVE75Y FIRE DAMPER VE OVE76Y FIRE DAMPER VE OVE77Y FIRE DAMPER VE OVE78Y UNIT I AEER HVAC SUPPLY VE BALANCING DAMPER OVE79Y UNIT 2 AEER HVAC EXHAUST VE BALANCING DAMPER OVE80YA DAMPER VE OVE8OYB DAMPER VE Table B-1 b Page 17 of 17 B-75 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Table B-2. Base List 2 Room Column Floor Eq Component Tag Equipment Name System Code Building Number No Elev 1FC01TA FUEL POOL SKIMMER SURGE FC RB 13 D 820 TNK 1A 1FC01TB FUEL POOL SKIMMER SURGE FC RB 13 F 820 TNK 1B FUEL POOL COOLING DSCH 1FC130 SKIMMER-TANK RETURN FC VALVE FUEL POOL RHR SUCT 1FC132 SUPPLY HI POINT VENT FC VALVE FUEL POOL RHR SUCT 1FC133 SUPPLY HEADER DRAIN FC VALVE 1FC138 FUEL POOL SKIMMER SURGE FC TANKS OUTLET VALVE 1 FCI 39A A FUEL POOL COOLING PUMP FC SUCT VALVE 1FC139B B FUEL POOL COOLING PUMP FC SUCT VALVE 1FC140 FUEL POOL RHR SUCT FC SUPPLY VALVE DRYER SEPARATOR/RX WELL 1FC141 DRN FUEL POOL CLG PMP FC SUCT HDR RTN CK VLV 1FC143 FUEL POOL STORAGE INLET FC RHR RETURN DRAIN VALVE FUEL POOL STORAGE INLET RHR RETURN VALVE FUEL POOL SKIMMER SURGE 1FC147 TANK LEVEL INST ROOT FC VALVE ___FUEL POOL STORAGE INLET 1FC155 RHR RETURN HI POINT VENT FC_VALVE I I. I I B-76

".OUKIrI" I lIUJlN iU I LUI 'KU I rILt:V/- I IUIN (Column)T T I -lIVI Licensing z aiety runction Replace?Basis? I I I R HVAC SUPPLY OA (10) Air Handlers AB 786 13 N VC Y Auxiliary

& Support 42X (03) Medium Voltage AB 731 10 N AP Y Auxiliary

& Support Switchgear AB7110NA Y Auxiliary&_Suppor R, 136X (04) Transformers AB 731 10 L AP Y Electrical Systems 3 (02) Low Voltage Switchgear RB 786 13 C AP Y Auxiliary

& Support and Breaker Panels AP Y Auxiliary_&_Support 3R 135X (02) Low Voltage Switchgear AB 710 10 L AP Y Auxiliary

& Support and Breaker Panels LAP Y Auxiliary_&_Support R, 135X (04) Transformers AB 710 10L AP Y Electrical Systems GR 136X (02) Low Voltage Switchgear AB 731 10 L AP Y Auxiliary

