ML12353A207

12Q0108.50-R-002, 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 2, Part 1 of 16

ML12353A207
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-002, Rev 1
Download: ML12353A207 (159)

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U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 27, 2012 Page 5 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 2 Report Number: 12Q0108.50-R-002, Revision 1 (911 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 2 2601 North 21st Road, Marseilles, Illinois, 61341-9757 Facility Operating License No. NPF-18 NRC Docket No. 50-374 Correspondence No.: RS-12-163

-- Exeton Exelon Generation Company, LLC (Exelon)

PO Box 805398 Chicago, IL 60680-5398 Prepared by:

Stevenson & Associates 1661 Feehanviflle Drive, Suite 150 Mount Prospect, IL 60056 Report Number 12Q0108.50-R-002, Rev. 1 Printe ame Preparer Marlene Delaney Reviewer Tony Perez Approver:

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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 2 Document Type: Report Report Number: 12Q0108.50-R-002 Project Name:

NTTF R2.3 Seismic Walkdowns for Exelon - LaSalle Job No.: 12Q0108.50 Client: A ExeLon 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

~Date:

10/31/2012 Reviewed by: Tony Perez

__Dat:_1/31201

,Approved by: Tony Perez Fz ate: 10/31/2012

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Contents List of Tables..............................................................................................

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

iv I

Introduction...................................................................................................................

1-1 1.1 P u rp o s e...................................................................................................................

1 -1 1.2 Background............................................................................

............ I.............1-1.

1.3 Plant Overview.

1-2 1.4 Approach.............................................................................

-..:................................ 1-2 1.5 Conclusion.............................................................................. 1-2 2

Seism ic Licensing Basis.........................................

2-1 2.1 Overview...........................................................

................... 21 2.2 SAFE SHUTDOWN EARTHQUAKE (SSE)...........................

2-1 2.3 DESIGN OF SEISM IC CATEGO RY I SSCS...........................................................

2-1 2.3.1 Sum mary of Seism ic Design......................................

................................. 2-1 2.3.2 Sum mary of Codes and Standards................................................................ 2-2 3

Personnel Qualifications..........................

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

3-1 3.2 Project Personnel....................................................................................................

3-1 3.2.1 Stevenson & Associates Personnel..........

3-2 3.2.2 Additional Personnel......................................................................................

3-4 4

Selection of SSCs...........................................................................................................

4-1 4.1 O v e rv ie w.................................................................................................................

4 -1 4.2 SW EL Development................................................................................................

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

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 Seism ic W alkdowns................................................................................................

5-1 5.2.1 Adverse Anchorage Conditions.....................................................................

5-2

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 5.2.2 Configuration Verification...............................................................................

5-2 5.2.3 Adverse Seismic Spatial Interactions............................................................

5-3 5.2.4 Other Adverse Seismic Conditions.............................

5-4 5.2.5 Conditions Identification during Seismic Walkdowns.....................................

5-4 5.3 A rea W a lk-B ys........................................................................................................

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

5-6 5.4 Supplemental Information on Electrical Cabinet Inspections..................................

5-6 6

Licensing Basis Evaluations.....................................................................................

6-1 7

IPEEE Vulnerabilities Resolution Report................................................................

7-1 8

Peer Review....................................................................................................................

8-1 9

References......................................................................................................................

9-1 Appendices A

Project Personnel Resumes and SWE Certificates...............................................

A-I 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............................

E-1 F

Peer Review Report...................................................................................................

F-I1 ii

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 List of Tables Table 2-1. List of Codes, Standards, and Specifications................................................. 2-3 T able 3-1. P erso nnel R oles....................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation......................................................

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

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

5-11 Table B-la. Base List Ia - Items Exclusive to Unit 2............................

B-3 Table B-lb. Base List lb - Items Common to Units I and2.........................................

B-57 Table B-2. Base List 2.................................................

B-74 T a ble B -3. S W E L 1.............................................................................................

B -75 T a ble B -4. S W E L 2..........................................................................

B -79 Table C-1. Summary of Seismic Walkdown Checklists................................................

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

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

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

E-3 iii

12Q0108.50-R-002 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 2 1st Century. The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 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 informationto 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 2 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

12Q.108.50-R-002 Rev. 1 Correspohdence No.: RS-12-163 Seismic Licensing 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-002 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 2, the SWEL is comprised of:

SWEL 1 resulted with 113 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 2 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-002 Rev. I 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 108 of the 115 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 43 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 2 ten (10) 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 Seismic Walkdown Checklists (SWCs), Area Walk-By Checklists (AWCs), and entered into the CAP. For vii

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 those conditions that required, seismic licensing basis evaluations were completed and documented within the IR. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.

IPEEE Vulnerabilities IPEEE vulnerabilities are addressed in Section 7 of this report. No vulnerabilities were identified as a result of the effort that addressed the Individual Plant Examination of External Events (IPEEE). (Ref. 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 2 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 ten (10) 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

12QO108.50-R-002 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-002 Rev. I 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 1st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 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 2 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) 1-1

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 1.3 PLANT OVERVIEW The LaSalle County Station consists of two operating boiling water reactor (BWR) generating units. Thesite 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)

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 bySargent & 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. 19 and 20) 1.4 APPROACH The EPRI guidance document is used for the LaSalle County Generating Station Unit 2 engineering walkdowns and evaluations described in this report. In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:

Seismic Licensing Basis Personnel Qualifications Selection of Systems, Structures, and Components (SSC)

Seismic Walkdowns and Area Walk-Bys Seismic Licensing Basis Evaluations IPEEE Vulnerabilities Resolution Report Peer Review

1.5 CONCLUSION

Seismic walkdowns have been performed at the LaSalle County Generating Station Unit 2 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 ten (10) minor conditions. Other than these minor conditions, the Seismic Walkdowns identified no degraded, nonconforming, or 1-2

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 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.

1-3

12Q0108.50-R-002 Rev. 1 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 3.8 Design of Category I Structures 3.9 Mechanical Systems and Components 3.10 Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment These UFSAR sections should be referred to for a detailedunderstanding of the seismic licensing basis.

2.3.1 Summary of Seismic Design Design Response 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-002 Rev. I Correspondence No.: RS-12-163 Design 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 to the 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

12Q0108.50-R-002 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

ACI 318 Building Code 1963 Requirements for Reinforced Concrete 2

ACI 318 Building Code 1971 Requirements for Reinforced Concrete 3

ACI 214 Recommended Practice 1965 for Evaluation of Compression Test Results 4

ACI 301 Specifications for 1972 Exceptions are Structural Concrete for listed in Buildings UFSAR t

Appendix E 5

AC1 306 Recommended Practice 1966 Additions are for Cold Weather listed in Concreting UFSAR Appendix E 6

ACI 315 Manual of Standard 1957 Practice for Detailing Reinforced Concrete Structures 7

ACI 347 Recommended Practice 1968 for Concrete Formwork 2-3

12Q0108.50-R-002 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 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 A123.1 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-002 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 Cold-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 XI, 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 AS 1250 Structures 2-5

12Q0108.50-R-002 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

Naeeient 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 X)

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.

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12Q0108.50-R-002 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 allaspects 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-002 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

12Q0108.50-R-002 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.

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12Q0108.50-R-002 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 2. (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.

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12Q.108.50-R-002 Rev. 1 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/c(onduit 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).

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.2QO1. 8.50-R-002 Rev. I 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, #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-002 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 2.

(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.

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12Q0108.50-R-002 Rev. 1 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 2 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,

& 18) 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 2.

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12Q0108.50-R-002 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 108 of the 115 total items identified on the LaSalle Unit 2 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 10CFR50.54(f) letter due to their being inaccessible. Inaccessibility of this equipment was either based on the location of 5-1

1200108.50-R-002 Rev. I 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.

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12Q0108.50-R-002 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 115 54 31 43 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.

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12Q0108.50-R-002 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 seven (7) 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, e.g., on the order of about 35 feet from the SWEL item. This vicinity is described on the Area Walk-By Checklist (AWC), shown in Appendix D of this report. A total of 47 AWCs were completed for LaSalle Unit 2. 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)

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-002 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 Floodinq/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.

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12Q0108.50-R-002 Rev. I 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. Four (4) 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-002 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.

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12..108.50-R-002 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)

During the performance of Fukushima Seismic Walkdowns on Unit Two, it was noted that the S-hooks associated with the chains 2C11-D001002, 2C11-holding fluorescent lighting fixtures D001090, 2C1 1-D001095, were not completely crimped closed.

2C1 1-DO01 184, 2C1 1-D2259-Two of the areas noted were in the 125, 2C11-D2259-126, 2C11-vicinity of the Unit 2 North and South D2259-127, 2C11-D2603-125, Hydraulic Control Unit,(HCU) banks 2C11-D2603-126, 2C11-in the Reactor Building (761' 1406922 No D2603-127, 2C11-D3459-125, Elevation). It should be noted that 2C1 1-D3459-126, 2C1 1-the S-hooks are closed enough such D3459-127, 2C11-D3807-125, that they would not allow the fixture 2C11-D3807-126, 2C1 1-to become disconnected during a D3807-127 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, base plate thread engagements on a population of Switchgears and Transformers were inspected as part of the walkdown. On Transformer 236X (2AP21 E-303B), the southwest 1-inch diameter anchor bolt has 7/8 2AP21-303B inch thread engagement, 1/8 inch 1405542 Yes with no thread engagement. A preliminary evaluation was performed by Engineering. Per Engineering, there is no structural adequacy concern; therefore the anchor bolt as-found thread engagement is not a seismic issue, and the transformer remains fully-functional.

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12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Actions Action Complete Item ID Description of Issue Request (Yes/No, ID (IR)

See Notes 1 & 2)

Out of the 34 anchor bolts connecting the 2A Diesel Generator Skid to the foundation, the one on the SE corner is missing a washer and a nut. The bolt is 1.5" diameter with 2" of clearance from top of the bolt to the skid.

The issue was identified during NRC Near Term Task Force Fukushima Seismic Walkdown. The skid beam 2DG01K is embedded in the foundation and 1405600 Yes there is no indication of uplift in the anchorage area. The rest of the bolts have the required washers and nuts.

The DG has been functioning well with this existing condition.

Engineering performed a preliminary evaluation for this condition and found that the existing condition meets all design requirements with substantial margin on bolt stresses.

For the 2A RHR WS Strainer 2E12-D300B, two south anchor nuts on the Strainer legs were found not fully tightened. There was a 1/4 inch to 1/2 inch gap under the installed nuts.

2E12-D300B Based on a preliminary evaluation by 1406061 Yes Engineering, the 2E12-D300B Strainer would have still performed its design function during a seismic event even with the nuts not fully tightened.

Installed missing nut and washer on anchor bolt (see IR 1405600). Nut is mechanically tight but does not have 2DG01K full thread engagement as procedure 1406114 Yes requires. 2A DG remains fully operational per Engineering preliminary evaluation.

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12Q.108.50-R-002 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 Two Reactor Building, it was noted that a lighting fixture located on the 761' Elevation by the CRD Accumulator (Northwest) has three chains supporting the lighting fixture.

2C1 1-DO01 095, 2C1 1-D3459-The fixture should have four chains 125, 2C11-D3459-126, 2C11-supporting the fixture. Per 1411336 Yes D3459-127 Engineering, this is not a seismic issue due to the fact that the fixture is being supported by the third chain and is also supported by the flex conduit going into the fixture.

However, the chain and associated S-hook should be replaced due to housekeeping issues.

During the performance of Fukushima Seismic Walkdowns in the Unit 2 Reactor Building, it was noted that there was a pipe clamp that was not installed on a short run of tube above valve 2E22-N005-HRR on instrument panel 2H22-P024. Per Engineering, this is not a 2E22-N004, 2E22-N005 seismic concern since the short 1419068 Yes unsupported length of the tube is less than the maximum permitted unsupported length set forth in the design requirements in PI-LSNS-16.

Moreover, the line is robustly supported along its entire run from containment to the subject instrument panel.

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.

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12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Table 5-3. Conditions Identified during Area Walk-Bys Actions Action Cmlt Item ID Description of Issue Request ID Complete (I R)

(Yes/No, See Notes 1 & 2)

During the performance of Fukushima Seismic Walkdowns on Unit Two, 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 Two Diesel Generator Penthouse, as well as the 1-01, 3-04, Unit Two Hydraulic Control Units (HCUs) in the 3-05 Reactor Building (761' Elevation). It should be 1406922 No noted 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, populations of lighting fixtures were inspected as part of the walkdown. Three lighting fixtures located in the Unit 2 Diesel Generator Penthouse, elevation 736 (J & 22) need repair.

1-01 The north and middle 4 foot-long lighting fixtures 1405563 No have broken plastic covers that must be replaced.

The south 4 foot-long lighting fixture S-hooks on the chains are not closed properly. There is no safety-related equipment near the light fixtures that would be impacted during a seismic event due to light fixtures falling from the S-hooks.

During the performance of Fukushima Seismic Walkdowns in the Unit Two "B" RHR Heat Exchanger Room (Elevation 694'), it was noted that there is a two inch by four inch piece of wood 1-20 in the overhead stuck between pipes. If the piece 1406885 Yes of wood were to become dislodged during a seismic event, there are no soft targets in the area below. Therefore, this is not a seismic interaction issue, but rather a housekeeping issue per Engineering.

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12Qo108.50-R-002 Rev.

1 Correspondence No.: RS-12-163 Actions Action Cmlt Item ID Description of Issue Request ID Complete (IR)

(Yes/No, See Notes 1 & 2)

During the performance of Fukushima Seismic Walkdowns in the Unit Two Reactor Building, it was noted that 2B33-S001 B "2B Reactor Recirculation Pump Low Frequency Motor Generator Set" motor termination junction box had 4-02 a missing bolt. The missing bolt is located on the 1414874 Yes north end, west side of the box. The missing bolt is one of several bolts that attach the cover plate to the junction box. The missing bolt has no significant effect on the junction box integrity, therefore per Engineering 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.

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12QO108.50-R-002 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.

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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

12Qo108.50-R-002 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.

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12Q0108.50-R-002 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-134, Sheet 1 Rev. AT, P&ID CSCS Equipment Cooling Water System

10. Drawing M-134, Sheet 2 Rev. AK, P&ID CSCS Equipment Cooling Water System

11. Drawing M-134, Sheet 3 Rev. 0, P&ID CSCS Equipment Cooling Water System

12. Drawing M-144, Sheet 1 Rev. AL, P&ID Fuel Pool Cooing Filter & Demineralizing System 9-1

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163

13. Drawing M-144, Sheet 2 Rev. W, P&ID Fuel Pool Cooing Filter & Demineralizing System

14. Drawing M-87, Sheet 2 Rev. AR, P&ID Core Standby Cooling System Equipment Cooling Water System

15. Drawing M-770, Sheet 13 Rev. D, Substructure Piping

16. Drawing S-781, Rev. 0, Reactor Building Pool Liner Top Plan Elevation 843'-6"

17. Drawing S-782, Rev. K, Reactor Building Pool Liner Bottom Plan

18. Drawing S-784, Rev. L, Reactor Building Pool Liner Sections & Details

19. Exelon Generation Company, LLC, Docket No. 50-373, LaSalle County Station, Unit 1, Facility Operating License, License No. NPF-1 1

20. Exelon Generation Company, LLC, Docket No. 50-374, LaSalle County Station, Unit 2, Facility Operating License, License No. NPF-18 9-2

12Q0108.50-R-002 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, Equipment 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 1200108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 renson & 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

Stev 12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 enson & Associates Antonio J. Perez, P.E.

Engineering Supervisor - ME/CE/SE Design May 2004 - January 2006 Supervised a staff of 12 to 15 engineers (mechanical, civil, and structural design) who were charged with developing design changes, maintaining design and licensing basis documentation and supporting maintenance.

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

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

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

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

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

Motor Operated Valve Engineer June 2001 - May 2004

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

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

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

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

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

• Integrated mechanical systems and designed equipment for material handling systems.

" Procured equipment and coordinated delivery schedules with vendors.

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Stev 12Q.108.50-R-002 Rev.

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.

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12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 A-5

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 KIM L. HULL BACKGROUND

SUMMARY

Accomplished Lead Engineer/ Project Manager with significant experience in commercial nuclear power industry.

Demonstrated ability to lead and contribute on cross-functional project teams.

Possess strong analytical, problem resolution, collaboration, and communication skills when interacting with diverse audiences including regulatory inspectors, internal inspectors, management, and employees. Respected trainer with ability to develop and present information and measure effectiveness through evaluation techniques. Strengths include:

Project Management Design Modifications Plant Operational Support Procurement Management/Leadership Regulatory Compliance Training/Coaching Auditing Inspections KEY ACCOMPLISHMENTS Served as KNPP Lead Engineer/ Project Supervisor for approximately 125 plant design changes.

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

Thorough understanding of configuration control, management, and preparation of 10CFR50.59 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 III/Principal Engineer (2004 - 2009)

" Zesponsible 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-002 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 10CFR 50.59 process training for new engineers.

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

Contract Manager for Steam Generator Replacement (SGR).

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

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

Coordinated contractor mobilization, badging, and plant specific training.

Technical Specialist for Quality Assurance audits of vendors.

SGR Shift Manager for night shift Responsible Engineer for SGR related Physical Change Packages.

Responsible for SGR budget development up to 1998.

Prepared, reviewed, and awarded Bechtel Installation contract.

Participated in review and award of Ansaldo Fabrication contract.

Served on team to review and award Westinghouse Design contract.

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

Senior Engineer (Analytical Group) (1994-1998)

Responsible Engineer for Physical Change Packages.

Member KNPP Engineering Reorganization Team.

Recognized Technical Expert for KNPP systems.

Senior Project Supervisor (1992-1994)

Provided project management and engineering services for KNPP DCR packages.

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

Nuclear Services Supervisor (1991-1992)

Supervised initial Steam Generator replacement project effort.

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-002 Rev. 1 Correspondence No.: RS-12-163 A-8

12Q0108.50-R-002 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 Project 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 (ComEd, 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 En-gineer (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.

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12Q.108.50-R-002 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

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12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 A-11

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12Q0108.50-R-002 Rev. 1 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.

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12Q0108.50-R-002 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

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Certificate of Completion Dave Carter Success{ully Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns 17i Date: 06126/12 Bruce M. LK - Instructor NTTF 2.3 Seismic Walkdown Course t

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12Q0108.50-R-002 Rev. I 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 Erosion-corrosion criteria ASME Section 111, IX, XI, B3 1.1 High Energy Line Break Safety Analysis Project Management NRC GL 89-13 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 if54 A-16

12Q0108.50-R-002 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 5

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LaSalle County Generating Station Unit 2 12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 A-18

12Q0108.50-R-002 Rev. 1 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-002 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Mike Wodarcyk Successfulli Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Date: 06/26/12 Bruce M. Le

- Instructor NTTF 2.3 Seismic Walkdown Course A-20

12Q0108.50-R-002 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 0

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.

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12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 As a senior plant systems engineer, Mr. Ram has: l. Developed several test plans for modification packages for the replacement of low and medium voltage circuit breakers (ABB K-Line to Square D Masterpact; GE Magneblast to Wyle Siemens) and for the replacement of the entire Pressurizer Heater Bus switchgear; 2. Personally been involved in execution of these test plans during refueling outages;

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

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

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

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

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

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

preparation of relay testing specification with civil engineering input; working with and visiting seismic testing facilities for relay qualification and; developing pre.and post installation instructions including test procedures. He worked closely with teams consisting of maintenance, operations, and work MGMT during the development and implementation of theselprojects. 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 (Iontactor) 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-002 Rev. 1 Correspondence No.: RS-12-163 275 Mishawumn Road, Suile 200, Woburn, MA 01801 S Ael (781) 932-9580 Fra (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-0336104 (Civil), Georgia License. No. 015562, Ohio License No. E-57497 Professional History 2012 - Present Stevenson & Associates, Charlotte, North Carolina, Senior Consultant and General Manager, Charlotte, NC Office' 1980-2012 AREVA Inc., Charlotte, NC, Engineering Manager Professional Experience Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities as an Engineering Manager have included work from the conceptual design through to the installation support phases of projects. Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations. The efforts have also included significant client and/or regulatory interface, as required. These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed. In addition, he has extensive experience in proposal and report development, as well as personnel training activities.

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

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

Other Code experience includes the American Institute of Steel Construction (AISC), American Concrete BOSTON oCLEVELAND oCHICA GO oMINNEA POLLS oPHOENIX A-23

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 275 Aishawum Road, Suite 200, WVohurn, A.L4 01801 Tel (781) 932-9580 I-ax (781) 933-4428 WWW. vccsa. coin Stevenson & Associates Engineering Solutions for Nuclear Power Institute (ACI), and ASME (ANSI) B3 1.1 and B31.3 codes. He serves on the AREVA College of Experts in the areas of structural and dynamic analysis and is also fluent in using numerous piping and finite element computer programs, as well as in typical frame analysis programs.

Engineering Manager, Civil and Layout Department AREVA NP Inc.

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

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

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

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

Examples of typical projects include the following:

Mixed Oxide (MOX) Fuel 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, To1ko 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 sCHICA GO "MINNEA POLISPPHOENIX A-24

1200108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 275 Mishawum Road, Suite 200, Woburn, MA 01801 ATel (781) 932-9580 Fax (781) 933-4428 www.

WWveCSa. 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 I 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, ComEd - 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 oCLEVELA ND oCHICA GO oMINNEAPOLISoPHOENIX A-25

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 275 Atishawumn Road. Suite 200, R-ohurn,.M.A 01801 7Te (781,) 932-9580 /,-ax (781) 933-4428 WWW. v14 eSCa.

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 1II, 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, CornEd - 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 1 and 2, D. C. Cook Units I 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 eCLEVELAND eCHICA GO.MINNEAPOLIS*PHOENIX A-26

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Todd Bacon Successfulli 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-27

12Q0108.50-R-002 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-002 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 StationpM, Byron StationPM, Dresden StationpM, Quad Cities StationPM Consumers Power Co. - Palisades Nuclear StationPM Entergy - Arkansas Nuclear One Florida Power & Light - Turkey Point Station New York Power Authority - James A. Fitzpatrick Nuclear Power Plant Niagara Mohawk Power Corporation - Nine Mile Point Station PM Northern States Power Co. - Monticello Nuclear Generating Plant Northern States Power Co. - Prairie Island Nuclear Generating Plant Omaha Public Power District - Fort Calhoun Station (SPRA)

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

Wisconsin Public Service - Kewaunee Nuclear Power PlantPM (SPRA)

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

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

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

Walter Djordjevic Page 2 S

A-29

12Q0108.50-R-002 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-1 06.

