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: 13) 03826 NC ELECT MEMB CORP RAL, NC
: 13) 03826 NC ELECT MEMB CORP RAL, NC
: 14) 03831 LL LOSH B&W LYNCHBURG, VA
: 14) 03831 LL LOSH B&W LYNCHBURG, VA
: 15) 05331 LEE HARMON CN01NC Rec'd By Page 1 of 2                                Date
: 15) 05331 LEE HARMON CN01NC Rec'd By Page 1 of 2                                Date DOCUMENT NO F
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QACOND      REV #/ DATE I      DISTR CODE      1      2  3    4    5        6      7      8      9    10  11    12  13 114    15  TOTAL
QACOND      REV #/ DATE I      DISTR CODE      1      2  3    4    5        6      7      8      9    10  11    12  13 114    15  TOTAL
_______  4                -,-                4      -1  4  4    -,---------{      4  -I-      ,-    4        4    -    4    4    4
_______  4                -,-                4      -1  4  4    -,---------{      4  -I-      ,-    4        4    -    4    4    4

Latest revision as of 08:25, 12 March 2020

Updated Final Safety Analysis Report, Revision 14 - List of Effective Dates for UFSAR Tables & Figures
ML092990601
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 10/20/2009
From: Barrett P, Gordon Peterson
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML092990598 List:
References
Download: ML092990601 (66)


Text

{{#Wiki_filter:DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 10/20/09 PRIORITY Rush OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK092930015

1) 00199 TIM ROBINSON EC03C
2) 00297 VTRAVICK, DRP/RPB1-ATLANTA Duke Energy QA CONDITION D Yes
  • No
3) 00933 CNS DOC MGMT CN04DM OTHER ACKNOWLEDGEMENT REQUIRED E Yes
4) 02023 D MCAMERON NCEMC CN030G DO( CUMENT TRANSMITTAL FORM IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE
5) 02198 NGD VAULT MG02NGD ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE

6) 02216 C LITCHFORD LYNCHBURG, VA
7) 03759 U S NUC REG WASHINGTON, DC CAT AWBA NUCLEAR STATION Duke Energy
8) 03761 J HTHOMPSON, WASHINGTON, DC 20093 UFSAR UPDATE 4800 Concord Road
9) 03781 WESTINGHOUSE ELEC CORP (3781) Document Management
10) 03788 MIKE MCGARRY W &S WASH, D.C. CN04DM
11) 03796 SCIENTECH DUNEDIN, FL York, South Carolina 29745
12) 03801 LIBRARIAN NC MUN PWR AG RAL,NC -7
13) 03826 NC ELECT MEMB CORP RAL, NC
14) 03831 LL LOSH B&W LYNCHBURG, VA
15) 05331 LEE HARMON CN01NC Rec'd By Page 1 of 2 Date DOCUMENT NO F

QACOND REV #/ DATE I DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 13 114 15 TOTAL _______ 4 -,- 4 -1 4 4 -,---------{ 4 -I- ,- 4 4 - 4 4 4 .2009 UPDATED FINAL SAFETY NA 014 10/20/09 CADM-01A CD2 CD1 CD5 CD1 CD1 CD1 ICD1 CD1 CD1 CD1YCD1 CD1 CD1 CD1 CD2 22

.ANALYSIS REPORT                                        NA        014  10/20/09 REMARKS:                                                                                                                                               J R MORRIS VICE PRESIDENT CATAWBA NUCLEAR STATION BY:

P BARRETT CNO1SR PB/RBE

Duke EEUKERGY CAROLNAS, LLC Duke ItreEnergye 4800 Concord Road Catawba Nuclear Station Yolk, SC 29745 Carolinas October 14, 2009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station Docket No. 50-413 and 50-414 2009 UFSAR Update Attached is one CD-ROM containing one copy of the Catawba Nuclear Station 2009 Updated Final Safety Analysis Report. The effective date of the changes provided by this submittal is April 18, 2009. This UFSAR Update is provided pursuant to the requirements of 10CFR5O.71 (e). The CD-ROM is provided based on the guidance found in NRC Regulatory Issue Summary (RIS) 2001-05, "Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM." RIS 2001-05 waives the requirement that licensees receive case-by-case approval required by 10CFR50.4 for submittal by electronic information exchange (EIE) or by CD-ROM. The RIS also waives the requirement that multiple copies of paper or electronic documents be submitted to the NRC. Attachment I is a list of effective dates for UFSAR tables and figures. Attachment 2 is a list which summarizes information removed from the UFSAR in this revision. These lists are required to be furnished as a part of each UFSAR Update. There have been no UFSAR changes made per IOCFR50.59 that have not been previously reported to the Commission [reference the Catawba Nuclear Station 10CFR50.59 Annual Summary Reports dated March 31, 2008 (which includes all changes made per I0CFR50.59 from January 1, 2007 to December 31, 2007) and March 31, 2009 (which includes all changes made per I0CFR50.59 from January 1, 2008 through December 31, 2008]. www.duke-energy, com A C

U.S. Nuclear Regulatory Commission Document Control Desk October 14,, 2009 Page 2 I certify that I am a duly authorized officer of Duke Energy Corporation, and that the information contained herein accurately represents changes made to the Catawba Nuclear Station UFSAR since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirement. There are no commitments associated with the submittal of the Catawba Nuclear Station 2009 UFSAR Update. If there are any questions concerning this submittal, please contact P. W. Barrett at (803)701-4138. Attachments

U.S. Nuclear Regulatory Commission Document Control Desk October 14, 2009 Page 3 AFFIDAVIT Gary R. Peterson, being duly sworn, states that he is Vice President of Duke Energy Corporation; that he is authorized on the part of the said corporation to sign and file with the Nuclear Regulatory Commission this Updated Final Safety Analysis Report for Catawba Nuclear Station; and that all statements and matters set forth herein are true and.correct to the best of his knowledge. Gary R. Peterson, Vice President Subscribed and sworn to me: 1011qle 5 Date Notary Public: My Commission Expires: 7/212 4 gf> .

                                                          ýOYP.

Date NOTA.~y PUBLIC*~ MY COMMISs10NEVXIRES JULY 2,2014

U.S. Nuclear Regulatory Commission Document Control Desk October 14, 2009 Page 4 xc: Luis A. Reyes U.S. Nuclear Regulatory Commission Acting Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Andy Hutto Senior Resident-Inspector (CNS) U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.H. Thompson, Project Manager ( U.S. Nuclear Regulatory Commission One White Flint North, 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738

U.S. Nuclear Regulatory Commission Document Control Desk October 14, 2009 Page 5 bxc: NCMPA-I NCEMC bxc w/o attachments: R. D. Hart (CN01RC) K. L. Ashe (MGO1RC) K. R. Alter (ON03RC) R. L. Gill (EC050) P. R. Newton (PB05E) B. J. Horsley (PBO1C) P. W. Barrett (CN01RC) ELL SREC PMPA Document Control File 801.01 RGC Date File

ATTACHMENT 1 LIST OF EFFECTIVE DATES FOR UFSAR TABLES AND FIGURES

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) Chapter 1 Tables 3/27/03 1-1. Shared Facilities and Equipment 10/22/01 1-2. Design Comparison 10/22/01 1-3. Significant Design Changes 10/22/01 1-4. Deleted per 2001 Update 4/18/09 1-5. Information Provided on the Subcooling Monitor 10/22/01 1-6. Reactor Vessel Level Instrumentation System 10/22/01 1-7. Criteria for Auxiliary Feedwater System Design Basis Conditions 10/22/01 1-8. Summary of Assumptions Used in AFWs Design Verification Analyses 10/22/01 1-9. Summary of Sensible Heat Source 10/22/01 1-10. Regulatory Guide 1.97, Rev. 2 Review 4/18/09 1-11. Regulatory Guide 1.97, Rev. 2 Review 10/22/01 1-12. Deleted per 2001 Update Chapter 2 Tables 3/27/03 2-1. 1977 Population 0-5 Miles (0-8 km) 3/27/03 2-2. 1970 Population Distribution 0-10 Miles (0-16.1 kin) 3/27/03 2-3. 1980 Projected Population Distribution 0-10 Miles (0-16.1 km) 3/27/03 2-4. 1981 Projected Population Distribution (Initial Expected Year of Plant Start-up) 0-10 Miles (0-16.1 km) 3/27/03 2-5. 1990 Projected Population Distribution 0-10 Miles (0-16.1 km) 3/27/03 2-6. 2000 Projected Population Distribution 0-10Miles (0-16.1 km) 3/27/03 2-7. 2010 Projected Population Distribution 0-10 Miles (0-16.1 km) 3/27/03 2-8. 2020 Projected Population Distribution 0-10 Miles (0-16.1 km) 3/27/03 2-9. 1970 Population Distribution 0-50 Miles (0-80.4 km) 3/27/03 2-10. 1980 Projected Population Distribution 0-50 Miles (0-80.4 km) 3/27/03 2-11. 1981 Projected Population Distribution (Initial Expected Year of Plant Start-up) 0-50 Miles (0-80.4 kin) 3/27/03 2-12. 1990 Projected Population Distribution 0-50 Miles (0-80.4 km) 3/27/03 2-13. 2000 Projected Population Distribution0-5OMiles (0-80.4 kin) 3/27/03 2-14. 2010 Projected Population Distribution 0-50 Miles (0-80.4 km) 3/27/03 2-15. 2020 Projected Population Distribution 0-50Miles (0-80.4 km) 3/27/03 2-16. 1977 Seasonal Recreational Transient Population 3/27/03 2-17. 1977 Average Daily Recreational Transient Population 3/27/03 2-18. 1977 Daily Industrial Transient Population 3/27/03 2-19. Peak Day Transient Population 0-5 Miles (0-8 km) 3/27/03 2-20. 1977 Transient Population Recreation Areas and Facilities 3/27/03 2-21. 1977 Transient Population Industrial and Institutional 10/24/04 2-22. Description of Nearby and Significant Industries 10/24/04 2-23. Annual Aircraft Operations Douglas Municipal Airport 10/24/04 2-24. Aviation Routes - Annual Usage Page I of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/24/04 2-25. Hazardous Chemicals Received at Nearby Facilities 10/24/04 2-26. Hazardous Chemicals Shipped and Received by Nearby Industries 3/27/03 2-27. Tropical Cyclones Affecting the Site Area, 1964-1980 3/27/03 2-28. Tornado Occurrences 1956-1980 (20 Square Centered on Site) 3/27/03 2-29. Catawba Nuclear Station Vicinity Climatology 3/27/03 2-30. Catawba Nuclear Station Onsite Data January 1, 1976 - December 31, 1977 3/27/03 2-31. Structural Design Meteorological Data 3/27/03 2-32. Ultimate Heat Sink Meteorological Data Worst Cooling Periods 3/27/03 2-33. Ultimate Heat Sink Meteorological Data Highest Evaporation Periods 10/24/04 2-34. Catawba Semiannual Calibration Listing - Page 1 10/24/04 2-35. 1979 - 1977 Wind Occurrences (10 m) 10/24/04 2-36. Hourly Dilution Factors at the Exclusion Area Boundary for Each Sector 10/24/04 2-37. Hourly Dilution Factors at the Low Population Zone Boundary for Selected Sectors 10/22/01 2-38. Cumulative Frequency Distribution at Integer Percentile Levels - 8 Hour Average 10/22/01 2-39. Cumulative Frequency Distribution at Integer Percentile Levels - 16 Hour Average 10/22/01 2-40. Cumulative Frequency Distribution at Integer Percentile Levels - 72 Hour Average 10/22/01 2-41. Cumulative Frequency Distribution at Integer Percentile Levels - 624 Hour Average 10/24/04 2-42. Annual Average X/Q Values to 50 Miles - Sector Average 10/24/04 2-43. Annual Average X/Q Values with Depletion to 50 Miles - Sector Average 3/27/03 2-44. 1975 - 1977 Wind Occurrences (40 m) 10/24/04 2-45. Annual Average D/Q Values to 50 Miles - Sector Average 4/24/06 2-46. Catawba Nuclear Station Annual Average X/Q Values at Intake Vents Control Room X/Q Values for Accident Conditions 10/22/01 2-47. Dilution Factors for Accident Releases 10/24/04 2-48. Catawba Nuclear Station Dilution Factors for Routine Releases - Offsite 10/24/04 2-49. Relative Frequency Distribution 10/24/04 2-50. Charlotte, N. C. - Climatic Comparison 10/24/04 2-51. Dams on the Catawba River 10/24/04 2-52. Surface Water Intakes 3/27/03 2-53. Flood Peak Return Period 10/22/01 2-54. Deleted Per 1992 Update 3/27/03 2-55. Maximum Storms in the Southeast 10/22/01 2-56. Deleted Per 1990 Update 10/22/01 2-57. Deleted Per 1990 Update 3/27/03 2-58. Rainfall Subarea Coefficients 3/27/03 2-59. Parameters Used in Flood Routing 3/27/03 2-60. Storage And Discharge Values For Reservoirs For Rising Reservoir Condition 3/27/03 2-61. Maximum Reservoir Elevations Resulting From PMF 3/27/03 2-62. Reservoir Inflow, Outflow and Elevation for PMF 3/27/03 2-63. Coincident Wind/Wave Activity 3/27/03 2-64. Maximum Reservoir Elevations Resulting From Seismic Dam Failures With SPF Page 2 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 3/27/03 2-65. Maximum Reservoir Elevations Resulting From Seismic Failure at Cowans Ford Dam With SPS 3/27/03 2-66. Standby Nuclear Service Water Pond 3/27/03 2-67. Low Flow into Lake Wylie 3/27/03 2-68. Lake Wylie Minimum Surface Water Elevations 3/27/03 2-69. Summary of Residential Well Survey Data Immediate Vicinity of Site 3/27/03 2-70. Groundwater Intakes 3/27/03 2-71. River Bank Groundwater Intakes 3/27/03 2-72. Rock Permeability Test Results 3/27/03 2-73. Soil Permeability Test Results 3/27/03 2-74. Summary of Pumping Test No. 1 - Test Well A-85TW 3/27/03 2-75. Summary of Pumping Test No. 2 - Test Well A-48TW 3/27/03 2-76. Results of Physical and Chemical Tests on Groundwater 3/27/03 2-77. Ion Exchange Capacity of Soils 10/22/01 2-78. Groundwater Monitoring Program 10/24/04 2-79. Observation Well Monitoring 3/27/03 2-80. Geologic Time Scale 3/27/03 2-81. Summary of Regional Tectonic Structures 3/27/03 2-82. Summary Of Stress Measurements 3/27/03 2-83. Site Geologic History As Related to Regional Geology 3/27/03 2-84. Historic Earthquakes--Southeastern United States 3/27/03 2-85. Earthquakes With Epicenters Located Within 50 Miles of the Catawba Site 3/27/03 2-86. Historic Earthquakes Probably Felt At The Catawba Site 3/27/03 2-87. Summary of Rock And Water Levels In The Test Borings 3/27/03 2-88. Summary of Test Pits 3/27/03 2-89. Laboratory Permeability Test Results Compacted Plant Area Residual Soils 10/22/01 2-90. Summary of Significant Foundation Engineering Characteristics 10/22/01 2-91. Summary of Significant Foundation Engineering Characteristics 10/22/01 2-92. Summary of Significant Foundation Engineering Characteristics - Seismic Design Criteria 3/27/03 2-93. Soil and Partially Weathered Rock Permeability Constant Head Field Tests Standby Nuclear Service Water Pond Dam 3/27/03 2-94. Summary of Design Static Shear Strength Parameters For Standby Nuclear Service Water Pond Dam 3/27/03 2-95. Rock Permeability Constant Head Field Tests Standby Nuclear Service Water Pond Dam Foundation 3/27/03 2-96. SNSW Pond Dam - Equipment Used During Dam Construction 3/27/03 2-97. Safety Factors of SNSW Pond Dam Under Static Loading 3/27/03 2-98. Laboratory Cyclic Triaxial Tests 3/27/03 2-99. Laboratory Cyclic Triaxial Tests 3/27/03 2-100. Laboratory Cyclic Triaxial Tests 3/27/03 2-101. Safety Factors of SNSW Pond Dam Under Earthquake Loading, Pseudo-Dynamic and Newmark Analyses Section Through Borings Al17 & All8 3/27/03 2-102. Soil Permeability Laboratory Test Results 3/27/03 2-103. Soil Permeability Laboratory Test Results 3/27/03 2-104. SNSW Pond Dam Filter Permeability Laboratory Test Results 4/24/06 2-105. Design Basis Values of Control Room X/Qs Page 3 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) Chapter 3 Tables 10/22/01 3-1. Summary of Criteria - Structures 4/24/06 3-2. Summary of Criteria - Equipment (page 1) 10/22/01 3-3. Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units 11/15/07 3-4. Summary of Criteria - Mechanical System Components 10/22/01 3-5. System Piping Classification 10/22/01 3-6. System Valve Classification 4/24/06 3-7. Equipment Generated Missiles Safety Related Structures Design Characteristics 10/22/01 3-8. Summary Of Control Rod Drive Mechanism Missile Analysis 10/22/01 3-9. Piping Temperature Element Assembly - Missile Characteristics 10/22/01 3-10. Characteristics Of Other Missiles Postulated Within Reactor Containment 10/22/01 3-11. Hypothetical Missile Data 43-Inch Last Stage Bucket, 1800-RPM Low Pressure Turbine 4/24/06 3-12. Turbine Missile Strike Probability High Trajectory Missiles 10/22/01 3-13. Turbine Missile Penetration and Damage Probabilities High Trajectory Missiles 4/24/06 3-14. Turbine Missile Total Plant Damage Probability High Trajectory Missiles 10/22/01 3-15. Design Basis Tornado Generated Missiles 10/22/01 3-16. Design Basis Tornado Generated Missiles -Minimum Barrier Thickness 10/22/01 3-17. High-Energy Mechanical Piping Systems Analyzed for Consequences of Postulated Piping Breaks 10/22/01 3-18. Moderate-Energy Mechanical Piping Systems Analyzed for Consequences of Postulated Piping Breaks 10/22/01 3-19. Comparison of Duke Pipe Rupture Criteria And NRC Requirements of Branch Technical Positions APCSB 3-1 (November 1975), MEB 3-1 (November 1975), and NRC Regulatory Guide 1.46 (May 1973) 10/22/01 3-20. Postulated Break Locations For The Main Coolant Loop 10/22/01 3-21. Stress Criteria For Reactor Containment Mechanical Penetrations (2) Duke Class B 10/22/01 3-22. Stress Allowables for Design of Pipe Rupture Restraints 10/22/01 3-23. Deleted Per 1990 Update 10/22/01 3-24. Deleted per 2001 Update 10/22/01 3-25. Summary of Modal Contributions to Total Forces for North South Earthquake 10/22/01 3-26. Comparison Of Response Spectrum And Time-History Responses 10/22/01 3-27. Comparison of two Dimensional Versus Three Dimensional Analysis 10/22/01 3-28. Static and Seismic Incremental Lateral Earth Pressures for Check of Substructure Walls Using Mononobe-Okabe Incremental Lateral Pressure 10/22/01 3-29. Scope Limits for Alternate Seismic Analysis 10/22/01 3-30. Seismic Instrumentation Implementation 11/15/07 3-31. Codes and Specifications for Design of Category I Structures 10/22/01 3-32. Load Combinations for Category I Structures 10/22/01 3-33. Concrete Mix Designs 10/22/01 3-34. Quality Control Tests for Aggregates Page 4 of 57.