& Support and Breaker Panels ;B7110LA Y Auxiliary_&_Support

135X-1 (01) Motor Control Centers RB 761 14- A AP Y Auxiliary

& Support; 135X-3 (01) Motor Control Centers AB 710 11 L AP Y Auxiliary

& Support C 136X-1 (01) Motor Control Centers RB 820 12 C AP Y Auxiliary

& Support C 136X-3 (01) Motor Control Centers AB 731 10 L AP Y Auxiliary

& Support 3C ACCUMULATOR (21) Tanks and Heat DW 778 -B21 Y RCPC Exchangers I LINE SAFETY RELIEF (07) Pneumatic-Operated DW 783 B21 Y RCPC Valves 3OLENOID VALVE 'A' (08) Motor-Operated and Solenoid-Operated Valves)L (07) Pneumatic-Operated DW 735 12 J B21 Y RCPC Valves STEAM ISOLATION (07) Pneumatic-Operated RB 735 12 J B21 Y RCPC Valves IOID, O/B MSIV (08) Motor-Operated and Solenoid-Operated Valves I OTBD DRAIN LINE (08) Motor-Operated and RB 735 12 K B21 Y RCPC Solenoid-Operated Valves T CRD HYDRAULIC 26- (00) Other RB 761 G-F 9 SOUTH Cll Y RRC T CRD HYDRAULIC 30- (00) Other RB 761 C-D 9 SOUTH Cll Y RRC T CRD HYDRAULIC 42- (00) Other RB 761 G-F 14.5 Cll Y RRC NORTH T CRD HYDRAULIC 34- (00) Other RB 761 C-D 14.5 Cll Y RRC I_ NORTH AM WATER (21) Tanks and Heat RB 761 G-F 9 SOUTH C11 Y RRC R Exchangers AM INLET VALVE (07) Pne u m atic-Ope rated 00-70-f'-, C n oni I-ru4 V 00r%

MIVI VVM I Cm R Exh a) 1 dingrs dllU"I Exchangers RB 761 C-D 9 SOUTH C11 Y RRC AM INLET VALVE (07) Pneumatic-Operated RB 761 0-09 SOUTH C11 Y RRC Valves AM OUTLET VALVE (07) Pneumatic-Operated RB 761 C-D 9 SOUTH C11 Y RRC Valves AM WATER (21) Tanks and Heat RB 761 C-D 14.5 C11 Y RRC R Exchangers NORTH AM INLET VALVE (07) Pneumatic-Operated NORTHC-D 14.5 Valves RB 761 NORTH C Y RRC AM OUTLET VALVE (07) Pneumatic-Operated RB 761 C-D 14.5 Cli Y RRC_Valves NORTH AM WATER (21) Tanks and Heat RB 761 0-014.5 Cli Y RRC R Exchangers NORTH AM INLET VALVE (07) Pneumatic-Operated RB 761 C-D 14.5 C11 Y RRC Valves NORTH _____R AM OUTLET VALVE (07) Pneumatic-Operated RB 761 C-D 14.5 Cli Y RRC Valves NORTH C11__RR JID CONTROL (21) Tanks and Heat RB 820 10 C 041 Y RRC 4JK Exchangers RB_820 10_CC41 YRRC:UID CONTROL PUMP (05) Horizontal Pumps RB 820 11 C 041 Y RRC ERY CHARGER NO. 1 (16) Battery Chargers & AB 710 9J DC Y Electrical Systems I nverters (01) Motor Control Centers AB 710 10 L DC Y Electrical Systems:-RY (15) Battery on Rack AB 710 9J DC Y Electrical Systems)ISTRIBUTION BUS 1 (14) Distribution Panels and Automatic Transfer Switches AB 710 10 L DC Y Electrical Systems IBUTION PANEL 112X (14) Distribution Panels and Automatic Transfer Switches AB 731 12 L DC Y Electrical Systems BATTERY (15) Battery Racks AB 731 L-N 12-13 DC Y Electrical Systems DISTRIBUTION BUS 1B (14) Distribution Panels and Automatic Transfer Switches AB 731 12 L DC Y Electrical Systems ERY CHARGER NO. 1 B (16) Battery Chargers & AB 731 L-N 11-12 DC Y Electrical Systems Inverters I I I I I I Ii IA r e rAI I/f%^% R A -I-% ... -A -A k/ 1L) 1IdI1tZ5 dI 1U rledL IExchangers DG 710 J 7-8 DG Y Auxiliary

& Support IG WATER STRAINER (00) Other DG 674 J 9 DG Y Auxiliary

& Support 14ERATOR (17) Engine Generators DG 710 J 7-8 DG Y Auxiliary

& Support IG WATER PUMP (05) Horizontal Pumps AB 674 J DG Y Auxiliary

& Support NG AIR COMPRESSOR (12) Air Compressors DG 710 L-J 7-8 DG Y Auxiliary

& Support RATOR CONTROL (20) Instrument and Control DG 710 L 8-9 DG Y Auxiliary

& Support Panels DG_710_L_8-9 DY ulr& pt OTOR COOLER (08) Motor-Operated and F AV oeodOeae avsRB 694 14B DG Y Auxiliary