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

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

1984 ANS Conference, "Qualification of Class 1E Devices Using I n-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

12Q0108.5(-R-002 Rev. 1 Correspondence No.: RS-12-163 Certificate of Completion Walter Djordjevic Successulllj Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns Bruce M. Lor-Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-31

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 N

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-002 Rev. 1 Correspondence No.: RS-12-163

"" Exeton.

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

12001*08.50-R-002 Rev. 1 CnrrO=nnnjtonr n" P.0.12-R';

im j~.*I*

IELECTRIC POWER aarU f

i I~ RESEARCH INSTITUTE Certificateof 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-64

12Q0108.50-R-002 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 2, there is no Rapid Drain-Down Equipment List.

The following contents are found in Appendix B:

SW EL Approval Signature Page...................................................................

B-2 Table B-la. Base List 1a - Items Exclusive to Unit 2........................................... B-3 Table B-1 b. Base List lb - Items Common to Units 1 and 2................................. B-57 T able B -2. B ase List 2................................................................................. B -74 T a ble B -3. S W E L 1.................................................................................... B -75 Table B-4. SWEL 2 B-79 B-1

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SA Stevenson & Associates Seismic Walkdown Interim Report, Rev. 3 In Response to NTTF Recommendation 2.3: Seismic LaSalle County Generating Station - Unit 2 Tony Perez

/ _

09/18/2012 Equipment Selection Preparer date Kim L. Hul

~

~09/19/2012 Equipment See Revy date Station O Frions Staff Member date Refer to Attachment 3 for synopsis of Station Operations role and responsibility.

Thomas Dean Operations Support Manager B-2

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Table B-la. Items Exclusive to Unit 2 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2AP01 E 6.9KV SWGR 251 AP AB 18 N 710 2AP03E 4160V SWGR 241X AP AB 20 N 710 2AP04E-3 TRANSFORMER, 231X AP 2AP05E 4160V SWGR 242X AP AB 20 N 731 2AP06E DIV II 4160V SWGR 242Y AP AB 20 N 731 2AP07E DIV III 4160V SWITCHGEAR 243 AP AB 20 L 687 2AP07E-001 SYSTEM AUX TRANSFORMER 242 AP 2AP08E 6.9KV SWGR 251-1 AP RB 21 D 786 2AP1 1 E 480V SWGR 231X AP AB 16 N 815 2AP12E 480V SWGR 231Y AP TB 29 V 731 2AP13E 480V SWGR 232X AP AB 20 L 786 2AP15E 480V SWGR 233 AP RB 19 C 786 2AP17E 480V SWGR 234X AP RB 16 C 786 2AP19E DIV I 480V SWGR 235X AP AB 20 L 710 2AP19E-103B TRANSFORMER, 235X AP AB 20 L 710 2AP20E DIV I 480V SWGR 235Y AP AB 19 L 710 2AP20E-203B TRANSFORMER, 235Y AP 2AP21E DIV II 480V SWGR 236X AP.

AB 20 L 731 2AP21E-303B TRANSFORMER, 236X AP AB 20 L 731 2AP22E DIV II 480V SWGR 236Y AP AB 19 L 731 2AP22E-403B TRANSFORMER, 236Y AP 2AP23E 480V SWGR 237X AP AB 19 N 794 2AP24E 480V SWGR 237Y AP AB 23 N 794 2AP31 E 480V SWGR 233A AP AB 18 L 786 2AP58E 480V MCC 232X-1 AP AB 16 L 815 2AP65E 480V MCC 234X-2 AP RB 15 A 740 2AP71E DIV I 480V MCC 235X-1 AP RB 20 A 761 2AP73E DIV I 480V MCC 235X-3 AP AB 19 L 710 2AP75E DIV I 480V MCC 235Y-1 AP RB 21 D 740 2AP76E DIV I 480V MCC 235Y-2 AP RB 19 J 710 2AP78E DIV II 480V MCC 236X-1 AP RB 18 C 820 2AP79E DIV III 480V MCC 243-1 AP AB 20 L 687 2AP80E 2AP80E - 480 VAC MCC 236X-2 AP AB 21 L 731 2AP81E DIV II 480V MCC 236X-3 AP AB 21 L 731 2AP82E DIV II 480V MCC 236Y-1 AP RB 15 E 710 2AP83E MCC 236Y-2 AP RB 16 J 740 2B21-AOOIA ACCUMULATOR, MSIV B21 2B21-AO01B ACCUMULATOR, MSIV B21 2B21-AO01C ACCUMULATOR, MSIV B21 2B21-AO01D ACCUMULATOR, MSIV B21 2B21-AO02A ACCUMULATOR, MSIV B21 2B21-AO02B ACCUMULATOR, MSIV B21 2B21-AO02C ACCUMULATOR, MSIV B21 2B21-AO02D ACCUMULATOR, MSIV B21 2B21-AO03C ACCUMULATOR, ADS B21 Table B-la Page 1 of 54 B-3

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2B21-AO03D ACCUMULATOR, ADS i

B21 2B21-AO03E ACCUMULATOR, ADS B21 2B21-AO03R ACCUMULATOR, ADS B21 2B21 -A003S ACCUMULATOR, ADS I

B21 2B21-AO03U ADS ACCUMULATOR B21 2B21-AO03V ACCUMULATOR, ADS iB21 2B21-AO04A ACCUMULATOR, MSRV i

B21 2B21-AO04B ACCUMULATOR, MSRV iB21 2B21-AO04C ACCUMULATOR, MSRV I

B21 DW 777 2B21-AO04D ACCUMULATOR, MSRV

__B21 2B21-A004E ACCUMULATOR, MSRV I

B21 2B21-AO04F ACCUMULATOR, MSRV B 821 2B21-AO04G ACCUMULATOR, MSRV B21 2B21-AO04H ACCUMULATOR, MSRV

__B21 2B21-AO04J ACCUMULATOR, MSRV B21 2B21-AO04K ACCUMULATOR, MSRV B21 2B21-AO04L ACCUMULATOR, MSRV B21 2B21-AO04M ACCUMULATOR, MSRV 821 2B21-AO04N ACCUMULATOR, MSRV B21 2B21-AOO4P ACCUMULATOR, MSRV FB21 2B21-AO04R ACCUMULATOR, MSRV B21 2B21-AO04S ACCUMULATOR, MSRV B

821 2B21-AO04U ACCUMULATOR, MSRV r

B21 2B21-AO04V ACCUMULATOR, MSRV B21 2B21-AO05A ACCUMULATOR, FOR 2B21-F032A, B21 OUTBOARD CHECK 2B21-A005B ACCUMULATOR, FOR 2B21-F032B, B21 OUTBOARD CHECK

_I 2B21-FO13A D MS LINE SAFETY/RELIEF VLVý B21 2B21-FO13A-A SRV A IMF-2 SOLENOID VALVE A' B21 2B21-F013B A MS LINE SAFETY/RELIEF VLVI B21 2B21-FO13B-A SRV B IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13C C MS LINE SAFETY/RELIEF VLVI B21 DW 777 2B21-FO13C-A SRV C IMF-2 SOLENOID VALVE 'A' B21 DW 783 2B21-FO13C-B SRV C IMF-2 SOLENOID VALVE 1'B' B21 2B21-FO13C-C SRV C IMF-2 SOLENOID VALVE I'C' B21 2B21-FO13D B MS LINE SAFETY/RELIEF VLVI B21 2B21-FO13D-A SRV D UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13D-B SRV D UMF-1 SOLENOID VALVE 'B' B21 2B21-FO13D-C SRV D UMF-1 SOLENOID VALVE 'C' B21 2B21-FO13E C MS LINE SAFETY/RELIEF VLV, B21 2B21-FO13E-A SRV E IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13E-B SRV E IMF-2 SOLENOID VALVE 'B' B21 2B21-FO13E-C SRV E IMF-2 SOLENOID VALVE 'C' B21 2B21-FO13F B MS LINE SAFETY/RELIEF VLV, B21 2B21-FO13F-A SRV F UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13G D MS LINE SAFETY/RELIEF VLV 821 Table B-la Page 2 of 54 B-4

12Q.108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column Floor Tag EquipmentNameCode No Elev 2B21-FO13G-A SRV G IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13H D MS LINE SAFETY/RELIEF VLV B21 2B21-FO13H-A SRV H IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13J A MS LINE SAFETY/RELIEF VLV B21 2B21-FO13J-A SRV J IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13K B MS LINE SAFETY/RELIEF VLV B21 2B21-FO13K-A SRV K UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13K-B SRV K UMF-1 SOLENOID VALVE 'B' B21 2B21-FO13L VALVE, RX VSSL SAFETY RELIEF B21 2B21-FO13L-A SRV L IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13M B MS LINE SAFETY/RELIEF VLV B21 2B21-FO13M-A SRV M IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13N C MS LINE SAFETY/RELIEF VLV B21 2B21-FO13N-A SRV N IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13P A MS LINE SAFETY/RELIEF VLV B21 2B21-FO13P-A SRV P UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13P-B SRV P UMF-1 SOLENOID VALVE 'B' B21 2B21-FO13R C MS LINE SAFETY/RELIEF VLV B21 2B21-FO13R-A SRV R IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13R-B SRV R IMF-2 SOLENOID VALVE 'B' B21 2B21-FO13R-C SRV R IMF-2 SOLENOID VALVE 'C' B21 2B21-F013S VALVE, RX VSSL SAFETY RELIEF B21 2B21-F013S-A SRV S UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13S-B SRV S UMF-1 SOLENOID VALVE 'B' B21 2B21-FO13S-C SRV S UMF-1 SOLENOID VALVE 'C'

B21, 2B21-F013U D MS LINE SAFETY/RELIEF VLV B21 2B21-FO13U-A SRV U IMF-2 SOLENOID VALVE 'A' B21 2B21-FO13U-B SRV U IMF-2 SOLENOID VALVE 'B' B21 2B21-FO13U-C SRV U IMF-2 SOLENOID VALVE 'C' B21 2B21-FO13V A MS LINE SAFETY/RELIEF VLV B21 2B21-FO13V-A SRV V UMF-1 SOLENOID VALVE 'A' B21 2B21-FO13V-B SRV V UMF-1 SOLENOID VALVE'B' B21 2B21-FO13V-C SRV V UMF-1 SOLENOID VALVE 'C' B21 MS INBD ISOL VLV DRNLINE INBD ISOL 2B21-F016 821 DW 18 G 735 STOP 2B21-F019 MS INBD ISOL VLV DRNLINE OTBD ISOL B21 RB 18 J 735 STOP 2B21-F020 MS EQUALIZING LINE UPSTRM STOP B21 RB 18 J 735 2B21-F022A A MS INBD ISOL VLV B21 DW 18 J 735 2B21-F022A-P2 VALVE, SOLENOID, I/B MSIV B21 2B21-F022A-P3 VALVE, SOLENOID, I/B MSIV B21 2B21-F022B B MS INBD ISOL VLV B21 2B21-F022B-P2 VALVE, SOLENOID, I/B MSIV B21 2B21-F022B-P3 VALVE, SOLENOID, I/B MSIV B21 2B21-F022C C MS INBD ISOL VLV B21 DW 18 J 735 2B21-F022C-P2 VALVE, SOLENOID, I/B MSIV B21 2B21-F022C-P3 VALVE, SOLENOID, I/B MSIV B21 Table B-la Page 3 of 54 B-5

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2B21-F022D D MS INBD ISOL VLV B21 2B21-F022D-P2 VALVE, SOLENOID, I/B MSIV B21 2B21-F022D-P3 VALVE, SOLENOID, I/B MSIV B21 2B21-F028A A MS OTBD ISOL VLV B21 RB 18 J 735 2B21-F028A-P2 VALVE, SOLENOID, O/B MSIV B21 2B21-F028A-P3 VALVE, SOLENOID, O/B MSIV B21 2B21-F028B B MS OTBD ISOL VLV B21 RB 18 J 735 2B21-F028B-P2 VALVE, SOLENOID, O/B MSIV B21 2B21-F028B-P3 VALVE, SOLENOID, O/B MSIV B21 2B21-F028C C MS OTBD ISOL VLV B21 RB 18 J 735 Outboar 2821 -F028C-P2 VALVE, SOLENOID, O/B MSIV B21 d MSIV 735 Room 2B21-F028C-P3 VALVE, SOLENOID, O/B MSIV B21 2821 -F028D D MS OTBD ISOL VLV B21 RB 18 J 735 2B21-F028D-P2 VALVE, SOLENOID, O/B MSIV B21 2821 -F028D-P3 VALVE, SOLENOID, O/B MSIV B21 2B21-F032A SOLENOID VALVE B21 I

2B21-F032A-A ACTUATOR, FW CHECK CYLINDER A B21 2821 -F032A-AC VALVE, A CYL CLOSE FW CHECK B21 2B21-F032A-AO VALVE, A CYL OPEN FW CHECK B21 2B21-F032A-BC VALVE, B CYL CLOSE FW CHECK B21 2B21-F032A-BO VALVE, B CYL OPEN FW CHECK B21 2B21-F032B B FW INLT TESTABLE CK VLV B21 RB 18 J 735 2B21-F032B-AC VALVE, A CYL CLOSE FW CHECK B21 2B21-F032B-AO VALVE, A CYL OPEN FW CHECK B21 2B21-F032B-BC VALVE, B CYL CLOSE FW CHECK B21 2B21-F032B-BO VALVE, B CYL OPEN FW CHECK B21 2821 -F037A2 VALVE, VAC RELIEF B21 2B21-F037B1 VALVE, VAC RELIEF B21 2B21-F037C1 VALVE, VAC RELIEF B21 2B21-F037N2 VALVE, VAC RELIEF B21 2B21-F065A RX FW HDR STOP VLV B21 RB 18 J 735 2B21-F065B RX FW HDR STOP VLV B21 RB 18 J 735 2B21-F067A A MS OTBD ISOL ABOVE SEAT DRN VLV B21 RB 18 H 735 2B21-F067B B MS OTBD ISOL ABOVE SEAT DRN VLV B21 RB 18 H 735 2B21-F067C C MS OTBD ISOL ABOVE SEAT DRN VLV B21 RB 18 H 735 2B21-F067D D MS OTBD ISOL ABOVE SEAT DRN VLV B21 RB 18 H 735 MS OTBD ISOL VLV DWNST DRN DWNST 2B21-F071 B21 TB 20 S 663 ORIFICED STOP 21321 -F073 MS TUNNEL STM LINE DRN DOWSTREAM 821 TB 20 S 663 ORIFICED STOP 2B21-F418A MS AUX SPLY STM STOP VLV B21 TB 19 V 728 2B21-F418B MS AUX SPLY STM STOP VLV B21 TB 19 S 741 Table B-Ia Page 4 of 54 B-6

12Qo108.50-R-002 Rev.

1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2B33-F019 RX RECIRC PROCESS SMPL INBDISOL B33 DW 17 C 740 STOP 2B33-F020 RX RECIRC PROCESS SMPL OTBD ISOL B33 RB 17 B 740 STOP 2C11-D001 ASSY - CONTROL UNIT CRD HYDRAULIC C11 2C11-D001001 CONTROL UNIT CRD HYDRAULIC 26-59 C11 2C11-D001002 CONTROL UNIT CRD HYDRAULIC 22-59 C11 RB G-F15-16 761 SOUTH 2C11-D001003 CONTROL UNIT CRD HYDRAULIC 18-59 C11-2C11-D001004 CONTROL UNIT CRD HYDRAULIC 26-55 C11 2C11-D001005 CONTROL UNIT CRD HYDRAULIC 22-55 C1 1 2C11-D001006 CONTROL UNIT CRD HYDRAULIC 18-55 C11 2C11-D001007 CONTROL UNIT CRD HYDRAULIC 26-51 C11 2C11-D001008 CONTROL UNIT CRD HYDRAULIC 22-51 C11 2C11-D001009 CONTROL UNIT CRD HYDRAULIC 18-51 C11 2C11-D001010 CONTROL UNIT CRD HYDRAULIC 14-51 Cll 2C11-D001011 CONTROL UNIT CRD HYDRAULIC 10-51 Cll 2C11-D001012 CONTROL UNIT CRD HYDRAULIC 14-55 C11 2C11-D001013 CONTROL UNIT CRD HYDRAULIC 26-47 C11 2C11-D001014 CONTROL UNIT CRD HYDRAULIC 22-47 C11 2C11-D001015 CONTROL UNIT CRD HYDRAULIC 18-47 C11 2C11-D001016 CONTROL UNIT CRD HYDRAULIC 14-47 C11 2C11-D001017 CONTROL UNIT CRD HYDRAULIC 10-47 C11 2C11-D001018 CONTROL UNIT CRD HYDRAULIC 06-47 C11 2C11-D001019 CONTROL UNIT CRD HYDRAULIC 26-43 Cll 2C11-D001020 CONTROL UNIT CRD HYDRAULIC 22-43 C11 2C11-D001021 CONTROL UNIT CRD HYDRAULIC 18-43 C11 2C11-D001022 CONTROL UNIT CRD HYDRAULIC 14-43 C11 2C11-D001023 CONTROL UNIT CRD HYDRAULIC 10-43 Cll 2C11-D001024 CONTROL UNIT CRD HYDRAULIC 06-43 C11 2C11-D001025 CONTROL UNIT CRD HYDRAULIC 02-43 C11 2C11-D001026 CONTROL UNIT CRD HYDRAULIC 26-39 C11 2C11-D001027 CONTROL UNIT CRD HYDRAULIC 22-39 C11 2C11-D001028 CONTROL UNIT CRD HYDRAULIC 18-39 Cll 2C11-D001029 CONTROL UNIT CRD HYDRAULIC 14-39 C11 2C11-D001030 CONTROL UNIT CRD HYDRAULIC 10-39 C11 2C11-D001031 CONTROL -UNIT CRD HYDRAULIC 06-39 C11 2C11-D001032 CONTROL UNIT CRD HYDRAULIC 02-39 C11 2C11-D001033 CONTROL UNIT CRD HYDRAULIC 26-35 Cll 2C11-D001034 CONTROL UNIT CRD HYDRAULIC 22-35 C11 2C11-D001035 CONTROL UNIT CRD HYDRAULIC 18-35 C1l 2C11-D001036 CONTROL UNIT CRD HYDRAULIC 14-35 C11 2C11-D001037 CONTROL UNIT CRD HYDRAULIC 10-35 C11 2C11-D001038 CONTROL UNIT CRD HYDRAULIC 06-35 C11 2C11-D001039 CONTROL UNIT CRD HYDRAULIC 02-35 C11 2C11-D001040 CONTROL UNIT CRD HYDRAULIC 26-31 C11 Table B-la Page 5 of 54 B-7

12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D001041 CONTROL UNIT CRD HYDRAULIC 22-31 C11 2C11-D001042 CONTROL UNIT CRD HYDRAULIC 18-31 Cl 1 2Cl1-D001043 CONTROL UNIT CRD HYDRAULIC 14-31 Cl 2C11-D001044 CONTROL UNIT CRD HYDRAULIC 10-31 C11 2C11-D001045 CONTROL UNIT CRD HYDRAULIC 06-31 C11 2C11-D001046 CONTROL UNIT CRD HYDRAULIC 02-31 Cl 1 2C1 1-D001047 CONTROL UNIT CRD HYDRAULIC 30-27 C11 2C11-D001048 CONTROL UNIT CRD HYDRAULIC 26-27 Cl 1 2C1 1-0001049 CONTROL UNIT CRD HYDRAULIC 22-27 C11 2C11-D001050 CONTROL UNIT CRD HYDRAULIC 18-27 C11 2C1l-D001051 CONTROL UNIT CRD HYDRAULIC 14-27 C11 2C11-D001052 CONTROL UNIT CRD HYDRAULIC 10-27 C11 2Cl1-D001053 CONTROL UNIT CRD HYDRAULIC 06-27 C11 2C11-D001054 CONTROL UNIT CRD HYDRAULIC 02-27 C11 2C1l-D001055 CONTROL UNIT CRD HYDRAULIC 30-23 Cl1 2C11-D001056 CONTROL UNIT CRD HYDRAULIC 26-23 CI 1 2C 1-DO01 057 CONTROL UNIT CRD HYDRAULIC 22-23 Cl 1 2C 11-D001058 CONTROL UNIT CRD HYDRAULIC 18-23 Cl 1 2C11-D001059 CONTROL UNIT CRD HYDRAULIC 14-23 C11 2C11-D001060 CONTROL UNIT CRD HYDRAULIC 10-23 C11 2C11-D001061 CONTROL UNIT CRD HYDRAULIC 06-23 Cl1 2C11-D001062 CONTROL UNIT CRD HYDRAULIC 02-23 Cl1 2C11-D001063 CONTROL UNIT CRD HYDRAULIC 30-19 C11 2C11-D001064 CONTROL UNIT CRD HYDRAULIC 26-19 Cll 2C1 1-D001065 CONTROL UNIT CRD HYDRAULIC 22-19 C11 2C11-D001066 CONTROL UNIT CRD HYDRAULIC 18-19 Cll 2C11-D001067 CONTROL UNIT CRD HYDRAULIC 14-19 Cl1 2C11-D001068 CONTROL UNIT CRD HYDRAULIC 10-19 Cll 2C11-D001069 CONTROL UNIT CRD HYDRAULIC 06-19 Cl1 2C11-D001070 CONTROL UNIT CRD HYDRAULIC 02-19 C11 2C11-D001071 CONTROL UNIT CRD HYDRAULIC 30-15 Cl1 2C11-D001072 CONTROL UNIT CRD HYDRAULIC 26-15 Cll 2C11-D001073 CONTROL UNIT CRD HYDRAULIC 22-15 C11 2C11-D001074 CONTROL UNIT CRD HYDRAULIC 18-15 CIl 2C11-D001075 CONTROL UNIT CRD HYDRAULIC 14-15 Cl 1 2C11-D001076 CONTROL UNIT CRD HYDRAULIC 10-15 Cll 2C11-D001077 CONTROL UNIT CRD HYDRAULIC 06-15 C11 2C11-D001078 CONTROL UNIT CRD HYDRAULIC 30-11 Cl1 2C11-D001079 CONTROL UNIT CRD HYDRAULIC 26-11 C11 2Cl 1-D001080 CONTROL UNIT CRD HYDRAULIC 22-11 C11 2C11-D001081 CONTROL UNIT CRD HYDRAULIC 18-11 Cl1 2C11-D001082 CONTROL UNIT CRD HYDRAULIC 14-11 C11 2C11-D001083 CONTROL UNIT CRD HYDRAULIC 10-11 C11 2C11-D001084 CONTROL UNIT CRD HYDRAULIC 14-07 C11 2C11-D001085 CONTROL UNIT CRD HYDRAULIC 30-07 C11 2C11-D001086 CONTROL UNIT CRD HYDRAULIC 26-07 Ci 1 2C11-D001087 CONTROL UNIT CRD HYDRAULIC 22-07 Cl 1 Table B-i a Page 6 of 54 B-8