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 3-35. Comparison of Concrete Design Criteria 10/22/01 3-36. Shell Wall Design Forces and Reinforcement 10/22/01 3-37. Containment Vessel Loading Combinations 10/22/01 3-38. Containment Stress Limits 10/22/01 3-39. Containment Coatings'(deleted per 1997 Update) 10/22/01 3-40. Containment Materials 10/22/01 3-41. Containment Allowable Stress Intensities 10/22/01 3-42. Containment Stress Intensities 10/22/01 3-43. Containment Buckling Factors of Safety 10/22/01 3-44. Statistical Containment Material Properties Based on Mill Test Reports 10/22/01 3-45. Ultimate Containment Capacity Analysis Summary 10/22/01 3-46. Design Properties of Seals 10/22/01 3-47. Catawba Compartment Pressurization Analysis 10/22/01 3-48. Maximum Blowdown LOCA Load Resultants For The Containment Interior Structure 10/22/01 3-49. Crane Wall Design 3/27/03 3-50. Design Transients for ASME Code Class I Piping 10/22/01 3-51. Loading Combinations for ASME Class I Components and Supports 10/22/01 3-52. Allowable Stresses for ASME Section III Class I Components 10/22/01 3-53. Class I Valve Faulted Condition Criteria 10/22/01 3-54. Maximum Reactor Vessel Displacements at Reactor Vessel Centerline 10/22/01 3-55. Maximum Reactor Vessel Support Loads For Postulated Pipe Rupture Conditions 10/22/01 3-56. Computer Programs Used in Analysis 10/22/01 3-57. Computer Programs Used in Analysis 10/22/01 3-58. Computer Programs Used in Analysis 10/22/01 3-59. Computer Programs Used in Analysis 10/22/01 3-60. Computer Programs Used in Analysis 10/22/01 3-61. Computer Programs Used in Analysis 10/22/01 3-62. Computer Programs Used in Analysis 10/22/01 3-63. Computer Programs Used in Analysis 10/22/01 3-64. Computer Programs Used in Analysis 10/22/01 3-65. Computer Programs Used in Analysis 10/22/01 3-66. Computer Programs Used in Analysis 10/22/01 3-67. Computer Programs Used in Analysis 10/22/01 3-68. Computer Programs Used in Analysis 10/22/01 3-69. Computer Programs Used in Analysis 10/22/01 3-70. Computer Programs Used in Analysis 10/22/01 3-71. Computer Programs Used in Analysis 10/22/01 3-72. Computer Programs Used in Analysis 10/22/01 3-73. Computer Programs Used in Analysis 10/22/01 3-74. Computer Programs Used in Analysis 10/22/01 3-75. Computer Programs Used in Analysis 10/22/01 3-76. Computer Programs Used in Analysis 10/22/01 3-77. Computer Programs Used in Analysis 10/22/01 3-78. Computer Programs Used in Analysis 10/22/01 3-79. Computer Programs Used in Analysis 10/22/01 3-80. Computer Programs Used in Analysis 10/22/01 3-81. Computer Programs Used in Analysis 10/22/01 3-82. Computer Programs Used in Analysis 10/22/01 3-83. CRDM Moments - Head Adaptor Location 10/22/01 3-84. Piping Systems Included In Vibration Test Program Page 5 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 3-85. Piping Systems Included In Transient Vibration Test Program 10/22/01 3-86. Piping Systems Included In Thermal Expansion Test Program 10/22/01 3-87. Maximum Deflections Allowed for Reactor Internal Support Structures 10/22/01 3-88. Design Loading Combinations for ASME Code Class 2 and 3 Components and Supports 10/22/01 3-89. Design Loading Combinations for ASME Code Core Support Structures 10/22/01 3-90. Stress Criteria for Safety Related ASME Class 2 and Class 3 Tanks 10/22/01 3-91. Stress Criteria for Safety Related Class 2 Tanks 10/22/01 3-92. Stress Criteria for ASME Code Class 2 and Class 3 Inactive Pumps 10/22/01 3-93. Design Criteria for Active Pumps 10/22/01 3-94. Stress Criteria for Safety Related ASME Code Class 2 and Class 3 Valves 10/22/01 3-95. Stress Criteria and Load Combination Requirements for Duke Class A Piping 10/22/01 3-96. Stress Criteria and Load Combination Requirements for Duke Class B, C, and F Piping 10/22/01 3-97. Stress Limits for Duke Safety Related Equipment and Valves 10/22/01 3-98. Deleted Per 1990 Update 10/22/01 3-99. Deleted Per 1990 Update 10/22/01 3-100. Deleted Per 1990 Update 10/22/01 3-101. Loading Conditions, Load Combination, and Allowable Stresses for Supports, Restraints and Anchors for Duke Classes A, B, C and F(6) 10/22/01 3-102. Loading Conditions and Load Combination Requirements for Snubbers Duke Classes A, B, C, F 10/22/01 3-103. Active Pumps 11/15/07 3-104. Active Valves 3/27/03 3-105. Deleted per 2003 Update 3/27/03 3-106. Deleted per 2003 Update 10/22/01 3-107. Control Complex Areas Ventilation Systems Analysis Results 10/22/01 3-108. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 562+0 10/22/01 3-109. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 562+0 10/22/01 3-110. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 595+4 10/22/01 3-11-1. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 595+4 10/22/01 3-112. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 628+8 10/22/01 3-113. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 628+8 10/22/01 3-114. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 662+0 10/22/01 3-115. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 662+0 10/22/01 3-116. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 691+2 10/22/01 3-117. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 691+2 Page 6 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 3-118. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 713+1 10/22/01 3-119. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 713+1 Chapter 4 Tables 3/27/03 4-1. Reactor Design Comparison Table 4/24/06 4-2. Analytical Techniques In Core Design 10/22/01 4-3. Design Loading Conditions For Reactor Core Components 3/27/03 4-4. Reactor Core Description 4/24/06 4-5. Nuclear Design Parameters 10/22/01 4-6. Nuclear Design Parameters 10/22/01 4-7. Reactivity Requirements For Rod Cluster Control Assemblies 11/15/07 4-8. UO2 Benchmark Critical Experiments [3] 10/22/01 4-9. Axial Stability Index Pressurized Water Reactor Core With A 12 Foot Height 3/27/03 4-10. Typical Neutron Flux Levels (n/cm 2-sec) At Full Power 10/22/01 4-11. Deleted per 1998 Update 10/22/01 4-12. Deleted per 2001 Update 10/22/01 4-13. Saxton Core II Isotopics Rod My, Axial Zone 6 3/27/03 4-14. Critical Boron Concentrations, HZP, BOL 3/27/03 4-15. Benchmark Critical Experiments B4C Control Rod Worth 3/27/03 4-16. Comparison Of Measured And Calculated Moderator Coefficients At HZP, BOL 10/22/01 4-17. Thermal And Hydraulic Comparison Table (Deleted per 2000 Update) 10/22/01 4-18. Deleted Per 1993 Update 10/22/01 4-19. Void Fractions At Nominal Reactor Conditions With Design Hot Channel Factors 10/22/01 4-20. Measurements Required In The Calculation Of Reactor Flow Using A Calorimetric Technique 4/24/06 4-21 Statistically combined Uncertainty Factors for Fq, FAH, and F, 3/27/03 4-22. Elbow Tap Coefficients 4/24/06 4-23. Fuel Assembly Design Information for Current Demonstration Programs 4/24/06 4-24. Mechanical and Thermal Hydraulic Analysis Methods for Current Demonstration Programs Chapter 5 Tables 10/22/01 5-1. System Design and Operating Parameters - page 1 10/22/01 5-2. Applicable Code Addenda for RCS Components 10/22/01 5-3. Code Cases Applicable for Operation, Maintenance, and Testing Activities 10/22/01 5-4. ASME Code Cases Used For Catawba Units 1 &2 Class 1 Components 10/22/01 5-5. Typical Plant Thermal-Hydraulic Parameters 10/22/01 5-6. Class 1 Primary Components Material Specifications 10/22/01 5-7. Class 1 and 2 Auxiliary Components Material Specifications 10/22/01 5-8. Reactor Vessels Internals for Emergency Core Cooling 10/22/01 5-9. Reactor Coolant Chemistry Specification (Deleted per 1998 Update) 11/15/07 5-10. Leakage Detection Sensitivity 10/22/01 5-11. Reactor Vessel Quality Assurance Program 10/24/04 5-12. Toughness Properties for the Catawba Unit 1 Reactor Vessel Page 7 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/24/04 5-13. Fracture Toughness Properties for the Catawba Unit 2 Reactor Vessel 10/24/04 5-14. Fracture Toughness Properties Of The Catawba Unit 1 Reactor Vessel Beltline Region Material 10/24/04 5-15. Fracture Toughness Properties Of The Catawba Unit 2 Reactor Vessel Beltline Region Material 10/22/01 5-16. Catawba Unit 1 Closure Head Bolting Material Properties 10/22/01 5-17. Catawba Unit 2 Closure Head Bolting Material Properties 10/22/01 5-18. Reactor Vessel Design Parameters 10/24/04 5-19. Chemical Composition Of The Catawba Unit 1 Reactor Vessel Beltline Region Material 10/24/04 5-20. Chemical Composition Of The Catawba Unit 2 Reactor Vessel Beltline Region Material 10/22/01 5-21. Catawba Unit I Reactor Vessel Beltline Region Toughness Properties 10/22/01 5-22. Catawba Unit 2 Reactor Vessel Beltline Region Toughness Properties 10/22/01 5-23. Reactor Coolant Pump Design Parameters 10/22/01 5-24. Reactor Coolant Pump Quality Assurance Program 11/15/07 5-25. Steam Generator Design Data 10/22/01 5-26. Steam Generator Quality Assurance Program - page 1 10/22/01 5-27. Reactor Coolant Piping Design Parameters 10/22/01 5-28. Reactor Coolant Piping Quality Assurance Program 10/22/01 5-29. Design Bases for Residual Heat Removal System Operation 4/18/09 5-30. Residual Heat Removal System Component Data 11/15/07 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation 10/22/01 5-32. Pressurizer Design Data 11/15/07 5-33. Pressurizer Quality Assurance Program 10/22/01 5-34. Pressurizer Relief Tank Design Data 10/22/01 5-35. Relief Valve Discharge To The Pressurizer Relief Tank 10/22/01 5-36. Reactor Coolant System Boundary Valve Design Parameters 10/22/01 5-37. Pressurizer Valves Design Parameters 10/22/01 5-38. Component Supports 10/22/01 5-39. Materials 4/18/09 5-40. Reactor Vessel Material Surveillance Program - Withdrawal Schedule 10/22/01 5-41. Reactor Coolant System Pressure Isolation Valves 4/18/09 5-42. RT PTS Calculations for Catawba Unit I Beltline Region Materials at 54 EFPY 10/24/04 5-43. RT PTS Calculations for Catawba Unit 2 Beltline Region Materials at 54 EFPY 10/24/04 5-44. Evaluation of Upper Shelf Energy for Catawba Unit 1 Beltline Region Materials at 54 EFPY 10/24/04 5-45. Evaluation of Upper Shelf Energy for Catawba Unit 2 Beltline Region Materials at 54 EFPY 11/15/07 5-46.Summary of Reactor Coolant System Leakage Detection Instrumentation Exceptions and Comments to Regulatory Guide (RG) 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems", (rev.0) Chapter 6 Tables 10/24/04 6-1. Engineered Safety Feature Materials (Page 1) 4/24/06 6-2. Parameters of Final Post-accident Chemistry 10/22/01 6-3. Protective Coatings on Westinghouse-supplied Equipment Inside Containment 10/22/01 6-4. Organic Materials Inside Containment Page 8 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 6-5. Potential Water Traps Inside Containment 10/22/01 6-6. Catawba Ice Condenser Design Parameters 4/18/09 6-7. ECCS and Spray Flow Rates Assumed in Peak Containment Pressure Transient 10/22/01 6-8. Structural Heat Sink Data For Peak Containment Temperature Transient 10/22/01 6-9. Structural Heat Sink Data For Peak Containment Pressure Transient (Deleted per 1997 Update) 10/22/01 6-10. Energy Accounting for Peak Containment Pressure Transient (106 Btu) (Deleted per 1997 Update) 10/22/01 6-11. Mass And Energy Release Rates For Peak Reverse Differential Pressure 11/15/07 6-12. Allowance Leakage Area for Various Reactor Coolant System Break Sizes 10/22/01 6-13. TMD Element Input Data 10/22/01 6-14. TMD Flow Path Input Data 10/22/01 6-15. Calculated Maximum Peak Pressures In Lower Compartment Elements Assuming Unaugmented Flow 10/22/01 6-16. Calculated Maximum Peak Pressures In The Ice Condenser Compartment Assuming Unaugmented Flow 10/22/01 6-17. Calculated Maximum Differential Pressures Across The Operating Deck Assuming Unaugmented Flow 10/22/01 6-18. Calculated Maximum Differential Pressures Across The Upper Crane Wall Assuming Unaugmented Flow 4/18/09 6-19. Containment Sump Volume Vs. Time Peak Containment Pressure Transient 3/27/03 6-20. Containment Sump Volume Vs. Elevation 10/22/01 6-21. Sensitivity Studies For D.C. Cook Plant 10/22/01 6-22. Mass and Energy Releases into Steam Generator Enclosure 10/22/01 6-23. TMD Input Data - 2 Node Steam Generator Enclosure 10/22/01 6-24. Peak Differential Pressures-2 Node Steam Generator Enclosure 10/22/01 6-25. TMD Input Data - 9 Node Steam Generator Enclosure 10/22/01 6-26. Peak Differential Pressure-9 Node Steam Generator Enclosure 10/22/01 6-27. Mass and Energy Release Rates Into Pressurizer Enclosure 10/22/01 6-28. TMD Input Data - 2 Node Pressurizer Enclosure 10/22/01 6-29. TMD Input Data - 4 Node Pressurizer Enclosure 10/22/01 6-30. Mass and Energy Release Rates Into Reactor Cavity 10/22/01 6-31. Reactor Cavity Analysis Volumes - Cold Leg Break 10/22/01 6-32. Reactor Cavity Analysis Flow Paths - Cold Leg Break 10/22/01 6-33. Reactor Cavity Design Pressures 10/22/01 6-34. Mass and Energy Release Rates for Blowdown 10/22/01 6-35. Mass and Energy Release Rates for Blowdown 10/22/01 6-36. Mass and Energy Release Rates for Blowdown 10/22/01 6-37. Mass and Energy Release Rates for Blowdown 10/22/01 6-38. Mass and Energy Release Rates for Blowdown 10/22/01 6-39. Mass and Energy Release Rates for Blowdown 10/22/01 6-40. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 10/22/01 6-41. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 10/22/01 6-42. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 10/22/01 6-43. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 10/22/01 6-44. Mass and Energy Release Rates for Post-Reflood (Deleted per 1997 Update) 10/22/01 6-45. Mass and Energy Releases Rates for Post-Reflood (Deleted per 1997 Update) Page 9 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 6-46. Mass and Energy Release Rates Post-Reflood (Deleted per 1997 Update) 10/22/01 6-47. Mass and Energy Release Rates for Peak Containment Temperature Transient for Double Ended Steam Line Rupture 10/22/01 6-48. Mass and Energy Release Rates for Peak Containment Temperature Transient for Double Ended Steam Line Rupture (Deleted per 1997 Update) 10/22/01 6-49. Mass and Energy Release Rates for Peak Containment Temperature Transient (Deleted per 1997 Update) 10/22/01 6-50. Mass and Energy Release Rates for Peak Containment Temperature Transient (Deleted per 1997 Update) 10/22/01 6-51. Mass and Energy Release Rates for Peak Containment Superheat Duration Transient (Deleted per 1997 Update) 10/22/01 6-52. Mass and Energy Release Rates for Peak Containment Superheat Duration Transient (Deleted per 1997 Update) 10/22/01 6-53. Mass and Energy Balances (Deleted per 1997 Update) 10/22/01 6-54. Mass and Energy Balances (Deleted per 1997 Update) 10/22/01 6-55. Mass and Energy Balances (Deleted per 1997 Update) 10/22/01 6-56. Mass and Energy Balances (Deleted per 1997 Update) 10/22/01 6-57. Mass and Energy Balances (Deleted per 1997 Update) 10/22/01 6-58. Double Ended Pump Suction Guillotine Max SI 10/22/01 6-59. DCP/Double Ended Pump Suction Guillotine Mini SI 10/22/01 6-60. Basis for Peak Containment Pressure Mass and Energy Release Analysis (Deleted per 2000 Update) 10/22/01 6-61. Mass and Energy Release Rates For Minimum Post-LOCA Containment Pressure 10/22/01 6-62. Minimum Post-LOCA Containment Pressure Broken Loop Accumulator Flow to Containment 10/22/01 6-63. Containment and Active Heat Sink Data for Peak Reverse Differential Pressure 10/22/01 6-64. Structural Heat Sink Data For Minimum Post-LOCA Containment Pressure 10/22/01 6-65. Structural Heat Sink Data for Peak Reverse Differential Pressure 10/22/01 6-66. Containment and Active Heat Sink Data for Minimum Post-LOCA Containment Pressure 10/22/01 6-67. Summary Of Steamline and Feedwater Line Isolation Times (Deleted per 2000 Update) 3/27/03 6-68. Air Return Fans and Hydrogen Skimmer Fans Failure Analysis 10/22/01 6-69. Deleted Per 1990 Update 4/18/09 6-70. Containment Spray Pump Design Parameters 11/15/07 6-71. Containment Spray Heat Exchanger Operating Parameters 10/22/01 6-72. Containment Spray System Single Failure Analyses 10/22/01 6-73. Failure Mode and Effects Analysis - Containment Spray System - Active Components 3/27/03 6-74. Potential Bypass Leak Paths Through Containment Isolation Valves 4/24/06 6-75. Typical Annulus Conditions vs. Time Following Design Basis Accident 4/24/06 6-76. Dual Containment Characteristics 4/18/09 6-77. Containment Isolation Valve Data 3/27/03 6-78. Comparison of Containment Purge System With Branch Technical Position CSB 6-4, Revision 2 4/24/06 6-79. Applicable Codes, Standards and Guides Used in the Design of the Electric H2 Recombiner Attachment I Page 10 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 4/24/06 6-80. Electric Hydrogen Recombiner Typical Parameters 10/22/01 6-81. Containment Hydrogen Sample and Purge System Design Data 4/24/06 6-82. Deleted per 2006 Update 4/24/06 6-83. Deleted per 2006 Update 10/22/01 6-84. Deleted Per 1991 Update 10/22/01 6-85. Deleted Per 1991 Update 10/22/01 6-86. Deleted Per 1991 Update 10/24/04 6-87. Emergency Core Cooling System Component Parameters 10/22/01 6-88. ECCS Relief Valve Data 10/22/01 6-89. Motor Operated Isolation Valves In ECCS 10/22/01 6-90. Materials Employed For Emergency Core Cooling System Components 4/18/09 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System