& Support r VALVE Sole noid-Ope rated Valves CONTROL PANEL (20) Instrument and Control Panels DG 710 L 8-9 DG Y Auxiliary

& Support 1A DIG BANK A (07) Pneumatic-Operated DG 710 L-J 7-8 DG Y Auxiliary

& Support SUPPLY Valves DG 710 L-J_7-8 DGY Auiliar&Spp (21) Tanks and Heat DG 710 J-H 5-7 DO Y Auxiliary

& Support Exchangers OILTRANSFER (05) Horizontal Pumps DG 674 6 J DO Y Auxiliary

& Support XCHANGER (21) Tanks and Heat RB 710 A-B 9-10 E12 Y RCICIDHR Exchangers-IEAT REMOVAL PMP (06) Vertical Pumps RB 673 C E12 Y RCIC/DHR:E WATER PUMP (05) Horizontal Pumps DG 674 16B E12 Y RCIC/DHR:E WATER STRAINER (00) Other DG 674 J 9 E12 Y RCIC/DHR LET VALVE (08) Motor-Operated and_________

oeodOeae avsRB 694 A-B 9 E12 Y RCIC/DHR Solenoid-Operated Valves;UP POOL SUCT ISOL (08) Motor-Operated and RCIC/DHR Solenoid-Operated Valves AM CONDENSING SUP (08) Motor-Operated and ISOL VALVE Solenoid-Operated Valves:ULL FLOW TEST ISOL (08) Motor-Operated and Solenoid-Operated Valves AM CONDENSING RCIC (07) Pneumatic-Operated RB 694 -E12 Y RCIC/DHR RELIEF VALVE Valves ASS VALVE (08) Motor-Operated and Solenoid-Operated Valves R 6 T1%-r AlRA eki r--rI r-r% ee lidV-7% ~ .. L .~ .. ~

,- I r-MIVI IINJLa I=F VALVE VUa/v) I-IIUes dtU Valves RB 710 E12 Y RCIC/DHR VICE WATER OUTLET (08) Motor-Operated and Solenoid-Operated Valves VICE WATER OUTLET (08) Motor-Operated and SoeodOeae avsRB 673 13 A E12 Y RCIC/DHR Solenoid-Operated Valves VICE WATER DSCH (19) Temperature Senesors RB 694 B 10 E12 Y RCIC/DHR IT VICE WATER INLET (18) Instrument Racks RB 673 C 9 E12 Y RCIC/DHR (18) Instrument Racks RB 673 C 9 E12 Y RCIC/DHR LET TEMPERATURE (19) Temperature Senesors RB 694 A 10 E12 Y RCIC/DHR (06) Vertical Pumps RB 673 20 A E21 Y RCIC/DHR H FLOW XMITTER (18) Instrument Racks RB 673 14 A E21 Y RCIC/DHR CORE SPRAY (06) Vertical Pumps RB 673 F E22 Y RCIC ON ISOL VALVE (08) Motor-Operated and Solenoid-Operated Valves UP POOL SUCT ISOL (08) Motor-Operated and Solenoid-Operated Valves OW TEST ISOL VALVE (08) Motor-Operated and Solenoid-Operated Valves RB 694 10.D E22 Y RCIC SCH PRESS (18) Instrument Racks RB 673 9 F E22 Y RCIC SCH FLOW. (18) Instrument Racks' RB 673 9 G E22 Y RCIC (05) Horizontal Pumps RB 673 14 A E51 Y RCIC)N OTBD ISOL VALVE (08) Motor-Operated and Solenoid-Operated Valves RB 740 13 G E51 Y RCIC JP POOL SUCT ISOL (08) Motor-Operated and Solenoid-Operated Valves STEAM SUPPLY (08) Motor-Operated and" Solenoid-Operated Valves 3CH PRESS (18) Instrument Racks RB 673 14 C E51 Y RCIC EMERG CORE COOL (20) Instrument and Control MCR 768 -H13 Y Racks & Panels Panels RWCU/RX RECIRC (20) Instrument and Control Panels MCR 768 H13 Y Racks & Pane..-IG01A U-1 DW SUCT. (08) Motor-Operated and--_ _ _ Solenoid-Operated Valves-IG01A U-1 SUP POOL (08) Motor-Operated and RB m1 11 B HG Y CIF Cur_ I V Mm 1x~z~v~r'10)