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D001088 CONTROL UNIT CRD HYDRAULIC 18-07 Cll 2C11-D001089 CONTROL UNIT CRD HYDRAULIC 30-03 C11 2C11-D001090 CONTROL UNIT CRD HYDRAULIC 26-03 C11 RB C-D15-16 761 SOUTH 2C11-D001091 CONTROL UNIT CRD HYDRAULIC 22-03 C11 2C11-D001092 CONTROL UNIT CRD HYDRAULIC 18-03 Cll 2C11-D001093 CONTROL UNIT CRD HYDRAULIC 42-59 C11 2C11-D001094 CONTROL UNIT CRD HYDRAULIC 38-59 C11 2C11-D001095 CONTROL UNIT CRD HYDRAULIC 34-59 C11 RB G-F20-21 761 NORTH 2C11-D001096 CONTROL UNIT CRD HYDRAULIC 30-59 Cll 2C11-D001097 CONTROL UNIT CRD HYDRAULIC 42-55 C11 2C11-D001098 CONTROL UNIT CRD HYDRAULIC 38-55 Cll 2C11-D001099 CONTROL UNIT CRD HYDRAULIC 34-55 C11 2C11-D001100 CONTROL UNIT CRD HYDRAULIC 30-55 C11 2C11-D001101 CRD INSERT STOP VLV C11 2C11-D001102 CRD WITHDRAWAL STOP VLV C11 2C11-D001106 CONTROL UNIT CRD HYDRAULIC 34-51 Cll 2C11-D001108 CONTROL UNIT CRD HYDRAULIC 54-47 Cll 2C11-DO01109 CONTROL UNIT CRD HYDRAULIC 50-47 Cll 2C11-D001110 CONTROL UNIT CRD HYDRAULIC 46-47 C11 2C11-D001112 CONTROL UNIT CRD HYDRAULIC 38-47 Cll 2C11-D001114 CONTROL UNIT CRD HYDRAULIC 30-47 C11 2C11-D001115 CONTROL UNIT CRD HYDRAULIC 58-43 Cll 2C11-D001117 CONTROL UNIT CRD HYDRAULIC 50-43 C11 2C11-D001118 CONTROL UNIT CRD HYDRAULIC 46-43 C11 2C11-D001119 CONTROL UNIT CRD HYDRAULIC 42-43 C11 2C11-D001120 CONTROL UNIT CRD HYDRAULIC 38-43 Cll 2CI1-D001121 CONTROL UNIT CRD HYDRAULIC 34-43 C11 2C11-D001122 CONTROL UNIT CRD HYDRAULIC 30-43 Cll 2C11-D001123 CONTROL UNIT CRD HYDRAULIC 58-39 C11 2C11-D001124 CONTROL UNIT CRD HYDRAULIC 54-39 Cll 2C11-D001125 CONTROL UNIT CRD HYDRAULIC 50-39 Cll 2C11-D001126 CONTROL UNIT CRD HYDRAULIC 46-39 C11 2C11-D001127 CONTROL UNIT CRD HYDRAULIC 42-39 C11 2C11-D001128 CONTROL UNIT CRD HYDRAULIC 38-39 Cll 2C11-D001129 CONTROL UNIT CRD HYDRAULIC 34-39 C11 2C11-D001130 CONTROL UNIT CRD HYDRAULIC 30-39 C11 2C11-D001131 CONTROL UNIT CRD HYDRAULIC 58-35 C11 2C11-D001132 CONTROL UNIT CRD HYDRAULIC 54-35 C11 2C11-D001133 CONTROL UNIT CRD HYDRAULIC 50-35 C11 2C11-D001134 CONTROL UNIT CRD HYDRAULIC 46-35 C11 2C11-D001135 CONTROL UNIT CRD HYDRAULIC 42-35 Cll 2C11-D001136 CONTROL UNIT CRD HYDRAULIC 38-35 C11 2C11-D001137 CONTROL UNIT CRD HYDRAULIC 34-35 C11 2C11-D001138 CONTROL UNIT CRD HYDRAULIC 30-35 Cll 2C11-D001139 CONTROL UNIT CRD HYDRAULIC 58-31 C11 Table B-la Page 7 of 54 B-9

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component i

System Column Floor Tag Equipment Name Building Tag____________

Code No Elev 2C11-D001140 CONTROL UNIT CRD HYDRAULIC 54-31 C11 2C11-D001141 CONTROL UNIT CRD HYDRAULIC 50-31

.C11 2C11-DO01142 CONTROL UNIT CRD HYDRAULIC 46-31 C11 2C11-D001143 CONTROL UNIT CRD HYDRAULIC 42-31 C11 2C11-DOO 1144 CONTROL UNIT CRD HYDRAULIC 38-31 C11 2C11-D001145 CONTROL UNIT CRD HYDRAULIC 34-31 C11 2C11-DD001146 CONTROL UNIT CRD HYDRAULIC 30-31 CI1 2C11-D001147 CONTROL UNIT CRD HYDRAULIC 58-27 C11 2C11-D001148 CONTROL UNIT CRD HYDRAULIC 54-27 C11 2C11-D001149 CONTROL UNIT CRD HYDRAULIC 50-27 C11 2C11-D001150 CONTROL UNIT CRD HYDRAULIC 46-27 C11 2C11-D001151 CONTROL UNIT CRD HYDRAULIC 42-27 Cll 2C11-D001152 CONTROL UNIT CRD HYDRAULIC 38-27 C1l 2C11-D001153 CONTROL UNIT CRD HYDRAULIC 34-27 C11 2C11-D001154 CONTROL UNIT CRD HYDRAULIC 58-23 C11 2C11-D001155 CONTROL UNIT CRD HYDRAULIC 54-23 C11 2C11-D001156 CONTROL UNIT CRD HYDRAULIC 50-23 C11 2Cll-D001157 CONTROL UNIT CRD HYDRAULIC 46-23 Cil 2C11-D001158 CONTROL UNIT CRD HYDRAULIC 42-23 C11 2C11-D001159 CONTROL UNIT CRD HYDRAULIC 38-23 C11i 2C11-D001160 CONTROL UNIT CRD HYDRAULIC 34-23 C11 2C11-D001161 CONTROL UNIT CRD HYDRAULIC 58-19 CIl 2C11-D001162 CONTROL UNIT CRD HYDRAULIC 54-19 C11 2C11-D001163 CONTROL UNIT CRD HYDRAULIC 50-19 Cil 2C1 1-D001164 CONTROL.UNIT CRD HYDRAULIC 46-19 C11 2C11-D001165 CONTROL UNIT CRD HYDRAULIC 42-19 Cll 2C11-D001166 CONTROL UNIT CRD HYDRAULIC 38-19 Cll 2Cll-D001167 CONTROL UNIT CRD HYDRAULIC 34-19 Cil 2C11-D001168 CONTROL UNIT CRD HYDRAULIC 54-15 Cll 2C11-D001169 CONTROL UNIT CRD HYDRAULIC 50-15 Cll 2C11-D001170 CONTROL UNIT CRD HYDRAULIC 46-15

-Cll 2C11-D001171 CONTROL UNIT CRD HYDRAULIC 42-15 C11 2C11-D001172 CONTROL UNIT CRD HYDRAULIC 38-15 Cll 2C11-D001173 CONTROL UNIT CRD HYDRAULIC 34-15 C1l 2C11-D001174 CONTROL UNIT CRD HYDRAULIC 46-07 C11 2C11-D001175 CONTROL UNIT CRD HYDRAULIC 50-11 C11 2C11-D001176 CONTROL UNIT CRD HYDRAULIC 46-11 C11 2C11-D001177 CONTROL UNIT CRD HYDRAULIC 42-11 C11 2C11-D001178 CONTROL UNIT CRD HYDRAULIC 38-11 C11 2C11-D001179 CONTROL UNIT CRD HYDRAULIC 34-11 C11 2C11-D001180 CONTROL UNIT CRD HYDRAULIC 42-03 C11 2C11-D001181 CONTROL UNIT CRD HYDRAULIC 38-03 Cll 2C11-D001182 CONTROL UNIT CRD HYDRAULIC 34-03 C11 2C11-D001183 CONTROL UNIT CRD HYDRAULIC 42-07 C11 2C11-D001184 CONTROL UNIT CRD HYDRAULIC 38-07 Cii RB C-D20-21 761 NORTH 2C11-D001185 CONTROL UNIT CRD HYDRAULIC 34-07 C11 Table B-i a Page 8 of 54 B-1 0

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C 11 -D0219 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 02-19 2C11-D0219-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0219-126 CRD HCU SCRAM INLET VALVE C11 2C11-D0219-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D0223 CONTROL ROD DRIVE HYDRAULIC Cli 2C11-D0223__ CONTROL UNIT 02-23 2C11-D0223-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D0223-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0223-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D0227 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 02-27 2C11-D0227-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D0227-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0227-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1 -D0231 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 02-31 2C11-D0231-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0231-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0231-127 CRD HCU SCRAM OUTLET VALVE C11 2Cii-D0235 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 02-35 2C11-D0235-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C1 1-D0235-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0235-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D0239 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 02-39 2C11-D0239-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 2Cll-D0239-126 CRD HCU SCRAM INLET VALVE Cll 2C1 1-D0239-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 02-43 2C1 1-D0243-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C1 -D0243-126 CRD HCU SCRAM INLET VALVE Cii 2C11-D0243-127 CRD HCU SCRAM OUTLET VALVE Cii 2C11-D0615 CONTROL ROD DRIVE. HYDRAULIC C11 CONTROL UNIT 06-15 2C11-D0615-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D0615-126 CRD HCU SCRAM INLET VALVE C11 Table B-la Page 9 of 54 B-11

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D0615-127 CRD HCU SCRAM OUTLET VALVE C11 2C 11 -D0619 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 06-19 2C11-D0619-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0619-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0619-127 CRD HCU SCRAM OUTLET VALVE C11l 2C11-D0623 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 06-23 2C11-D0623-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0623-126 CRD HCU SCRAM INLET VALVE Cil 2C11-D0623-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D0627 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 06-27 2C11-D0627-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0627-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0627-127 CRD HCU SCRAM OUTLET VALVE C11l 2C11 -D0631 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 06-31 2C1 -D0631-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0631-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0631-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D0635 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-35 2C1 1-D0635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D0635-126 CRD HCU SCRAM INLET VALVE Cll 2C1 1-D0635-127 CRD HCU SCRAM OUTLET VALVE Cii 2C1 1-D0639 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-39 2C1 1-D0639-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D0639-126 CRD HCU SCRAM INLET VALVE C11 2C1 1-D0639-127 CRD HCU SCRAM OUTLET VALVE Cil 2C1 1-D0643 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 06-43 2C11-D0643-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D0643-126 CRD HCU SCRAM INLET VALVE Cil 2C11-D0643-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 l-D0647 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 06-47 2C11-D0647-125 CRD HCU SCRAM WATER ACCUMULATOR C11 Table B-la Page 10 of 54 B-1 2

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D0647-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D0647-127 CRD HCU SCRAM OUTLET VALVE Cil 2C11-D1011 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 10-11 2C11-D101-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1011-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1011-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1015 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 10-15 2C11-D1015-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D1015-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1015-127 CRD HCU SCRAM OUTLET VALVE Cll 2Cli-D1019 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-19 2C11-D1019-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D1019-126 CRD HCU SCRAM INLET VALVE Cll 2Cll-D1019-127 CRD HCU SCRAM OUTLET VALVE Cil 2C11-D1023 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-23 2C11-D1023-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1023-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1023-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-Di027 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-27 2C11-D1027-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1027-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1027-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1031 CONTROL ROD DRIVE HYDRAULIC C1I CONTROL UNIT 10-31 2C1 1-D1031-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1031-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1031-127 CRD HCU SCRAM OUTLET VALVE C11 2Cli-D1035 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 10-35 2C1 1-D1035-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1035-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1035-127 CRD HCU SCRAM OUTLET VALVE Ci1 2C11-Di039 CONTROL ROD DRIVE HYDRAULIC Cli

_CONTROL UNIT 10-39 Table B-1 a Page 11 of 54 B-13

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D1039-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1039-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1039-127 CRD HCU SCRAM OUTLET VALVE Cl 1 2C1 1 -D1 043 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 10-43 2C11-D1043-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1043-126 CRD HCU SCRAM INLET VALVE C11l 2C11-D1043-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1047 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 10-47 2C11-D1047-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1047-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1047-127 CRD HCU SCRAM OUTLET VALVE Cill 2C1 1 -D1 051 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 10-51 2C11-D1051-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1051-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1051-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 14-07 2C11-D1407-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 2C11-D1407-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1407-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 14-11 2C11-D1411-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 2C11-D1411-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1411-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC 2Cll-D1415 ICONTROL UNIT 14-15 Cll 2C11-D1415-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1415-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1415-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1419 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-19 2C1l-D1419-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D1419-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1419-127 CRD HCU SCRAM OUTLET VALVE Ci1 Table B-1 a Page 12 of 54 B-14

12Q-108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Building Column Floor Ta Equipment Name Code No Elev 2C11-D1423 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 14-23 2C11-D1423-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 2C11-D1423-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1423-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-Di427 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 14-27 2C11-D1427-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1427-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1427-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1431 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 14-31 2C11-D1431-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2011-D1431-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1431-127 CRD HCU SCRAM OUTLET VALVE Cl 1l 2C11-D1435 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 14-35 C11 2C1 1-D1435-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1435-126 CRD HCU SCRAM INLET VALVE Cl 2C11-D1435-127 CRD HCU SCRAM OUTLET VALVE Cll_

2C11-D1439 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 14-39 2C11-D1439-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1439-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1439-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D1443 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 14-43 2C1 1-D1443-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1443-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1443-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D1447 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-47 2C1 1-D1447-125 CRD HCU SCRAM WATER ACCUMULATOR C1i 2C11-D1447-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1447-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1451 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 14-51 2C11-D1451-125 CRD HCU SCRAM WATER ACCUMULATOR C11 22C11-D1451-126 CRD HCU SCRAM INLET VALVE C1ii Table B-la Page 13 of 54 B-1 5

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D1451-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1455 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 14-55 2C11-D1455-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1455-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1455-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1803 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 18-03 2C11-D1803-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1803-126 CRD HCU SCRAM INLET VALVE Cil 2C11-D1803-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1807 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 18-07 2C11-D1807-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1807-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1807-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1811 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 18-11 2Cll-D1811-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1811-126 CRD HCU SCRAM INLET VALVE Cll 2Cil-D1811-127 CRD HCU SCRAM OUTLET VALVE Cll 2Cli-D1815 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 18-15 2C11-D1815-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1815-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1815-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1819 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 18-19 2C11-D1819-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1819-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1819-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1823 CONTROL ROD DRIVE HYDRAULIC C1I CONTROL UNIT 18-23 2C11-D1823-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1823-126 CRD HCU SCRAM INLET VALVE Cil 2C11-D1823-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1827 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 18-27 2C11-D1827-125 CRD HCU SCRAM WATER ACCUMULATOR Cii Table B-la Page 14 of 54 B-1 6

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Ta Equipment Name Code No Elev 2C11-D1827-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1827-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1831 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 18-31 2C1 I -D1 831-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D1831-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1831-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1835 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 18-35 2C11-D1835-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1835-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1835-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1839 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 18-39 2C11-D1839-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1839-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1839-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1843 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 18-43 2C1l-D1843-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D1843-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1843-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1847 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 18-47 2C11-D1847-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D1847-126 CRD HCU SCRAM INLET VALVE C11 2C11-D1847-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D1851 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 18-51 2C11-D1851-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D1851-126 CRD HCU SCRAM INLET VALVE Cii 2C11-D1851-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D1855 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 18-55 2C11-D1855-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1855-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1855-127 CRD HCU SCRAM OUTLET VALVE Ci1 2C11-D1859 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 18-59 Table B-ia Page 15 of 54 B-1 7

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Ta Equipment Name Code No Elev 2C1 I -DI 859-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D1859-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D1859-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 I -D2203 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 22-03 2C1 -D2203-125 CRD HCU SCRAM WATER ACCUMULATOR C1i 2C11-D2203-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2203-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D2207 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-07 2C11-D2207-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2207-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2207-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D2211

-~

CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-11 2C11-D2211-125 CRD HCU SCRAM WATER ACCUMULATOR C1I 2C11-D2211-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2211-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 22-15 2C11-D2215-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2215-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2215-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 22-19 2C11-D2219-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2219-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2219-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 22-23 2CIl-D2223-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2223-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2223-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 22-27 2C1 1-D2227-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2227-126 CRD HCU SCRAM INLET VALVE Cll 2C1l-D2227-127 CRD HCU SCRAM OUTLET VALVE Cll Table B-I a Page 16 of 54 B-1 8

12Qo108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Ta Equipment Name Code No Elev 2C 11 -D2231 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-31 2C11-D2231-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2231-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2231-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 i-D2235 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-35 2C11-D2235-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2235-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2235-127 CRD HCU SCRAM OUTLET VALVE C 11 2C11-D2239 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 22-39 2C11-D2239-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2239-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2239-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D2243 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 22-43 2C11-D2243-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2243-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2243-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-02247 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-47 2C1 1-D2247-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2247-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2247-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-02251 CONTROLROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-51 2C11-D2251-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C1 1-D2251-126 CRD HCU SCRAM INLET VALVE Cil 2C11-D2251-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D2255 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 22-55 2C11-D2255-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2255-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2255-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 i-D2259 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 22-59 2C11-D2259-125 CRD HCU SCRAM WATER ACCUMULATOR Cii RB G-F 15-16 761 SOUTH Table B-la Page 17 of 54 B-1 9

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D2259-126 CRD HCU SCRAM INLET VALVE Cil RB G-F 15-16 761 SOUTH 2C11-D2259-127 CRD HCU SCRAM OUTLET VALVE C11 RB G-F 15-16 761 SOUTH 2C11-D2603 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 26-03 2C11-D2603-125 CRD HCU SCRAM WATER ACCUMULATOR Cll RB C-D 15-16 761 SOUTH 2C11-D2603-126 CRD HCU SCRAM INLET VALVE Cll RB C-D 15-16 761 SOUTH 2C11-D2603-127 CRD HCU SCRAM OUTLET VALVE Cll RB C-D 15-16 761 SOUTH 2C1 1-D2607 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 26-07 2C1 -D2607-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2607-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2607-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D2611 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-11 2C11-D2611-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2611-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2611-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1 -D2615 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 26-15 2C1 -D2615-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2615-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2615-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D2619 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 26-19 2C1 1-D2619-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2619-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2619-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D2623 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-23 2C1 1-D2623-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2623-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2623-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 i-D2627 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 26-27 2C1 -D2627-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D2627-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 18 of 54 B-20

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D2627-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D2631 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-31 2C11-D2631-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2631-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2631-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1i-D2635 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-35 2CII-D2635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2635-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2635-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-02639 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-39 2C11-D2639-125 CRD HCU SCRAM WATER ACCUMULATOR Cl1 2C11-D2639-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2639-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D2643 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-43 2C1 -D2643-125 CRD HCU SCRAM WATER ACCUMULATOR Ci1 2C11-D2643-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2643-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D2647 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-47 2Cll-D2647-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D2647-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2647-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D2651 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 26-51 C11 2Cll-D2651-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11 -D2651-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2651-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D2655 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 26-55 2C11-D2655-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D2655-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D2655-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 i-D2659 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 26-59 C11 2C11-D2659-125 CRD HCU SCRAM WATER ACCUMULATOR Cii Table B-i a Page 19 of 54 B-21

12Qo108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D2659-126 CRD HCU SCRAM INLET VALVE C11 2C11-D2659-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D3003 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-03 2C1 -D3003-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3003-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3003-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D3007 CONTROL ROD DRIVE HYDRAULIC Cli

_CONTROL UNIT 30-07 2C11-D3007-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D3007-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3007-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3011 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-11 2C11-D3011-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D3011-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3011-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D3015 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-15 2C1l-D3015-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D3015-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3015-127 CRD HCU SCRAM OUTLET VALVE Cll 2C 11 -D3019 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 30-19 2C1 1-D3019-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3019-126 CRD HCU SCRAM INLET VALVE Cll 2C1l-D3019-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D3023 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 30-23 2C1 1-D3023-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2Cll-D3023-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3023-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D3027 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 30-27 2C1 1-D3027-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3027-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3027-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 i-D3031 CONTROL ROD DRIVE HYDRAULIC C1i

_CONTROL UNIT 30-31 Table B-I a Page 20 of 54 B-22

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D3031-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3031-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3031-127 CRD HCU SCRAM OUTLET VALVE Cil 2C1 1-D3035 CONTROL ROD DRIVE HYDRAULIC Cl1 CONTROL UNIT 30-35 2C11-D3035-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3035-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3035-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D3039 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 30-39 2C11-D3039-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3039-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3039-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D3043 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 30-43 2C11-D3043-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D3043-126 CRD HCU SCRAM INLET VALVE Cll 2Cll-D3043-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 30-47 2C11-D3047-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3047-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3047-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 30-51 2C1 1-D3051-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3051-126 CRD HCU SCRAM INLET VALVE Cli 2C11-D3051-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 30-55 2C1 1-D3055-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3055-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3055-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 i-D3059 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 30-59 2C11-D3059-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3059-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3059-127 CRD HCU SCRAM OUTLET VALVE C11 Table B-la Page 21 of 54 B-23