                  - Active Components 10/22/01     6-92. Single Active Failure Analysis For Emergency Core Cooling System Components 4/18/09      6-93. Sequence Of Changeover Operation From Injection To Recirculation 10/22/01     6-94. Emergency Core Cooling System Recirculation Piping Passive Failure Analysis 10/22/01     6-95. Safety Related Solenoid Valves Inside Containment Below Elevation 571'0" 10/22/01     6-96. Active Valves Inside Containment Below Elevation 571'0" 10/22/01     6-97. Emergency Core Cooling System Shared Functions Evaluation 10/22/01     6-98. Normal Operating Status Of Emergency Core Cooling System Components For Core Cooling 10/22/01     6-99. Parameters for Boron Precipitation Analysis 10/22/01     6-100. Comparison of Control Room Protection Against Toxic Gas Hazards With Regulatory Guide 1.95 10/22/01     6-101. Comparison of Control Room Protection Against Toxic Gas Hazards With Regulatory Guide 1.78 10/22/01     6-102. Ice Condenser Elemental Iodine Removal Efficiency 10/22/01     6-103. Process Lines Subject to Augmented Inservice Inspection 10/22/01     6-104. Wall Panel Design Loads 10/24/04     6-105. Ice Basket Load Summary 10/22/01     6-106. Summary of Stresses in Basket Due to Design Loads 10/22/01     6-107. Ice Basket Material Minimum Yield Stress 10/22/01     6-108. Allowable Stress Limits (D + OBE) For Ice Basket Materials 10/22/01     6-109. Allowable Stress Limits (D + SSE), (D + DBA) For Ice Basket Materials 10/22/01     6-110. Allowable Stress Limits (D + SSE + DBA) For Ice Basket Materials 10/22/01     6-111. Ice Basket Clevis Pin Stress Summary 10/22/01     6-112. Ice Basket Mounting Bracket Assembly Stress Summary 10/22/01     6-113. Ice Basket Plate Stress Summary 10/22/01     6-114. Ice Basket V-Bolt Stress Summary 10/22/01     6-115. Ice Basket - Basket End Stress Summary 10/22/01     6-116. Ice Basket Coupling Screw Stress Summary 10/22/01     6-117. Ice Basket Coupling Screw Stress Summary 10/22/01     6-118. Ice Basket Coupling Screw Stress Summary 10/22/01     6-119. Ice Basket Coupling Screw Stress Summary 10/22/01     6-120. Crane and Rail Assembly Design Loads 10/22/01     6-121. Refrigeration System Parameters 10/22/01     6-122. Lower Inlet Door Design Parameters and Loads Attachment I                                                                     Page 11 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 6-123. Top Deck Design Parameters and Loads 10/22/01 6-124. Summary of Results 10/22/01 6-125. Intermediate Deck Design Parameters and Loads 10/22/01 6-126. Summary of Waltz Mill Tests 10/24/04 6-127. Ice Condenser Temperature Instrumentation 10/22/01 6-128. Ice Condenser Allowable Limits 10/22/01 6-129. Summary of Catawba Loads-Tangential Case Obtained Using The Two-Mass Dynamic Model 10/22/01 6-130. Summary of Catawba Loads-Radial Case Obtained Using the Two-Mass Dynamic Model 10/22/01 6-131. Summary of Load Results of Five Non-Linear Dynamic Models 10/22/01 6-132. Summary of Parameters Used In The Seismic Analysis 10/22/01 6-133. Selection of Steels in Relation to Prevention of Non-Ductile Fracture of Ice Condenser Components 10/22/01 6-134. Swivel Bracket Stress Summary (Ref.19) Load Case IV 10/22/01 6-135. Containment Coating 10/22/01 6-136. Cruciform Cable Suspension System Design/Test Load Summary 10/22/01 6-137. External Coupling Ring and Rivet Design Load/Stress Summary 10/22/01 6-138. Ice Basket Load Summary - Basic Design Loads (2000 Lb. Basket) Chapter 7 Tables 10/22/01 7-1. List of Reactor Trips 10/22/01 7-2. Protection System Interlocks 4/24/06 7-3. Reactor Trip System Instrumentation 10/22/01 7-4. Reactor Trip Correlation 10/22/01 7-5. Instrumentation Operating Condition for Engineered Safety Features 10/22/01 7-6. Instrument Operating Conditions for Isolation Functions 10/22/01 7-7. Interlocks for Engineered Safety Features Actuation System 10/22/01 7-8. Auxiliary Shutdown Panel A Instrumentation And Controls Available For Hot Shutdown 10/22/01 7-9. Auxiliary Shutdown Panel B Instrumentation And Controls Available For Hot Shutdown 10/22/01 7-10. Auxiliary Feedwater Pump Turbine Control Panel Instrumentation And Controls Available For Hot Shutdown 4/24/06 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation 10/22/01 7-12. Plant Control System Interlocks 10/22/01 7-13. Deleted Per 1990 Update 10/22/01 7-14. ESF Bypass Indication 3/27/03 7-15. ESF Response Times 3/27/03 7-16. Main Control Board Indicators and/or Recorders Available to the Operator (Condition II, II and IV Events). Chapter 8 Tables 10/22/01 8-1. Class 1E Loads 10/22/01 8-2. Transmission Structures Design Specifications 4/24/06 8-3. Description of Transmission Lines 10/22/01 8-4. Grid Frequency Decay Analysis Attachment I Page 12 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 8-5. Transmission System Availability 4/18/09 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems 10/22/01 8-7. Catawba Nuclear Station - Switchgear Control Power Sources 10/22/01 8-8. Single Failure Analysis of the Onsite Power Systems 10/22/01 8-9. Deleted Per 1991 Update 10/22/01 8-10. Single Failure Analysis of the 125VDC Vital Instrumentation and Control Power System 10/24/04 8-11. Single Failure Analysis of the 120VAC Vital Instrumentation and Control Power System 10/22/01 8-12. Single Failure Analysis of the 125VDC Diesel Essential Auxiliary Power System Chapter 9 Tables 10/22/01 9-1. Spent Fuel Cooling System Component Design Parameters 4/24/06 9-2. Nuclear Service Water System Component Design Parameters 4/18/09 9-3. Nuclear Service Water System Flow Rates Outside the Nuclear Service Water Pumphouse 4/18/09 9-4. Nuclear Service Water System Failure Analysis 3/27/03 9-5. Nominal Nuclear Service Water System Flow Rates in the Nuclear Service Water Pumphouse 11/15/07 9-6. Component Cooling System Heat Load and Flow Requirements 10/22/01 9-7. Component Cooling System Valve Alignment for Various Modes of Operation 4/24/06 9-8. Component Cooling System Component Design Data - page 1 10/22/01 9-9. Component Cooling System 10/24/04 9-10. Makeup Demineralized Water System Component Design Parameters 11/15/07 9-11. Filtered Water System and Drinking Water System Component Design Parameters - page 1 10/22/01 9-12. Deleted Per 1994 Update 10/22/01 9-13. Deleted Per 1994 Update 10/22/01 9-14. Condensate Storage System Design Parameters 10/22/01 9-15. Refueling Water System Component Design Data 4/24/06 9-16. Conventional Low Pressure Service Water System Component Design Parameters 10/22/01 9-17. Compressed Air Systems Component Design Parameters 10/22/01 9-18. Nuclear Sampling System Sample Locations and Data 10/22/01 9-19. Temperature and Pressure Reduction for Samples in the Conventional Systems Sample Panel 10/24/04 9-20. Types of Analyses Provided in the Conventional Sampling Lab 3/27/03 9-21. Chemical and Volume Control System Design Parameters 3/27/03 9-22. CVCS Principal Component Data Summary 3/27/03 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System 10/24/04 9-24. Boron Recycle System Component Data Summary 10/22/01 9-25. Boron Thermal Regeneration System Component Data 10/22/01 9-26. Control Room Area Ventilation System Failure Analysis 10/22/01 9-27. Fuel Handling Area Exhaust System Failure Analysis 10/22/01 9-28. Auxiliary Building Ventilation System Failure Analysis 10/22/01 9-29. Purge System Isolation Valve Design and Test Criteria 10/22/01 9-30. Annulus Ventilation System Attachment I Page 13 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 9-31. Summary of Fire Protection Documents Submitted to the NRC 10/22/01 9-32. Communications Available for Transient and Accident Conditions 3/27/03 9-33. Communications and Lighting Available for Safe Shutdown of Plant 10/22/01 9-34. Single Failure Analysis of the Emergency Lighting Systems 10/24/04 9-35. Lighting Systems Available to illuminate Safety Related Equipment 10/24/04 9-36. 8-Hour Lighting for Post-Fire Alternate Shutdown Utilizing the Standby Shutdown System 10/22/01 9-37. Diesel Generator Engine Fuel Oil System Single Failure Analysis 10/24/04 9-38. Deleted Per 2004 Update 10/22/01 9-39. Diesel Generator Engine Cooling Water System Single Failure Analysis 10/22/01 9-40. Diesel Generator Engine Cooling Water System Alarm and Shutdown Setpoints 10/22/01 9-41. Diesel Generator Engine Starting Air System Single Failure Analysis 10/22/01 9-42. Diesel Generator Engine Lube Oil System Single Failure Analysis 10/22/01 9-43. Diesel Generator Engine Lube Oil System Alarm and Shutdown Setpoints 10/22/01 9-44. Diesel Generator Engine Intake and Exhaust System Single Failure Analysis 10/22/01 9-45. Comparison of VQ System to BTP CSB 6-4 10/22/01 9-46. Groundwater Drainage System Component Design Parameters Chapter 10 Tables 10/22/01 10-1. Design and Performance Characteristics of the Major Equipment and Tanks 10/22/01 10-2. Turbine Speed Control System Protection Devices 10/22/01 10-3. Turbine Speed Control System Valve Closure Time 10/22/01 10-4. Turbine Speed Control System Component Failure Analysis 10/22/01 10-5. Branch Steam Paths Active After Postulated Accident of Break in Safety Grade Portion of Main Steam Line and a Single Non-closable Main Steam Isolation Valve 10/22/01 10-6. Main Condenser Design Parameters 10/22/01 10-7. Main Condenser Evacuation System Component Design Parameters 10/22/01 10-8. Turbine Bypass System Failure Mode And Effects Analysis 3/27/03 10-9. Condenser Circulating Water System Component Design Parameters 10/22/01 10-10. Condensate Cleanup System Component Design Parameters 10/22/01 10-11. Condensate and Feedwater System Component Design Parameters 10/24/04 10-12. Maximum Allowance Blowdown Flowrate 10/22/01 10-13. Steam Generator Blowdown System Component Design Parameters 10/22/01 10-14. Failure Analysis, Steam Generator Blowdown System 10/22/01 10-15. Auxiliary Feedwater System Motor Driven Pump Design Data 10/22/01 10-16. Auxiliary Feedwater System Turbine Driven Pump Design Data 10/22/01 10-17. Auxiliary Feedwater System Component Failure Analysis Attachment I Page 14 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 10-18. Auxiliary Feedwater System Instrumentation and Control 10/22/01 10-19. Moisture Separator/Reheater and Feedwater Heater Drains System C Feedwater Heater Drain Tank Pump Design Data Chapter 11 Tables 10/22/01 11-1. Parameters Used in Calculating Maximum Reactor Coolant Activities 10/22/01 11-2. Design Basis Reactor Coolant Radioactivity Concentrations 10/22/01 11-3. Parameters Used in Calculating Normal Primary and Secondary Coolant Activities 11/15/07 11-4. Primary and Secondary Activity During Normal Operation 3/27/03 11-5. Tritium Source Terms 10/22/01 11-6. Maximum Expected Daily Flows to Liquid Radwaste System 10/22/01 11-7. Makeup Demineralized Water Chemistry 4/24/06 11-8. Liquid Radwaste System Component Design Parameters 10/22/01 11-9. Normal Expected Daily Flows to Liquid Radwaste System (2 Units) 4/24/06 11-10. Tanks Outside Containment Which Contain Potentially Radioactive Liquids 11/15/07 11-11. Catawba Nuclear Station Estimated Radioactive Releases in Liquid Effluents (curies/year/unit) 11/15/07 11-12. Estimated Doses from Radioactive Liquid Effluents Released from the Station 10/22/01 11-13. Waste Gas System Component Data 11/15/07 11-14. Estimated Annual Airborne Effluent Releases 11/15/07 11-15. Estimated Doses from Gaseous Effluent Releases from the Station 10/22/01 111-16. Estimated Maximum Specific Activities Input to Nuclear Solid Waste Disposal System 11/15/07 11-17. Solid Radwaste System Component Data 10/22/01 11-18. Estimated Maximum Volumes Discharged from Solid Radwaste System (Two Units) (Deleted per the 1997 Update) 4/24/06 11-19. Liquid Process Radiation Monitoring Equipment 11/15/07 11-20. Airborne Process Radiation Monitoring Equipment 10/22/01 11-21. System Component Design Parameters 10/22/01 11-22. Adjacent-to-Line Radiation Monitoring System Chapter 12 Tables 10/22/01 12-1. Design Basis Source Strengths for Fluids 10/22/01 12-2. Design Basis Source Strengths for Demineralizers Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/gamma) 10/22/01 12-3. Design Basis Source Strengths for Filters Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/gamma) 10/22/01 12-4. Reactor Coolant System Nitrogen- 16 Activity 10/22/01 12-5. Fluxes on Inside Surface of Primary Concrete 10/22/01 12-6. Design Source Strengths for Outside Storage Tanks 10/22/01 12-7. Spent Fuel Source Term - (MeV/cc - sec) 10/22/01 12-8. Source Terms for Calculating Airborne Radioactivity in Auxiliary Building Cubicles 10/22/01 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Attachment I Page 15 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) Building Cubicles ([tCi/ml) 10/22/01 12-10. Concentration Estimates of Airborne Radioactivity in Turbine Building 10/22/01 12-11. Concentration Estimates of Airborne Radioactivity in Upper Containment During Operation 10/22/01 12-12. Concentration Estimates of Airborne Radioactivity in the Administration Building 10/22/01 12-13. Concentration Estimates of Airborne Radioactivity in the Control Room 10/22/01 12-14. Concentration Estimates of Airborne Radioactivity in Fuel Handling Area 11/15/07 12-15. Design Radiation Zones 10/22/0 1 12-16. Present W E-Specs On Cobalt Content of Materials 10/22/01 12-17. Catawba Radiation Zones - Reactor Building 11/15/07 12-18. Catawba Radiation Zones - Auxiliary Building 4/24/06 12-19. Design Shield Thickness 10/22/01 12-20. Primary Shield Description 10/22/01 12-21. Parameters Used for Design Basis Accident Analysis of Control Room Direct Dose 10/22/01 12-22. Design Basis Accident Containment Source Strength 4/24/06 12-23. Comparison of Control Room Area Pressurizing Air Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 4/24/06 12-24. Comparison Of Auxiliary Building Filtered Exhaust System With Regulatory Guide 1.52 Revision 2, March 1978 4/24/06 12-25. Comparison Of Fuel Handling Area Exhaust Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 4/24/06 12-26. Comparison Of Annulus Ventilation Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 10/22/01 12-27. Filter System Design Parameters 4/18/09 12-28. Comparison of Containment Purge Filter System With Regulatory Guide 1.52 Revision 2, March 1978 10/22/0 1 12-29. Area Radiation Monitoring System 10/22/01 12-30. Estimated - Station Organization and Work Area 10/22/01 12-31. Dose Assessment - Number of Personnel and Times of Occupancy in Radiation Areas 11/15/07 12-32. Routine Operation Dose Assessment 11/15/07 12-33. Total Occupational Radiation Exposure Estimates (for one unit) 11 /15/07 12-34. Occupational Radiation Exposure Estimate for Reactor Operations and Surveillance (for one unit) 11/15/07 12-35. Occupational Radiation Exposure Estimate For Routine Maintenance (For One Unit) 11 /15/07 12-36. Occupational Radiation Exposure Estimate For Waste Processing (For One Unit) 11/15/07 12-37. Occupational Radiation Exposure Estimate For Refueling (For One Unit) 11/15/07 12-38. Occupational Radiation Exposure Estimate For Inservice Inspection (For One Unit) 11 /15/07 12-39. Occupational Radiation Exposure Estimate For Special Maintenance* (For One Unit) 4/18/09 12-40. RCA Description and RCA Control Points 10/22/01 12-41. Design Source Strengths for the Retired Steam Generator Storage Facility Iae16oS Page 16 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) Chapter 13 Tables 10/22/01 13-1. Placeholder 10/22/01 13-2. Deleted per 1990 Update Chapter 14 Tables 10/22/01 14-1. Compliance with Regulatory Guides 10/22/01 14-2. Preoperational and Startup Test Schedule Chapter 15 Tables 10/22/01 15-1. Deleted Per 1992 Update 4/18/09 15-2. Summary of Accidents Analyzed With Computer Codes 4/18/09 15-3. Summary of Computer Codes and Methodologies Used in Accident Analyses 4/18/09 15-4. Summary of Input Parameters for Accident Analyses 10/22/01 15-5. Deleted Per 1992 Update 10/22/01 15-6. Rod Drop Times Used in FSAR Analyses 10/22/01 15-7. Trip Points and Time Delays to Trip Assumed in Accident Analyses 10/22/01 15-8. Deleted Per 1992 Update 10/22/01 15-9. Deleted Per 1992 Update 10/22/01 15-10. Deleted Per 1992 Update 10/22/01 15-11. Deleted Per 1992 Update 4/24/06 15-12. Iodine and Noble Gas Inventory in Reactor Core and Fuel Rod Gaps 10/24/04 15-13. Reactor Coolant Specific Activities for Iodine and Noble Gas Isotopes 11/15/07 15-14. Offsite Doses (Rem) 4/18/09 15-15. Time Sequence of Events for Incidents Which Cause an Increase In Heat Removal By The Secondary System 10/22/01 15-16. Deleted Per 1992 Update 10/24/04 15-17. Parameters for Postulated Main Steam Line Break Offsite Dose Analysis 4/18/09 15-18. Time Sequence Of Events For Incidents Which Cause A Decrease In Heat Removal By The Secondary System 10/22/01 15-19. Parameters for Loss of Offsite Power Offsite Dose Analysis 4/18/09 15-20. Time Sequence of Events for Incidents Which Cause in a Decrease in Reactor Coolant System Flow 10/22/01 15-21. Deleted Per 1992 Update 4/24/06 15-22. Parameters for Postulated Locked Rotor Offsite Dose Analysis 4/24/06 15-23. Time Sequence of Events for Incidents which Cause Reactivity and Power Distribution Anomalies 10/22/01 15-24. Deleted Per 1992 Update 4/24/06 15-25. Parameters Used in the Analysis of the Rod Cluster Control Assembly Ejection Accident 4/24/06 15-26. Parameters for Postulated Rod Ejection Offsite Dose Analysis 10/22/01 15-27. Deleted Per 1995 Update 4/26/04 15-28. Time Sequence of Events For Inadvertent Opening of a Pressurizer Safety Valve Attachment I Page 17 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 15-29. Parameters for Postulated Instrument Line Break Offsite Dose Analysis 10/22/01 15-30. Deleted Per 1990 Update 10/24/04 15-31. Parameters for Postulated Steam Generator Tube Rupture Offsite Dose Analysis 10/22/01 15-32. Input Parameters Used in the Small Break LOCA Analyses 10/22/01 15-33. Deleted Per 1994 Update 10/22/01 15-34. Deleted Per 1994 Update 10/22/01 15-35. Deleted Per 1995 Update 10/22/01 15-36. Deleted Per 1994 Update 10/22/01 15-37. Deleted Per 1995 Update 11/15/07 15-38. Small Break LOCA Time Sequence of Events (Westinghouse Evaluation Model) 11/15/07 15-39. Small Break LOCA Results Fuel Cladding Data (Westinghouse Evaluation Model) 4/18/09 15-40. Parameters for LOCA Offsite Dose Analysis 4/24/06 15-41. Parameters for LOCA Control Room Dose Analysis 10/22/01 15-42. Parameters for Postulated Liquid Storage Tank Rupture Evaluation 10/22/01 15-43. Parameters for Postulated Refueling Water Storage Tank Rupture Accident 3/27/03 15-44. Activities for Postulated Refueling Water Storage Tank Rupture Accident 10/24/04 15-45. Activities in Highest Inventory Discharged Assembly for Postulated Fuel Handling Accidents 4/24/06 15-46. Parameters for Postulated Fuel Handling Accident Outside Containment 10/24/04 15-47. Deleted Per 2004 Update 4/24/06 15-48. Parameters for Post-LOCA Subcriticality Analysis 4/24/06 15-49. Time Sequence of Events For Steam Generator Tube Rupture 10/22/01 15-50. Input Parameters Used in the Large Break LOCA Analyses (B&W Evaluation Model) 10/22/01 15-51. Large Break LOCA Time Sequence of Events (B&W Evaluation Model) 10/22/01 15-52. Large Break LOCA Results Fuel Cladding Data (B&W Evaluation Model) 10/22/01 15-53. Maximum Injected ECCS Flows Assumed in LBLOCA Analyses - Two Trains Operational 10/22/01 15-54. Minimum ECCS Flow Assumed in SBLOCA Analyses(Westinghouse Evaluation Model) 10/22/01 15-55. SBLOCA Reanalyses PCT Results, Summary (Westinghouse Evaluation Model) (Deleted per 2000 Update) 10/22/01 15-56. SBLOCA Reanalyses PCT Results, (B&W Evaluation Model, Unit 2) (Deleted per 2000 Update) 11/15/07 15-57. Minimum ECCS Flow Assumed in SBLOCA Analyses - One Train Operational (B&W Evaluation Model) 4/24/06 15-58. Parameters for Postulated Weir Gate Drops 4/24/06 15-59. Input Parameters Used in the Small Break LOCA Analyses (Unit 1) 11/15/07 15-60. Small Break LOCA Time Sequence of Events (Unit 1) 11/15/07 15-61. Small Break LOCA Results Fuel Cladding Data (Unit 1) 10/22/01 15-62. Deleted per 2001 Update 10/22/01 15-63. Deleted per 2001 Update 10/22/01 15-64. Deleted per 2001 Update Attachment I Page 18 of 57

Catawba UFSAR List of Effective Dates for Tables Revised to Include the 2009 Update (Revision 14) 10/22/01 15-65 Minimum Injected ECCS Flows Assumed in LBLOCA Analysis - One Train Operational 10/22/01 15-66 Deleted per 2001 Update 10/22/01 15-67 Deleted per 2001 Update 10/22/01 15-68 Large Break LOCA - Time Sequence of Events for Reference Transient 10/22/01 15-69 Key Large Break LOCA Parameters and Initial Transient Assumptions 10/22/01 15-70 Best-Estimate Large Break LOCA - Overall Results 4/24/06 15-71 Plant Operating Range Allowed by the Best-Estimate Large Break LOCA Analysis 10/22/01 15-72 Rod Census Used in Best-Estimate Large Break LOCA Analysis 4/24/06 15-73 Core Isotopic Inventory Used in the Calculation of Offsite Radiation Doses for the Locked Rotor and Rod Ejection Accidents 4/24/06 15-74 Parameters for the Steam Generator Tube Rupture Supplemental Offsite Dose Analysis 4/18/09 15-75. Fission Product Radioactivity Levels in a Mixed Oxide Lead Test Assembly 4/18/09 15-76. Fission Product Radioactivity Levels in a Mixed Oxide Lead Test Assembly ( Fuel Handling Accident and Weir Gate Drop) 4/18/09 15-77. LOCA Release Fractions 4/18/09 15-78. Non LOCA Gap Fractions 4/18/09 15-79. Iodine Partition Fractions for Post LOCA ESF Leakage in the Auxiliary Building 4/18/09 15-80. Iodine Partition Fractions for EST Back Leakage to Refueling Water Storage Tank Following a Design Basis Rod Ejection Accident 4/18/09 15-81. Effect of Operation of Unit I with four MOX LTAs on Post Accident Radiation Doses Chapter 16 Tables No tables Chapter 17 Tables No tables Chapter 18 Tables 3/27/03 18.1. Summary Listing of the Programs, Activities and TLAA 4/18/09 18.2. Catawba Reactor Vessel Capsule Withdrawal Schedule Attachment I Page 19 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Chapter 1 Figures 10/22/01 1-1. Duke Power Company Service Area 4/24/06 1-2. General Arrangement Plan @ EL. 522 +0 4/24/06 1-3. General Arrangement Plan @ EL. 543 +0 11/15/07 1-4. General Arrangement Plan @ EL. 560 +0 4/18/09 1-5. General Arrangement Plan @ EL. 577 +0 4/18/09 1-6. General Arrangement Plan @ EL. 594+0 4/18/09 1-7. General Arrangement Plan @ EL. 619 +0 10/22/01 1-8. General Arrangement Roof Plan 10/24/04 1-9. General Arrangement Longitudinal Section 11/15/07 1-10. General Arrangement Containment and Reactor Building Plan @ EL. 523 +11 4/18/09 1-11. General Arrangement Containment and Reactor Building Plan @ EL. 552 +0 10/22/01 1-12. General Arrangement Containment and Reactor Building Plan @ EL. 565 +3 10/24/04 1-13. General Arrangement Containment and Reactor Building Plan @ EL. 594 +10 3/4 11/15/07 1-14. General Arrangement Containment and Reactor Building Plan @ EL. 605 +10 4/18/09 1-15. General Arrangement Containment and Reactor Building Plan @ EL. 652 +7 1/2 10/24/04 1-16. General Arrangement Containment and Reactor Building Section (Laydown Space) 10/24/04 1-17. General Arrangement Containment and Reactor Building Section 10/22/01 1-18. General Arrangement Containment and Reactor Building Refueling Canal Layout Longitudinal Section 4/18/09 1-19.1 Site Plan 4/18/09 1-19.2 Site Plan 4/18/09 1-20. Plot Plan 10/22/01 1-21. Electrical Symbol Identification 11/15/07 1-22. Symbols for Flow Diagrams 11/15/07 1-23. Symbols for Flow Diagrams 4/18/09 1-24. Catawba Symbols and Abbreviations for Flow Diagrams 10/22/01 1-25. Post-accident Radiation Zones @ EL. 522+0 10/22/01 1-26. Post-accident Radiation Zones @ EL. 543+0 10/22/01 1-27. Post-accident Radiation Zones @ EL. 560+0 10/22/01 1-28. Post-accident Radiation Zones @ EL. 577+0 4/18/09 1-29. Post-accident Radiation Zones @ EL. 594+0 10/22/01 1-30. Post-accident Radiation Zones @ EL. 605+10 & 619+0 10/22/01 1-31. Inadequate Core Cooling Instrumentation Configuration 10/22/01 1-32. Loss of Offsite Power (Deleted per 2001 Update) 10/22/01 1-33. Feedline Rupture with Offsite Power (Deleted per 2001 Update) 10/22/01 1-34. Feedline Rupture without Offsite Power (Deleted per 2001 Update) 10/22/01 1-35. Incore Thermocouple System Configuration Attachment I Page 20 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Chapter 2 Figures (no dates are available on Chapter 2 Figures unless noted) 10/24/04 2-1. Regional Location 10/24/04 2-2. Site Location 10/24/04 2-3. Site Area 10/24/04 2-4. Release Points 03/27/03 2-5. Significant Population Groupings, Ten Miles 03/27/03 2-6. Significant Population Groupings, Fifty Miles 10/24/04 2-7. Vicinity Topography 10/24/04 2-8. Five Mile (Eight Kilometer) Area 03/27/03 2-9. Population Centers 03/27/03 2-10. Cumulative Population, Year of Plant Start-Up 10/24/04 2-11. Cumulative Population, End of Plant Life 10/24/04 2-12. Locations and Routes 03/27/03 2-13. Tornado Frequency 1916 - 1955 10/24/04 2-14. Visible Plume Length Frequency (June - November) 10/24/04 2-15. Visible Plume Length Frequency (December - May) 03/27/03 2-16. Vicinity Topography - Profile 10/22/01 2-17. Relative Elevations of Meteorological Instruments 10/24/04 2-18. Cumulative Frequency Distribution of Hourly Dilution Factors at the Exclusion Area Boundary (Northeast Sector) 10/24/04 2-19. Cumulative Frequency Distribution of Hourly Dilution Factors at the Low Population Zone Boundary (Northeast Sector) 10/24/04 2-20. Site Earthwork 03/27/03 2-21. Plan-Profile of Catawba River 10/24/04 2-22. Surface Water Users 10/24/04 2-23. Yard Drainage 10/24/04 2-24. Power Block Area Features 10/24/04 2-25. Catch Basin Inlet Details 10/24/04 2-26. Administration and Security Fence Base Details 4/18/09 2-27. Local Intense Precipitation PMP Floor Routing Using Puls Graphical Method 4/18/09 2-28. PMP Flood Routing; Type I Inlets - 100% Efficient; Type II Inlets