II15IUMUIIl MdUIKS DG 710 J 7-8 DG Y Auxiliary

& Support ROOM VENTILATION (20) Instrument and Control Panels RB 694 PL Y Racks & Panels ZOOM VENTILATION (20) Instrument and Control RB 694 13 H PL Y Racks & Panels Panels DOM VENTILATION (20) Instrument and Control Panels RB 694 13 B PL Y Racks & Panels-COMBINER-BLWR INL (19) Temperature Senesors RB 786 B 10 HG Y CF GE FROM RX BLDG (07) Pneumatic-Operated RB 740 11 H VQ Y CF Valves GE INLET DWNST ISOL (07) Pneumatic-Operated RB 740 11 -H VQ Y CF Valves 4T/PURGE OTLT (07) Pneumatic-Operated RB 710 14 E VQ Y CF Valves qT/PURGE OTLT (08) Motor-Operated and BYP-20 FT.OVHD Solenoid-Operated Valves GE OTLT UPSTRM ISOL (07) Pneumatic-Operated RB 807 13 G VQ Y CF Valves GE OTLT UPSTRM ISOL (08) Motor-Operated and Solenoid-Operated Valves GE OTLT DWNST ISOL (07) Pneumatic-Operated RB 807 13 G, VQ Y CF Valves\IT/PURGE OUTLET (07) Pneumatic-Operated RB 710 14 E VQ Y CF'ALVE Valves iR DIV-2 VENT SUPPLY (09) Fans AB 731 10 L VX Y Auxiliary

& Support R DIV-2 BATT ROOM (09) Fans AB 731 10 L VX Y Auxiliary

& Support OOM COOLER VENT (10) Air Handlers RB 694 8.9 E VY Y Auxiliary

& Support RHR PUMP B/C ROOM (10) Air Handlers RB 694 09 D VY Y Auxiliary

& Support.PCS PUMP ROOM (10) Air Handlers RB 694 15 D VY Y Auxiliary

& Support HR WS PP A-i B CUBE (10) Air Handlers DG 736 7 H VY Y Auxiliary

& Support HR WS PP A-i B CUBE (10) Air Handlers DG 736 7 H VY Y Auxiliary

& SupportSUPPLY OTBD (08) Motor-Operated and RB 740 13 B WR Y Auxiliary

& Support Solenoid-Operated Valves 1.2Q.108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 Table B-4. SWEL 2 Seismic Associated ID DESCRIPTION CLASS SYSTEM BUILDING ELEVATION LOCATION Licensing with Rapid Comments__Basis? Draindown?

FUEL POOL RHR SUCT 1FC133 SUPPLY HEADER DRAIN (00) Other FC RB 673 Y N VALVE I I I I I FUEL POOL RHR SUCT 1FC140 FUEL VAL (00) Other FC RB 807 Y N__ _ _SUPPLY VALVE I__ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _B-82 12Q0108.50-R-001 Rev. 1 Correspondence No.: RS-12-163 C Seismic Walkdown Checklists (SWCs)Table C-1 provides a description of each item, anchorage verification confirmation, a list of Area Walk-By Checklists associated with each item, comments, and page numbers of each Seismic Walkdown Checklist.

C-1