1200108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag1 Equipment Name Code Building No Elev CONTROL ROD DRIVE HYDRAULIC 2C1 I -D3403 CONTROL UNIT 34-03 Cli 2C1 1 -D3403-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3403-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3403-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3407 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-07 2C11-D3407-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2Cll-D3407-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3407-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1 -D3411 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-11 2C11-D3411-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3411-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3411-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1 -D3415 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-15 2C11-D3415-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3415-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3415-127 CRD HCU SCRAM OUTLET VALVE C11 2C 11 -D3419 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-19 2C11-D3419-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3419-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3419-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3423 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 34-23 2C1 1-D3423-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3423-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3423-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D3427 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 34-27 2C1 -D3427-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3427-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3427-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1i-D3431 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-31 2C11-D3431-125 CRD HCU SCRAM WATER ACCUMULATOR Cil 2C11-D3431-126 CRD HCU SCRAM INLET VALVE C11 Table B-i a Page 22 of 54 B-24

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D3431-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D3435 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 34-35 2C11-D3435-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3435-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3435-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D3439 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 34-39 2C11-D3439-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3439-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3439-127 CRD HCU SCRAM OUTLET VALVE C11 2011 -D3443 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 34-43 2C1 -D3443-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3443-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3443-127 CRD HCU SCRAM OUTLET VALVE C11 2011 -D3447 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 34-47 2C11-D3447-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3447-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3447-127 CRD HCU SCRAM OUTLET VALVE C11 2C11 -D3451 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 34-51 2C11-D3451-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3451-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3451-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D3455 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 34-55 2C1 1-D3455-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3455-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3455-127 CRD HCU SCRAM OUTLET VALVE C11 201 1-D3459 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 34-59 2C1 1-D3459-125 CRD HCU SCRAM WATER ACCUMULATOR C11 RB G-F 20-21 761 NORTH 2C11-D3459-126 CRD HCU SCRAM INLET VALVE Cll RB G-F20-21 761 NORTH 2C11-D3459-127 CRD HCU SCRAM OUTLET VALVE Cii RB G-F20-21 761 NORTH 201 1-D3803 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-03 Table B-1 a Page 23 of 54 B-25

12Q*0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C1 -D3803-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2Cll-D3803-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3803-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D3807 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 38-07 2C1 -D3807-125 CRD HCU SCRAM WATER ACCUMULATOR Cll RB C-D 20-21 761 NORTH 2C11-D3807-126 CRD HCU SCRAM INLET VALVE Cll RB C-D 20-21 761 NORTH 2C11-D3807-127 CRD HCU SCRAM OUTLET VALVE C11 RB C-D 20-21 761 NORTH 2C11-D3811 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-11 2C11-D3811-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3811-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3811-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3815 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-15 2C11-D3815-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2Cil-D3815-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3815-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1 -D3819 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 38-19 2C11-D3819-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D3819-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3819-127 CRD HCU SCRAM OUTLET VALVE Cli 2C1 1-03823 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 38-23 2C1 1-D3823-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3823-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3823-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-D3827 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-27 2C1 1-D3827-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3827-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3827-127 CRD HCU SCRAM OUTLET VALVE Ci1 2C11 i-D3831 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 38-31 2C11-D3831-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3831-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 24 of 54 B-26

12Qo108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C1 1 -D3831-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D3835 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 38-35 2Cll-D3835-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3835-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D3835-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3839 CONTROL ROD DRIVE HYDRAULIC C11

_CONTROL UNIT 38-39 2C1 1-D3839-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3839-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3839-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D3843 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-43 2C11-D3843-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D3843-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3843-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D3847 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-47 2C11-D3847-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3847-126 CRD HCU SCRAM INLET VALVE Cll 2C1 1-D3847-127 CRD HCU SCRAM OUTLET VALVE Cii 2C11 -D3851 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 38-51 2C1 1-D3851-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D3851-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3851-127 CRD HCU SCRAM OUTLET VALVE Cll 2Cil-D3855 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-55 2C1 1-D3855-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3855-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3855-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 i-D3859 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 38-59 2C1 1-D3859-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D3859-126 CRD HCU SCRAM INLET VALVE C11 2C11-D3859-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D4203 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-03 2C1 1-D4203-125 CRD HCU SCRAM WATER ACCUMULATOR Cii Table B-i a Page 25 of 54 B-27

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2Cll-D4203-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4203-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D4207 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-07 2C11-D4207-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4207-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4207-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D4211 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-11 2C11-D4211-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4211-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4211-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D4215 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 42-15 2C11-D4215-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4215-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4215-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D4219 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-19 2C11-D4219-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4219-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4219-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-04223 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-23 2C1 -D4223-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D4223-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4223-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D4227 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 42-27 2C1 1-D4227-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4227-126 CRD HCU SCRAM INLET VALVE Cll 2Cll-D4227-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D4231 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 42-31 2C1 1-D4231-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C1l-D4231-126 CRD HCU SCRAM INLET VALVE C11 2C1 1-D4231-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 i-D4235 CONTROL ROD DRIVE HYDRAULIC Cii

_CONTROL UNIT 42-35 Table B-I a Page 26 of 54 B-28

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Ta Equipment Name Code Building No Elev 2C11-D4235-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4235-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4235-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D4239 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 42-39 2C1 -D4239-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4239-126 CRD HCU SCRAM INLET VALVE Cll 2C1 -D4239-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D4243 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 42-43 2C11-D4243-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4243-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4243-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D4247 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 42-47 2C1 -D4247-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D4247-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4247-127 CRD HCU SCRAM OUTLET VALVE C1l CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 42-51 2C11-D4251-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4251-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4251-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 42-55 2C1 1-D4255-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4255-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4255-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 42-59 2C1 -D4259-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D4259-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4259-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D4607 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 46-07 2C11 -D4607-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4607-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4607-127 CRD HCU SCRAM OUTLET VALVE Cll Table B-i a Page 27 of 54 B-29

12Qo 1 08.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 46-11 2C11-D4611-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4611-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4611-127 CRD HCU SCRAM OUTLET VALVE C11 2C 11 -D4615 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 46-15 2C11-D4615-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4615-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4615-127 CRD HCU SCRAM OUTLET VALVE C11 2C 11 -D4619 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 46-19 2C1 1-D4619-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4619-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4619-127 CRD HCU SCRAM OUTLET VALVE Cll 201 1-D4623 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 46-23 2C11-D4623-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4623-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4623-127 CRD HCU SCRAM OUTLET VALVE Cll 201 1-D4627 CONTROL ROD DRIVE HYDRAULIC C1I CONTROL UNIT 46-27 2C11-D4627-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4627-126 CRD HCU SCRAM INLET VALVE Cll 2C1 1-D4627-127 CRD HCU SCRAM OUTLET VALVE C11I 2C11-D463l CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 46-31 2C11-D4631-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4631-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4631-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D4635 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 46-35 2C01 -D4635-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4635-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4635-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D4639 CONTROL ROD DRIVE HYDRAULIC Cl1 CONTROL UNIT 46-39 2C1 1-D4639-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4639-126 CRD HCU SCRAM INLET VALVE Cll Table B-la Page 28 of 54 B-30

12Q-108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2C11-D4639-127 CRD HCU SCRAM OUTLET VALVE Cil 2C1 1 -D4643 CONTROL ROD DRIVE HYDRAULIC CII CONTROL UNIT 46-43 2C11-D4643-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D4643-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D4643-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 46-47 2C11-D4647-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4647-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4647-127 CRD HCU SCRAM OUTLET VALVE Cll 2C 11 -D4651 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 46-51 2C11-D4651-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D4651-126 CRD HCU SCRAM INLET VALVE C11 2C11-D4651-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D4655 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 46-55 2C1 -D4655-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D4655-126 CRD HCU SCRAM INLET VALVE Cll 2C1 -D4655-127 CRD HCU SCRAM OUTLET VALVE Cii 2C11-D5011 CONTROL.ROD DRIVE HYDRAULIC Cii CONTROL UNIT 50-11 2C11-D5011-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5011-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5011-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D5015 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 50-15 2C11-D5015-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5015-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5015-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D5019 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-19 2C1 1-D5019-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5019-126 CRD HCU SCRAM INLET VALVE Cii 2C11-D5019-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 i-D5023 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 50-23 2C11-D5023-125 CRD HCU SCRAM WATER ACCUMULATOR Cli Table B-la Page 29 of 54 B-31

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column Floor Tag EquipmentNameCode Buildin No Elev 2C11-D5023-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5023-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D5027 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 50-27 2C11-D5027-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5027-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5027-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1 -D5031 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-31 2C11-D5031-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5031-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5031-127 CRD HCU SCRAM OUTLET VALVE C11 2C11-D5035 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 50-35 2Cll-D5035-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2Cli-D5035-126 CRD HCU SCRAM INLET VALVE C11i 2Cli-D5035-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-D5039 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 50-39 2C1 -D5039-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C1 -D5039-126 CRD HCU SCRAM INLET VALVE Cll 2C1 -D5039-127 CRD HCU SCRAM OUTLET VALVE Ci1l 2C1 1-D5043 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 50-43 2C1 1-D5043-125 CRD HCU SCRAM WATER ACCUMULATOR C1i 2C1 -D5043-126 CRD HCU SCRAM INLET VALVE Cli 2C11-D5043-127 CRD HCU SCRAM OUTLET VALVE CIl 2C1 i-D5047 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 50-47 2C1 -D5047-125 CRD HCU SCRAM WATER ACCUMULATOR CII 2C11-D5047-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5047-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1i-D5051 CONTROL ROD DRIVE HYDRAULIC Cl CONTROL UNIT 50-51 2C1 -D5051-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D5051-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5051-127 CRD HCU SCRAM OUTLET VALVE C1l 2C1 1I-D5415 CONTROL ROD DRIVE HYDRAULIC Ci1 CONTROL UNIT 54-15 Table B-I a Page 30 of 54 B-32

12Q.108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column Floor Tag EquipmentNameCode No Elev 2C11-D5415-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5415-126 CRD HCU SCRAM INLET VALVE C11 2C1 1-D5415-127 CRD HCU SCRAM OUTLET VALVE C1l 2C11-D5419 CONTROL ROD DRIVE HYDRAULIC C11 CONTROL UNIT 54-19 2C11-D5419-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5419-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5419-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-05423 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 54-23 2C11-D5423-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5423-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5423-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-05427 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 54-27 2C1 1-D5427-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5427-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5427-127 CRD HCU SCRAM OUTLET VALVE C11 CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 54-31 2C11-D5431-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5431-126 CRD HCU SCRAM INLET VALVE C11_

2C11-D5431-127 CRD HCU SCRAM OUTLET VALVE C11_

CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 54-35 2C1 1-D5435-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2C11-D5435-126 CRD HCU SCRAM INLET VALVE C11 2C1 1-D5435-127 CRD HCU SCRAM OUTLET VALVE Cll CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 54-39 2C1 1-D5439-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5439-126 CRD HCU SCRAM INLET VALVE Cll 2C1 1-D5439-127 CRD HCU SCRAM OUTLET VALVE Cll 2C1 1-05443 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 54-43 2C1 1-D5443-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5443-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5443-127 CRD HCU SCRAM OUTLET VALVE C11 Table B-la Page 31 of 54 B-33

12Q.108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Column Floor Ta Equipment Name Code Building No Elev 2C11-D5447 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 54-47 2C11-D5447-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5447-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5447-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11 i-D5819 CONTROL ROD DRIVE HYDRAULIC C1i CONTROL UNIT 58-19 2C11-D5819-125 CRD HCU SCRAM WATER ACCUMULATOR Cli 2Cll-D5819-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5819-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D5823 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 58-23 2Cll-D5823-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5823-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5823-127 CRD HCU SCRAM OUTLET VALVE C11 2C1 1-05827 CONTROL ROD DRIVE HYDRAULIC Cli CONTROL UNIT 58-27 2C1 -D5827-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D5827-126 CRD HCU SCRAM INLET VALVE C11 2C11-D5827-127 CRD HCU SCRAM OUTLET VALVE C11 2Ci11l-D5831 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 58-31 2C1 1-D5831-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D5831-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5831-127 CRD HCU SCRAM OUTLET VALVE CI 1 2C11-D5835 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 58-35 2C1 1-D5835-125 CRD HCU SCRAM WATER ACCUMULATOR C11 2C11-D5835-126 CRD HCU SCRAM INLET VALVE C11 2C1l-D5835-127 CRD HCU SCRAM OUTLET VALVE Cl1 2C1 1-D5839 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 58-39 2C11-D5839-125 CRD HCU SCRAM WATER ACCUMULATOR Cll 2C11-D5839-126 CRD HCU SCRAM INLET VALVE Cll 2C11-D5839-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-D5843 CONTROL ROD DRIVE HYDRAULIC Cii CONTROL UNIT 58-43 2C11-D5843-125 CRD HCU SCRAM WATER ACCUMULATOR Cii 2C11-D5843-126 CRD HCU SCRAM INLET VALVE C11 Table B-i a Page 32 of 54 B-34

12Q.108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2C11-D5843-127 CRD HCU SCRAM OUTLET VALVE Cll 2C11-F380 VALVE, AIR SCRAM DISH VOL VENT C11 2C11-F381 SCRAM DSCH VOLUME DRN VLV (ABOVE C11 RB 20 D 740 PERSONNEL HATCH) 2C11-F388 VALVE, AIR SCRAM DISCH VOL VENT C11 2C11-F389 VALVE, AIR SCRAM DISCH VOL VENT C11 2C41-A001 TNK STBY LIQUID CONT SOLUTION C41 RB 17 C 820 2C41-C001A SBLC PMP A C41 RB 17 C 820 2C41-C001B SBLC PMP B C41 RB 17 C 820 2C61-P001 ASSY - PANEL, REMOTE S/D INSTR C61 2CM017A SUP CHBR / DW 02 MONITOR INLET CM UPSTRM ISOL VALVE TRITIUM GRAB SAMPLE STATION INLET UPSTRM ISOL VALVE 2CM018A SUP CHBR / DW 02 MONITOR INLET CM DWNST ISOL VALVE TRITIUM GRAB SAMPLE STATION INLET DWNST ISOL VALVE 2CM019A DW HUMIDITY MONITOR A OTLT UPSTRM CM 2CM019B DW HUMIDITY MONITOR B OTLT UPSTRM CM ISOL DW HUMIDITY MONITOR A OTLT DWNSTRM ISOL 2CM020B DW HUMIDITY MONITOR B OTLT DWNST CM ISOL 2CM021 B PNL 2PL77J DW SMPL INLT STOP CM 2CM022A PNL 2PL76J DW SMPL INLT STOP CM 2CM023B PNL 2PL77J SUP POOL SMPL INLT STOP CM 2CM024A PNL 2PL76J SUP POOL INLT STOP CM 2CM025A PNL 2PL76J SMPL OTLT STOP CM 2CM026B PNL 2PL77J SMPL OTLT STOP CM 2CM027 PRI CNMT CAM SUP CHBR UPSTRM INLT CM ISOL 2CM028 PRI CNMT CAM SUP CHBR INLT DWNST CM ISOL 2CM029 PRI CNMT CAM DW UPSTRMINLT ISOL CM 2CM030 PRI CNMT CAM DW DWNST INLT ISOL CM PRI CNMT 24 POINT CAM UPSTRM INLT 2CM031 CM ISOL 2CM032 PRI CNMT 24 POINT CAM DWNST INLT CM ISOL 2CM033 PRI CNMT AIR MONITORING PNLS 2PL75J CM AND 2PL15J COM UPSTRM OUTL Table B-1 a Page 33 of 54 B-35

12Q.108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev PRI CNMT AIR MONITORING PNLS 2PL75J AND 2PL15J COM DWNST 2CM03PA PRI CNMT H2-02 POST LOCA MONITOR CM RB 17 B 761 PMP 2CM03PB PRI CNMT H2-02 POST LOCA MONITOR CM RB 17 B 761 PMP 2CM085 HRSS U-2 CNMT AIR SMPL UPSTRM STOP CM 2CM086 HRSS U-2 CNMT AIR SMPL DWNST STOP CM 2CM089 HRSS CNMT AIR SMPL PNL RTN TO U-2 CM CNMT UPSTRM STOP HRSS CNMT AIR SMPL PNL RTN TO U-2 CNMT DWNST STOP 2DC01 E ASSY - BATTERY, 250 VDC DC AB J 20-21 710 2DC02E DIV I 250 VDC DISTRIBUTION BUS 2 DC AB 20 L 710 TRIP UNIT - 221X FEED FROM 250V DC 2DC02E-2A BU 2DC BUS #2 2DCO2E-2B TRIP UNIT - 221Y FEED FROM 250V DC DC BUS #2 2DC03E 250VDC BATTERY CHARGER DC AB L 20 710 2DC05E 250VDC MCC 221X DC AB 20 L 710 2DC06E DIV I 250VDC MCC 221Y DC 2DC06E-1D TRIP UNIT - 221Y X-TIE TO 121Y DC 2DC07E ASSY - BATTERY, 125 VDC DIV-1 DC 2DC08E DIV I 125VDC DISTRIBUTION BUS 2A DC AB 710 2DCO8E-3A TRIP UNIT - 125VDC DISTRIBUTION PANEL DC 2DC1OE (211X) FEED 2DCO8E-3B TRIP UNIT-211Y FEED FROM 125V D-1 DC BUS 2A 2DC09E DIV I 125VDC BATTERY CHARGER (2AA)

DC 2DC10E 125VDC DISTRIBUTION PANEL 211X DC AB 18 L 710 2DC11E DIV I 125VDC DISTRIBUTION PANEL 211Y DC AB 18 L 710 2DC12E 125VDC DISTRIBUTION PANEL 212X DC AB 18 L 731 2DC13E DIV II 125VDC DISTRIBUTION PANEL 212Y DC AB 18 L 731 2DC14E ASSY - BATTERY, 125 VDC DIV-2 DC AB 17 L 731 2DC15E DIV II 125VDC DISTRIBUTION BUS 2B DC AB 18 L 731 TRIP UNIT - 125VDC DISTRIBUTION PANEL 2DC15E-3A DC 2DC12E (212X) FEED 2DCI5E-3B TRIP UNIT - DIV II 125VDC DISTRIBUTION DC PANEL 2DC13E (212Y) FEED 2DC16E DIV II 125VDC BATTERY CHARGER 2BB DC AB 17.5 L 731 2DC17E DIV 2 125VDC BATTERY CHARGER (2BA)

DC Table B-I a Page 34 of 54 B-36

12Qo108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2DC18E ASSY - BATTERY,DIV 3 125V DC 2DC18E 2DC18E DIV 3 BATTERY, CABLE 2DC046 DC NEGATIVE LEAD RED NEGATIVE LEAD 2DC18E 2DC18E DIV 3 BATTERY, CABLE 2DC046 DC POSITIVE LEAD BLK POSITIVE LEAD DC 2DC19E DIV III 125VDC BATTERY CHARGER DC 2DC23E DIV I 125VDC BATTERY CHARGER (2AB)

DC 2DC34E BATTERY 24 VDC 2D DC AB 19 N 749 2DC39E 48/24VDC DISTRIBUTION PANEL 2A DC AB 17 L 749 2DG01 I 2A DG COOLING WTR STRNR BACKWASH DG DG 21 J 674 OTLT 2DG01A 2A DG COOLER DG DG J 22 710 2DG01D SILENCER, DG ENGINE DG 2DG01F 2A DG COOLING WATER STRAINER DG DG C 7 674 2DG01K 2A DIESEL GENERATOR DG DG J 22 710 2DG01 K-A PUMP, AC TURBO SOAKBACK (B7A)

DG 2DG01K-B PUMP, DC TURBO SOAKBACK DG 2DG01 K-C PUMP, AC LUBE OIL CIRC (B7)

DG 2DG01K-D PUMP, SCAVENGING OIL DG 2DG01K-E FILTER, TURBOCHARGER OIL DG 2DG01K-G PUMP, RIGHT BANK WTR DG 2DG01 K-H PUMP, LEFT BANK WTR DG 2DG01 K-I PUMP, MAIN LUBE OIL DG 2DG01K-J PUMP, PISTON COOL DG 2DG01 K-K PUMP, ENGINE DRIVEN FUEL DG 2DG01K-L PUMP, ELECT MTR DRIVEN FUEL DG 2DG01 K-N HEAT EXCHANGER, DG COOLING WTR DG 2DG01P 2A DG COOLING WATER PUMP DG RB 21 J 674 2A DG STARTING AIR COMPRESSOR 2DG01S PCAEDG DG.