                       - 100% Efficient 4/18/09           2-29. PMP Flood Routing; Type I Inlets - 100% Efficient; Type II Inlets
                       - 50% Efficient 4/18/09           2-30. PMP Flood Routing; Type I Inlets - 100% Efficient; Type II Inlets
                       - 0% Efficient 4/18/09           2-31. PMP Flood Routing; Switchyard 4/18/09           2-32. PMP Flood Routing; Cooling Tower Yard 4/18/09           2-33. Deleted per 2009 Update 10/24/04          2-34. Probable Maximum Precipitation 10/24/04          2-35. Basin Subareas and Thiessen Polygons and Isohyetal Map for Probable Maximum Precipitation 10/24/04          2-36. Lag Time 10/24/04          2-37. Basin Subarea Unit Hydrographs 10/24/04          2-38. Reservoir Inflows, Outflows, and Elevations for Wylie Reservoir 10/24/04          2-39. PMF Hydrograph, Lake Wylie 10/24/04          2-40. Fetch Map 10/24/04          2-41. Wylie Reservoir Inflows, Outflows and Elevations 10/24/04          2-42. SNSW PMF Hydrographs 10/24/04          2-43. NSW Pump House Sections 10/24/04          2-44.01 LPSW Intake Structure Attachment I                                                                      Page 21 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/24/04 2-44. LPSW Intake Structure (Part 2 of 3) 10/24/04 2-44. LPSW Intake Structure (Part 3 of 3) 10/24/04 2-45. NSW and SNSW Discharge Structures 10/24/04 2-46. SNSW Intake Structure 10/24/04 2-47. Location of Wells Surveyed 10/24/04 2-48. Groundwater Users 10/24/04 2-49. River Bank Wells 10/24/04 2-50. Reconstruction Groundwater Contour Map 10/24/04 2-51. Site Cross-Section 03/27/03 2-52. Monthly Groundwater Hydrograph (October, 1973 to September, 1977) 03/27/03 2-53. Groundwater Level, Daily Rainfall and Lake Level 03/27/03 2-54. Schematic Equipment Arrangement for Rock Permeability Testing 03/27/03 2-55. Schematic Equipment Arrangement for Soil Permeability Testing 03/27/03 2-56. Pumping Test No. 1 - A85-TW Location, Plan 03/27/03 2-57. Pumping Test No. 2 - A48TW Location, Plan 03/27/03 2-58. Core of Depression - Pumping Test 1 03/27/03 2-59. Core of Depression - Pumping Test 2 10/24/04 2-60. Auxiliary and Reactor Building Groundwater Drainage System 10/24/04 2-61. Auxiliary and Reactor Building Groundwater Drainage System 10/24/04 2-62. Plot of Water Level at Structure Versus Rebound Time 10/24/04 2-63. Auxiliary and Reactor Building Groundwater Drainage System 10/24/04 2-64. Auxiliary and Reactor Building Groundwater Drainage System 03/27/03 2-65. Powerhouse Foundation 2-66. Location of Compacted Backfill (Powerhouse Area) 03/27/03 2-67. Regional Physiographic Map 03/27/03 2-68. Regional Geologic Map 03/27/03 2-69. Regional Tectonic Map 03/27/03 2-70. Regional Geologic Cross-Section 03/27/03 2-71. Regional Aeromagnetic Map 03/27/03 2-72. Regional Bouguer Gravity Anomaly Map 03/27/03 2-73. Subregional Geologic Index 03/27/03 2-74. Regional Linear Features Map 03/27/03 2-75. Subregional Geologic Map 03/27/03 2-76. Subregional Drainage Map with Linear Stream Segments 03/27/03 2-77. Regional In Situ Stresses 03/27/03 2-78. Boring Location Plan 03/27/03 2-79. Boring Location Plan 03/27/03 2-80. Subsurface Profiles 03/27/03 2-81. Subsurface Profiles 03/27/03 2-82. Subsurface Profiles 03/27/03 2-83. Subsurface Profiles 03/27/03 2-84. Subsurface Profiles 03/27/03 2-85. Subsurface Profiles 03/27/03 2-86. Subsurface Profiles 03/27/03 2-87. Subsurface Profiles 03/27/03 2-88. Subsurface Profiles 03/27/03 2-89. Subsurface Profiles 03/27/03 2-90. Subsurface Profiles 03/27/03 2-91. Subsurface Profiles 03/27/03 2-92. Subsurface Profiles 03/27/03 2-93. Subsurface Profiles Attachment I Page 22 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 03/27/03 2-94. Seismic Refraction Traverses 03/27/03 2-95. Seismic Refraction Traverses 03/27/03 2-96. Seismic Refraction Traverses 03/27/03 2-97. Seismic Refraction Traverses 03/27/03 2-98. Uphole Seismic Data, Boring A-61 03/27/03 2-99. Uphole Seismic Data, Boring A-63 03/27/03 2-100. Contours on Top of Continuous Rock 03/27/03 2-101. Equal Area Projections of Poles to Planes - Powerhouse Excavation 03/27/03 2-102. Equal Area Projections of Poles to Planes - SNSW Pond Dam Excavations 03/27/03 2-103. Geologic Map of Powerhouse Excavation - Reactor and Auxiliary Building Area 03/27/03 2-104. Geologic Map of Powerhouse Excavation - Turbine and Service Building Area 03/27/03 2-105. Geologic Map of SNSW Pond Dam Excavation 03/27/03 2-106. Regional Epicenter Map 03/27/03 2-107. Epicenters of Earthquakes Located Within 50-Mile Radius of the Site 03/27/03 2-108. Epicenters of Earthquakes Probably Felt at the Catawba Site 03/27/03 2-109. Acceleration - Intensity Relationships 10/24/04 2-110. Design Response Spectra, .08g 10/24/04 2-11 f. Design Response Spectra, .08g 10/24/04 2-112. Design Response Spectra, .15g 10/24/04 2-113. Design Response Spectra, 25 feet of Overburden, .08g at Rock 10/24/04 2-114. Actual Foundation Conditions at Structures Designed Using Response Spectrum Computed for 25 FT. of Overburden (Fill) 10/22/01 2-115. Soil Columns for Unit 2 Fuel Oil Storage Tanks and Unit 2 Above Ground Storage Tank 10/24/04 2-116. Comparison of Computed Response Spectra and Design Response Spectrum 03/27/03 2-117. Location Plan for Seismic Refraction Lines on Rock In Powerhouse Excavation 03/27/03 2-118. Results of Seismic Refraction Lines - NSW Intake Structure and NSW Pump Structure 03/27/03 2-119. Seismic Refraction Profiles - NSW Pipe Lines 03/27/03 2-120. Results of Seismic Refraction Lines in Powerhouse Excavation 03/27/03 2-121. Summary of Grain Size Distribution of Residual Soils from Adamellite 03/27/03 2-122. Summary of Optimum Moisture and Maximum Dry Density of Residual Soils from Plant Area 03/27/03 2-123. Typical Consolidation Test Results of Compacted Residual Soils from Plant Area 03/27/03 2-124. Summary of Consolidation Characteristics of Partially Weathered Rock Materials 03/27/03 2-125. Summary of Mohr Diagrams of Compacted Residual Soils from Plant Area 03/27/03 2-126. Summary of Mohr Diagrams for Partially Weathered Rock Materials 03/27/03 2-127. Summary of Stress-Strain Data on Rock Core 03/27/03 2-128. Summary of Rock Test Data From Plant Area Substructure Excavation 03/27/03 2-129. Dynamic Moduli of Foundation Materials - Plant Area 03/27/03 2-130. Contours of Plant Excavation Bottom at Start of Blasting Attachment I Page 23 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/24/04 2-131. Soil Column Analysis - NSW Pipeline 10/24/04 2-132. Sections Through Powerhouse 10/24/04 2-133. Cross Sections Through NSW and SNSW Pump Structure and Diesel Fuel Oil Storage Tanks 10/24/04 2-134. Selected Subsurface Profiles Through NSW Pipe Lines 10/24/04 2-135. Earth Pressure Distribution on Subsurface Walls 10/24/04 2-136. Number of Moisture Tests Versus Moisture Content for Compacted Group I Backfill 10/24/04 2-137. Number of Compaction Tests Versus Percent Compaction for Group I Backfill 10/24/04 2-138. Number of Compaction Tests Versus Relative Density for Granular Backfill 10/24/04 2-139. Nuclear Service Water System Yard Layout - Longitudinal Profiles 10/24/04 2-140. Typical Section, Standby Nuclear Service Water Pond Dam 10/24/04 2-141. Standby Nuclear Service Water Pond Dam, Details 10/24/04 2-142. Plan, Standby Nuclear Service Water Pond Dam 10/24/04 2-143. Profile of Standby Nuclear Service Water Pond Outlet Works 03/27/03 2-144. Boring Location Plan, Standby Nuclear Service Water Pond Dam 10/24/04 2-145. Section Along Axis of Standby Nuclear Service Water Pond Dam 10/24/04 2-146. Section A-87 Through A-96, South of Standby Nuclear Service Water Pond Dam 10/24/04 2-147. Section A-103 SI Through A-103 S2, Standby Nuclear Service Water Pond Dam 10/24/04 2-148. Standby Nuclear Service Water Pond Dam, Section A- 116 Through A-119 10/24/04 2-149. Standby Nuclear Service Water Pond Dam, Section A- 117 Through A- 118 03/27/03 2-150. Summary of Grain Size Distribution, Residual Soils at Standby Nuclear Service Water Pond Dam - Foundation Saprolites 03/27/03 2-151. Summary of Mohr Diagrams for Foundation Soils, Standby Nuclear Service Water Pond Dam 03/27/03 2-152. Cyclic Triaxial Strength Results 03/27/03 2-153. Cyclic Strength of Soils 03/27/03 2-154. Summary of Consolidation Characteristics for Residual Soils, Standby Nuclear Service Water Pond Dam 03/27/03 2-155. Cross Hole Seismic Data, Boring A-103 03/27/03 2-156. Cross Hole Seismic Data, Boring A-105 03/27/03 2-157. Dynamic Tests on Foundation Soils 03/27/03 2-158. Summary of Mohr Diagrams of Partially Weathered Rock 10/24/04 2-159. Standby Nuclear Service Water Pond Dam Foundation Plan 10/24/04 2-160. Standby Nuclear Service Water Pond Dam Foundation Bedrock-South Abutment 03/27/03 2-161. Standby Nuclear Service Water Pond Dam Fill Sources and Quantities Placed Versus Date 03/27/03 2-162. Summary Grain Size Distribution, Residual Sands - General Borrow Areas Investigated for PSAR 03/27/03 2-163. Summary Grain Size Distribution Residual Soils- Silty Sands, SNSW Pond Dam Embankment Borrow Area Utilized 03/27/03 2-164. Earth Embankment Material, Grain Size Distribution, Standby Nuclear Service Water Pond Dam 03/27/03 2-165. Optimum Moisture, Maximum Dry Density for Soil During PSAR Investigation and Borrow Area Studies, Standby Nuclear Service Water Pond Dam Attachment I Page 24 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 03/27/03 2-166. Dry Density versus Optimum Moisture Content, From Proctor Tests on Soils Placed on SNSW Pond Dam 03/27/03 2-167. Summary of Mohr Diagrams of Structural Fill Obtained During PSAR Investigations 03/27/03 2-168. Summary of Mohr Diagrams of Structural Fill from Borrow Areas Used for Standby Nuclear Service Water Pond Dam Embankment 03/27/03 2-169. Summary of Mohr Diagrams for Structural Fill Sampled from Standby Nuclear Service Water Pond Embankment 03/27/03 2-170. Distribution of Field Density Tests with Percent Compaction on Standby Nuclear Service Water Pond Dam Embankment 03/27/03 2-171. Typical Consolidation Tests of Compacted Soils Obtained During PSAR Investigation and from Borrow Areas Used for Standby Nuclear Service Water Pond Dam Embankment 03/27/03 2-172. Slope Protection, Filter layer, Grain Size Distribution 03/27/03 2-173. Number of Moisture Tests Versus Moisture Content for Standby Nuclear Service Water Pond Dam 03/27/03 2-174. Number of Moisture Tests Versus Moisture Content for Standby Nuclear Service Water Pond Dam 03/27/03 2-175. Number of Compaction Tests Versus Percent Compaction for Standby Nuclear Service Water Pond Dam 03/27/03 2-176. Blanket Drain Course. Filter, Density Test Distribution 03/27/03 2-177. Blanket Drain Top Layer Fine Filter Density Test Distribution 03/27/03 2-178. Blanket Drain, Coarse Fitler, Grain Size Distribution 03/27/03 2-179. Blanket Drain, Fine Filter-Top Layer, Grain Size Distribution 03/27/03 2-180. Blanket Drain, Fine Filter-Bottom Layer, Grain Size Distribution 10/22/01 2-181. Cross-Section for Stability Analysis 10/24/04 2-182. Dynamic Modulus for Embankment and Foundation Materials 10/24/04 2-183. Dynamic Modulus and Combining Pressure for Foundation Soils - Saprolites 10/24/04 2-184. Failure Surfaces of Lowest Safety Factor - Static Analysis 10/24/04 2-185. Finite Element Representation 10/24/04 2-186. Static Finite Element Analysis, Vertical Effective Normal Stress in Embankment 10/24/04 2-187. Static Finite Element Analysis, Horizontal Shear Stressin Embankment 10/24/04 2-188. Static Finite Element Analysis, Principal Stress Ratios in Embankment 03/27/03 2-189. Cyclic Triaxial Tests - Typical Strain and Pore Pressure Data (Remolded Samples) 03/27/03 2-190. Variation of Damping for Embankment and Foundation Materials 03/27/03 2-191. Variation of Modulus for Embankment and Foundation Materials 03/27/03 2-192. Dynamic Tests on Embankment Materials 03/27/03 2-193. Time History of Synthetic EQ- 1 03/27/03 2-194. Time History of Synthetic EQ-2 03/27/03 2-195. Time History of Synthetic EQ-3 03/27/03 2-196. Time History of Synthetic EQ-4 03/27/03 2-197. Failure Potential Under Cyclic Loading 10/24/04 2-198. Seismic Coefficient SNSW Pond Dam 10/24/04 2-199. Standby Nuclear Service Water Pond Dam Instrumentation Details Attachment I Page 25 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/24/04 2-200. Local Safety Factors Against 5% Strain 03/27/03 2-201. SNSW Pond Dam Piezometric Readings 03/27/03 2-202. SNSW Pond Dam Settlement Versus Time 10/24/04 2-203. SNSW Pond Dam Crest Elevation 10/22/01 2-204. Design Response Spectrum for Direct Generation Chapter 3 Figures 10/1/91 3-1. Wind Pressure Distribution On The Reactor Building 10/1/91 3-2. Wind Pressure Distribution For Rectangular Structures 10/1/91 3-3. Turbine Building Tornado Velocity Distribution 10/1/91 3-4. Tornado Wind Loads - Design Velocity Vs. Radius From Center Of Tornado 10/1/91 3-5. Turbine Missile Ejection Zones 10/1/91 3-6. Loss Of Reactor Coolant Accident Boundary Limits 10/22/01 3-7. Location Of Postulated Breaks In Main Reactor Coolant Loop 10/22/01 3-8. Analytical Method For Resolving Pipe Break Consequences (Deleted per 2001 Update) 10/1/91 3-9. Reactor Coolant Loop Model 10/1/91 3-10. Time-History Dynamic Solution For Local Loading 10/1/91 3-11. Typical Cold Penetration 10/1/91 3-12. Typical Main Steam And Feedwater Penetration 10/1/91 3-13. Typical Hot Penetration 10/1/91 3-14. Deleted Per 1990 Update 10/1/91 3-15. Deleted Per 1990 Update 10/1/91 3-16. Deleted Per 1990 Update 10/1/91 3-17. Deleted Per 1990 Update 10/1/91 3-18. Deleted Per 1990 Update 10/1/91 3-19. Deleted Per 1990 Update 10/1/91 3-20. Deleted Per 1990 Update 10/1/91 3-21. Deleted Per 1990 Update 10/1/91 3-22. Deleted Per 1990 Update 10/1/91 3-23. Deleted Per 1990 Update 10/1/91 3-24. Deleted Per 1990 Update 10/1/91 3-25. Deleted Per 1990 Update 10/1/91 3-26. Deleted Per 1990 Update 10/1/91 3-27. Deleted Per 1990 Update 10/1/91 3-28. Deleted Per 1990 Update 10/1/91 3-29. Deleted Per 1990 Update 10/1/91 3-30. Deleted Per 1990 Update 10/1/91 3-31. Deleted Per 1990 Update 10/1/91 3-32. Deleted Per 1990 Update 10/1/91 3-33. Deleted Per 1990 Update 10/1/91 3-34. Deleted Per 1990 Update 10/1/91 3-35. Deleted Per 1990 Update 10/1/91 3-36. Deleted Per 1990 Update 10/1/91 3-37. Deleted Per 1990 Update 10/1/91 3-38. Deleted Per 1990 Update 10/1/91 3-39. Deleted Per 1990 Update 10/1/91 3-40. Deleted Per 1990 Update 10/1/91 3-41. Deleted Per 1990 Update 10/1/91 3-42. Deleted Per 1990 Update 10/1/91 3-43. Deleted Per 1990 Update Attachment I Page 26 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 3-44. Deleted Per 1990 Update 10/1/91 3-45. Deleted Per 1990 Update 10/1/91 3-46. Deleted Per 1990 Update 10/1/91 3-47. Deleted Per 1990 Update 10/1/91 3-48. Deleted Per 1990 Update 10/1/91 3-49. Deleted Per 1990 Update 10/1/91 3-50. Deleted Per 1990 Update 10/1/91 3-51. Deleted Per 1990 Update 10/1/91 3-52. Deleted Per 1990 Update 10/1/91 3-53. Deleted Per 1990 Update 10/1/91 3-54. Deleted Per 1990 Update 10/1/91 3-55. Deleted Per 1990 Update 10/1/91 3-56. Deleted Per 1990 Update 10/1/91 3-57. Deleted Per 1990 Update 10/1/91 3-58. Deleted Per 1990 Update 10/1/91 3-59. Deleted Per 1990 Update 10/1/91 3-60. Deleted Per 1990 Update 10/1/91 3-61. Deleted Per 1990 Update 10/1/91 3-62. Deleted Per 1990 Update 10/1/91 3-63. Deleted Per 1990 Update 10/1/91 3-64. Deleted Per 1990 Update 10/1/91 3-65. Deleted Per 1990 Update 10/1/91 3-66. Deleted Per 1990 Update 10/1/91 3-67. Deleted Per 1990 Update 10/1/91 3-68. Deleted Per 1990 Update 10/1/91 3-69. Deleted Per 1990 Update 10/1/91 3-70. Deleted Per 1990 Update 10/1/91 3-71. Deleted Per 1990 Update 10/1/91 3-72. Deleted Per 1990 Update 10/1/91 3-73. Deleted Per 1990 Update 10/1/91 3-74. Deleted Per 1990 Update 10/1/91 3-75. Deleted Per 1990 Update 10/1/91 3-76. Deleted Per 1990 Update 10/1/91 3-77. Deleted Per 1990 Update 10/1/91 3-78. Deleted Per 1990 Update 10/1/91 3-79. Deleted Per 1990 Update 10/1/91 3-80. Deleted Per 1990 Update 10/1/91 3-81. Deleted Per 1990 Update 10/1/91 3-82. Deleted Per 1990 Update 10/1/91 3-83. Deleted Per 1990 Update 10/1/91 3-84. Deleted Per 1990 Update 10/1/91 3-85. Deleted Per 1990 Update 10/1/91 3-86. Deleted Per 1990 Update 10/1/91 3-87. Deleted Per 1990 Update 10/1/91 3-88. Deleted Per 1990 Update 10/1/91 3-89. Deleted Per 1990 Update 10/1/91 3-90. Deleted Per 1990 Update 10/1/91 3-91. Deleted Per 1990 Update 10/1/91 3-92. Deleted Per 1990 Update 10/1/91 3-93. Deleted Per 1990 Update 10/1/91 3-94. Deleted Per 1990 Update 10/1/91 3-95. Deleted Per 1990 Update 10/1/91 3-96. Deleted Per 1990 Update 10/1/91 3-97. Deleted Per 1990 Update Attachment I Page 27 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 3-98. Deleted Per 1990 Update 10/1/91 3-99. Deleted Per 1990 Update 10/1/91 3-100. Deleted Per 1990 Update 10/1/91 3-101. Deleted Per 1990 Update 10/1/91 3-102. Deleted Per 1990 Update 10/1/91 3-103. Deleted Per 1990 Update 10/1/91 3-104. Deleted Per 1990 Update 10/1/91 3-105. Deleted Per 1990 Update 10/1/91 3-106. Deleted Per 1990 Update 10/1/91 3-107. Deleted Per 1990 Update 10/1/91 3-108. Deleted Per 1990 Update 10/1/91 3-109. Deleted Per 1990 Update 10/1/91 3-110. Deleted Per 1990 Update 10/1/91 3-111. Deleted Per 1990 Update 10/1/91 3-112. Deleted Per 1990 Update 10/1/91 3-113. Deleted Per 1990 Update 10/1/91 3-114. Deleted Per 1990 Update 10/1/91 3-115. Deleted Per 1990 Update 10/1/91 3-116. Deleted Per 1990 Update 10/1/91 3-117. Deleted Per 1990 Update 10/1/91 3-118. Deleted Per 1990 Update 10/1/91 3-119. Deleted Per 1990 Update 10/1/91 3-120. Deleted Per 1990 Update 10/1/91 3-121. Deleted Per 1990 Update 10/1/91 3-122. Deleted Per 1990 Update 10/1/91 3-123. Deleted Per 1990 Update 10/1/91 3-124. Deleted Per 1990 Update 10/1/91 3-125. Deleted Per 1990 Update 10/1/91 3-126. Deleted Per 1990 Update 10/1/91 3-127. Deleted Per 1990 Update 10/1/91 3-128. Deleted Per 1990 Update 10/1/91 3-129. Deleted Per 1990 Update 10/1/91 3-130. Deleted Per 1990 Update 10/1/91 3-131. Deleted Per 1990 Update 10/1/91 3-132. Deleted Per 1990 Update 10/1/91 3-133. Deleted Per 1990 Update 10/1/91 3-134. Deleted Per 1990 Update 10/1/91 3-135. Deleted Per 1990 Update 10/1/91 3-136. Deleted Per 1990 Update 10/1/91 3-137. Deleted Per 1990 Update 10/1/91 3-138. Deleted Per 1990 Update 10/1/91 3-139. Deleted Per 1990 Update 10/1/91 3-140. Deleted Per 1990 Update 10/1/91 3-141. Deleted Per 1990 Update 10/1/91 3-142. Deleted Per 1990 Update 10/1/91 3-143. Deleted Per 1990 Update 10/1/91 