J 22 710 PACKAGE 2DG02F FILTER/SILENCER, DG AIR INTAKE DG 2DG02JA 2A DG A GENERATOR CONTROL PANEL DG DG J 22 710 2DG02JB 2A DG B GENERATOR CONTROL PANEL DG 2DG032 DG 0 COOLING WTR FROM U2 VY/LP DG RB 20 D 694 COOLERS OTLT STOP 2DG034 2A DG COOLER INLET HEADER RELIEF DG VALVE 2DG035 LPCS PMP MOTOR COOLER INLT UPSTRM DG RB 20 B 694 STOP 2DG03J 2A DG ENGINE CONTROL PANEL DG DG J 22 710 2DG04J 2A DG TRANSFORMER PANEL DG 2DG055A 2A DG A STARTING AIR RECEIVER DG RELIEF VALVE 2A DG B STARTING AIR RECEIVER I

_2DG055B

_RELIEF VALVE DG Table B-I a Page 35 of 54 B-37

12Q.108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor T

Equipment Name Buildingle 2A DG A/C STARTING AIR MOTORS 2DG061A SUPPLY CONTROL VALVE DG DG 22 J 710 2DG061 B 2A DG BID STARTING AIR MOTORS DG SUPPLY CONTROL VALVE 2DG062A 2A DG A/C STARTING AIR MOTORS DG PINION SUPPLY SOLENOID VALVE 2A DG B/D STARTING AIR MOTORS PINION SUPPLY SOLENOID VALVE 2DG08TA 2A DG A STARTING AIR RECEIVER DG 2DG08TB 2A DG B STARTING AIR RECEIVER DG 2DG10TA ACCUMULATOR, DG AIR START DG 2DG10TB ACCUMULATOR, DG AIR START DG 2DG15MA 2A DG A STARTING AIR STRAINER DG 2DG15MB 2A DG B STARTING AIR STRAINER DG 2DG23M 2B DG LUBE OIL SOAK BACK PUMPS DG DSCH STRAINER 2B DG LUBE OIL CIRC PUMP DSCH 2DG24M DG STRAINER 2DG25M 2A DG LUBE OIL SOAK BACK PUMPS DG DSCH STRAINER 2DG26M 2A DG LUBE OIL CIRC PUMP DSCH DG STRAINER 2DO001T DG 2A FUEL STGE TK DO 2DO002P PUMP, DIESEL OILTRANSFER DO 2DO002T DG 2B FUEL STORAE TANK DO 2DO004T DG 2B DAY TK DO 2DO005T DG 2A DAY TK DO DG J 22 710 2DO01P PUMP, DIESEL OILTRANSFER DO DG 674 2DO01P 2A DG FUEL TRANSFER PUMP DO 2DO01T 2A DG FUEL STORAGE TANK DO 2DO024 UNIT 2 DFP FUEL OIL XFR SOL SUCT VLV DO 2DO02P 2B DG FUEL TRANSFER PUMP DO AB 22 L 674 2DO02T 2B DG FUEL STORAGE TANK DO 2DO04T 2B DG DAY TANK DO 2DO05T 2A DG DAY TANK DO 2DO09M STRNR SUCT STRG TNK DO 2DO10M STRNR SUCT FUEL STRG TNK DO 2D024M Y TYPE STRNR 150# C.S. BODY #20 MESH DO S.S.

Y TYPE STRNR 150# C.S. BODY #20S.S.

2DO25M DO MESH 2E12-B001A 2A RHR HEAT EXCH E12 2E12-B001B 2B RHR HEAT EXCH E12 RB B 15 710 2E12-C002A 2A RESIDUAL HEAT REMOVAL PMP E12 RB 21 G 673 2E12-C002B 2B RESIDUAL HEAT REMOVAL PMP E12 RB 15 C 673 2E12-C002C 2C RESIDUAL HEAT REMOVAL PMP E12 RB 16 B 673 Table B-I a Page 36 of 54 B-38

12QO108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2E12-C003 RHR B/C WTR LEG PMP 2E12-C003 E12 2E12-C300A A RHR SERVICE WATER PUMP E12 AB 24 R 674 2E12-C300B B RHR SERVICE WATER PUMP E12 DG 22.2 N/R 674 2E12-C300C C RHR SERVICE WATER PUMP E12 2E12-C300D D RHR SERVICE WATER PUMP E12 2E12-D300A A RHR SERVICE WATER STRAINER E12 2E12-D300B B RHR SERVICE WATER STRAINER E12 DG 21.5 J-H 674 2E12-D3O1A 2A RHR SUPPRESSION POOL SUCTION E12 STRAINER 2E12-D301B 2B RHR SUPPRESSION POOL SUCTION E12 STRAINER 2C RHR SUPPRESSION POOL SUCTION 2E12-D301C STANRE12 STRAINER CHMBR_1 2E12-D314A CONDENSING CHAMBER E12 2E12-D314B CONDENSING CHAMBER E12 2E12-D315A CONDENSING CHAMBER E12 2E12-D315B CONDENSING CHAMBER E12 2E12-D322A PULSATION DAMPENER E12 2E12-D322B PULSATION DAMPENER E12 2E12-D322C PULSATON DAMPENER E12 2E12-D322D PULSATION DAMPENER E12 2E12-D323A PULSATION DAMPENER E12 2E12-D323B PULSATION DAMPENER E12 2E12-D323C PULSATION DAMPENER E12 2E12-D323D PULSATION DAMPENER E12 2E12-F003A A RHR HX OTLT STOP E12 RB 20 H 694 2E12-F003B B RHR HX OTLT STOP E12 RB 16 B 694 2E12-F004A A RHR PMP SUCT FROM SUP POOLSTOP E12 RB 19 G 673 2E12-F004B B RHR PMP SUCT FROM SUP POOLSTOP E12 RB 16 D 673 2E12-F004C C RHR PMP SUCT FROM SUP POOLSTOP E12 RB 16 C 673 2E12-F005 VALVE, RELIEF, RHR PP SDC SUCT LINE E12 A RHR PMP SUCT FROM S/D COOLING 2E12-F006A E12 STOP 2E12-OO6B B RHR PMP SUCT FROM S/D COOLING E1 2E12-F008 RHR S/D COOLING SUCT. HDR OTBD ISOL E12 STOP 2E12-F009 RHR S/D COOLING SUCT. HDR INBD ISOL E12 DW 17 D 740 STOP -220' 2E12-F011A A RHR HX STM COND TO SUP CHBR STOP E12 RB 20 H 694 2E12-F011B BRHRHXSTMCONDTOSUPCHBRSTOP E12 RB 16 A 694 Table B-I a Page 37 of 54 B-39

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2E12-F016A A RHR CONT SPRAY UPSTRM ISOL STOP E12 RB 20 D 761 2E12-F016B B RHR CONT SPRAY UPSTRM ISOL STOP E12 RB 18 H 761 2E12-F017A A RHR CONT SPRAY DWNST ISOL STOP E12 RB 20 D 761 2E12-F017B B RHR CONT SPRAY DWNST ISOL STOP E12 RB 18 H 761 2E12-F021 C RHR PMP FULL FLOW TEST STOP E12 RB 15 G 740 2E12-F023 RHR HX HEAD SPRAY DSCH HDR ISOL E12 RB 20 H 740 STOP 2E12-F024A A RHR PMP FULL FLOW TEST STOP E12 RB 20 G 710 2E12-F024B B RHR PMP FULL FLOWTEST STOP E12 RB 16 B 710 2E12-F025A VALVE, RHR A PP DISCH RELIEF E12 2E12-F025B VALVE, RHR B PP DISCH RELIEF E12 2E12-F025C VALVE, RHR C PP DISCH RELIEF E12 2A RHR HX STM COND OTLT TO RCIC 2E12-F026A E12 RB 20 H 694 STOP 2E12-F026B BRHRHXSTMCONDOTLTTORCIC E12 RB 16 A 694 STOP 2E12-F027A A RHR SUP CHBR SPRAY ISOL VALVE E12 RB 20 H 710 2E12-F027B B RHR SUP CHBR SPRAY ISOL STOP E12 RB 16 B 731 2E12-F030 VALVE, RHR LINE 2RH05A S-POOL RELIEF E12 2E12-F036A VALVE, RHR RI PP SUCT LINE RELIEF E12 2E12-F036B VALVE, RHR RI PP SUCT LINE RELIEF E12 RB 20 C 694 2E12-FO4OA A RHR HX BD DWNST ISOL TO RBEDT E12 RB 20 H 694 STOP 2E12-FO4OB B RHR HX BD DWNST ISOL TO RBEDT E12 R

2E12-F041STOP2 RB 16 A 694 2E12-F041A A RHR INJ. TEST CHK. -150' E12 DW 19 D 777 2E12-F042A A RHR LPCI INJECTION LINE STOP E12 RB 19 A 761 2E12-F042B B RHR LPCI INJECTION LINE STOP E12 RB 18 H 761 2E12-F042C C RHR LPCI INJECTION LINE STOP E12 RB 18 H 761 2E12-F047A A RHR HX INLT STOP E12 RB 20 H 710 2E12-F047B B RHR HX INLT STOP E12 RB 16 C 710 2E12-F048A A RHR HX BYP STOP E12 RB 20 G 710 2E12-F048B B RHR HX BYP STOP E12 RB 15 B 694 2E12-F049A A RHR HX BD UPSTRM ISOL TO RBEDT E12 RB 20 H 694 2E12-F049B B RHR HX BD UPSTRM ISOL TO RBEDT E12 RB 15 B 694 2E12-F051A A RHR HX STM INLT PRESS CONT VLV E12 2E12-FO51B B RHR HX STM INLT PRESS CONT VLV E12 RB 15 B 710 2E12-F052A A RHR HX STM INLT STOP E12 RB 20 H 710 2E12-F052B B RHR HX STM INLT STOP E12 RB 15 B 710 2E12-F053A A RHR S/D COOLING DSCH ISOL STOP E12 2E12-F053B B RHR S/D COOLING DSCH ISOL STOP -

E12 RB 15 R 740

_ROOM BY EQUIP HATCH Table B-1 a Page 38 of 54 B-40

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2E12-F055A VALVE, RI DISCH LINE RELIEF E12 2E12-F055B VALVE, RI DISCH LINE RELIEF E12 RB 710 2E12-F060A A RHR HX OTLT PROCESS SMPL UPSTRM E12 STOP 2E12-FO6OB B RHR HX OTLT PROCESS SMPL UPSTRM E12 STOP 2E12-F064A "A" RHR PMP MINIMUM FLOW BYP STOP E12 RB 20 G 663 2E12-F064B B RHR PMP MIN FLOW BYP STOP E12 RB 15 C 673 2E12-F064C C RHR PMP MINIMUM FLOW BYP STOP E12 RB 16 B 673 2E12-F065A A RHR HX STM COND OTLT STOP (LEVEL E12 CONT) 2E12-F065B B RHR HX STM COND OTLT (LEVEL CONT E12 M/A STATION) 2E12-F068A A RHR HEAT EXCH OTLT E12 "RB 19 A 673 2E12-F068B B RHR HEAT EXCH OTLT STOP VLV E12 RB 16 A 673 2E12-F073A A RHR HX SHELL SIDE VENT DWNST E12 RB 20 G 710 STOP 2E12-F073B B RHR HX SHELL SIDE VENT DWNST E12 RB 15 A 710 STOP 2E12-F074A A RHR HX SHELL SIDE VENT UPSTRM E12 RB 20 H 710 STOP 2E12-F074B B RHR HX SHELL SIDE VENT UPSTRM E12 RB 15 B 710 STOP 2E12-F075A A RHR HX OTLT PROCESS SMPL DWNST E12 STOP 2E12-F075B B RHR HX OTLT PROCESS SMPL DWNST E12 STOP 2E12-F087A A RHR HX STM INLT PCV BYP STOP E12 RB 20 H 710 2E12-F087B B RHR HX STM INLT PCV BYP STOP E12 RB 15 B 710 2E12-F088A VALVE, RHR PP A SUCT S-POOL RELIEF E12 2E12-F088B VALVE, RHR PP B SUCT S-POOL RELIEF E12 2E12-F088C VALVE, RHR PP C SUCT S-POOL RELIEF E12 SPLY FROM FUEL POOL EMER MU PMP 2E12-F093 DWS TPE12 RB 15 C 694 DWNST STOP____

2E12-F094 SPLY FROM FUEL POOL EMER MU PMP E12 RB 15 C 694 UPSTRM STOP 2E12-F097 VALVE, XTIE VENT E12 A RHR SHTDN COOLING LOOP TESTABLE 2E12-F099A C

YSTP-0'E12 DW 19 E 740

___________CK BYP STOP -100'____

2E12-F099B B RHR SHTDN COOLING LOOP TESTABLE E12 DW 17 D 740 CK BYP VLV -230' 2E12-F311A A RHR HX SHELL SIDE RELIEF VALVE E12 2E12-F311B B RHR HX SHELL SIDE RELIEF VALVE E12 Table B-i a Page 39 of 54 B-41

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Ta Equipment Name Code Building No Elev 2E12-F312A A RHR HX OTLT TO U-1 H2 RECOMBINER E12 RB 20 H 710 MO STOP 2E12-F312B B RHR HX OTLT TO U-2 H2 RECOMBINER E12 RB 16 B 710 MO STOP 2E12-F313A VALVE, RHR HX CHANNEL RELIEF E12 2E12-F313B VALVE, RHR HX CHANNEL RELIEF E12 A SERVICE WTR STRNR BACKWASH 2E12-F336A E12 STOP 2E12-F336B B SERVICE WTR STRNR BACKWASH E12 STOP 2E12-F460 SHUTDOWN COOLING SUCTION RELIEF E12 VALVE 2E12-N005A RHR HE 2A SERV WTR DISCH TEMP E12 2E12-N005B RHR HE 2B SERV WTR DISCH TEMP E12 RB A 16 694 2E12-N007A RHR HE 2A SERV WTR INLET FLOW E12 2E12-N007B RHR HE 2B SERV WTR INLET FLOW E12 RB B 15 673 2E12-N015A RHR FLOW 2A E12 2E12-N015B RHR FLOW2B E12 RB B 15 673 2E12-N015C RHR FLOW 2C E12 2E12-N027A RHR HE 2A DISCH TO RX VESSEL TEMP E12 2E12-N027B RHR HE 2B DISCH TO RX VESSEL TEMP E12 RB A 15 673 2E12-N034A RHR PUMP 2A DISCH PRESSURE E12 2E12-N034B RHR PUMP 2B DISCH PRESSURE E12 RB B 15 673 2E12-N034C RHR PUMP 2C DISCH PRESSURE E12 2E12-N510 RHR HEAT EXCHANGER 2A EFFLUENT E12 2E12-N511 RHR HX B EFFLUENT E12 2E21-CO01 PMP LO PRESS CORE SPRAY E21 RB 20 B 673 2E21-C002 PMP LO PRESS CORE SPRAY WTR LEG E21 RB 20 B 673 2E21-D302 SUCTION STRAINER E21 2E21-F001 LPCS PMP SUCT STOP E21 RB 20 B 673 2E21-F005 LPCS INJECTION VLV E21 RB 20 D 761 2E21-F011 LPCS MINIMUM FLOW BYP STOP E21 RB 20 B 673 2E21-F012 LPCS PMP FULL FLOW TEST VLV E21 RB 19 A 710 2E21-F018 VALVE, LPCS PP DISCH TO S-POOL E21 RELIEF 2E21-F031 VALVE, LPCS PP SUCTION S-POOL RELIEF E21 2E21-N003 LPCS PP DISCH FLOW XMITTER E21 RB 20 A 673 2E22-CO01 PMP HI PRESS CORE SPRAY E22 RB 15 F 673 2E22-C002 HPCS DIESEL COOL WATER PUMP E22 2E22-C003 HI PRESS CORE SPRAY WTR LEG PMP E22 RB 15 F 673 2E22-D300 2B DG COOLING WATER STRAINER E22 2E22-D302 STRAINER, SUCTION HPCS E22 2E22-D315 FILTER, INTAKE E22 I Table B-la Page 40 of 54 B-42

12..108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2E22-D317A 2B DG A STARTING AIR STRAINER E22 2E22-D317B 2B DG B STARTING AIR STRAINER E22 2E22-F004 HPCS INJECTION ISOL VALVE E22 RB 16 C 761 2E22-F010 HPCS TEST DSCH TO CST UPSTRM STOP E22 DECLUTCH LEVER 2E22-F012 HPCS PUMP MIN FLOW ISOL VALVE E22.

RB 16 G 673 2E22-F014 HPCS PUMP SUCT RELIEF VALVE E22 2E22-F015 HPCS PUMP SUP POOL SUCT ISOL VALVE E22 RB 16 D 673 2E22-F023 HPCS FULL FLOW TEST ISOL VALVE E22 RB 16 E 694 2E22-F035 HPCS PUMP DSCH RELIEF VALVE E22 2B DG COOLING WATER STRAINER BACKWASH VALVE 2E22-F345 2B DG COOLER INLET HEADER RELIEF E22 VALVE 2E22-F369A 2B DG A STARTING AIR RECEIVER E22 RELIEF VALVE 22B DG B STARTING AIR RECEIVER 2E22-F369B REIFVLEE22 RELIEF VALVE 2E22-F370A 2B DG C STARTING AIR RECEIVER E22 RELIEF VALVE 2E22-F370B 2B DG D STARTING AIR RECEIVER E22 RELIEF VALVE 2B DG A/C STARTING AIR MOTORS SUPPLY CONTROL VALVE 2E22-F381 B 2B DG B/DSTARTING AIR MOTORS E22 SUPPLY CONTROL VALVE 2E22-F382A 2B DG A/C STARTING AIR MOTORS E22 PINION SUPPLY SOLENOID VALVE 2E22-F382B 2B DG B/D STARTING AIR MOTORS E22 PINION SUPPLY SOLENOID VALVE 2E22-K001 HPCS DG AMPS E22 2E22-N004 HPCS PP DISCH PRESS XMITTER E22 RB 15 F 673 2E22-N005 HPCS PP DISCH FLOW XMITTER E22 RB 15 F 693 2E22-N530 2B DG SOAK BACK LUBE OIL PRESS E22 2B DG GROUNDING TRANSFORMERS AND BUS 213 DISTRIBUTION PANEL 2E22-P301B 2B DG AUXILIARY CONTROL PANEL E22 AB 22 N 710 2E22-T302A 2B DG A STARTING AIR RECEIVER E22 DG 710 2E22-T302B 2B DG B STARTING AIR RECEIVER E22 DG 710 2E22-T302D 2B DG D STARTING AIR RECEIVER E22 DG 710 2E32-C001 ASSY - BLOWER, MSIV LCS UPSTREAM E32 EXH CASSY - BLOWER, MSIV LCS DWNSTRM 2E32-C002B E32 EXH 2E32-CO02F ASSY - MSIV-LCS DOWNSTREAM E32 EXHAUST BLOWER Table B-1 a Page 41 of 54 B-43

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev A LINE INBD LCS UPSTRM BLEED VLV -OB 2E32-F001A E32 RB 18 J 740 MSIV ROOM 2E32-FOOI E B LINE INBD LCS UPSTRM BLEED VLV -OB E32 RB 18 J 740

__MSIV Room 2E32-FO01J C LINE INBD LCS UPSTRM BLEED VLV -OB E32 RB 18 J 740 MSIV ROOM D LINE INBD LCS UPSTRM BLEED VLV -OB 2E32-OOIN MSIV ROOME3 2E32-FO02A A LINE INBD LOS DWNST BLEED VLV -OB E32 RB 18 J 740 MSIV ROOM 2E32-FOO2E B LINE INBD LCS DWNST BLEED VLV -OB E32 RB 18 J 740 MSIV ROOM I

C LINE INBD LCS DWNST BLEED VLV -OB 2E32-F002A E32 RB 18 J 740 MSIV ROOM 2E32-FOO2N D LINE INBD LCS DWNST BLEED VLV -OB E32 RB 12 J 740 MSIV ROOM A LINE INBD LCS DEPRESSURIZATION 2E32-F VLV-STM TUNNELB 18 7

2E32-FOO3E B LINE INBD LCS DEPRESSURIZATION E32 TB 18 L 687 VLV -STM TUNNEL 2E32-FOO3J C LINE INBD LCS DEPRESSURIZATION E32 TB 18 L 687 VLV -STM TUNNEL D LINE INBD LCS DEPRESSURIZATION 2E32-F003NEL-TMTNE E32 TB 18 L 687 VLV -STM TUNNEL 2E32-F006 OTBD LOS UPSTRM BLEED STOP-OB MSIV E32 RB 18 J 740 ROOM 2E32-FOO7 OTBD LOS DWNST BLEED STOP -OB MSIV E3 B

1J 74 2E32-F003J E32 RB 18 J 674 ROOM TUNNEL 2E32-F008 OTBD LOS UPSTRM DEPRESSURIZATION E32 RB 18 J 740 VLV -OB MSIV ROOM 2E32-F009 OTBD LOS DWNST DEPRESSURIZATION E32 RB 18 J 740 VLV -OB MSIV ROOM 2E51 -0001 RX CORE ISOL COOLING PMP E51 RB A-B 20-21 673 2E51 -03 PMP ROIC DWNTR LEG E51 RB 20 C 694 2E51-F004 VALVE, COND PP DISCH ISOL I/O E51 2E51 -F005 VALVE, COND PP DISCH ISOL 0/B E51 2E51-F0078 RIC STM SPLY OTBD ISOL E51 RB 19 B 740 2E51-FOIO ROIC PMP SUOT FROM O.S.T. DWNST E51 RB 20 B 694 STOP 2E51-F013 ROIC INJECTION STOP E51 RB 19 H 740 2E51-F015 VLV 2 IN AO CONT E51 2E51-F017 VALVE, RELIEF RI PP SUCT TO 2RE08 E51 RELIEF 2E51-7019 ROIC MINIMUM FLOW BYP STOP E51 RB 20-A 673 2E51-F022 RCIC FULL FLOW TEST UPSTRM STOP E51 RB 1

Table B-l a Page 42 of 54 B-44

12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component E

System Column Floor Tag Equipment Name Code Building No Elev 2E51-F02.5 RCIC STM SPLY DRN POT OTLT UPSTRM E51 RB 20 A 673 STOP RCIC STM SPLY DRN POT OTLT DWNST 2E51 -F026 STPE51 RB 20 A 673 STOP 2E51-F031 RCIC PMP SUCT FROM SUP POOL STOP E51 RB 19 C 673 2E51-F045 RCIC TURB STM SPLY STOP E51 RB 20 A 673 2E51-F046 RCIC TURB LUBE OIL COOLER INLT STOP E51 2E51-F059 RCIC FULL FLOW TEST DWNST STOP E51 RB 20 B 694 2E51-F063 STM SPLY INBD ISOL E51 DW 19 D 777 2E51-F064 RCIC STM INLT TO RHR HEAT EXCH E51 RB 19 B 740 2E51-F065 RCIC INJECTION OTBD TESTABLE CK E51 RB 19 G 740 2E51-F066 RCIC INJECTION INBD TESTABLE CK E51 DW 13 D 807 2E51-F068 RCIC TURB EXH ISOL IN RACEWAY E51 RB 20 694 2E51-F069 RCIC BARO CNDSR VAC PMP DSCH STOP E51 RB 20 C 704 2E51-F076 IRCIC STM SPLY INBD ISOL VLV WARM UP E61 BYP 2E51-F080 RCIC TURB EXH VAC BKR DWNST STOP E51 RB 19 B 706 2E51-F086 RCIC TURB EXH VAC BKR UPSTRM STOP E51 RB 20 D 704 VALVE, RI STM SUPPLY BYP TO RHR HX-2E51-F091 DO NOT USE! THIS VALVE HAS BEEN E51 RB 19 B 740 REMOVED. DO NOT USE!