3-144. Deleted Per 1990 Update 10/1/91 3-145. Deleted Per 1990 Update 10/1/91 3-146. Deleted Per 1990 Update 10/1/91 3-147. Deleted Per 1990 Update 10/1/91 3-148. Deleted Per 1990 Update 10/1/91 3-149. Deleted Per 1990 Update 10/1/91 3-150. Deleted Per 1990 Update 10/1/91 3-151. Deleted Per 1990 Update Attachment I Page 28 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 3-152. Deleted Per 1990 Update 10/1/91 3-153. Deleted Per 1990 Update 10/1/91 3-154. Deleted Per 1990 Update 10/1/91 3-155. Deleted Per 1990 Update 10/1/91 3-156. Deleted Per 1990 Update 10/1/91 3-157. Deleted Per 1990 Update 10/1/91 3-158. Deleted Per 1990 Update 10/1/91 3-159. Deleted Per 1990 Update 10/1/91 3-160. Deleted Per 1990 Update 10/1/91 3-161. Deleted Per 1990 Update 10/1/91 3-162. Deleted Per 1990 Update 10/1/91 3-163. Deleted Per 1990 Update 10/1/91 3-164. Deleted Per 1990 Update 10/1/91 3-165. Deleted Per 1990 Update 10/1/91 3-166. Deleted Per 1990 Update 10/1/91 3-167. Deleted Per 1990 Update 10/1/91 3-168. Deleted Per 1990 Update 10/1/91 3-169. Deleted Per 1990 Update 10/1/91 3-170. Deleted Per 1990 Update 10/1/91 3-171. Deleted Per 1990 Update 10/1/91 3-172. Deleted Per 1990 Update 10/1/91 3-173. Deleted Per 1990 Update 10/1/91 3-174. Deleted Per 1990 Update 10/1/91 3-175. Deleted Per 1990 Update 10/1/91 3-176. Deleted Per 1990 Update 10/1/91 3-177. Deleted Per 1990 Update 10/1/91 3-178. Deleted Per 1990 Update 10/1/91 3-179. Deleted Per 1990 Update 10/1/91 3-180. Deleted Per 1990 Update 10/1/91 3-181. Deleted Per 1990 Update 10/1/91 3-182. Deleted Per 1990 Update 10/1/91 3-183. Deleted Per 1990 Update 10/1/91 3-184. Deleted Per 1990 Update 10/1/91 3-185. Deleted Per 1990 Update 10/1/91 3-186. Deleted Per 1990 Update 10/1/91 3-187. Deleted Per 1990 Update 10/1/91 3-188. Deleted Per 1990 Update 10/1/91 3-189. Deleted Per 1990 Update 10/1/91 3-190. Deleted Per 1990 Update 10/1/91 3-191. Deleted Per 1990 Update 10/1/91 3-192. Deleted Per 1990 Update 10/1/91 3-193. Deleted Per 1990 Update 10/1/91 3-194. Deleted Per 1990 Update 10/1/91 3-195. Deleted Per 1990 Update 10/1/91 3-196. Deleted Per 1990 Update 10/1/91 3-197. Deleted Per 1990 Update 10/1/91 3-198. Deleted Per 1990 Update 10/1/91 3-199. Deleted Per 1990 Update 10/1/91 3-200. Deleted Per 1990 Update 10/1/91 3-201. Deleted Per 1990 Update 10/1/91 3-202. Deleted Per 1990 Update 10/1/91 3-203. Deleted Per 1990 Update 10/1/91 3-204. Deleted Per 1990 Update 10/1/91 3-205. Deleted Per 1990 Update Attachment I Page 29 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 3-206. Deleted Per 1990 Update 10/1/91 3-207. Deleted Per 1990 Update 10/1/91 3-208. Deleted Per 1990 Update 10/1/91 3-209. Deleted Per 1990 Update 10/1/91 3-210. Deleted Per 1990 Update 10/1/91 3-211. Deleted Per 1990 Update 10/1/91 3-212. Deleted Per 1990 Update 10/1/91 3-213. Design Response Spectrum,. 15g 10/1/91 3-214. Response Acceleration Spectra 10/1/91 3-215. Response Acceleration Spectra 10/1/91 3-216. Damping Valve For Seismic Analysis Of Piping (Applicable To Both OBE and SSE, Independent Of Pipe Diameter) 10/1/91 3-217. Containment Interior Structure Lumped Mass Model 10/1/91 3-218. Auxiliary Building Elevation 10/1/91 3-219. Exterior Doghouse And UHI Elevation 10/1/91 3-220. Diesel Generator Building Elevation 10/22/01 3-221. Nuclear Service Water Pump Structure Elevation 10/1/91 3-222. Reactor Building First And Second Horizontal Mode Shapes 10/1/91 3-223. Reactor Building First And Second Vertical Mode Shapes 10/1/91 3-224. Reactor Building Shear Force, Q (lb/in), Due To SSE 10/1/91 3-225. Reactor Building Meridional Force, N&phi. (lb/in), Due To SSE 10/1/91 3-226. Reactor Building Meridional Moment, M&phi. (in-lb/in.), Due To SSE 10/1/91 3-227. Reactor Building Membrane Shear N (lb/in) Due To SSE 10/22/01 3-228. Reactor Building Hoop Force N&phi. (lb/in) Due To SSE 10/22/01 3-229. Reactor Building Hoop Moment M&phi. (in-lb/in) Due To SSE 10/1/91 3-230. Containment Interior Structure First Four Horizontal Mode Shapes North-South Direction 10/1/91 3-231. Containment Interior Structure First Four Horizontal Mode Shapes East-West Direction 10/1/91 3-232. Containment Interior Structure First Tow Vertical Mode Shapes Vertical Direction 10/1/91 3-233. Reactor Building Interior Structure Response Loads North-South, SSE 10/1/91 3-234. Reactor Building Interior Structure Response Loads East-West, SSE 10/1/91 3-235. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 556+8, (OBE) 10/1/91 3-236. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 592+2, (OBE) 10/1/91 3-237. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 609+10, (OBE) 10/1/91 3-238. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 643+6, (OBE) 10/1/91 3-239. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 668+10, (OBE) 10/1/91 3-240. Response Acceleration Spectrum, Damping = 0.05, Reactor Interior, North-South Direction, Elevation 609+10, (OBE) 10/1/91 3-241. Soil Pressure Diagram For Substructure Walls Of Auxiliary Building 10/1/91 3-242. Multi-Degree Of Freedom System 10/1/91 3-243. Reactor Building And Containment Structural Outline No Date Available 3-244. Reactor Building Bottom Radial Bars Attachment I Page 30 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) No Date Available 3-245. Reactor Building Top Radial Bars No Date Available 3-246. Reactor Building Circular Bars No Date Available 3-247. Containment Vessel And Equipment Anchorage Details No Date Available 3-248. Reactor Building Shell Wall Developed Elevation No Date Available 3-249. Reactor Building Shell Wall Developed Elevation No Date Available 3-250. Reactor Building Shell Wall Developed Elevation No Date Available 3-251. Reactor Building Equipment Hatch Reinforcing No Date Available 3-252. Dome And Ring Girder Reinforcing No Date Available 3-253. Dome And Ring Girder Reinforcing No Date Available 3-254. Dome And Ring Girder Reinforcing 10/1/91 3-255. Equipment Hatch Model 10/1/91 3-256. K-Shell Model For Reactor Building Analysis 10/1/91 3-257. Axis Orientation For Reactor Building Analysis 10/1/91 3-258. Reactor Building Shell And Crane Wall (Reinforcement Details) 10/1/91 3-259. Containment Geometry No Date Available 3-260. Containment Personnel And Equipment Hatch Typical Details No Date Available 3-261. Containment Mechanical And Electrical Penetrations Typical Details No Date Available 3-262. Containment Vessel And Cylinder Plate Layout And Penetration Location No Date Available 3-263. Containment Vessel And Cylinder Plate Layout And Penetration Location 10/24/04 3-264. Containment Vessel Penetration Details No Date Available 3-265. Containment Vessel Base Linear Plate Embedded Items No Date Available 3-266. Containment Vessel Base Linear Plate Test Channel Layout 10/1/91 3-267. Containment Vessel Model For "KSHEL" Analysis 10/1/91 3-268. Containment Vessel Model For "Stardyne" Localized Analysis 10/1/91 3-269. Containment Vessel Model For "Wilson-Ghosh" Analysis 10/1/91 3-270. TMD Compartment Pressure Transients - Ice Condenser Region 10/1/91 3-271. TMD Compartment Pressure Transients - Ice Condenser Region 10/1/91 3-272. TMD Compartment Pressure Transients - Ice Condenser Region 10/1/91 3-273. TMD Compartment Pressure Transients - Ice Condenser Region 10/1/91 3-274. Fourier Series Representation Of Transient Pressures 10/1/91 3-275. Containment Vessel Model For "BOSOR4" Stability Analysis 10/1/91 3-276. Localized "Nastran" Model For Stability Analysis 10/1/91 3-277. Containment Vessel Model For "Marc" Ultimate Capacity Analysis 11/15/07 3-278. Reactor Building Pressure Seals And Gaskets 11/15/07 3-279. Reactor Building Pressure Seals And Gaskets 10/1/91 3-280. Catawba Operating Floor Elastic Model 10/1/91 3-281. Catawba Operating Floor Element Model 10/22/01 3-282. Fixed End Supports 10/22/01 3-283. Pinned End Supports 10/1/91 3-284. Fixed End Supports 10/1/91 3-285. Pinned End Supports 10/22/01 3-286. Calculation Of Safety-Related Masonry Walls 10/1/91 3-287. Reactor Coolant Loop Supports System Dynamic Structural Model 10/1/91 3-288. Through-Wall Thermal Gradients 10/1/91 3-289. Reactor Internals Mathematical Model For DARI Variables 10/1/91 3-290. Reactor Internals Mathematical Model For WOSTAS Variables 10/1/91 3-291. Pre And Post Hot Functional Examination Points For Internals And Integrity Attachment I Page 31 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 3-292. Auxiliary Building Auxiliary Feedwater System 10/1/91 3-293. Full Length Control Rod Drive. Mechanism 10/1/91 3-294. Full Length Control Rod Drive Mechanism Schematic 10/1/91 3-295. Nominal Latch Clearance At Minimum And Maximum Temperature 10/1/91 3-296. Control Rod Drive Mechanism Latch Clearance Thermal Effect 10/1/91 3-297. Lower Core Support Assembly (Core Barrel Assembly) 10/1/91 3-298. Upper Core Support Structure 10/1/91 3-299. Plan View Of Upper Core Support Structure 10/1/91 3-300. Direct Generation Interactive Scheme Flow Chart 5/2/97 3-301. Reactor Coolant Loop Model for Steam Generator Replacement 5/2/97 3-302. Reactor Coolant Loop Model for Steam Generator Replacement 5/2/97 3-303. Reactor Coolant Loop Model for Steam Generator Replacement 5/2/97 3-304. Reactor Coolant Loop Model for Steam Generator Replacement 4/8/00 3-305. Loop Layout and Global Coordinates 4/8/00 3-306. RPV Shell Submodel 4/8/00 3-307. Core Barrel Sub model 4/8/00 3-308. Reactor Internals Sub model 4/8/00 3-309. Hydrodynamic Masses in Vessel/Barrel Downcomer Annulus 10/22/01 3-310. Response Acceleration Spectra Chapter 4 Figures 10/1/93 4-1. 17 x 17 Fuel Assembly Cross Section 10/22/01 4-2. 17 x 17 Optimized Fuel Assembly Outline (Deleted per 2001 Update) 10/24/98 4-3. MK-BW Fuel Rod Assembly 10/1/93 4-4. Deleted Per 1993 Update 10/1/93 4-5. Deleted Per 1993 Update 10/22/01 4-6. Elevation View of Mid-Grid to Guide Thimble Joint (Deleted per 2001 Update) 10/22/01 4-7. Top Grid to Nozzle Attachment (Deleted per 2001 Update) 10/22/01 4-8. Guide Thimble to Bottom Nozzle Joint (Deleted per 2001 Update) 10/1/91 4-9. Full Length Rod Cluster Control and Drive Rod Assembly with Interfacing Components 10/22/01 4-10. Rod Cluster Control Assembly Outline 10/22/01 4-11. Hybrid B4C Absorber Rod 10/22/01 4-12. Composite Core Component Rods and Assembly Outline (Deleted per 2001 Update) 4/8/00 4-13. Deleted per 2000 Update 10/1/94 4-14. Deleted Per 1994 Update 10/22/01 4-15. Secondary Source Assembly (Deleted per 2001 Update) 10/1/91 4-16. Thimble Plug Assembly 4/8/00 4-17. Fuel Loading Arrangement 4/8/00 4-18. Fuel Loading Arrangement 4/8/00 4-19. Production and Consumption of Higher Isotopes 4/8/00 4-20. Boron Concentration Versus Typical Cycle Burnup With and Without Burnable Poison Rods 4/8/00 4-21. Deleted per 2000 Update 4/8/00 4-22. Typical Burnable Poison Loading Pattern 4/8/00 4-23. Typical Burnable Poison Loading Pattern 4/8/00 4-24. Normalized Power Density Distribution Near Beginning-Of-Life, Unrodded Core, Hot Full Power, No Xenon 4/8/00 4-25. Normalized Power Density Distribution Near Beginning-Of-Life, Unrodded Core, Hot Full, Equilibrum Xenon Attachment I Page 32 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/8/00 4-26. Normalized Power Density Distribution Near Beginning-Of-Life, Group D 28% Inserted, Hot Full Power, Equilibrum Xenon 4/8/00 4-27. Normalized Power Density Distribution Near Middle-Of-Life, Hot Full Power, Equilibrum Xenon 4/8/00 4-28. Normalized Power Density Distribution Near End-Of-Life, Unrodded Core, Hot Full Power, Equilibrum Xenon 4/8/00 4-29. Normalized Power Density Distribution Near End-Of-Life, Group D 28% Inserted, Hot Full Power, Equilibrum Xenon 4/8/00 4-30. Rodwise Power Distribution in a Typical Assembly (G-9) Near Beginning-Of-Life, Hot Full Power, Equilibrium Xenon, Unrodded Core 4/8/00 4-31. Rodwise Power Distribution in a Typical Assembly (G-9) Near End-Of-Life, Hot Full Power, Equilibrium Xenon, Unrodded Core 4/8/00 4-32. Typical Axial Power Shapes Occurring at Beginning-Of-Life 4/8/00 4-33. Typical Axial Power Shapes Occurring at Middle-Of-Life 4/8/00 4-34. Typical Axial Power Shapes Occurring at End-Of-Life 4/8/00 4-35. Comparison of Assembly Axial Power Distribution with Core Average Axial Distribution, D Bank Slightly Inserted 10/24/98 4-36. Deleted per the 1998 Update 4/8/00 4-37. Deleted per 2000 Update 4/8/00 4-38. Deleted per 2000 Update 4/8/00 4-39. Deleted per 2000 Update 4/8/00 4-40. Peak Linear Power During Control Rod Malfunction Overpower Transient 4/8/00 4-41. Peak Linear Power During Boration/Dilution Overpower Transients 4/8/00 4-42. Typical Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution 4/8/00 4-43. Comparison of Calculated and Measured Axial Shape 4/8/00 4-44. Comparison of Calculated and Measured Peaking Factors, FQX PREL MAX Envelope as a Function of Core Height 4/8/00 4-45. Doppler Temperature Coefficient at BOL and EOL, Cycle 1 4/8/00 4-46. Doppler - Only Power Coefficient - BOL, EOL, Cycle 1 4/8/00 4-47. Doppler - Only Power Defect Coefficient - BOL, EOL, Cycle 1 4/8/00 4-48. Moderator Temperature Coefficient - BOL Cycle 1, No Rods 4/8/00 4-49. Moderator Temperature Coefficient - EOL Cycle 1 4/8/00 4-50. Moderator Temperature Coefficient as a Function of Boron Concentration - BOL Cycle 1, No Rods 4/8/00 4-51. Hot Full Power Temperature Coefficient During Cycle 1 for the Critical Boron Concentration 4/8/00 4-52. Total Power Coefficient - BOL, EOL, Cycle 1 4/8/00 4-53. Total Power Defect - BOL, EOL, Cycle 1 10/1/91 4-54. Rod Cluster Control Assembly Pattern 4/8/00 4-55. Accidental Simultaneous Withdrawal of Two Control Banks, EOL, HZP, Banks C and B Moving in the Same Plane 10/24/98 4-56. Deleted per the 1998 Update 10/24/98 4-57. Deleted per the 1998 Update 10/1/91 4-58. Axial Offset Versus Time PWR Core with 12-ft. Height and 121 Assemblies 10/1/91 4-59. XY Xenon Test Thermocouple Response Quadrant Tilt Difference Versus Time 10/24/98 4-60. Deleted per the 1998 Update Attachment I Page 33 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 4-61. Comparison of Calculated and Measured Boron Concentration for 2-Loop Plant, 121 Assemblies, 12-Foot Core 10/1/91 4-62. Comparison of Calculated and Measured CB 3-Loop Plant with 157 Assemblies, 12-Foot Core 10/1/91 4-63. Comparison of Calculated and Measured CB 4-Loop Plant, 193 Assemblies, 12-Foot Core 10/1/91 4-64. Deleted per 1997 Update 5/2/97 4-65. Measured Versus Predicted Critical Heat Flux - BWCMV 10/1/91 4-66. TDC Versus Reynolds Number for 26-inch Grid Spacing 10/22/01 4-67 Normalized Radial Flow and Enthalpy Distribution at 4-ft Elevation (Deleted per 2001 Update) 10/22/01 4-68. Normalized Radial Flow and Enthalpy Distribution at 8-ft Elevation (Deleted per 2001 Update) 10/22/01 4-69. Normalized Radial Flow and Enthalpy Distribution at 12-ft Elevation - Core Exit (Deleted per 2001 Update) 10/1/91 4-70. Void Fraction Versus Themodynamic Quality H-Hsat/Hg-Hsat 10/22/01 4-71. Thermal Conductivity of U02 (Data Corrected to 95% Theoretical Density) (Deleted per 2001 Update) 11/30/95 4-72. Deleted Per 1995 Update 10/1/92 4-73. Deleted Per 1992 Update 10/1/91 4-74. Distribution of Incore Instrumentation 10/24/98 4-75. Typical 17 X 17 Mark-BW Fuel Assembly with Debris Filter Bottom Nozzle 03/27/03 4-76. Unitl Reactor Coolant System Temperature - Percent Power Map 03/27/03 4-77. Unit 2 Reactor Coolant System Temperature - Percent Power Map 10/24/98 4-78. Replacement of Secondary Sources 4/8/00 4-79. Typical Burnable Poison Rod (BWFC) Cross Section 4/8/00 4-80. Typical Burnable Poison Arrangement within An Assembly Burnable Poison Rods 4/8/00 4-81. Typical Burnable Poison Arrangement within An Assembly IFBA Fuel Rods 10/22/01 4-82. RFA 17x17 Fuel Assembly Cross Section 4/8/00 4-83. WABA Assembly Diagram 4/8/00 4-84. WABA Burnable Poison Rod Cross Section 4/8/00 4-85. 