2E51-F374 GATE VALVE E51 2E51-F375 GATE VALVE E51 2E51-N004 RI PP DISCH PRESS XMITTER E51 2FI-HG022 H2 RECOMBINER IN GAS FLOW HG 2FI-HG023 H2 RECOMBINER TOTAL GAS INLET FLOW HG IND 2FT-HG022 H2 RECOMBINER IN GAS FLOW XMITTER HG H2 RECOMBINER TOTAL GAS INLET FLOW 2FT-HG023 HG XMITT 2G33-F001 RWCU INBD ISOL VLV G33 DW 17 F 740 2G33-F004 RWCU OTBD ISOL VLV G33 RB 19 G 774 2G33-F040 RWCU DSCH HDR STOP OB MSIV ROOM G33 RB 18 J 740 2G33-F1 00 RWCU SUCT STOP FROM "A" RECIRC G33 DW 19 D 740 LINE 2H13-P601 ASSY - PANEL, EMERG CORE COOL SYST H13 MCR 2H13-P602 ASSY - PANEL, RWCU/RX RECIRC H13 MCR CONTROL 2H13-P603 ASSY - PANEL, RX CONTROL H13 Table B-I a Page 43 of 54 B-45

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2H13-P608 ASSY - CABINET, POWER RANGE H13 NEUTRON MONITOR 2H22-P001 ASSY - PANEL, LPCS INSTR RACK H22 RB 673 2H22-P002 ASSY_-_PANEL, RWCU SYST INSTR RACK H22 RB 761 2H22-P004 ASSY_-_PANEL, A RX LEVEL/PRESSURE H22 RB 761 2H22-P005 ASSY_-_PANEL, C RX LEVEL/PRESSURE H22 RB 761 2H22-P006 ASSY_-_PANEL, RR PP A LOCAL H22 RB 710 CONTROL 2H22-P007 CRD & RX VESSEL TEMP RECORDR PNL H22 CR 768 2H22-P009 ASSY -_PANEL, B JET PP INSTR H22 RB 710 2H22-PO10 ASSY - PANEL, A JET PP INSTR H22 RB 20 F 710 2H22-P015 ASSY_-_PANEL, A MAIN STEAM FLOW H22 RB 710 INSTR 2H22-P017 ASSY - PANEL, A RI INSTR H22 RB 673 2H22-P018 ASSY - PANEL, A RHR INSTR H22 RB 673 2H22-P021 ASSY_- PANEL, B/C RHR INSTR H22 RB 673 2H22-P022 ASSY - PANEL, RR PP B LOCAL CONTROL H22 2H22-P024 ASSY -_PANEL, HPCS LOCAL INSTR H22 RB 673 2H22-P025 ASSY_-_PANEL, D MAIN STEAM FLOW H22 RB 710 INSTR 2H22-P026 ASSY - PANEL, D RX LEVEL/PRESSURE H22 LOCAL 2H22-P027 ASSY_-_PANEL, B RX LEVEL/PRESSURE H22 RB 761 LOCAL 2H22-P028 2B DG PROTECTION RELAY CABINET H22 2H22-P029 ASSY - PANEL, B RI LOCAL INSTR H22 RB 673 2H22-P030 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 17 G 740 ENCLOSURE A-1 2H22-P031 SRM / IRM PREAMPLIFIER PANEL B H22 RB 16 D 740 2H22-P032 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 19 C 740 ENCLOSURE A-2 2H22-P033 ASSY_-_PANEL, SRM/IRM PREAMP H22 RB 19 G 740 ENCLOSURE B-2 2H22-P073 ASSY - PANEL, MSIV LEAKAGE CONTROL H22 DIV-1 2H22-P074 ASSY_- _PANEL, MSIV LEAKAGE CONTROL H22 RB 673 DIV-2 2H22-P075 ASSY - PANEL, LLS/SRV DIV-2 INSTR H22 RACK 2H22-P076 ASSY - PANEL, LLS/SRV DIV-2 INSTR H22

_RACK I

I Table B-i a Page 44 of 54 B-46

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name No Elev 2HGT01A H2 RECOMB 2HG1A U-2 DW SUCT. VLV HG RB 20 E 786 2HG001 B H2 RECOMB 1 HG01A U-2 DW SUCT VLV HG RB 20 E 786 2HG002A H2 RECOMB 2HG01A U-2 DW SUCT VLV HG RB 20 E 786 2HG002B H2 RECOMB 2HG01A U-2 DW SUCT VLV HG RB 20 E 786 2HG003 UNIT 2 SUP POOL RTN ISO HG RB 16 B 740 H2 RECOMB 2HG01A U-2 SUP POOL DIS 2HGO05A HG RB 15 B 710 VLV-OVH D AT 210' 2HGO05B H2 RECOMB 11HGOIA U-2 SUP POOL DIS HG RB 17 B 710

__VLV H2 RECOMB 2HG01A U-2 SUP POOL DIS 2HGO06A HG RB 15 B 710 VLV-OVHD AT 210' 2HGO06B H2 RECOMB 2HGO1A U-2 SUP POOL DIS HG RB 17 B 710 VLV 2HG009 U-1 SUP POOL RTN ISOL HG 2HG018 U-1 CLG WTR X-TIE ISOL HG RB 16 B 740 2HG01A ASSY - BLOWER, H2 RECOMBINER HG RB 16 B 786 2HG025 ASSY - VALVE, HG 2HG026 ASSY - VALVE, HG 2HG027 LOCAL HY RECOMBINER WTR INLT VLV HG RB 16 A 761 2HT01E H2/02 MON HEAT TRACE PNL HT AB 710 2HT02E H2/02 MON HEAT TRACE PNL HT AB 731 21NO01A DWSUCT UPSTRM ISOL IN RB 19 C 761 21NO01B DWSUCT DWNST ISOL IN RB 19 B 761 21N017 DW PNEUMATIC TO DW IN RB 19 B 761 21N02HA ADS N2 EMERG PRESSURIZATION IN BOTTLE STORAGE RACK NORTH ADS N2 EMERG PRESSIZATION BOTTLE STORAGE BANK STORAGE RACK 21N031 DW PNEUMATIC TIP INDEXER PURGE IN 21N045 VALVE, N2 STORAGE MANIFOLD RELIEF IN 21N046 VALVE, ADS SUPPLY RELIEF IN 21N074 DW PNEUMATIC DRYER PURGE OTLT IN RB 19 B 761 21N075 DW PNEUMATIC DRYER PURGE OTLT IN RB 19 B 761 21N100 S SIDE N2 TO DW ISOL VLV IN 21N101 N SIDE N2 TO DW ISOL VLV IN 2PA05J TRANSDUCER & SENPOWER SUPPLY CAB PA AB 15 L 731 2PA07J ASSY - CABINET, TURB SUPERVISORY PA AB 15 N 731 2PA12J ASSY - PANEL, H2 RECOMBINER PA CONTROL 2PA13J ASSY - CABINET, NSSS ISOL LOGIC AUX PA AB 731 RELAY DIV-1 2PA14J ASSY_-_CABINET, NSSS ISOL LOGIC AUX PA AB 731

_RELAY DIV-2 I

Table B-la Page 45 of 54 B-47

12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2PA17J STANDBY GAS TREATMENT PANEL PA 2PI-DG055A 2A DG LUBE OIL FILTER PRESS DG 2PI-DG055B 2A DG LUBE OIL FILTER PRESS DG 2PI-DG056 2A DG MAIN LUBE OIL PRESS DG 2PI-DG057A 2A DG FUEL OIL PRESS DG 2PI-DG057B 2A DG FUEL OIL PRESS DG 2PI-DG059 2A DG FUEL OIL PRESS DG 2PI-DG060A 2A DG FUEL OIL PRESS DG 2PI-DG060B 2A DG FUEL OIL PRESS DG 2PI-DG063 2A DG ENGINE COOLING WATER PRESS DG 2PI-DG086 2A DG SCAVENGING AIR PRESS DG 2PI-DG094 2A DG A AIR RECEIVER PRESS DG DG J 22 710 2PI-DG095 2A DG B AIR RECEIVER DG 2PI-DG098A 2A DG A BANK STARTER AIR SUPPLY DG PRESS IND 2PI-DG098B 2A DG B BANK STARTER AIR SUPPLY DG 2PI-DG121 2A DG SOAK BACK LUBE OIL PRESS DG 2PI-DG122 2A DG CRANKCASE PRESS DG 2PL17J ASSY - PANEL, STANDBY GAS PL TREATMENT CONTROL 2PL24J ASSY - PANEL, DG ROOM VENT SYST DIV-PL 3

2PL25J ASSY - PANEL, DG ROOM VENT SYST DIV-PL 2

2PL27JA ASSY - PANEL, REACTOR BUILDING PL VENTILATION DIV-2PL27JB ASSY - PANEL, REACTOR BUILDING PL VENTILATION DIV-2PL28J ASSY.-.PANEL, VT PL AB 20 L 815 2PL29J ASSY - PANEL, SWGR HEAT RMVL DIV-1 PL 2PL30J ASSY - PANEL, SWGR HEAT RMVL DIV-2 PL 2PL31J ASSY - PANEL, M/G SET ROOM VENT PL 2PL32J ASSY - PANEL, HPCS CUBE VENT PL 2PL33J ASSY - PANEL, RHR B/C CUBE VENT PL RB B 17 687 2PL34J ASSY - PANEL, RHR A CUBE VENT PL RB 19 H 694 2PL35J ASSY - PANEL, LPCS CUBE VENT PL RB 19 A 694 2PL72J ASSY _-_PANEL, P/C VENT HVAC PL RB 20 C 740 2PL73J ASSY - PANEL, RHR SERV WTR PP A/B PL ROOM VENT 2PL74J ASSY - PANEL, RHR SERV WTR PP C/D PL ROOM VENT 2PL76J ASSY - PANEL, A P/C HYDROGEN/OXYGEN PL MONITORING 2PL77J ASSY_-_PANEL, B P/C PL RB 761 1____

1HYDROGEN/OXYGEN MONITORING P

R 7

2PL86J ASSY - PANEL, RX BLDG HEATING PL Table B-1 a Page 46 of 54 B-48

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2PLF3J ASSY - PANEL, HYDORGEN RECOMBINER PL LOCAL 2PLF5J ASSY_-_CABINET, S-POOL TEMP MONIT PL RB 761 POWER SUPPLY 2PLF6J ASSY_-_CABINET, S-POOL TEMP MONIT PL RB 761 POWER SUPPLY 2PLGIJ ASSY - PANEL, CONT MONIT VLV AUX PL RELAY DIV-1 2PLG2J ASSY - PANEL, CONT MONIT VLV AUX PL RELAY DIV-2 2PLG3J ASSY - CABINET, ISOLATOR-DEMOD PL AB 17 N 749 2PLH2J INSTRUMENT PANEL PL 2PLH6J PANEL, COND BOOSTER PUMP MIN FLOW PL CONTROL 2PM01J ASSY - PANEL, ELECT CONTROL PM 2PM03J ASSY_-_PANEL, PM AB 16 L 768 FEEDWATER/CONDENSATE 2PM05J ASSY - PANEL, HVAC CONSOLE PM 2PM06J ASSY - PANEL, HVAC CONSOLE PM 2PM07J ASSY - PANEL, STANDBY GAS PM TREATMENT SYST 2PM13J ASSY - PANEL, CONTAIN MONITOR/LEAK PM DETECTION 2PM16J ASSY - PANEL, P/C MONITOR/LEAK PM DETECTION 2PM18J SAFETY RELIEF VALVE POSITION IND PNL PM 2PT-HG023 H2 RECOMBINER IN GAS PRESS XMITTER HG 2RE024 DW EQUIPT DRN INBD ISOL RE 2RE025 DW EQUIPT DRN OTBD ISOL RE 2RE026 DW EQUIPT DRN HX OTLT TO GLAND RE SEAL LEAKOFF RESERVOIR DW EQUIPT DRN HX OTLT TO GLAND SEAL LEAKOFF RESERVOIR OTBD ISOL 2RF012 DW FLR DRN INBD ISOL RF RB 17 H 710 2RF013 DW FLR DRN OTBD ISOL RF RB 17 H 710 2SI-DG028 METER, FREQUENCY 2PMOIJ A DG DG 2SI-DG067 2A DG FREQUENCY METER DG 2TE-HGO14A HYDROGEN RECOMBINER GAS INLET (TE-HG RB A 15 761 1A) 2TE-HGO14B HYDROGEN RECOMBINER GAS INLT HG SPARE(TE-1 B 2TE-HGO15SA HYDROGEN RECOMBINER BLWR INL GAS HG (TE-2A)

I I

2TE-HGO15B SPARE TC BLWR INL GAS (TE-2B)

HG I-I Table B-la Page 47 of 54 B-49

12-o108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component E

I I System Column Floor Tag Equipment Name Code Building No Elev 2TE-HG016A HYDROGEN RECOMBINER HEATER GAS HG (TE-4A) 2TE-HGO16B SPARE TC HEATER GAS (TE-4B)

HG 2TE-HGO17A HYDROGEN RECOMBINER HTRI OUTLET HG GAS (TE-5 2TE-HGO17B SPARE TC (TE-5B) HEATER GAS OUT HG 2TE-HGO1 8A HYDROGEN RECOMBINER HEATER WALL HG (TE-6A) 2TE-HGO18B SPARE TC HEATER WALL (TE-6B)

HG 2TE-HGO1 9A HYDROGEN RECOMBINER REA!C CHMBR HG GAS(TE-7A IHG 2TE-HG019B SPARE TC REAC CHMBR GAS(TE-7B HG 2TE-HGO20A H2 RECOMB REACTION CHAMBER SHELL HG (TE-8A 2TE-HGO20B SPARE TC H2 RECOMB CHMBR SHELL (TE HG 8B)

I HYDROGEN RECOMBINER RETURN GAS 2TE-HGO21A TE-9A HG 2TE-HGO21B SPARE H2 RECOMBINER RETURN GAS HG TEMP SPAR 2TE-VD003 2E22S001 ROOM TEMP CONT SENSOR VD 2TE-VD005 2E22S001 ROOM TEMP IND/ALM VD 2TE-VD008 2DG01 K ROOM MOD DMPR TEMP CONT VD 2TE-VD013 2E22S001 ROOM MOD DMPR TEMP CONT VD I

2TE-VD015 2B HPCS DG COOLING WTR PP, ROOM VD VENT RTN TEMP ELEMENT RX BLDG MG SET VENT AREA RET AIR 2TE-VX007 TMVx TEMPi 2TE-VX008 SWGR HEAT RMVL DIV-2 AREARET AIR VX 2TE-

_X008 TEMP 2TE-VX009 SWGR HEAT RMVL DIV-1 AREA RET AIR VX TEMP 2TE-VY023 RHR SER WATER PUMP A & B TEMP CONT VY 2TE-VY024 RHR SER WATER PUMP C & D TEMP VY CONT H2 RECOMBINER REACTION CHAMBER 2TIC-HG019 GAiHG GA 2TI-DG054 2A DG MAIN LUBE OIL TEMP DG 2TI-DG062 2A DG ENGINE JACKET WATER TEMP DG 2TI-VX010 RX BLDG MG SET VENT SYST TEMP/IND VX 2TI-VX01 1 SWGR HEAT RMVL DIV-2 TEMP/IND VX 2TI-VX012 SWGR HEAT RMVL DIV-1 TEMP/IND VX 2VD01OYB

DAMPER, VD Table B-I a Page 48 of 54 B-50

.2QO1.8.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2VD011YA

DAMPER, VD 2VD011YB

DAMPER, VD 2VD01C ASSY - FAN, HPCS DG ROOM VENT VD 2VD01 F DIESEL GEN ROOM VENT SPLY VD 2VD01J TIME DELAY PANEL VD AB 674 2VD01YA

DAMPER, VD 2VD01YAB DAMPER, DG ROOM VENT VD 2VD01YB

DAMPER, VD 2VD02C ASSY - FAN, HPCS DG FUEL STOR TANK VD ROOM VENT 2VD02F DIESEL GEN ROOM VENT SPLY VD 2VD02J TIME DELAY PANEL VD AB 674 2VD02YA

DAMPER, VD 2VD02YAB DAMPER, DG ROOM VENT VD 2VD02YB

DAMPER, VD 2VD03C ASSY - FAN, DG ROOM VENT SUPPLY VD 2VD03YA

DAMPER, VD 2VD03YAB DAMPER, DG ROOM VENT VD 2VD03YB

DAMPER, VD 2VD04C ASSY - FAN, DG FUEL STOR TANK ROOM VD VENT 2VD04Y DAMPER, DG ROOM VENT VD 2VD05C ASSY - FAN, HPCS DG COOL WTR PP VD ROOM VENT SUPPL 2VD05Y DAMPER, DG ROOM VENT VD 2VD06C ASSY - FAN, HPCS SWGR BATT ROOM VD EXH 2VD06Y DAMPER, DG ROOM VENT VD 2VD070 ASSY - FAN, HPCS COOLING WTR PUMP VD RM RETURN 2VD07C ASSY - FAN, HPCS DG COOL WTR PP VD ROOM RETURN 2VD07Y DAMPER, DG ROOM VENT VOD 2VD08Y DAMPER, DG ROOM VENT VD 2VD09YA

DAMPER, VD 2VD09YAB DAMPER, DG ROOM VENT VD 2VD09YB

DAMPER, VD 2VDOYAB DAMPER, DG ROOM VENT VD 2VD10YA

DAMPER, VD 2VD10YAB DAMPER, DG ROOM VENT VD 2VD10YB

DAMPER, VD 2VD11YA

DAMPER, VD 2VD11YAB DAMPER, DG ROOM VENT VD 2VD11YB

DAMPER, VD 2VD12Y DAMPER, DG ROOM VENT VD 2VD13Y DAMPER, DG ROOM VENT VD 2VD14Y DAMPER, DG ROOM VENT VD Table B-la Page 49 of 54 B-51

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2VD15Y DAMPER, DG ROOM VENT VD 2VD16Y DAMPER, DG ROOM VENT VD 2VD17Y DAMPER, DG ROOM VENT VD 2VD18Y

DAMPER, VD 2VD19Y

DAMPER, VD 2VD1YAB DAMPER, DGROOM VENT VD 2VD20Y DAMPER, DG ROOM VENT I

VD 2VD21Y DAMPER, DG ROOM VENT VD 2VD22Y DAMPER, DG ROOM VENT VD 2VD23Y DAMPER, DG ROOM VENT VD 2VD24Y DAMPER, DG ROOM VENT VD 2VD25Y DAMPER, DG ROOM VENT VD 2VD26Y DAMPER, DG ROOM VENT VD 2VD27Y DAMPER, DG ROOM VENT VD 2VD29Y DAMPER, DG ROOM VENT VD 2VD30Y DAMPER, DG ROOM VENT VD 2VD30Y DAMPER, DG ROOM VENT I

VD 2VD40Y DAMPER, DG ROOM VENT VD 2VD41Y DAMPER, DG ROOM VENT VD 2VD42Y DAMPER, DG ROOM VENT VD 2VD43Y DAMPER, DG ROOM VENT 2A DG VD 2VD44Y DAMPER, DG ROOM VENT VD 2VD45Y DAMPER, A DG VENTILATION VD 2VG001 SBGT SUCT FROM RX BLDG VG RB 16 C 820 ATMOSPHERE

__VG RB_16 C_820 2VG003 SBGT TRAIN OTLT DMPR VG RB 17 B 820 2VG01C ASSY -. FAN, STAND-BY GAS PRIMARY VG RB 17 A 820 2VG01J ASSY - PANEL, AUX RELAY VG AB*

731 2VG02C ASSY_-_FAN, STAND-BY GAS TREATMENT VG RB

-17 A 802 SYST COOL I

A PCCW DW COOLER COILS COMBINED 2VP053A

!VP RB 17 G 761 OTLT OTBD ISOL B PCCW DW COOLER COILS COMBINED 2VP053B.

OTTOBDI VP RB G

761

_______OTLT OTBD ISOL 2VP063A A PCCW DW COOLER COILS COMBINED VP

• RB 17 G 761 INLT OTBD ISOL

_i VP

_B1__6 2VP063B B PCCW DW COOLER COILS COMBINED VP RB G

761 2VP063B______ INLT OTBD ISOL

__VP RB__76 2VP113A A PCCW LOOP SPLY TO DW COOLER VP DW 17 D 761 INBDISOL VP W

7 6

B PCCW LOOP SPLY TO DW COOLER 2VP113B INDSL!I VP

.DW 17 D 761 INBD ISOL B PCCW LOOP RTN FROM DW COOLER 2VP114B INBDISOL VP DW 17 D 761 2VP197A VALVE, SAFETY RELIEF VP Table B-la Page 50 of 54 B-52

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component Equipment Name System Building Column Floor Tag Code No Elev 2VP197B VALVE, SAFETY RELIEF VP 2VP198A VALVE, SAFETY RELIEF VP 2VP198B VALVE, SAFETY RELIEF VP 2VQ026 SUP POOL VENT/PURGE FROM RXBLDG VQ RB 17 H 710 UPSTRM ISOL SUP POOL VENT/PURGE FROM RXBLDG 2VQ027 DWS SLVQ RB 17 H 710 DWNST ISOL 2VQ029 DW VENT/PURGE FROM RX BLDG VQ RB 17 H 740 UPSTRM ISOL 2VQ030 DW VENT/PURGE FROM RX BLDG DWNST VQ RB 17 H 740 ISOL 2VQ031 SUP POOL VENT/PURGE OTLT UPSTRM VQ RB 20 E 710 ISOL 2VQ032 SUP POOL VENT/PURGE OTLT UPSTRM VQ RB 20 E 710 ISOL BYP 2VQ034 DW VENT/PURGE OTLT UPSTRM ISOL VQ RB 20 E 786 2VQ035 DW VENT/PURGE OTLT UPSTRM ISOL VQ RB 20 E 786 BYP 2VQ036 DW VENT/PURGE OTLT DWNST ISOL VQ RB 20 E 786 2VQ037 PRI CNMT VENT/PURGE TO FILTUNIT VQ AB 20 L 786 UPSTRM ISOL 2VQ038 VALVE, SECONDARY CONTAINMENT VQ ISOLATION 2VQ040 SUP POOL VENT/PURGE OTLT DWNST VQ RB 20 F 710 ISOL 2VQ041 VALVE, BUTTERFLY VQ 2VQ042 DW N-2 INRTG LINE ISOL VQ RB 17 H 710 2VQ043 SUP POOL N-2 INRTG LINE ISOL VQ RB 17 H.