17x 17 Westinghouse Robust Fuel Assembly Outline 4/8/00 4-86. Westinghouse Robust Fuel Assembly 10/22/01 4-87. Hybrid B 4C Absorber Rod (BWFC Demo) 4/24/06 4-88. Typical 17 x17 Mark BW/MOX1 Fuel Assembly Configuration Chapter 5 Figures 4/18/09 5-1. Flow Diagram of Reactor Coolant System ( Unit 1 Only) 4/18/09 5-2. Flow Diagram of Reactor Coolant System ( Unit 2 Only) 4/18/09 5-3. Flow Diagram of Reactor Coolant System 5/2/97 5-4. Simplified Schematic of Reactor Vessel Head Vent System 4/24/06 5-5. Flow Diagram of Reactor Coolant System ( Unit 1 Only) 4/18/09 5-6. Flow Diagram of Reactor Coolant System 10/1/91 5-7. Identification and Location of Catawba Unit 1 Reactor Vessel Beltline Region Weld and Forging Material 10/1/91 5-8. Identification and Location of Catawba Unit 2 Reactor Vessel Beltline Region Weld and Plate Material 10/1/91 5-9. Reactor Vessel (Part 1 of 2) 10/1/91 5-9. Reactor Vessel (Part 2 of 2) 03/27/03 5-10. Reactor Vessel Head View Showing Top-Mounted Control Rod Mechanism Housing Locations and UHI Head Adaptors Attachment I Page 34 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 03/27/03 5-11. Welding Detail for UHI Head Adaptor 10/1/91 5-12. Reactor Coolant Controlled Leakage Pump 10/24/98 5-13. Reactor Coolant Pump Hot Performance Curve 10/24/98 5-14. Steam Generator (Unit 1) 10/1/91 5-15. Counter Flow Preheat Steam Generator (Unit 2) 03/27/03 5-16. Flow Diagram of Conventional Chemical Addition System 4/18/09 5-17. Flow Diagram of Residual Heat Removal System 4/18/09 5-18. Flow Diagram of Residual Heat Removal System 10/1/91 5-19. Deleted per 2000 Update 10/1/91 5-20. Deleted per 2000 Update 10/1/91 5-21. Pressurizer 10/1/91 5-22. Pressurizer Relief Tank 10/1/91 5-23. Typical Steam Generator Lower Lateral Support 10/24/98 5-24. Typical Steam Generator Upper Support (Unit 2) 10/1/91 5-25. Typical Column Assembly for the Steam Generator and Reactor Coolant Pump 10/1/91 5-26. Typical Reactor Coolant Pump Lateral Support 10/1/91 5-27. Typical Reactor Coolant Pump Lateral Support 10/1/91 5-28. Pressurizer Support System Elevation 10/1/91 5-29. Pressurizer Lower Lateral Support 10/1/91 5-30. Pressurizer Upper Lateral Support 10/1/91 5-31. Typical Reactor Vessel Support 10/22/01 5-32. Typical Unit 1 Steam Generator Upper Support 10/22/01 5-33. Flow Diagram of the Reactor Coolant System 11/15/07 5-34. Flow Diagram of the Reactor Coolant System 4/18/09 5-35 Flow Diagram of the Reactor Coolant System Chapter 6 Figures 4/24/06 6-1. Containment Sump pH Vs. Time 10/1/91 6-2. Sensitivity of Peak Pressure to Air Compression Ratio 10/1/91 6-3. Steam Concentration in a Vertical Distribution Channel 10/1/91 6-4. Peak Compression Pressure Versus Compression Ratio 10/1/91 6-5. Upper Compartment Compression Pressure Versus Energy Release for Tests at 110% and 200% of Initial DBA Blowdown Rate 4/18/09 6-6. Peak Containment Pressure Transient 4/18/09 6-7. Peak Containment Pressure Transient 4/18/09 6-8. Peak Containment Pressure Transient 4/18/09 6-9. Peak Containment Pressure Transient 4/18/09 6-10. Peak Containment Pressure Transient 4/8/00 6-11. Containment Spray Return Drains from Air Return Pit Fans 4/8/00 6-12. Containment Spray Return Drains from Air Return Pit Fans 4/8/00 6-13. Drain Piping Arrangement Refueling Canal 10/1/91 6-14. Ice Melted Versus Energy Release for Tests at Different Blowdown Rates 10/1/91 6-15. Upper Compartment Peak Compression Pressure Versus Blowdown Rate for Tests with 175% Energy Release 10/1/91 6-16. Peak Reverse Differential Pressure Transient 10/1/91 6-17. Peak Reverse Differential Pressure Transient 10/1/91 6-18. Pressure Increase Versus Deck Area from Deck Leakage Tests 10/1/91 6-19. Energy Release at Time of Compression Peak Pressure from Full-Scale Section Test with 1-Foot Diameter Baskets 5/2/97 6-20. Peak Containment Temperature Transient for Double-Ended Steam Line Attachment I Page 35 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Breaks 5/2/97 6-21. Peak Containment Superheat Duration Transient 5/2/97 6-22. Deleted per 1997 Update 10/1/91 6-23. Typical Upper and Lower Compartment Pressure Transient for Break Compartment Having a DEHL Break 10/1/91 6-24. Typical Upper and Lower Compartment Pressure Transient for Break Compartment Having a DECL Break 10/1/91 6-25. Plan at Equipment Rooms Elevation 10/1/91 6-26. Compartment Section View 10/1/91 6-27. Plan View at Ice Condenser Elevation- Ice Condenser Compartments 10/1/91 6-28. Layout of Containment Shell 10/1/91 6-29. TMD Code Network 10/1/91 6-30. Nine Volume Nodalization of the Steam Generator Enclosure 10/1/91 6-31. Double Ended Steam Line Break in Steam Generator Enclosure 10/1/91 6-32. Double Ended Steam Line Break in Steam Generator Enclosure 10/1/91 6-33. Double Ended Steam Line Break in Steam Generator Enclosure 10/1/91 6-34. Double Ended Steam Line Break in Steam Generator Enclosure 10/1/91 6-35. Double Ended Steam Line Break in Steam Generator Enclosure 10/1/91 6-36. Two Volume Nodalization of the Steam Generator Enclosure 10/1/91 6-37. Two Volume Nodalization of the Pressurizer Enclosure 10/1/91 6-38. Four Volume Nodalization of the Pressurizer Enclosure 10/1/91 6-39. Developed View of the TMD Code Network for the Reactor Cavity Analysis 10/1/91 6-40. Flowpath Connections for the Reactor Cavity Analysis 10/1/91 6-41. Containment Model for the Reactor Cavity Analysis 4/8/00 6-42. Reactor Vessel Nozzle Break Supports 10/1/91 6-43. Reactor Cavity Analysis, Element 1 10/1/91 6-44. Reactor Cavity Analysis, Element 2 10/1/91 6-45. Reactor Cavity Analysis, Element 3 10/1/91 6-46. Reactor Cavity Analysis, Element 4 10/1/91 6-47. Reactor Cavity Analysis, Element 5 10/1/91 6-48. Reactor Cavity Analysis, Element 6 10/1/91 6-49. Reactor Cavity Analysis, Element 7 10/1/91 6-50. Reactor Cavity Analysis, Element 8 10/1/91 6-51. Reactor Cavity Analysis, Element 9' 10/1/91 6-52. Reactor Cavity Analysis, Element 10 10/1/91 6-53. Reactor Cavity Analysis, Element 11 10/1/91 6-54. Reactor Cavity Analysis, Element 12 10/1/91 6-55. Reactor Cavity Analysis, Element 13 10/1/91 6-56. Reactor Cavity Analysis, Element 14 10/1/91 6-57. Reactor Cavity Analysis, Element 15 10/1/91 6-58. Reactor Cavity Analysis, Element 16 10/1/91 6-59. Reactor Cavity Analysis, Element 17 10/1/91 6-60. Reactor Cavity Analysis, Element 18 10/1/91 6-61. Reactor Cavity Analysis, Element 19 10/1/91 6-62. Reactor Cavity Analysis, Element 20 10/1/91 6-63. Reactor Cavity Analysis, Element 32 10/1/91 6-64. Reactor Cavity Analysis, Element 33 10/1/91 6-65. Reactor Cavity Analysis, Element 34 10/1/91 6-66. Reactor Cavity Analysis, Element 35 10/1/91 6-67. Reactor Cavity Analysis, Element 36 10/1/91 6-68. Reactor Cavity Analysis, Element 37 10/1/91 6-69. Reactor Cavity Analysis, Element 38 Attachment I Page 36 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 6-70. Reactor Cavity Analysis, Element 39 10/1/91 6-71. Reactor Cavity Analysis, Element 40 10/1/91 6-72. Reactor Cavity Analysis, Element 41 10/1/91 6-73. Reactor Cavity Analysis, Element 42 10/1/91 6-74. Reactor Cavity Analysis, Element 43 10/1/91 6-75. Reactor Cavity Analysis, Element 44 10/1/91 6-76. Reactor Cavity Analysis, Element 45 10/1/91 6-77. Reactor Cavity Analysis, Element 46 10/1/91 6-78. Reactor Cavity Analysis, Element 47 10/1/91 6-79. Reactor Cavity Analysis, Element 53 10/1/91 6-80. Reactor Cavity Analysis, Element 54 10/1/91 6-81. Hot Leg Double Ended Guillotine Break 10/1/91 6-82. Hot Leg Double Ended Guillotine Break 10/1/91 6-83. Cold Leg Double Ended Guillotine Break 10/1/91 6-84. Cold Leg Double Ended Guillotine Break 10/1/91 6-85. Hot Leg Single Ended Split Break 10/1/91 6-86. Hot Leg Single Ended Split Break 10/1/91 6-87. Cold Leg Single Ended Split Break 10/1/91 6-88. Cold Leg Single Ended Split Break 10/1/91 6-89. Comparison of Satan to Henry Fauske 10/1/91 6-90. Comparison of Satan to Moody Subcooled 10/1/91 6-91. Zaloudek Measured Data Versus Modified Zaloudek Correlation 10/1/91 6-92. Zaloudek Short Tube Data 10/1/91 6-93. Exit Plane Quality as a Function of Upstream Pressure for Saturated Liquid 10/1/91 6-94. Henry ANL 7740 Data 10/1/91 6-95. Loft Tests 809 and 813 Gage P-1 10/22/01 6-96. Minimum Pressure Analysis (Deleted per 2001 Update) 10/22/01 6-97. Minimum Pressure Analysis (Deleted per 2001 Update) 10/22/01 6-98. Minimum Pressure Analysis (Deleted per 2001 Update) 10/22/01 6-99. Minimum Pressure Analysis (Deleted per 2001 Update) 10/22/01 6-100. Minimum Pressure Analysis (Deleted per 2001 Update) 10/22/01 6-101. Minimum Pressure Analysis (Deleted per 2001 Update) 10/1/91 6-102. Illustration of Choked Flow Characteristics 4/8/00 6-103. Flow Diagram of Containment Air Return Exchange & Hydrogen Skimmer System 4/8/00 6-104. Reactor Building Plan at Elev. 565 + 3 Hydrogen Skimmer System 4/8/00 6-105. Reactor Building Hydrogen Skimmer System 10/1/91 6-106. Containment Air Return Fan Performance Curve 10/1/91 6-107. Hydrogen Skimmer Fan Performance Curve 10/1/91 6-108. Areas of Potential Hydrogen Pockets 4/18/09 6-109. Flow Diagram of Containment Spray System 10/1/91 6-110. Containment Spray Pump Performance Curve 4/18/09 6-111. Recirculation Sump Screen Assembly 4/8/00 6-112. Containment Piping Penetration Valve Arrangements 4/8/00 6-113. Containment Piping Penetration Valve Arrangements 4/8/00 6-114. Containment Piping Penetration Valve Arrangements 4/8/00 6-115. Containment Piping Penetration Valve Arrangements 11/15/07 6-116. Flow Diagram of Containment Valve Injection Water System 10/1/91 6-117. Fuel Transfer Tube 4/24/06 6-118. Model B Electric Hydrogen Recombiner-Cutaway 4/24/06 6-119. Recombiner Control System Schematic 10/22/01 6-120. Flow Diagram of Containment Hydrogen Sample & Purge System Page 37 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 6-121. Deleted Per 1991 Update 10/1/91 6-122. Deleted Per 1991 Update 10/1/91 6-123. Deleted Per 1991 Update 10/24/04 6-124. Deleted Per 2004 Update 4/24/06 6-125. Deleted per 2006 Update 4/24/06 6-126. Deleted per 2006 Update 03/27/03 6-127. Deleted Per 2003 Update 4/18/09 6-128. Flow Diagram of Safety Injection System 10/24/04 6-129. Flow Diagram of Safety Injection System 11/15/07 6-130. Flow Diagram of Safety Injection System 4/18/09 6-131. Flow Diagram of Safety Injection System 4/18/09 6-132. Safety Injection System 10/1/91 6-133. Residual Heat Removal Performance Curve 10/1/91 6-134. Centrifugal Charging Pump Performance Curve 10/1/91 6-135. Safety Injection Pump Performance Curve 4/8/00 6-136.01 ECCS Process Flow Diagram 4/8/00 6-136.02 ECCS Process Flow Diagram 4/8/00 6-136.03 ECCS Process Flow Diagram 4/8/00 6-137. Ice Condenser 10/1/91 6-138. Isometric of Ice Condenser 10/1/91 6-139. Floor Structure 10/1/91 6-140. Wear Slab Top Surface Area Showing Typical CoolantPiping Layout 10/1/91 6-141. Lattice Frame Orientation 10/1/91 6-142. Load Distribution For Tangential Seismic And Blowdown Loads In Analytical Model 10/1/91 6-143. Lattice Frame 10/1/91 6-144. Lattice Frame Analysis Model 10/1/91 6-145. Typical Bottom Ice Basket Assembly 10/1/91 6-146. Combinations of Concentric Axial Load and Distribution Load 10/1/91 6-147. Crane Assembly 10/1/91 6-148. Crane Rail Assembly 10/1/91 6-149. Refrigerant Cycle Diagram 10/1/93 6-150. Glycol Cycle to Each Containment 10/1/91 6-151. Schematic Flow Diagrams of Air Cooling Cycle 10/1/91 6-152. Air Handling Unit Support Structure 10/1/91 6-153. Flow Area - Pressure Differential 10/1/91 6-154. Lower Inlet Door Assembly 10/1/91 6-155. Details of Lower Inlet Door Showing Hinge, Proportioning Mechanism limit Switches and Seals 10/1/91 6-156. Inlet Door Frame Assembly 10/1/91 6-157. Inlet Door Panel Assembly 10/1/91 6-158. Lower Inlet Door Shock Absorber Assembly 10/1/91 6-159. Four Loop Ice Condenser Lower Support Structure Conceptual Plan and Sections 10/1/91 6-160. Four Loop Ice Condenser Lower Support Structure General Assembly 10/1/91 6-161. Ansys Model Assembly 10/1/91 6-162. Finite Element Model of Postal Frame 10/1/91 6-163. Schematic Diagram of Force Applied to Three Pier Lower Support Structure 10/1/91 6-164. Force Transient Hot Leg Break 10/1/91 6-165. DLF Spectra Hot Leg Break Force Transient 10/1/91 6-166. Top Deck Test Assembly Attachment I Page 38 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 0/1/91 6-167. Details of Top Deck Door Assembly 10/1/91 6-168. Intermediate Deck Door Assembly 10/1/91 6-169. Air Distribution Duct 10/1/91 6-170. Air Distribution Duct 5/2/97 6-171. Phase Diagram for NA2B407- 10 H/Water System at One Atmosphere 10/1/91 6-172. Ice Bed Compaction Versus Time 10/1/91 6-173. Test Ice Bed Compaction Versus Ice Bed Height 10/1/91 6-174. Total Ice Compaction Versus Ice Bed Height 10/22/01 6-175. Ice Condenser RTD Location 10/24/04 6-176. Block Diagram: Ice Condenser Temperature Monitoring System 10/1/91 6-177. Door Monitoring Zones 4/8/00 6-178. Wiring Diagram: "X" Switch 4/8/00 6-179. Wiring Diagram: "Y" Switches Lower Inlet Doors and Personnel Access Doors 10/22/01 6-180. Wiring Diagram: Access Door Switches (Deleted per 2001 Update) 10/1/91 6-181. Model of Horizontal Lattice Frame Structure 10/1/91 6-182. Group of Six Interconnected Lattice Frames 10/1/91 6-183. Lattice Frame Ice Basket Gap 10/1/91 6-184. Typical Displacement Time History for 12 Foot Basket with End Supports - Pluck Test 10/1/91 6-185. Non Linear Dynamic Model 10/1/91 6-186. 3 Mass Tangential Ice Basket Model 10/1/91 6-187. 9 Mass Radial Ice Basket Model 10/1/91 6-188. 48 Foot Beam Model 10/1/91 6-189. Phasing Mass Model of Adjacent Lattice Frame Bays 10/1/91 6-190. Phasing Study Model, 1 Level Lattice Frame 300 Degrees Non-Linear Model 10/1/91 6-191. Typical Crane Wall Displacement 10/1/91 6-192. Typical Ice Basket Displacement Response 10/1/91 6-193. Typical Ice Basket Impact Force Response 10/1/91 6-194. Typical Crane Wall Panel Load Response 10/1/91 6-195. Wall Panel Design Load Distribution Obtained Using the 48-Foot Beam Model Tangential Case 10/1/91 6-196. Wall Panel Design Load Distribution Obtained Using the 48-Foot Beam Model Radial Case 11/30/95 6-197. Ice Basket Swivel Bracket Assembly 5/2/97 6-198. Block Ice Minimum Restriction Basket Assembly 4/18/09 6-199. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses 4/18/09 6-200. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses 4/18/09 6-201. CNS- 1 Double-Ended LBLOCA Mass and Energy Release Analyses 4/18/09 6-202. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses 4/8/00 6-203. Deleted per 2000 Update 03/27/03 6-204. Post-LOCA Upper and Lower Compartment Pressures, Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-205. Post-LOCA Upper Compartment Heat Removal Rate, Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-206. Post-LOCA Lower Compartment Heat Removal Rate, Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-207. Post-LOCA Upper and Lower Compartment Temperature, Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-208. Post-LOCA Ice Bed Heat Removal Rate, Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-209. Post LOCA Heat Removal Rate by Lower Compartment Drain, Attachment I Page 39 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Minimum Containment Pressure Analysis for Large Break LOCA 03/27/03 6-210. Post LOCA Heat Removal Rate by Sump and Spray, Minimum Containment Pressure Analysis for Large Break LOCA Chapter 7 Figures 10/1/91 7-1. Protection System Block Diagram 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 1 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 2 10/1/93 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 3 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 4 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 5 10/22/01 7-2. 06 Instrumentation and Control System Diagrams - Index and Symbols - page 6 10/24/04 7-2.07 Instrumentation and Control System Diagrams - Index and Symbols - page 7 10/22/01 7-2.08 Instrumentation and Control System Diagrams - Index and Symbols - page 8 10/24/04 7-2.09 Instrumentation and Control System Diagrams - Index and Symbols - page 9 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 10 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 11 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 12 10/22/01 7-2. 13 Instrumentation and Control System Diagrams - Index and Symbols - page 13 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 14 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 15 10/1/91 7-2. 16 Instrumentation and Control System Diagrams - Index and Symbols - page 16 10/22/01 7-3. Setpoint Reduction Function for Overtemperature & Delta.T Trips 10/1/91 7-4. Typical ESF Test Circuits 10/1/91 7-5. Engineered Safeguards Test Cabinet Index, Notes, and Legend 10/22/01 7-6. Motor-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram 5/2/97 7-7. Turbine-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram 10/1/91 7-8. Component Cooling Water System Logic Diagram 10/1/91 7-9. Chemical and Volume Control System Logic Diagram 10/1/91 7-10. Residual Heat Removal Pump Logic Diagram 10/1/93 7-11. Deleted Per 1991 Update 10/1/93 7-12. Deleted Per 1993 Update 10/22/01 7-13. Cold Leg Accumulator Isolation Valves Control and Alarm Attachment I Page 40 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Logic 10/22/01 7-14. Containment Pressure Control System Logic 4/8/00 7-15. RWST Level Signal for Safety Injection System Recirculation Sump Isolation Valves 10/1/91 7-16. Safety Injection System Recirculation Sump Isolation Valves 10/1/91 7-17. Reactor Coolant System Overpressure Protection System for Low Pressure/Temperature Water Solid Conditions Logic Diagram 10/22/01 7-18. Rod Control System Block Diagram 10/1/91 7-19. Control Bank Rod Insertion Monitor Block Diagram 10/1/91 7-20. Rod Deviation Comparator 10/22/01 7-21. Pressurizer Pressure Control System Block Diagram 10/22/01 7-22. Pressurizer Level Control System Block Diagram 4/8/00 7-23. Steam Generator Water Level Control System Block Diagram 10/22/01 7-24. Main Feedwater Pump Speed Control System Block Diagram 10/22/01 7-25. Steam Dump Control System Block Diagram 11/15/07 7-26. Basic Flux-Mapping System 10/1/91 7-27. Deleted Per 1990 Update 10/1/91 7-28. Deleted Per 1990 Update 10/1/91 7-29. Deleted Per 1990 Update 4/8/00 7-30. Deleted per 2000 Update 10/22/01 7-31. Rod Control System Simplified Block Diagram 10/1/91 7-32. Control Bank D Power Cabinets 1BD and 2BD Partial Schematic Diagram 11/30/95 7-33. Deleted Per 1995 Update Chapter 8 Figures 4/18/09 8-1. Onsite Power System 4/8/00 8-2. Duke Transmission System 4/24/06 8-3. VACAR Subregion of the Southeastern Electric Reliability Council 4/8/00 8-4. Site Plan of Transmission Lines 4/8/00 8-5. Newport Transmission Line Plan 4/8/00 8-6. Allison Creek Transmission Line Plan 10/1/93 8-7. Roddey Transmission Line Plan 4/8/00 8-8. Clay Hill Transmission Line Plan 4/8/00 8-9. Moser Transmission Line Plan 10/1/93 8-10. 230KV Switchyard General Arrangement 10/1/93 8-11. 230KV Switchyard 125VDC Auxiliary Power System 10/1/93 8-12. 230KV Switchyard and Station Interconnections 10/1/93 8-13. Offsite Power System Protective Relaying Zones 4/8/00 8-14. Stability Analysis Diagram 4/8/00 8-15. Deleted per 2000 Update 4/8/00 8-16. Deleted per 2000 Update 4/8/00 8-17. Deleted per 2000 Update 4/8/00 8-18. Deleted per 2000 Update 4/18/09 8-19. Non-Class IE AC Power Systems 5/2/97 8-20. 13.8KV Normal Auxiliary Power System and 600 VAC Cooling Tower Auxiliary Power System 10/24/04 8-21. Essential and Blackout Auxiliary Power Systems 10/1/93 8-22. 125 VDC and 240/120 VAC Auxiliary Control Power Systems 10/1/94 8-23. 250 VDC Auxiliary Power System 10/24/04 8-24. 125 VDC and 120 VAC Vital Instrumentation and Control Power System Attachment I Page 41 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/24/06 8-25. 125 VDC Vital Instrumentation and Control Battery Duty Cycle 5/2/97 8-26. 125 VDC Diesel Essential Auxiliary Power System 4/24/06 8-27. 