710 2VQ047 DW N-2 MU LINE DWNST ISOL VQ RB 17 H 740 2VQ048 DW N-2 MU LINE UPSTRM ISOL VQ RB 17 H 740 2VQ050 SUP POOL N-2 MU LINE DWNST ISOL VQ RB 17 H 710 2VQ051 SUP POOL N-2 MU LINE UPSTRM ISOL VQ RB 17 H 710 2VQ068 DW VENT/PURGE OTLT DWNST ISOL BYP VQ RB 20 F 786 2VR04YA DAMPER, VR ISOLATION VR 2VR04YB DAMPER, VR ISOLATION VR 2VR05YA DAMPER, VR ISOLATION VR 2VR05YB DAMPER, VR ISOLATION VR 2VR08Y DAMPER, 30 INCH D VR 2VR09Y DAMPER, 30 INCH D VR 2VR10Y DAMPER, 54 INCH D VR 2VR11Y DAMPER, 42 INCH D VR 2VR12Y DAMPER, 42 INCH D VR 2VR13Y DAMPER, 42 INCH D VR 2VR14Y DAMPER, 42 INCH D VR 2VR65YA DAMPER, BALANCING VR Table B-I a Page 51 of 54 B-53

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2VR65YB DAMPER, RB VENT BALANCING OPPOSED VR 2VR66Y DAMPER, BALANCING VR 2VR90Y DAMPER, HELB IN MAIN STEAM TUNNEL VR U2 VR EXHAUST PLENUM 2VR91Y RB VENT SYS EXCESS FLOW CHECK VR DAMPER 2VX01C FAN, ESS SWGR DIV-1 VENT SUPPLY VX 2VX01F FILT ESS SWITCHGEAR DIV I VENT SPLY AIR 2VX01Y DAMPER, SWGR HEAT RMVL VX 2VX02C FAN, ESS SWGR DIV-1 BATT ROOM EXH VX 2VX02F FILT ESS SWITCHGEAR DIV 2 VENT SPLY AIR 2VX02Y

DAMPER, VX 2VX03C U2 250V DC BATTERY ROOM EXAUST FAN VX 2VX03F FILT RX PROT MG SET RM 1 SPLY AIR VX 2VX03Y

DAMPER, VX 2VX04C FAN, ESS SWGR DIV-2 VENT SUPPLY VX AB J 20-21 820 2VX04Y DAMPER, SWGR HEAT RMVL VX 2VX05C FAN, ESS SWGR DIV-2 BATT ROOM EXH VX AB N 17.6 731 2VX05Y DAMPER, SWGR HEAT RMVL VX 2VX06C FAN, RX PROT MG SET ROOM 1 BATT VX ROOM EXH 2VX06Y DAMPER SWGR HEAT REMOVAL VX 2VX06YA DAMPER, SWGR HEAT RMVL VX 2VX07C FAN, RX PROT MG SET ROOM 1 VENT VX SUPPLY 2VX07Y

DAMPER, VX 2VX08C FAN, RX PROT MG SET ROOM 1 BATT VX ROOM EXH 2VX08Y DAMPER, DIV-2 SWGR HEAT RMVL VX 2VX09Y DAMPER, SWGR HEAT RMVL ISOL VX GRAVITY SHUT 2VX10Y DAMPER, SWGR HEAT RMVL VX 2VX11Y DAMPER, SWGR HEAT RMVL VX 2VX12Y DAMPER, SWGR HEAT RMVL VX 2VX14Y

DAMPER, VX 2VX15Y DAMPER, SWGR HEAT RMVL VX 2VX16Y DAMPER, SWGR HEAT RMVL VX 2VX17Y DAMPER, SWGR HEAT RMVL VX 2VX19YA

DAMPER, VX 2VX22Y DAMPER, SWGR HEAT RMVL VX 2VX26Y

DAMPER, VX 1

1 Table B-i a Page 52 of 54 B-54

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Building Column Floor Tag Equipment Name Code No Elev 2VX30Y DAMPER, SWGR HEAT RMVL VX 2VX31Y DAMPER, SWGR HEAT RMVL VX 2VX32Y DAMPER, SWGR HEAT RMVL VX 2VX33Y DAMPER, SWGR HEAT RMVL VX 2VX34Y DAMPER, SWGR HEAT RMVL VX 2VX35Y DAMPER, SWGR HEAT RMVL VX 2VX36Y DAMPER, SWGR HEAT RMVL VX 2VX37Y DAMPER, SWGR HEAT RMVL VX 2VX38Y DAMPER, SWGR HEAT RMVL VX 2VX39Y DAMPER, SWGR HEAT RMVL VX 2VX40Y DAMPER, SWGR HEAT RMVL VX 2VX41Y DAMPER, SWGR HEAT RMVL VX 2VX42Y DAMPER, SWGR HEAT RMVL VX 2VX43Y DAMPER, SWGR HEAT RMVL VX 2VX50Y DAMPER SWGR HEAT REMOVAL VX 2VX51Y DAMPER, SWGR HEAT RMVL VX 2VX52Y DAMPER, SWGR HEAT RMVL VX 2VX53Y DAMPER, SWGR HEAT RMVL VX 2VX54Y DAMPER, SWGR HEAT RMVL VX 2VX55Y DAMPER, SWGR HEAT RMVL VX 2VX56Y DAMPER, SWGR HEAT RMVL VX 2VX57Y DAMPER SWGR HEAT REMOVAL VX 2VX58Y DAMPER SWGR HEAT REMOVAL VX 2VX59Y DAMPER SWGR HEAT REMOVAL VX 2VX60Y DAMPER, SWGR HEAT RMVL VX 2VY01A COIL, COOLER, CSCS EQUIP RHR A PP VY CUBE 2VY01C ASSY - FAN, RHR PUMP A ROOM VY COOLING 2VY01Y

DAMPER, VY 2VY02A ASSY - COIL, EQUIP COOL VY RB 16 D 694 2VY02C ASSY_-_FAN, CSCS EQUIP HPCS PP VY RB 16 F 694 CUBICAL SUPPLY 2VY02Y DAMPER, DIV-1 RHR WS PP ROOM VY 2VY03A COIL, COOLER, CSCS EQUIP RHR B/C PP CUBE 2VY03C ASSY_--FAN, RHR PUMP B/C ROOM VY RB 16 D 694 COOLING FAN 2VY03Y

DAMPER, VY 2VY04A COIL, COOLER, CSCS EQUIP LPCS PP VY CUBE 2VY04C ASSY - FAN, LPCS PUMP ROOM COOLING VY RB 20 D 694 2VY04Y DAMPER, ECCS EQUIP COOL VY 2VY05C DIV I CSCS PUMP ROOM SUPPLY FAN VY DG PENTHOU 736 2VY05Y

DAMPER, VY SE Table B-la Page 53 of 54 B-55

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component System Column Floor Tag Equipment Name Code Building No Elev 2VY06C ASSY - FAN, CSCS EQUIP RHR WS PP 2C-VY DG J 22 736 2B CUBE SUP 2VY06Y

DAMPER, VY 2VY07C ASSY - FAN, CSCS EQUIP RHR WS PP 2C-VY 2B CUBE SUP 2VY07Y DAMPER, ECCS EQUIP COOL VY 2VY08Y DAMPER, ECCS EQUIP COOL VY 2VY09Y DAMPER, ECCS EQUIP COOL VY 2VY1OY DAMPER, ECCS EQUIP COOL VY 2VY1 1Y DAMPER, ECCS EQUIP COOL VY 2WR029 DW EQUIP RBCCW INLT OTBD ISOL STOP WR RB 19 B 740 2WRO40 DW EQUIP RBCCW OTLT OTBD ISOL WR RB 17 C 786 STOP 2WR179 DW EQUIP RBCCW INLT INBD ISOL WR DW 18 C 740 2WR180 DW EQUIP RBCCWOTLT INBD ISOL WR DW 30 C 777 2WR225 VALVE WR 2WR226 VALVE WR I

Table B-i a Page 54 of 54 B-56

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Table B-I b. Base List 1 b - Items Common to Units 1 and 2 System IFloor Eq Component Tag Equipment Name Code Building Column No Elev 0AE-VC090A CONT ROOM A/C A CHLOR MONA VC 0AE-VC090B CONT ROOM A/C A CHLOR MON A VC OAP08E RSH AUX PWR XFMR AP OC11-F002A VALVE, AO C11 ODC04E BATTERY CHARGER 250 VDC SPARE DC ODC17E BATTERY CHARGER 125 VDC SPARE DC ODC23E BATTERY CHARGER 125 VDC SPARE DC 0DC36E BATTERY CHARGER 24/48 VDC DC ODG009 0 DG COOLING WATER STRAINER DG BACKWASH VALVE 0 DG COOLER INLET HEADER RELIEF 0DG014 DG VALVE 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 ODG01K-B PUMP, DC TURBO SOAKBACK DG ODG01 K-C PUMP, AC LUBE OIL CIRC DG 0DG01K-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 ODG01 K-G PUMP, RIGHT BANK WTR DG ODG01 K-H PUMP, LEFT BANK WTR DG ODG01K-I PUMP, MAIN LUBE OIL DG ODG01K-J PUMP, PISTON COOL DG 0DG01K-K PUMP, ENGINE DRIVEN FUEL DG ODG01 K-L PUMP, ELECT MTR DRIVEN FUEL DG ODG01K-M TRAP, TYPE EXH SCREEN DG 0DG01K-N HEAT EXCHANGER, DG COOLING DG WTR ODG01P 0 DG COOLING WATER PUMP DG AB 09 G 674 ODG01S 0 DG STARTING AIR COMPRESSOR DG PACKAGE ODG01SA ASSY - TANK, DG AIR VESSEL DG 0DG01SB ASSY - TANK, DG AIR VESSEL DG ODG029A 0 DG A STARTING AIR RECEIVER DG RELIEF VALVE ODG029B 0 DG B STARTING AIR RECEIVER DG RELIEF VALVE ODG02F FILTER/SILENCER, DG AIR INTAKE DG ODG02JA 0 DG A GENERATOR CONTROL PANEL DG Table B-lb Page 1 of 17 B-57

12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component Tag Equipment Name System Floor codeBuilding Column Nolev 0DG02JB 0 DG B GENERATOR CONTROL PANEL DG ODG035A ASSY - VALVE, 0 D/G BANK A DG STARTER AIR SUPPLY 0DG035B ASSY - VALVE, 0 DIG BANK B DG STARTER AIR SUPPLY 0 DG A/C STARTING AIR MOTORS PINION SUPPLY SOLENOID VALVE 0 DG B/D STARTING AIR MOTORS PINION SUPPLY SOLENOID VALVE ODG03J 0 DG ENGINE CONTROL PANEL DG 0DG049 RELIEF CHECK VALVE DG ODG04J PANEL, DG TRANSFORMER DG ODG050 0 DG LUBE OIL SOAK BACK PUMPS DG DSCH RELIEF CHECK VALVE ODG08M SS MESH.255AX 080 TYPE304, 30IN 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 ODG20MB ASSY - TANK, DG AIR VESSEL DG ODG23MA FILTER, AIR DG ODG23MB FILTER, AIR DG ODG25M 0 DG LUBE OIL SOAK BACK PUMPS DG DSCH STRAINER 0 DG LUBE OIL CIRC PUMP DSCH 0DG26M DG STRAINER ODGT4 TRANSFORMER, ODG02J PHASE DG SHIFTING ODO001P ASSY - PUMP, DG FUEL XFER DO ODO001T ASSY - TANK, 0 DG FUEL STORAGE DO 0D0004 0 DG FUEL OIL XFR PMP MU VLV DO ODO01P 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 F_

STRNR Table B-lb Page 2 of 17 B-58

12Q0108.50-R-002 Rev. I Correspondence No.: RS-12-163 Eq Component Tag Equipment Name System Building Column No Floor Code Elev ODO1OM 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 OPA1OJ 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 0PI-DG056 0 DG MAIN LUBE OIL PRESS DG OPI-DG057A 0 DG FUEL OIL PRESS DG 0PI-DG057B 0 DG FUEL OIL PRESS DG 0PI-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 DG PRESS 0PI-DG080 FUEL D/P DG 0PI-DG081 FUEL D/P DG 0PI-DG082 FUEL PRESS ENG PP DG OPI-DG083 OIL D/P DG 0PI-DG084 OIL D/P DG OPI-DG085 DG MAIN OIL PRESS DG OPI-DG086 0 DG SCAVENGING AIR PRESS DG 0PI-DG087 JACKET W-R PRESS DG 0PI-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-59

12Q...8.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component Tag Equipment Name BidSystem B

Fo Code uilding Column No Ilev 0PI-DG121 0 DG SOAK BACK LUBE OIL IDG 0PI-DG122 0 DG CRANKCASE PRESS i DG 0PI-DG60A DG 0 FUEL OIL PRESS I

DG 0PI-DG60B DG 0 FUEL OIL PRESS I

DG 0PI-DG63 DG ENGINE COOLING WTR PRESS DG_

VC COMPRESSOR A LO SUCTION OPI-VC133 VC PRESS 0PI-VC134 VC COMPRESSOR A LO OILIPRESS VC 0PI-VC135 VC COMPRESSOR A HI DISCH PRESS VC VC COMPRESSOR B LO SUCTION OPI-VC17'3 PRS+VC PRESS___

0PI-VC174 VC COMPRESSOR B LO OIL',PRESS VC 0PI-VC175 VC COMPRESSOR B HI DISCH PRESS VC 0PI-VE102 COMPRESSOR, 0VE04CA LOW SUCTION PRESSURE

___VE COMPRESSOR, 0VE04CA LOW OIL VE OPI-VE103_PRESSURE 0PI-VE104 COMPRESSOR, 0VE04CA HI' DISCH VE PRESSURE I_

I OPI-VE142 B AEER HVAC REFRIGERATION UNIT VE 0PI-VE142

_____LOW SUCT PRESS INDICATOR OPI-VE143 B AEER HVAC REFRIGERATION UNIT VE LOW OIL PRESS INDICATOR OPI-VE144 B AEER HVAC REFRIGERATION UNIT VE 0PI-VE144

_____HIGH DSCH PRESS INDICATOR OPL100J ASSY - PANEL, 480V. POWER PANEL PL AT INTAKE STRUCTURE OPL14J ASSY - PANEL, AUX BLDG/LAB HVAC PL OPL14JA 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 OPL43J ASSY - PANEL, AEER HVAC SYST B PL I

OPLB2J 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 0PLB9JA

___POWER SUPPLY IPL 0PLB9JB ASSY - PANEL, VCNENG FLTR TRAIN PL

__________B POWER SUPPL PL 0PILC9J ASSY_-_PANEL, HRSS VLV CONTROL PL AB 17 L 694 rT Table B-lb Page 4 of 17 B-60

12QO108.5O-R-002 Rev. 1 Correspondence No.: RS-12-163 Syte Floor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buildin Column NFlo 0PLD1J ASSY - PANEL, SBGT VENT SAMPLE PL CONDITIONER PL 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 I

ORGO15A REFRIGERANT LIQUID LINE SOLENOID RG IVALVE FOR OVC02AA Table B-lb Page 5 of 17 B-61

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No Floor code Elev REFRIGERANT LIQUID LINE SOLENOID VALVE FOR OVC02AA ORGO16A

VALVE, RG ORG016B

VALVE, RG ORGO34A VALVE,REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VC ORGO34B VALVE,REFRIGERANT LIQUID LINE RG SOLENOID VALVE FOR B VC ORGO53A REFRIGERANT LIQUID LINE SOLENOID RG VALVE FOR OVE01AA ORGO53B REFRIGERANT LIQUID LINE SOLENOID RG 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 COOLER SOLENOID VALVE ORG195B

'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 OSI-DG028B DG 0 FREQUENCY METER DG 0SI-DG067 0 DG FREQUENCY METER DG OTE-VC002 CONT RM HVAC ZONE MIX DMPR 16YA VC OTE-VC003 CONT RM HVAC ZONE MIX DMPR 19YA VC TEMP CONT RM HVAC ZONE MIX DMPR 22YA 0TE-VC003 VC OTE-VC005 CONT RM HVAC ZONE MIX DMPR 25YA VC TEMP OTE-VC006 CONT RM HVAC ZONE MIX DMPR 28YA VC TEMP OTE-VC042 CONT RM HVAC ZONE MIX DMPR 16YB VC

___REHTR CONT OTE-VC043 CONT RM HVAC ZONE MIX DMPR 19YB VC

_TEMP OTE-VC044 CONT RM HVAC ZONE MIX DMPR 22YB VC

_TEMP ELEMENT Table B-lb Page 6 of 17 B-62

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buidin Euel CONT RM HVAC ZONE MIX DMPR 25YB 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 OVC01SB OUTLET TEMP VC OTE-VD003 ODG01 K 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 0TE-VE033 VE TEMP OTE-VE042 AEER A/C RT DET DMPR VE OTE-VE043 AUX EQUIP RM A/C SYS MIX DAMPER VE REHEAT CONTROL TEMP ELEMENT B AUX ELEC EQUIP RM MIX DMPR VE 0TE-VE044 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_

OTI-DG064A 0 DG ENGINE COOLING WATER DG OUTLET TEMP OTI-DG092 DG CYLINDER WALL TEMP DG OTI-DG100 DG ODG01 K COOLING WTR TEMP DG OTI-DG101 DG ODG01 K JACKET WTR TEMP IN DG OTI-DG61 DG ENGINE RAW COOLING WTR DG TEMP OTI-DG64A DG ENGINE COOLING WTR OUT TEMP DG 0TI-DG64B DG ENGINE COOLING WTR IN TEMP DG OTI-DG64C DG ENGINE COOLING WTR TO OIL DG COOLR OTI-VC103 HEATER IN TEMP TRAIN OVC01SA VC OTI-VC104 HEATER OUT TEMP TRAIN OVC01SA VC 0TI-VC105 FLTR TRAIN A IN TEMP VC Table B-lb Page 7 of 17 B-63

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 System Floor Eq Component Tag Equipment Name Code Building Column No Elev 0TI-VC106 FLTR TRAIN A OUT TEMP VC OTI-VC143 HEATER IN TEMP TRAIN OVC01SB VC OTI-VC144 HEATER OUT TEMP TRAIN 0VC01SB VC OTI-VC145 FLTR TRAIN OVC01SB IN TEMP VC OTI-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 AEER A/C ZONE MIX DMPR REHTR VE 0TI-VE043 COVE_____

CON OTI-VE044 AEER A/C ZONE MIX DMPR REHTR VE CON OTI-VE081 AEER A/C SYST MIX AIR TEMP/IND VE OTI-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 FILT UNIT CONT ROOM HVAC SPLY OVC01FB VC AB 16 N 786 AIR I

FILT UNIT CONT RM HVAC EMER MU 0VC01 SA VC AIR OVC01SB FILT UNIT CONT RM HVAC EMER MU VC AIR 0VC01YA DAMPER, CR A/C SYST A TORNADO VC DMPR 0VC01YB DAMPER, CR A/C SYST B TORNADO DMPR I

OVC02CA ASSY - FAN, CR HVAC RETURN GA VC OVC02CB ASSY - FAN, CR HVAC RETURN GB VC OVC02SA GENERATOR, STEAM CR HVAC VC ELECTRIC 0VC02SB GENERATOR, STEAM CR HVAC VC ELECTRIC OVC02YA A EMER MU TRAIN INLT VC GVC02YB B EMER MU TRAIN INLT VC OVC033A SOLENOID VALVE VC OVC033B SOLENOID VALVE I

VC 0VC03CA ASSY - FAN, CR HVAC EMERG M/U AIR VC AB R 18 802 GA I

OVC03CB ASSY - FAN, CR HVAC EMERG M/U AIR VC 0B GVC03YA A EMER MU TRAIN OTLT VC OVC03YB B EMER MU TRAIN OTLT VC GVCG4CA ASSY - FAN, CR HVAC AIR COOLED OV04AVC

_CONDENSER GA I

I I_

I Table B-1 b Page 8 of 17 B-64

12QO108.50-R-002 Rev. I Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code No Eleo OVC04CB ASSY - FAN, CR HVAC AIR COOLED VC CONDENSER 0B OVC04YA A CONTROL ROOM HVAC BALANCING VC DAMPER B CONTROL ROOM HVAC BALANCING 0VC04YB VC DAMPER OVC05CA PANEL, INSTR CONTROL HVAC VC REFRIGERATION OVC05CB 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 VCNE 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 A CONTROL ROOM HVAC OUTSIDE OVC06YA AIR BALANCING DAMPER VC AIR BALANCING DAMPER OVC07YA A CONTROL ROOM HVAC AEEROVC AIR BALANCING DAMPER VC 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 A CONTROL ROOM HVAC BALANCING 0VC09YA VC DAMPER OVC09YB B CONTROL ROOM HVAC BALANCING VC DAMPER A CONTROL ROOM HVAC ISOL DAMPER OVC10YB B CONTROL ROOM HVAC ISOL VC DAMPER OVC11YA A CHARCOAL FILT INLT VC OVC11YB 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-1 b Page 9 of 17 B-65

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Eq Component Tag Equipment Name System Building Column No Fl Code BidnCounNFIrElev OVC13YB B CHARCOAL FILT BYP VC OVC14YA A CONTROL ROOM HVAC RETURN VC 0VC14YBA OTO OO VCRTR VC FAN DSCH DAMPER B CONTROL ROOM HVAC RETURN OVC14YB FAN DSCH DAMPER VC OVCI1 5YB A CONTROL ROOM HVAC RETURN VC FAN SUCT DAMPER OVC15YB B CONTROL ROOM HVAC RETURN V

FAN SUCT DAMPER OVC16YA DAMPER, CR A/C SYST A MIX VC OVC16YB DAMPER, CR A/C SYST B MIX VC OVCI1 7YA A CONTROL ROOM ZONE HEATING VC COIL OVC04AA OUTLET DAMPER OVC17YB B CONTROL ROOM ZONE HEATING VC COIL OVC04AB OUTLET DAMPER OVC18YA DAMPER, CR A/C SYST VC OVC18YB DAMPER, CR A/C SYST VC OVC1 9YA DAMPER, CR A/C MIX A VC OVC19YB DAMPER, CR A/C MIX B VC OVC20YA A CONTROL ROOM ZONE HEATING VC COIL OVC05AA OUTLET DAMPER OVC20YB B CONTROL ROOM ZONE HEATING VC 0VC20YB

_____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-1 b Page 10 of 17 B-66

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No FIOOrev VC28YA 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 0VC31Y RETURN BALANCING DAMPER UNIT 2 CONTROL ROOM HVAC RETURN BALANCING DAMPER 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 0VC43Y A CONTROL ROOM HVAC AIR COOLED VC CONDENSER DSCH CHECK DAMPER 0VC45Y 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

Table B-lb Page 11 of 17 B-67

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buidin Cuel OVC52YB B VCNE MINIMUM OUTSIDE AIR DOWNSTREAM ISOLATION DAMPER OVC53YA A CONTROL ROOM HVAC MAXIMUM VC OUTSIDE AIR ISOL DAMPER B CONTROL ROOM HVAC MAXIMUM OVC53YB OUTSIDE AIR ISOL DAMPER VC, A CONTROL ROOM HVAC MINIMUM OVC54YA OUTSIDE AIR BALANCING DAMPER V

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 0VC61Y DAMPER, CONTROL ROOM HVAC ISOL VC FIRE VC SUPPLY TO EAST AREA OF CONTROL ROOM FIRE DAMPER 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 OVD01YAB____ OPPOSED VD OVD01YB DAMPER DG RM VENT VD Table B-1 b Page 12 of 17 B-68

12Qo108.50-R-002 Rev.

1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buildin Cuel 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 OVEO1AA COIL AUX ELEC EQUIP RM HVAC SPLY VE D-X OVE01AB COIL AUX ELEC EQUIP ROOM HVAC VE ASSY - AUX EQUIPMENT ROOM OVE01 CA VE AB 786 HVAC SUPPLY FAN OVE01CA OVE01CB ASSY - FAN, HVAC SUPPLY VE OVE01FA FILT UNIT AUX ELEC EQUIP RM HVAC VE SPLY AIR OVE0lEB FILT UNIT AUX ELEC EQUIP RM HVAC VE SPLY AIR GEN AUX EL EQUIP RM HVAC ELEC 0VE01 SA VE STM OVE01SB GEN AUX EL EQUIP RM HVAC ELEC VE STM 0VE01TA ASSY - VESSEL, REFRIGERANT VE RECEIVER 0VE01TB ASSY - VESSEL, REFRIGERANT VE RECEIVER OVE01YA A AEER HVAC SUPPLY BALANCING VE DAMPER OVE0lYB 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 0VE02CB ASSY - FAN, HVAC RETURN AIR O/B VE Table B-1 b Page 13 of 17 B-69

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buildin Column NFeo A AEER HVAC SUPPLY BALANCING 0VE02YA VE DAMPER OVE02YB B AEER HVAC SUPPLY BALANCING VE DAMPER OVE03CA AUX ELEC EQUIP RM AIR COOLED VE CONDENSER FAN OA B AEER HVAC AIR COOLED CNDSR 0VE03CB FNVE FAN OVE03YA A AEER HVAC MANUAL PURGE AIR VE 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 CONTROL DAMPER 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 OVE01FA 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 0VE11YB 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-70

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Building Cuel OVE13YB B AEER HVAC SUPPLY AIR VE BALANCING DAMPER OVE14YA A AEER HVAC SUPPLY AIR VE BALANCING DAMPER B AEER HVAC SUPPLY AIR BALANCING DAMPER OVEI1 5YA 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 0VE18YA 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 0VE24Y 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 OVE29Y 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 1 AIR SUPPLY FIRE VE DAMPER OVE36Y AEER HVAC UNIT 1 AIR RETURN FIRE VE

_DAMPER I

Table B-1 b Page 15 of 17 B-71

12QO108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFloor SytmBuilding Column No Ee Eq Component Tag Equipment Name Code Buidin Cuel AEER HVAC UNIT 1 AIR SUPPLY FIRE OVE37Y VE OVE38Y AEER HVAC UNIT 1 AIR SUPPLY FIRE VE DAMPER OVE39Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 2 AIR RETURN FIRE OVE40Y DAMPER IVE OVE41Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER OVE42Y AEER HVAC UNIT 2 AIR RETURN FIRE VE DAMPER OVE43Y DAMPER, AFER 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 VE5YAEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER OVE51Y AEER HVAC UNIT 2 AIR SUPPLY FIRE VE DAMPER AEER HVAC UNIT 2 AIR SUPPLY FIRE OVE52Y DAMPER AEER HVAC UNIT 2 AIR RETURN FIRE 0VE50Y VE DAMPER OVE60Y AEER HVACPROCESS COMPUTER VEEROOM SUPPLY AIR FIRE DAMPER OVE61Y DAMPER, OPPOSED BLADE, HORIZ VE

___SHAFT A AEER HVAC RETURN AIR ISOL FR MAINTENANCE DAMPER OVE66YB B AEER HVAC RETURN AIR ISOL VE

____________MAINTENANCE DAMPER OVE67YA A AEER HVAC COOLER CNDSR FAN VE RECIRC DAMPER B AEER HVAC COOLER CNDSR FAN OVE67YB RECIRC DAMPER V

OVE68Y FIRE DAMPER VE OVE69Y FIRE DAMPER VE OVE70Y FIRE DAMPER VEBLADEHO OVE71Y FIRE DAMPER VE MOVE72Y FIRE DAMPER VE Table B-l b Page 16 of 17 B-72

12Q.108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 SystemFlo Eq Component Tag Equipment Name Code Building Column No FElev 0VE73Y FIRE DAMPER VE OVE74Y FIRE DAMPER VE OVE75Y FIRE DAMPER VE OVE76Y FIRE DAMPER VE OVE77Y FIRE DAMPER VE OVE78Y UNIT 1 AEER HVAC SUPPLY VE BALANCING DAMPER OVE79Y UNIT 2 AEER HVAC EXHAUST VE BALANCING DAMPER OVE80YA DAMPER VE OVE80YB DAMPER VE Table B-1 b Page 17 of 17 B-73

12Q0108.50-R-002 Rev. 1 Correspondence No.: RS-12-163 Table B-2. Base List 2 Room Floor Eq Component Tag Equipment Name System Code Building Number Column No Elev 2FC01TA NmFUELPOOLSKIMMERSURGETNK2A FC RB 17 D 820 2FC01TB FUEL POOL SKIMMER SURGE TNK 2A FC RB 17 F 820 FC FUEL POOL COOLING DSCH BYP TO SKIMMER TNK 2FC130 STOP FC 2FC132 FUEL POOL COOLING PMP SUCT HDR HI POINT VENT FC FUEL POOL-COOLING PMP SUCT HDR TORHR SYS DRN 2FC133 FC STOP 2FC138 Skimmer Surge Tank Outlet FC 2FC139A 2A FUEL POOL COOLING PMP SUCT STOP FC 2FC139B 2B FUEL POOL COOLING PMP SUCT STOP FC 2FC140 FUEL POOL SYS TO RHR SUCT STOP FC 2FC141 CHECK VALVE FC 2FC143 RHR DSCH TO FUEL STRG POOL LINE DRN STOP FC 2FC144 RHR DSCH STOP TO FUEL STRG POOL FC 2FC147 FUEL POOL SKIMMER SURGE TNK LEVEL INSTRLINE FC STOP 2FC155 RHR DSCH HDR TO FUEL POOL HI POINT VENT FC B-74

IJr-oumil'll I IUNI*

1:UlILUlIINI r_.Lr_, V/- I RJIINI LUUM/' I IUIN 0 *TI r

1lvI LI sfilly Basis?

OaIlty r UlIcLUlun HVAC EMERG M/U AIR OA (10) Air Handlers AB 802 R 18 VC Y

Auxiliary & Suppo FGR 242Y (03) Medium Voltage Switchgear AB 731 20 N AP Y

Auxiliary & Suppo (02) Low Voltage Switchgear and RB 786 19 C AP Y

Auxiliary & Suppo Breaker Panels RB_786 19_C AY uiaySp R 235X (02) Low Voltage Switchgear and AB 710 20 L AP Y

Auxiliary & Suppo Breaker Panels

.AB_710 20_L AY uiaySp

,, 235X (04) Transformers AB 710 20 L AP Y

Electrical System

R 236X (02) Low Voltage Switchgear and AB 731 20 L AP Y

Auxiliary & Suppo Breaker Panels AB_731 2LAPAuiay&Sp

,, 236X (04) Transformers AB 731 20 L AP Y

Electrical System 235X-1 (01) Motor Control Centers RB 761 20 A AP Y

Auxiliary & Suppo 235X-3 (01) Motor Control Centers AB 710 19 L AP Y

Auxiliary & Suppo 236X-1 (01) Motor Control Centers RB 820 18 C AP Y

Auxiliary & Suppo 236X-3 (01) Motor Control Centers AB 731 21 L AP Y

Auxiliary & Suppo

,, MSRV (21) Tanks and Heat Exchangers DW 777 B21 Y

RCPC

-TY/RELIEF VLV (07) Pneumatic-Operated Valves DW 777 B21 Y

RCPC

)LENOID VALVE 'A' (08) Motor-Operated and Solenoid-DW 783 B21 Y

RCPC Operated Valves DW_783 B21_Y RCPC VLV (07) Pneumatic-Operated Valves DW 735 18 J B21 Y

RCPC

,L VLV (07) Pneumatic-Operated Valves RB 735 18 J B21 Y

RCPC

)ID, 0/B MSIV (08) Motor-Operated and Solenoid-Outboard MSIV 735 B21 Y

RCPC

)ID,_O/BMSIVOperated Valves Room

'L ABOVE SEAT DRN VLV (08) Motor-Operated and Solenoid-RB 735 18 H B21 Y

RCPC

____ABOVESEAT_________ Operated Valves 735 18__B2_____

CRD HYDRAULIC 22-59 RB 761 G-F 15-16 Cll Y

RRC

______________(00)

Other SOUTH CRD HYDRAULIC 26-03 RB 761 C-D15-16 Cl1 Y

RRC (00) Other SOUTH G-F 20-21 CRD HYDRAULIC 34-59 RB 761 C11 Y

RRC (00) Other NORTH CRD HYDRAULIC 38-07 RB 761 C-D 20-21 C11 Y

RRC (00) Other NORTH

ýM WATER ACCUMULATOR RB 761 C11 Y

RRC (21) Tanks and Heat Exchangers SOUTH G-F 15-16

,M INLET VALVE RB71C1YRRC

_____INLETVALVE_(07)

Pneumatic-Operated Valves RB 761 SOUTH 1-Cli SM OUTLET VALVE RB 761 HC11 Y

RRC (07) Pneumatic-Operated Valves SOUTH kM WATER ACCUMULATOR RB 761 C11 Y

RRC (21) Tanks and Heat Exchangers R

SOUTH C_

F.- '

1 R5 A

kM WATER ACCUMULATOR RB 761 (21) Tanks and Heat Exchangers

'.3-rl,u-" I NORTH Cll Y

RRC

,M INLET VALVE RB 761 G-F 20-21 C11 Y

RRC (07) Pneumatic-Operated Valves NORTH kOULTVALVE RB71 G-F 20-21 C11 Y

RRC OU T(07)

Pneumatic-Operated Valves RNORTH C11_Y RRC C-D 20-21

,M WATER ACCUMULATOR (2)Tanks and Heat Exchangers RB 761 NORTH C1YRRC

____INLET

___VALVE_

(07) Pneumatic-Operated Valves 761___

NORTH C11 Y

R

,M OUTLET VALVE RB 761 C-D 20-21 C11 Y

RRC (07) Pneumatic-Operated Valves NORTH ID CONT SOLUTION (21) Tanks and Heat Exchangers RB 820 17 C C41 Y

RRC (05) Horizontal Pumps RB 820 17 C C41 Y

RRC Y, 250 VDC (15) Battery on Rack AB 710 J 20-21 DC Y

Electrical System (14) Distribution Panels and

'ISTRIBUTION BUS 2 Automatic Transfer Switches AB 710 20 L DC Y

Electrical System:

RY CHARGER (16) Battery Chargers & Inverters AB 710 L 205 DC Y

Electrical System!

?1X (01) Motor Control Centers AB 710 20 L DC Y

Electrical System:

I1STRIBUTION PANEL 212Y (14) Distribution Panels and ISTRIBUTION__PANEL_212Y iAutomatic Transfer Switches AB 731 18 L DC Y

Electrical System:

Y, 125 VDC DIV-2 (15) Battery Racks AB 731 17 L DC Y

Electrical System!

'ISTRIBUTION BUS 2B (14) Distribution Panels and ISTRIBUTION_____BUS

___2B Automatic Transfer Switches AB 731 18 L DC Y

Electrical System:

ATTERY CHARGER 2BB (16) Battery Chargers & Inverters AB 731 17.5 L DC Y

Electrical System:

3 WTR STRNR BACKWASH (08) Motor-Operated and Solenoid-DG 674 21 J DG Y

Auxiliary & Suppo

_ Operated Valves DG 674 21 JG__uxlir_&Sup (21) Tanks and Heat Exchangers DG 710 J 22 DG Y

Auxiliary & Suppo 3 WATER STRAINER (00) Other DG 674 C 7 DG Y

Auxiliary & Suppo ERATOR (17) Engine Generators DG 710 J 22 DG Y

Auxiliary & Suppo 3 WATER PUMP (05) Horizontal Pumps RB 674 21 J DG Y

Auxiliary & Suppo G AIR COMPRESSOR (12) Air Compressors DG 710 J 22 DG Y

Auxiliary & Suppo ZATOR CONTROL PANEL (20) Instrument and Control Panels DG 710 J 22 DG Y

Auxiliary & Suppo CONTROL PANEL (20) Instrument and Control Panels DG 710 J 22 DG Y

Auxiliary & Suppo RTING AIR MOTORS SUPPLY fE (07) Pneumatic-Operated Valves DG 710 22 J DG Y

Auxiliary & Suppo

)ILTRANSFER (05) Horizontal Pumps DG 674 DO Y

Auxiliary & Suppo 1(21) Tanks and Heat Exchangers DG 710 J 22 DO Y

Auxiliary & Suppo XCH (21) Tanks and Heat Exchangers RB 710 B 15 E12 Y

RCIC/DHR PAT PF=RAC)\\/Al PRAP ingi \\/Prtir..ql Pijmn.q PR 1R

_r (

I=1 9 v

Pr,.Ir,/nI-I

• STOP kUO) IVIUetUI-ed UIdUU dVlU vesUlUi-Operated Valves RB 694 16 B E12 Y

RCIC/DHR DT FROM SUP POOLSTOP (08) Motor-Operated and Solenoid-RB 673 16 D E12 Y

RCIC/DHR Operated Valves CODT U HR TPOperated Valves RB 673 16 D E12 Y

RCIC/DHR COND TO SUP CHBR STOP (08) Motor-Operated and Solenoid-RB 694 16 A E12 Y

RCIC/DHR Operated Valves COND OTLT TO RCIC STOP (08) Motor-Operated and Solenoid-RB 694 16 A E12 Y

RCIC/DHR Operated Valves__________

PP SUCT LINE RELIEF (07) Pneumatic-Operated Valves RB 694 20 C E12 Y

RCIC/DHR STOP (08) Motor-Operated and Solenoid-RB 694 15 B E12 Y

RCIC/DHR.

Operated Valves INLT PRESS CONT VLV (07) Pneumatic-Operated Valves RB 710 15 B E12 Y

RCIC/DHR H LINE RELIEF (07) Pneumatic-Operated Valves RB 710 E12 Y

RCIC/DHR

,CH OTLT (08) Motor-Operated and Solenoid-RB 673 19 A E12 Y

RCIC/DHR Operated Valves RIB 673 19__E1________

,CH OTLT STOP VLV (08) Motor-Operated and Solenoid-RB 673 16 A E12 Y

RCIC/DHR Operated Valves

,VWTR DISCH TEMP (19) Temperature Senesors RB 694 A 16 E12 Y

RCIC/DHR

,V WTR INLET FLOW (18) Instrument Racks RB 673 B 15 E12 Y

RCIC/DHR (18) Instrument Racks RB 673 B 15 E12 Y

RCIC/DHR IH TO RX VESSEL TEMP (19) Temperature Senesors RB 673 A 15 E12 Y

RCIC/DHR

)ISCH PRESSURE (18) Instrument Racks RB 673 B 15 E12 Y

RCIC/DHR CORE SPRAY (06) Vertical Pumps RB 673 20 B E21 Y

RCIC/DHR I FLOW XMITTER (18) Instrument Racks RB 673 20 A E21 Y

RCIC/DHR CORE SPRAY (06) Vertical Pumps RB 673 15 F E22 Y

RCIC

)N ISOL VALVE (08) Motor-Operated and Solenoid-RB 761 16 C E22 Y

RCIC Operated Valves IP POOL SUCT ISOL VALVE (08) Motor-Operated and Solenoid-RB 673 16 D E22 Y

RCIC Operated Valves

)W TEST ISOL VALVE (08) Motor-Operated and Solenoid-RB 694 16 E E22 Y

RCIC Operated Valves i PRESS XMITTER (18) Instrument Racks RB 673 15 F E22 Y

RCIC I FLOW XMITTER (18) Instrument Racks RB 693 15 F E22 Y

RCIC COOLING PMP (05) Horizontal Pumps RB 673 A-B 20-21 E51 Y

RCIC

'4 STOP (08) Motor-Operated and Solenoid-RB 740 19 H E51 Y

RCIC Operated Valves T FROM SUP POOL STOP (08) Motor-Operated and Solenoid-RB 673 19 C E51 Y

RCIC Operated Valves Al SPLY STOP (08) Motor-Operated and Solenoid-RB 673 20 A E51 Y

RCIC Operated Valves EMERG CORE COOL SYST (20) Instrument and Control Panels MCR I

H13 Y

Racks & Panels PXAIr.1 I/PY PFCIPr.

k.'U UA U-/_ OUt r1UJLL U10 VLV kUO) perVlUatUed

I1,U dValU eUsI uiu-Operated Valves RB 710 15 B HG Y

CF R, H2 RECOMBINER (09) Fans RB 786 16 B HG Y

CF CEIVER PRESS (18) Instrument Racks DG 710 J 22 DG Y

Auxiliary & Suppo RHR B/C CUBE VENT (20) Instrument and Control Panels RB 687 B 17 PIL Y

Racks & Paneis RHR A CUBE VENT RB 694 19 H PL Y

Racks & Panels

_____________________(20)

Instrument and Control Panels LPCS CUBE VENT RB 694 19 A PL Y

Racks & Panels

_PCS CUBE VENT

_____________ (20) Instrument and Control Panels RB 694 19 APLY Racks_&_Panels COMBINER GAS INLET (TE-RB 761 A 15 HG Y

CF (19) Temperature Senesors

'E FROM RX BLDG UPSTRM

_(07) Pneumatic-Operated Valves IE FROM RX BLDG DWNST

______URGE______UPI_____

(07) Pneumatic-Operated Valves RB 740 17 H VQ Y

CF T/PURGE OTLT UPSTRM (0)PemtcOperated Valves T/PURGE OTLT UPSTRM (08) Motor-Operated and Solenoid-R 1.2 QYC

______________Operated Valves RB______

710____

20____E_

VQ

__YCF 3E OTLT UPSTRM ISOL (07) Pneumatic-Operated Valves RB 786 20 E VQ Y

CF

'E OTLT UPSTRM ISOL BYP (08) Motor-Operated and Solenoid-786 20 E VQ Y

CF

,E_____________(7)____u____

Operated Valves RB 786 20 E VQ Y

CF

E OTLT DWNST ISOL (07) Pneumatic-Operated Valves RB 786 20 E VQ Y

CF T/PURGE OTLT DWNST ISOL RB702 QYCF

____________________(07)

Pneumatic-Operated Valves R

1 0FV R DIV-2 VENT SUPPLY (09) Fans AB 820 J 20-21 VX Y

Auxiliary & Suppo R DIV-2 BATT ROOM EXH (09) Fans AB 731 N 17.6 VX Y

Auxiliary & Suppo SCS EQUIP HPCS PP LY (10) Air Handlers RB 694 16 F VY Y

Auxiliary & Suppo HR PUMP B/C ROOM (10) Air Handlers RB 694 16 D VY Y

Auxiliary & Suppo CS PUMP ROOM COOLING (10) Air Handlers RB 694 20 D VY Y

Auxiliary & Suppo IP ROOM SUPPLY FAN (10) Air Handlers DG 736 PENTHOUSE VY Y

Auxiliary & Suppo CS EQUIP RHR WS PP 2C-2B (10) Air Handlers DG 736 J 22 VY Y

Auxiliary & Suppo SW ILT OBD SOL TOP (08) Motor-Operated and Solenoid-CW INLT OTBD ISOL STOP (08)

Valves RB 740 19 B WR Y

Auxiliary & Suppo CW OTLT OTBD ISOL STOP (08) Motor-Operated and Solenoid-RB 786 17 C WR Y

Auxiliary & Suppo

_Operated Valves RB 786 17IC WR I Auxiliar_&_Supp

12Q0108,50-R-002 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?

RB 673' D-'16 FUEL POOL COOLING Outside B RHR 2FC133 PMP SUCT HDR TO (00) Other FC RB 673 Room Y

N m-1 44-1 RHR SYS DRN STOP 2FC140FUEL POOL SYS TO RB 807' G-20 Y

N m-144-1 1RHR SUCT STOP (00) Other FC RB 807 by FC Pumps Y

N m-144-1 B-79