125 VDC Diesel Auxiliary Power Battery Duty Cycle 4/8/00 8-28. Peacock Transmission Line Plan Chapter 9 Figures 10/1/91 9-1. Fuel Building - General Arrangement 10/1/91 9-2. Fuel Building - Longitudinal Section Thru Fuel Receiving 4/8/00 9-3. Fuel Pool Racks 10/1/91 9-4. Fuel Building Plan @ El. 605+ 10 10/1/91 9-5. Fuel Building - Longitudinal Section Thru Fuel Pool 10/1/91 9-6. Cask Drop Evaluation 10/1/91 9-7. Cask Drop Evaluation 4/8/00 9-8. Spacer for Spent Fuel Storage 4/8/00 9-9. Spent Fuel Pool Racks - General Arrangement 4/8/00 9-10. Spent Fuel Pool Racks - Details 4/18/09 9-11. Flow Diagram of Spent Fuel Cooling System 11/15/07 9-12. Flow Diagram of Spent Fuel Cooling System 10/24/98 9-13. Spent Fuel Pool Temperature Versus Time 03/27/03 9-14. Refueling Machine 10/1/91 9-15. Fuel Handling Machine 10/1/91 9-16. New Fuel Elevator 10/1/91 9-17. Fuel Transfer System 5/2/97 9-18. Deleted per 1997 Update 10/1/91 9-19. Reactor Vessel Head Lifting Device 10/1/91 9-20. Reactor Internals Lifting Device 10/1/91 9-21. Reactor Vessel Stud Tensioner 4/18/09 9-22. Flow Diagram of Nuclear Service Water System 4/18/09 9-23. Flow Diagram of Nuclear Service Water System 4/18/09 9-24. Flow Diagram of Nuclear Service Water System 11/15/07 9-25. Flow Diagram of Nuclear Service Water System 4/18/09 9-26. Flow Diagram of Nuclear Service Water System 4/18/09 9-27. Flow Diagram of Nuclear Service Water System 4/18/09 9-28. Flow Diagram of Nuclear Service Water System 03/27/03 9-29. Flow Diagram of Nuclear Service Water System 4/18/09 9-30. Flow Diagram of Nuclear Service Water System 4/18/09 9-31. Flow Diagram of Nuclear Service Water System 4/18/09 9-32. Flow Diagram of Nuclear Service Water System 03/27/03 9-33. Flow Diagram of Nuclear Service Water System 10/1/91 9-34. Nuclear Service Water System Yard Layout 4/18/09 9-35. Flow Diagram of Component Cooling System 03/27/03 9-36. Flow Diagram of Component Cooling System 10/24/04 9-37. Flow Diagram of Component Cooling System 11/15/07 9-38. Flow Diagram of Component Cooling System 4/18/09 9-39. Flow Diagram of Component Cooling System 11/15/07 9-40. Flow Diagram of Component Cooling System 10/22/01 9-41. Flow Diagram of Component Cooling System 4/18/09 9-42. Flow Diagram of Component Cooling System 10/22/01 9-43. Flow Diagram of Component Cooling System 4/18/09 9-44. Flow Diagram of Makeup Demineralized Water System 4/18/09 9-45. Flow Diagram of Makeup Demineralized Water System 4/18/09 9-46. Flow Diagram of Makeup Demineralized Water System Page 42 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/18/09 9-47. Flow Diagram of Makeup Demineralized Water System 10/24/04 9-48. Flow Diagram of Makeup Demineralized Water System 4/18/09 9-49. Flow Diagram of Makeup Demineralized Water System 11/15/07 9-50. Flow Diagram of Filtered Water System 4/18/09 9-51. Flow Diagram of Filtered Water System 11/15/07 9-52. Flow Diagram of Drinking Water System 10/1/91 9-53. NSW Intake & SNSW Discharge Structures 10/1/91 9-54. Catawba SNSWP Area Volume Curves 10/1/94 9-55. Deleted Per 1994 Update 10/1/94 9-56. Deleted Per 1994 Update 4/8/00 9-57. Deleted per 2000 Update 10/24/98 9-58. Residual Decay Heat 4/18/09 9-59. Flow Diagram of Condensate Storage System 10/22/01 9-60. Flow Diagram of Condensate Storage System 10/22/01 9-61. Flow Diagram of Condensate Storage System 4/18/09 9-62. Flow Diagram of Refueling Water System 4/18/09 9-63. Flow Diagram of Conventional LPSW System 11/15/07 9-64. Flow Diagram of Conventional LPSW System 11/15/07 9-65. Flow Diagram of Conventional LPSW System 11/15/07 9-66. Flow Diagram of Conventional LPSW System 4/18/09 9-67. Flow Diagram of Conventional LPSW System 4/18/09 9-68. Flow Diagram of Conventional LPSW System 4/18/09 9-69. Flow Diagram of Conventional LPSW System 4/18/09 9-70. Flow Diagram of Instrument Air System 4/18/09 9-71. Flow Diagram of Instrument Air System 10/24/04 9-72. Flow Diagram of Instrument Air System 03/27/03 9-73. Flow Diagram of Station Air System 11/15/07 9-74. Flow Diagram of Station Air System 10/22/01 9-75. Flow Diagram of Breathing Air System 10/24/04 9-76. Flow Diagram of Breathing Air System 11/15/07 9-77. Flow Diagram of Breathing Air System 4/18/09 9-78. Flow Diagram of Nuclear Sampling System 10/22/01 9-79. Flow Diagram of Nuclear Sampling System 11/15/07 9-80. Flow Diagram of Nuclear Sampling System 03/27/03 9-81. Flow Diagram of Nuclear Sampling System 11/15/07 9-82. Flow Diagram of Nuclear Sampling System 4/24/06 9-83. Flow Diagram of Conventional Sampling System 4/24/06 9-84. Flow Diagram of Conventional Sampling System 4/24/06 9-85. Flow Diagram of Conventional Sampling System No Date Available 9-86. Flow Diagram of Conventional Sampling System 10/24/98 9-87. Flow Diagram of Conventional Sampling System 4/8/00 9-88. Deleted per 2000 Update 4/18/09 9-89. Flow Diagram of Chemical and Volume Control System 4/18/09 9-90. Flow Diagram of Chemical and Volume Control System 10/24/04 9-91. Flow Diagram of Chemical and Volume Control System 4/24/06 9-92. Flow Diagram of Chemical and Volume Control System 4/18/09 9-93. Flow Diagram of Chemical and Volume Control System 4/24/06 9-94. Flow Diagram of Chemical and Volume Control System 4/18/09 9-95. Flow Diagram of Chemical and Volume Control System 4/18/09 9-96. Flow Diagram of Chemical and Volume Control System 11/15/07 9-97. Flow Diagram of Chemical and Volume Control System 10/24/98 9-98. Flow Diagram of Boron Recycle System 10/24/04 9-99. Flow Diagram of Boron Recycle System 10/22/01 9-100. Flow Diagram of Boron Recycle System Attachment I Page 43 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/18/09 9-101. Flow Diagram of Boron Recycle System 4/18/09 9-102. Flow Diagram of Boron Recycle System 10/24/98 9-103. Flow Diagram of Boron Recycle System 4/18/09 9-104. Flow Diagram of Boron Recycle System 03/27/03 9-105. Flow Diagram of Boron Recycle System 10/24/98 9-106. Flow Diagram of Boron Thermal Regeneration System 10/22/01 9-107. Flow Diagram of Boron Thermal Regeneration System 11/15/07 9-108. Flow Diagram of Control Room Area Ventilation System 10/22/01 9-109. Flow Diagram of Control Room Area Ventilation System 4/8/00 9-110. Flow Diagram of Control Room Area Ventilation System 10/22/01 9-111. Flow Diagram of Battery Room Area Ventilation System EL. 554' + 0' 11/15/07 9-112. Flow Diagram of Control Area Chilled Water System 10/22/01 9-113. Flow Diagram of Control Area Chilled Water System 11/15/07 9-114. Flow Diagram of Control Area Chilled Water System 10/22/01 9-115. Flow Diagram of Control Area Chilled Water System 4/18/09 9-116. Flow Diagram of Control Area Chilled Water System 4/18/09 9-117. Flow Diagram of Control Area Chilled Water System 4/24/06 9-118. Flow Diagram of Fuel Handling Ventilation System 4/24/06 9-119. Flow Diagram of Fuel Handling Ventilation System 4/18/09 9-120. Flow Diagram of Unit 1 Vent Stack 4/18/09 9-121. Flow Diagram of Auxiliary Building Ventilation System 4/24/06 9-122. Flow Diagram of Auxiliary Building Ventilation System 4/18/09 9-123. Flow Diagram of Auxiliary Building Ventilation System 4/18/09 9-124. Flow Diagram of Auxiliary Building Ventilation System 4/24/06 9-125. Flow Diagram of Auxiliary Building Ventilation System 10/1/91 9-126. Auxiliary Shutdown Panel Air Conditioning System 10/1/91 9-127. Auxiliary Shutdown Panel Air Conditioning System 11/15/07 9-128. Flow Diagram of Diesel Building Ventilation System 11/15/07 9-129. Flow Diagram of Containment Purge System 03/27/03 9-130. Flow Diagram of Containment Purge System 4/24/06 9-131. Flow Diagram of Containment Ventilation System 11/15/07 9-132. Flow Diagram of Turbine Building Ventilation System 10/22/01 9-133. Flow Diagram of Turbine Building Ventilation System (Deleted per 2001 Update) 10/22/01 9-134. Flow Diagram of Nuclear Service Water Pump Structure Ventilation System 10/22/01 9-135. Flow Diagram of Annulus Ventilation System 4/24/06 9-136. Flow Diagram of Exterior Fire Protection System 10/1/92 9-137. Flow Diagram of Exterior Fire Protection System 4/18/09 9-138. Flow Diagram of Interior Fire Protection System 4/24/06 9-139. Flow Diagram of Interior Fire Protection System 4/24/06 9-140. Flow Diagram of Interior Fire Protection System 03/27/03 9-141. Flow Diagram of Interior Fire Protection System 4/24/06 9-142. Flow Diagram of Fire Protection System 4/8/00 9-143. Flow Diagram of Interior Fire Protection System 10/24/98 9-144. Flow Diagram of Interior Fire Protection System 10/1/91 9-145. Deleted Per 1990 Update 10/1/91 9-146. Deleted Per 1990 Update 10/1/91 9-147. Deleted Per 1990 Update 10/1/91 9-148. Deleted Per 1990 Update 10/1/91 9-149. Deleted Per 1990 Update 10/1/91 9-150. Deleted Per 1990 Update 10/1/91 9-151. Deleted Per 1990 Update Page 44 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/91 9-152. Deleted Per 1990 Update 10/1/91 9-153. Deleted Per 1990 Update 10/1/91 9-154. Deleted Per 1990 Update 10/1/91 9-155. Deleted Per 1990 Update 10/1/91 9-156. Deleted Per 1990 Update 10/1/91 9-157. Deleted Per 1990 Update 10/1/91 9-158. Deleted Per 1990 Update 10/1/91 9-159. Deleted Per 1990 Update 10/1/91 9-160. Deleted Per 1990 Update 10/1/91 9-161. Deleted Per 1990 Update 10/1/91 9-162. Deleted Per 1990 Update 10/1/91 9-163. Deleted Per 1990 Update 10/1/91 9-164. Deleted Per 1990 Update 10/1/91 9-165. Deleted Per 1990 Update 10/1/91 9-166. Deleted Per 1990 Update 10/1/91 9-167. Deleted Per 1990 Update 10/1/91 9-168. Deleted Per 1990 Update 03/27/03 9-169. Flow Diagram of Diesel Generator Engine Fuel Oil System 10/22/01 9-170. Flow Diagram of Diesel Generator Engine Fuel Oil System No Date Available 9-171. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-172. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-173. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-174. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-175. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-176. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-177. Diesel Generator Building Plan @ Elevation 556+0 No Date Available 9-178. Exterior Miscellaneous Piping No Date Available 9-179. Exterior Miscellaneous Piping No Date Available 9-180. Exterior Miscellaneous Piping 4/8/00 9-181. HVAC Diesel Generator Rooms 4/18/09 9-182. Flow Diagram of Diesel Generator Engine Cooling Water System 4/18/09 9-183. Flow Diagram of Diesel Generator Engine Starting Air System 4/18/09 9-184. Flow Diagram of Diesel Generator Engine Starting Air System 4/18/09 9-185. Flow Diagram of Diesel Generator Engine Lube Oil System 4/24/06 9-186. Flow Diagram of Diesel Generator Engine Lube Oil System 4/24/06 9-187. Flow Diagram of Diesel Generator Engine Lube Oil System 10/22/01 9-188. Flow Diagram of Diesel Generator Engine Air Intake and Exhaust System 4/8/00 9-189. Diesel Generator Area Unit 1 General Arrangement 4/8/00 9-190. Diesel Generator Area Unit 1 General Arrangement 4/8/00 9-191. Diesel Generator Area Unit I General Arrangement 4/8/00 9-192. Diesel Generator Rooms HVAC 4/18/09 9-193. Flow Diagram of Diesel Generator Room Sump Pump System 11/15/07 9-194. Flow Diagram of Containment Air Release and Addition System 11/15/07 9-195. Flow Diagram of Groundwater System 10/1/92 9-196. Flow Diagram of Groundwater System 10/22/01 9-197. Flow Diagram of the Makeup Demineralized Water System (Deleted per 2001 Update) 10/22/01 9-198. Flow Diagram of the Makeup Demineralized Water System (Deleted per 2001 Update) 10/22/01 9-199. Flow Diagram of the Makeup Demineralized Water System (Deleted per 2001 Update) 4/18/09 9-200. Flow Diagram of the Boron Recycle System 4/18/09 9-201. Flow Diagram of the Nuclear Sampling System Attachment I Page 45 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/24/98 9-202. Flow Diagram of the Nuclear Sampling System 10/24/98 9-203. Flow Diagram of the Nuclear Sampling System 03/27/03 9-204. Flow Diagram of the Component Cooling System 03/27/03 9-205. Flow Diagram of the Component Cooling System 11/15/07 9-206. Flow Diagram of the Component Cooling System 03/27/03 9-207. Flow Diagram of the Component Cooling System 4/18/09 9-208. Flow Diagram of the Nuclear Service Water System 4/18/09 9-209. Flow Diagram of the Nuclear Service Water System 4/18/09 9-210. Flow Diagram of the Nuclear Service Water System 4/18/09 9-211. Flow Diagram of the Containment Ventilation System 10/24/98 9-212. Flow Diagram of the Auxiliary Building Ventilation System 4/18/09 9-213. Flow Diagram of the Auxiliary Building Ventilation System 4/18/09 9-214. Flow Diagram of the Auxiliary Building Ventilation System 10/24/04 9-215. Flow Diagram of the Auxiliary Building Ventilation System 10/24/04 9-216. Flow Diagram of the Auxiliary Building Ventilation System 4/18/09 9-217. Flow Diagram of the Auxiliary Building Ventilation System 4/8/00 9-218, Placeholder 4/8/00 9-219, Placeholder 03/27/03 9-220. Flow Diagram of the Fire Protection System 4/24/06 9-221. Flow Diagram of the Fire Protection System 10/22/01 9-222. Flow Diagram of the Interior Fire Protection System 4/8/00 9-223. Flow Diagram of the Makeup Demineralized Water System 03/27/03 9-224. Flow Diagram of the Makeup Demineralized Water System 11/15/07 9-225. Flow Diagram of the Makeup Demineralized Water System 11/15/07 9-226. Flow Diagram of the Instrument Air System 11/15/07 9-227. Flow Diagram of the Instrument Air System 11/15/07 9-228. Flow Diagram of the Instrument Air System 11/15/07 9-229. Flow Diagram of the Instrument Air System 10/24/04 9-230. Flow Diagram of the Instrument Air System 4/24/06 9-231. Flow Diagram of the Instrument Air System 10/24/98 9-232. Flow Diagram of the Instrument Air System 4/24/06 9-233. Flow Diagram of the Auxiliary Building Ventilation System 4/18/09 9-234. Flow Diagram of the Instrument Air System 4/18/09 9-235. Flow Diagram of the Instrument Air System 11/15/07 9-236. Flow Diagram of the Instrument Air System 10/24/04 9-237. Flow Diagram of the Instrument Air System 4/24/06 9-238. Flow Diagram of the Instrument Air System 4/18/09 9-239. Flow Diagram of the Instrument Air System 4/24/06 9-240. Flow Diagram of the Instrument Air System 11/15/07 9-241. Flow Diagram of the Instrument Air System 4/18/09 9-242. Flow Diagram of the Instrument Air System 11/15/07 9-243. Flow Diagram of the Instrument Air System 4/18/09 9-244. Flow Diagram of the Instrument Air System 4/18/09 9-245. Flow Diagram of the Instrument Air System 10/24/98 9-246. Flow Diagram of the Instrument Air System 11/15/07 9-247. Flow Diagram of the Instrument Air System 11/15/07 9-248. Flow Diagram of the Station Air System 10/22/01 9-249. Flow Diagram of the Conventional Sampling System 11/15/07 9-250. Flow Diagram of the Station Air System 4/18/09 9-251. Flow Diagram of the Station Air System 10/24/04 9-252. Flow Diagram of the Station Air System 11/15/07 9-253. Flow Diagram of the Station Air System 4/24/06 9-254. Flow Diagram of the Station Air System 10/24/98 9-255. Flow Diagram of the Turbine Building Ventilation System Attachment I Page 46 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/18/09 9-256. Flow Diagram of the Turbine Building Ventilation System 10/24/04 9-257. Flow Diagram of the Turbine Building Ventilation System 4/18/09 9-258. Flow Diagram of the Turbine Building Ventilation System 4/18/09 9-259. Flow Diagram of the Turbine Building Ventilation System 4/24/06 9-260. Flow Diagram of the Conventional Sampling System 4/24/06 9-261. Flow Diagram of the Conventional Sampling System 10/22/01 9-262. Flow Diagram of the Conventional Sampling System 10/22/01 9-263. Flow Diagram of the Conventional Sampling System 4/18/09 9-264. Flow Diagram of the Boron Recycle System 4/18/09 9-265. Flow Diagram of the Nuclear Service Water System 4/18/09 9-266. Flow Diagram of the Nuclear Service Water System 4/24/06 9-267 Reserved for Future Use 4/18/09 9-268. Flow Diagram of the Chemical and Volume System 4/18/09 9-269. Containment Chilled Water System 4/18/09 9-270. Containment Chilled Water System Chapter 10 Figures 10/1/91 10-1. Heat Balance-Valves Wide Open 10/1/91 10-2. Heat Balance- 100% MWt No Date Available 10-3. Block Diagram of Control System (PWR) 4/24/06 10-4. Block Diagram of Control System 4/18/09 10-5. Flow Diagram of Main Steam System-Main Steam Vent to ATMOS 4/18/09 10-6. Flow Diagram of Main Steam to Auxiliary Equipment - Main Steam Bypass to Condenser 4/18/09 10-7. Flow Diagram of FDWP Turbine Exhaust 4/18/09 10-8. Flow Diagram of Main Steam System 4/18/09 10-9. Flow Diagram of Steam Supply to FWP Turbine System 4/18/09 10-10. Flow Diagram of Steam Supply to FWP Turbine System 4/18/09 10-11. Flow Diagram of Main Steam System - Main Steam to Atmosphere System 11/15/07 10-12. Flow Diagram of Main Steam System 4/18/09 10-13. Flow Diagram of Condenser Steam Air Ejection System No Date Available 10-14. Flow Diagram of Main Vacuum System 10/24/98 10-15. Flow Diagram of Main Turbine Leakoff & Steam Seal System 4/18/09 10-16. Flow Diagram of Main Turbine Leakoff and Steam Seal System 10/24/98 10-17. Flow Diagram of FDWP Turbine Steam Seal System 11/15/07 10-18. Flow Diagram of Condensate System 03/27/03 10-19. Flow Diagram of Condensate System 03/27/03 10-20. Flow Diagram of Condensate System 10/1/94 10-21. Flow Diagram of Condensate System 10/22/01 10-22. Flow Diagram of Condensate System 4/18/09 10-23. Flow Diagram of Condensate System 4/18/09 10-24. Flow Diagram of Condensate System 10/24/98 10-25. Flow Diagram of Condensate System 10/22/01 10-26. Flow Diagram of Condensate System 4/18/09 10-27. Flow Diagram of Feedwater System 4/18/09 10-28. Flow Diagram of Feedwater System 4/18/09 10-29. Flow Diagram of Steam Generator Blowdown System 03/27/03 10-30. Flow Diagram of Steam Generator Blowdown System 11/15/07 10-31. Flow Diagram of Steam Generator Blowdown System 5/10/97 10-32. Flow Diagram of Steam Generator Blowdown System 4/24/06 10-33. Flow Diagram of Auxiliary Feedwater System 4/24/06 10-34. Flow Diagram of Auxiliary Feedwater System Attachment I Page 47 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/24/06 10-35. Flow Diagram of Heater Drain System (HW) 4/18/09 10-36. Flow Diagram of Heater Drain System (HW) 4/24/06 10-37. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 4/24/06 10-38. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 4/24/06 10-39. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 4/24/06 10-40. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 4/18/09 10-41. System Overview of the Turbine Control System 03/27/03 1042. Flow Diagram of Auxiliary Feedwater System Chapter 11 Figures 4/18/09 11-1. Liquid Radwaste System 03/27/03 11-2. Liquid Radwaste System 11/15/07 11-3. Flow Diagram of Liquid Radwaste System 11/15/07 11-4. Flow Diagram of Liquid Radwaste System 4/18/09 11-5. Flow Diagram of Liquid Radwaste System 4/24/06 11-6. Flow Diagram of Liquid Radwaste System 4/24/06 11-7. Flow Diagram of Liquid Radwaste System 4/24/06 11-8. Flow Diagram of Liquid Radwaste System 10/22/01 11-9. Flow Diagram of Liquid Radwaste System 4/18/09 11-10. Flow Diagram of Liquid Radwaste System 4/18/09 11-11. Flow Diagram of Liquid Radwaste System 11/15/07 11-12. Flow Diagram of Liquid Radwaste System 4/18/09 11-13. Flow Diagram of Liquid Radwaste System 4/18/09 11-14. Flow Diagram of Liquid Radwaste System 4/24/06 11-15. Flow Diagram of Liquid Radwaste System 11/15/07 11-16. Flow Diagram of Liquid Radwaste System 11/15/07 11-17. Flow Diagram of Liquid Radwaste System 4/18/09 11-18. Flow Diagram of Liquid Radwaste System 11/15/07 11-19. Flow Diagram of Liquid Radwaste System 4/18/09 11-20. Flow Diagram of Liquid Radwaste System 10/1/93 11-21. Flow Diagram of Liquid Radwaste System 4/24/06 11-22. Flow Diagram of Liquid Radwaste System 11/15/07 11-23. Flow Diagram of Liquid Radwaste System 03/27/03 11-24. Flow Diagram of Liquid Radwaste System 10/24/04 11-25. Flow Diagram of Waste Gas System 10/24/04 11-26. Flow Diagram of Waste Gas System 4/18/09 11-27. Flow Diagram of Waste Gas System 10/22/01 11-28. Flow Diagram of Waste Gas System 03/27/03 11-29. Flow Diagram of Waste Gas System 4/24/06 11-30. Flow Diagram of Solid Radwaste System No Date Available 11-31. Flow Diagram of Solid Radwaste System 10/22/01 11-32. Flow Diagram of Solid Radwaste System 4/18/09 11-33. Flow Diagram of Solid Radwaste System 10/24/04 11-34. Flow Diagram of Solid Radwaste System 10/24/04 11-35. Flow Diagram of Solid Radwaste System No Date Available 11-36. Waste Solidification Facility Interim General Arrangement 4/18/09 11-37. Flow Diagram of Liquid Waste Recycle System 4/18/09 11-38. Flow Diagram of Liquid Waste Recycle System Attachmnent I Page 48 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/24/06 11-39. Flow Diagram of Liquid Waste Recycle System 10/24/04 11-40. Flow Diagram of Liquid Waste Recycle System 4/18/09 11-41. Flow Diagram of Liquid Waste Recycle System 4/18/09 11-42. Flow Diagram of Liquid Waste Recycle System 11/15/07 11-43. Flow Diagram of Liquid Waste Recycle System 10/22/01 11-44. Flow Diagram of Waste Gas System Chapter 12 Figures 10/1/91 12-1. Containment and Reactor Building - Unit 1 Elevation 523 + 11 10/1/91 12-2. Containment and Reactor Building - Unit 1 Elevation 552 + 0 10/1/91 12-3. Containment and Reactor Building - Unit 1 Elevation 565 + 3 10/1/91 12-4. Containment and Reactor Building - Unit 1 Elevation 594 + 10 3/4 10/1/91 12-5. Containment and Reactor Building - Unit 1 at Operating Floor Elevation 605 + 10 10/1/91 12-6. Containment and Reactor Building - Unit 1 Elevation 652 + 7 1/2 10/1/91 12-7. Containment and Reactor Building - Unit 1 Elevation 669 + 5 10/1/91 12-8. Containment and Reactor Building Sections 10/1/91 12-9. Auxiliary Building Unit 1 and 2 Elevation 522 + 0 10/1/91 12-10. Auxiliary Building Unit 1 and 2 Elevation 522 + 0 10/1/91 12-11. Auxiliary Building Unit 1 and 2 Elevation 543 + 0 10/1/91 12-12. Auxiliary Building Unit I and 2 Elevation 543 + 0 10/1/91 12-13. Auxiliary Building Unit 1 and 2 Elevation 543 + 0 10/1/91 12-14. Auxiliary Building Unit 1 and 2 Auxiliary Feedwater Pump Room 10/1/91 12-15. Auxiliary Building Elevation 560 + 0 10/1/91 12-16. Auxiliary Building Elevation 560 + 0 10/1/91 12-17. Auxiliary Building Elevation 560 + 0 10/1/91 12-18. Auxiliary Building Elevation 554 + 0, Battery Room 10/1/91 12-19. Auxiliary Building Elevation 560 + 0, Switchgear Room 10/1/91 12-20. Auxiliary Building Units I and 2 Elevation 577 + 0 10/1/91 12-21. Auxiliary Building Elevation 577 + 0 10/1/91 12-22. Auxiliary Building Units 1 and 2 Elevation 577 + 0 10/1/91 12-23. Auxiliary Building Elevation 574 + 0, Cable Room 10/1/91 12-24. Auxiliary Building Elevation 577 + 0, Switchgear Room 10/1/91 12-25. Auxiliary Building Elevation 594 + 0 10/1/91 12-26. Auxiliary Building Elevation 594 + 0 10/1/91 12-27. Auxiliary Building Elevation 594 + 0 10/1/91 12-28. Auxiliary Building Elevation 594 + 0, Cable Room 10/1/91 12-29. Primary Shield Neutron Flux Distribution 4/24/06 12-30. Typical Nuclear Safety Related Air Clean-Up System Chapter 13 Figures 4/18/09 13-1. Duke Power Corporate Organization 4/24/06 13-2. Power Generation Group Organization 4/18/09 13-3. Nuclear Generation Organization 10/24/04 13-4. Typical Nuclear Site Organization 11/30/95 13-5. Deleted Per 1995 Update 10/1/91 13-6. "At the Controls" Definition Attachment I Page 49 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) Chapter 14 Figures 10/22/01 14-1. Major Testing Milestone Schedule 10/22/01 14-2. Testing Following Initial Fuel Loading (Part 1 of 2) 10/22/01 14-2. Testing Following Initial Fuel Loading (Part 2 of 2) Chapter 15 Figures 10/1/92 15-1. Illustration of Overtemperature and Overpower A T Protection 5/2/97 15-2. Deleted per 1997 Update 5/2/97 15-3. Deleted per 1997 Update 4/8/00 15-4. Deleted per 2000 Update 4/8/00 15-5. Deleted per 2000 Update 4/8/00 15-6. Deleted per 2000 Update 4/24/06 15-7. (Part I of 3) Excessive Increase in Feedwater Flow 4/24/06 15-7. (Part 2 of 3) Excessive Increase in Feedwater Flow 4/24/06 15-7. (Part 3 of 3) Excessive Increase in Feedwater Flow 4/24/06 15-8. (Part 1 of 3) Excessive Increase in Feedwater Flow 4/24/06 15-8. (Part 2 of 3) Excessive Increase in Feedwater Flow 4/24/06 15-8. (Part 3 of 3) Excessive Increase in Feedwater Flow 4/8/00 15-9. Increase in Steam Flow 4/8/00 15-10. Increase in Steam Flow 4/8/00 15-11. Increase in Steam Flow 4/8/00 15-12. Increase in Steam Flow 4/24/06 15-13. Deleted per 2006 Update 5/2/97 15-14. Deleted per 1997 Update 5/2/97 15-15. Deleted per 1997 Update 5/2/97 15-16. Deleted per 1997 Update 4/18/09 15-17. Reactivity versus Temperature 4/18/09 15-18. (Part 1 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-18. (Part 2 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-18. (Part 3 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-18. (Part 4 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-19. (Part I of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-19. (Part 2 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-19. (Part 3 of 4) Failure of a Steam Generator Safety or Dump Valve 4/18/09 15-19. (Part 4 of 4) Failure of a Steam Generator Safety or Dump Valve 5/2/97 15-20. Deleted per 1997 Update 4/24/06 15-21. Steamline Break, Offsite Power Maintained 4/24/06 15-22. Steamline Break, Offsite Power Maintained 4/24/06 15-23. Steamline Break, Offsite Power Maintained 4/24/06 15-24. Steamline Break, Offsite Power Maintained 4/24/06 15-25. Steamline Break, Offsite Power Maintained 4/24/06 15-26. Steamline Break, Offsite Power Maintained 4/24/06 15-27. Turbine Trip, Maximum Secondary Pressure Case 4/24/06 15-28. Turbine Trip, Maximum Secondary Pressure Case 4/24/06 15-29. Turbine Trip, Maximum Secondary Pressure Case 4/24/06 15-30. Turbine Trip, Maximum Secondary Pressure Case 4/24/06 15-31. Turbine Trip, Maximum Secondary Pressure Case 4/24/06 15-32. Turbine Trip, Maximum Secondary Pressure Case 5/2/97 15-33. Feedwater System Pipe Break - Unit 2 5/2/97 15-34. Feedwater System Pipe Break - Unit 2 4/8/00 15-35. Deleted per 2000 Update Attachment I Page 50 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/24/06 15-36. Loss of Offsite Power 4/24/06 15-37. Loss of Offsite Power 4/24/06 15-38. Loss of Offsite Power 4/24/06 15-39. Loss of Offsite Power 4/24/06 15-40. Loss of Offsite Power 4/24/06 15-41. Part 1 of 2, Loss of Normal Feedwater 4/24/06 15-41. Part 2 of 2, Unit 1 Loss of Normal Feedwater Long - Term Core Cooling Analysis 4/24/06 15-42. Part 1 of 2, Unit 1 Loss of Normal Feedwater Long Term Core Cooling Analysis 4/24/06 15-42. Part 2 of 2, Unit 1 Loss of Normal Feedwater Long Term Core Cooling Analysis 4/24/06 15-43. Unit 1 Loss of Normal Feedwater Long - Term Core Cooling Analysis 5/2/97 15-44. Deleted per 1997 Update 5/2/97 15-45. Feedwater System Pipe Break - Unit 2 5/2/97 15-46. Feedwater System Pipe Break - Unit 2 5/2/97 15-47. Feedwater System Pipe Break - Unit 2 5/2/97 15-48. Feedwater System Pipe Break - Unit 2 5/2/97 15-49. Feedwater System Pipe Break - Unit 2 4/24/06 15-50. Deleted per 2006 Update 4/24/06 15-51. Deleted per 2006 Update 10/1/92 15-52. Deleted Per 1992 Update 10/1/92 15-53. Deleted Per 1992 Update 10/1/91 15-54. Reserved for Future Use 4/8/00 15-55. Partial Loss of Forced Reactor Coolant Flow 4/8/00 15-56. Partial Loss of Forced Reactor Coolant Flow 4/8/00 15-57. Partial Loss of Forced Reactor Coolant Flow 4/8/00 15-58. Partial Loss of Forced Reactor Coolant Flow 4/24/06 15-59. Deleted per 2006 Update 10/24/04 15-60. Complete Loss of Forced Reactor Coolant Flow 10/24/04 15-61. Complete Loss of Forced Reactor Coolant Flow 10/24/04 15-62. Complete Loss of Forced Reactor Coolant Flow 10/24/04 15-63. Complete Loss of Forced Reactor Coolant Flow 10/24/04 15-64. Complete Loss of Forced Reactor Coolant Flow 4/24/06 15-65. Deleted per 2006 Update 10/24/04 15-66. Locked Rotor, Offsite Power Lost 4/24/06 15-67. Bank Withdrawal at HZP 4/24/06 15-68. Bank Withdrawal at HZP 4/24/06 15-69. Bank Withdrawal at HZP 4/24/06 15-70. Bank Withdrawal at HZP 4/24/06 15-71. Bank Withdrawal at HZP 4/24/06 15-72. Bank Withdrawal at HZP 4/24/06 15-73. Uncontrolled RCCA Bank Withdrawal from 10% Power 4/24/06 15-74. Uncontrolled RCCA Bank Withdrawal from 10% Power 4/24/06 15-75. Uncontrolled RCCA Bank Withdrawal from 10% Power 4/24/06 15-76. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/24/04 15-77. Deleted Per 2004 Update 10/24/04 15-78. Deleted Per 2004 Update 10/24/04 15-79. Deleted Per 2004 Update 4/8/00 15-80. Single RCCA Withdrawal 10/1/92 15-81. Deleted per 1992 Update 4/24/06 15-82. Startup of a Reactor Coolant Pump at an Incorrect Temperature 4/24/06 15-83. Startup of a Reactor Coolant Pump at an Incorrect Temperature Attachment I Page 51 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/24/06 15-84. Startup of a Reactor Coolant Pump at an Incorrect Temperature 4/24/06 15-85. Startup of a Reactor Coolant Pump at an Incorrect Temperature 4/24/06 15-86. Startup of a Reactor Coolant Pump at an Incorrect Temperature 10/1/91 15-87. Interchange Between Region 1 and Region 3 Assembly 10/1/91 15-88. Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rods Being Retained by the Region 2 Assembly 10/1/91 15-89. Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rod Being Transferred to the Region 1 Assembly 10/1/91 15-90. Enrichment Error: A Region 2 Assembly Loaded into the Core Central Position 10/1/91 15-91 Loading a Region 2 Assembly into a Region 1 Position Near Core Periphery 10/1/92 15-92. Single RCCA Withdrawal 10/1/92 15-93. Single RCCA Withdrawal 10/1/92 15-94. Single RCCA Withdrawal 10/1/92 15-95. Dropped Rod Accident 10/1/92 15-96. Deleted per 1992 Update 11/30/95 15-97. Deleted per 1995 Update 11/30/95 15-98. Deleted Per 1995 Update 11/30/95 15-99. Deleted Per 1995 Update 4/24/06 15-100. Inadvertent Opening of a Pressurizer 'Safety Valve 4/24/06 15-101. (Part 1 of 2) Inadvertent Opening of a Pressurizer Safety Valve 4/24/06 15-101. (Part 2 of 2) Inadvertent Opening of a Pressurizer Safety Valve 5/2/97 15-102. Deleted per 1997 Update 4/8/00 15-103. Steam Generator Tube Rupture 4/8/00 15-104. Steam Generator Tube Rupture 4/8/00 15-105. Steam Generator Tube Rupture 4/8/00 15-106. Steam Generator Tube Rupture 4/8/00 15-107. Steam Generator Tube Rupture 4/8/00 15-108. Steam Generator Tube Rupture 10/22/01 15-109 Sequence of Events for Large Break Loss-of-Coolant Analysis (Deleted Per 2001 Update) 11/30/95 15-110. Deleted Per 1995 Update 10/22/01 15-111. Code Interface Description for Large Break Model (Deleted Per 2001 Update) 11/30/95 15-112. Deleted Per 1995 Update 11/30/95 15-113. Deleted Per 1995 Update 11/30/95 15-114. Deleted Per 1995 Update 11/30/95 15-115. Deleted Per 1995 Update 11/30/95 15-116. Deleted Per 1995 Update 11/30/95 15-117. Deleted Per 1994 Update 11/30/95 15-118. Deleted Per 1994 Update 11/30/95 15-119. Deleted Per 1994 Update 11/30/95 15-120. Deleted Per 1994 Update 11/30/95 15-121. Deleted Per 1994 Update 11/30/95 15-122. Deleted Per 1994 Update 11/30/95 15-123. Deleted Per 1994 Update 10/1/94 15-124. Deleted Per 1994 Update 10/1/94 15-125. Deleted Per 1994 Update 10/1/94 15-126. Deleted Per 1994 Update 10/1/94 15-127. Deleted Per 1994 Update 10/1/94 15-128. Deleted Per 1994 Update 10/1/94 15-129. Deleted Per 1994 Update 10/1/94 15-130. Deleted Per 1994 Update Page 52 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/1/94 15-131. Deleted Per 1994 Update 10/1/94 15-132. Deleted Per 1994 Update 10/1/94 15-133. Deleted Per 1994 Update 10/1/94 15-134. Deleted Per 1994 Update 10/1/94 15-135. Deleted Per 1994 Update 10/1/94 15-136. Deleted Per 1994 Update 10/1/94 15-137. Deleted Per 1994 Update 10/1/94 15-138. Deleted Per 1994 Update 10/1/94 15-139. Deleted Per 1994 Update 10/1/94 15-140. Deleted Per 1994 Update 10/1/94 15-141. Deleted Per 1994 Update 10/1/94 15-142. Deleted Per 1994 Update 10/1/94 15-143. Deleted Per 1994 Update 10/1/94 15-144. Deleted Per 1994 Update 10/1/94 15-145. Deleted Per 1994 Update 10/1/94 15-146. Deleted Per 1994 Update 10/1/94 15-147. Deleted Per 1994 Update 10/1/94 15-148. Deleted Per 1994 Update 10/1/94 15-149. Deleted Per 1994 Update 10/1/94 15-150. Deleted Per 1994 Update 10/1/94 15-151. Deleted Per 1994 Update 10/1/94 15-152. Deleted Per 1994 Update 10/1/94 15-153. Deleted Per 1994 Update 10/22/01 15-154. Deleted per 2000 Update 11/30/95 15-155. Deleted Per 1995 Update 10/22/01 15-156. Deleted per 2000 Update 10/22/01 15-157. Deleted per 2000 Update 10/22/01 15-158. Deleted per 2000 Update 10/22/01 15-159. Deleted per 2000 Update 10/22/01 15-160. Deleted per 2000 Update 10/22/01 15-161. Deleted per 2000 Update 10/22/01 15-162. Deleted per 2000 Update 10/22/01 15-163. Deleted per 2000 Update 4/8/00 15-164. Deleted per 2000 Update 4/8/00 15-165. Deleted per 2000 Update 4/8/00 15-166. Deleted per 2000 Update 4/8/00 15-167. Deleted per 2000 Update 4/8/00 15-168. Deleted per 2000 Update 10/22/01 15-169. B&W Large Break Analysis Code Interface (Deleted per 2001 Update) 4/8/00 15-170. Deleted per 2000 Update 4/8/00 15-171. Deleted per 2000 Update 4/8/00 15-172. Deleted per 2000 Update 4/8/00 15-173. Deleted per 2000 Update 4/8/00 15-174. Deleted per 2000 Update 4/8/00 15-175. Deleted per 2000 Update 4/8/00 15-176. Deleted per 2000 Update 4/8/00 15-177. Deleted per 2000 Update 4/8/00 15-178. Deleted per 2000 Update 4/8/00 15-179. Deleted per 2000 Update 4/8/00 15-180. Deleted per 2000 Update 4/8/00 15-181. Deleted per 2000 Update 11/30/95 15-182. Deleted Per 1995 Update 11/30/95 15-183. Deleted Per 1995 Update 11/30/95 15-184. Deleted Per 1995 Update Attachment I Page 53 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 11/30/95 15-185. Deleted Per 1995 Update 11/30/95 15-186. Deleted Per 1995 Update 11/30/95 15-187. Deleted Per 1995 Update 10/22/01 15-188. Licensing Summary of FTI LBLOCA Methods Topical Reports (Deleted Per 2001 Update) 10/22/01 15-189. RELAP5 Large Break LOCA Loop Noding (Deleted Per 2001 Update) 10/22/01 15-190. RELAP5/BEACH Large Break LOCA Reactor Vessel Noding (Deleted Per 2001 Update) 10/22/01 15-191. REFLOD3B Large Break LOCA Model (Deleted Per 2001 Update) 10/24/04 15-192. Locked Rotor - Offsite Power Lost 10/24/04 15-193. Locked Rotor - Offsite Power Lost 10/24/04 15-194. Locked Rotor Offsite - Power Lost 4/8/00 15-195. Locked Rotor Offsite - Power Lost 10/24/04 15-196. Locked Rotor Offsite - Power Lost 4/8/00 15-197. Dropped Rod Accident 4/8/00 15-198. Dropped Rod Accident 4/8/00 15-199. Dropped Rod Accident 4/8/00 15-200. Dropped Rod Accident 4/8/00 15-201. Rod Ejection Accident (BOC, HFP) 4/8/00 15-202. Rod Ejection Accident (EOC, HFP) 4/24/06 15-203. Bank Withdrawal at HZP - Peak RCS Pressure 4/24/06 15-204. Uncontrolled RCCA Bank Withdrawal from 12% Power 4/24/06 15-205. Steamline Break, Offsite Power Maintained 4/24/06 15-206. Steamline Break, Offsite Power Maintained 4/24/06 15-207. Steamline Break, Offsite Power Maintained 4/24/06 15-208. Steamline Break, Offsite Power Maintained 4/24/06 15-209. Steamline Break, Offsite Power Maintained 4/24/06 15-210. Steamline Break, Offsite Power Lost 4/24/06 15-211. Steamline Break, Offsite Power Lost 4/24/06 15-212. Steamline Break, Offsite Power Lost 4/24/06 15-213. Steamline Break, Offsite Power Lost 4/24/06 15-214. Steamline Break, Offsite Power Lost 4/24/06 15-215. Steamline Break, Offsite Power Lost 4/24/06 15-216. Steamline Break, Offsite Power Lost 4/24/06 15-217. Steamline Break, Offsite Power Lost 4/24/06 15-218. Steamline Break, Offsite Power Lost 4/24/06 15-219. Steamline Break, Offsite Power Lost 4/24/06 15-220. Steamline Break, Offsite Power Lost 4/8/00 15-221. Deleted per 1997 Update 4/8/60 15-222. Feedwater System Pipe Break - Unit 1 4/8/00 15-223. Feedwater System Pipe Break - Unit 1 4/8/00 15-224. Feedwater System Pipe Break - Unit 1 4/8/00 15-225. Feedwater System Pipe Break - Unit 1 4/8/00 15-226. Feedwater System Pipe Break - Unit 1 4/8/00 15-227. Feedwater System Pipe Break - Unit 1 4/8/00 15-228. Feedwater System Pipe Break - Unit 1 4/8/00 15-229. Steam Generator Tube Rupture 10/22/01 15-230. Licensing Summary of FTI SBLOCA Methods Topical Reports (Deleted Per 2001 Update) 10/22/01 15-231. RELAP5 Small Break LOCA Loop Noding (Deleted Per 2001 Update) 10/22/01 15-232. RELAP5 Small Break LOCA Reactor Vessel Noding (Deleted Per 2001 Update) 10/22/01 15-233. Catawba-1 LBLOCA, 9.7 ft Peak, Reflooding Rate - Core Entrance Location (Deleted Per 2001 Update) Attachment I Page 54 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 10/22/01 15-234. Catawba- 1 LBLOCA, 9.7 ft Peak, Hot Channel Quench Front and Collapsed Liquid Level (Deleted Per 2001 Update) 10/22/01 15-235. Catawba - 1 LBLOCA, 9.7 ft Peak, Cladding Temperature (Deleted Per 2001 Update) 10/22/01 15-236. Catawba - I LBLOCA, 9.7 ft Peak, Hot Channel Local Oxidation (Deleted Per 2001 Update) 10/22/01 15-237. Catawba - 1 LBLOCA, 9.7 ft Peak, Downcomer Water Level (Deleted Per 2001 Update) 10/22/01 15-238. Catawba - 1 LBLOCA, 9.7 ft Peak, ECCS Flows (Deleted Per 2001 Update) 10/22/01 15-239. Catawba - 1 LBLOCA, 9.7 ft Peak, Hot Channel Fluid Temperature, 8.6 ft. Elevation (Deleted Per 2001 Update) 10/22/01 15-240. Catawba - 1 SBLOCA, 2.5 Inch Break, RCS Pressure (Deleted Per 2001 Update) 10/22/01 15-241. Catawba - 1 SBLOCA, 2.5 Inch Break, Break Flow Rate (Deleted Per 2001 Update) 10/22/01 15-242. Catawba - 1 SBLOCA, 2.5 Inch Break, Hot Channel Froth and Collapsed Level (Deleted Per 2001 Update) 10/22/01 15-243. Catawba - I SBLOCA, 2.5 Inch Break, Cladding Temperature PCT Location (Deleted Per 2001 Update) 10/22/01 15-244. Catawba - 1 SBLOCA, 2.5 Inch Break, Vapor Temperature at PCT Location (Deleted Per 2001 Update) 10/22/01 15-245. Catawba - I SBLOCA, 3 Inch Break, RCA Pressure (Deleted Per 2001 Update) 10/22/01 15-246. Catawba - I SBLOCA, 3 Inch Break, Break Flow Rate (Deleted Per 2001 Update) 10/22/01 15-247. Catawba - I SBLOCA, 3 Inch Break, Hot Channel Froth and Collapsed Level (Deleted Per 2001 Update) 10/22/01 15-248. Catawba - I SBLOCA, 3 Inch Break, Cladding Temperature PCT Location (Deleted Per 2001 Update) 10/22/01 15-249. Catawba - 1 SBLOCA, 3 Inch Break, Vapor Temperature at PCT Location (Deleted Per 2001 Update) 10/22/01 15-250. Catawba - 1 Power Distribution Assumed for Small Break LOCA Analyses (Deleted Per 2001 Update) 4/8/00 15-251. Deleted per 2000 Update 4/8/00 15-252. Deleted per 2000 Update 4/8/00 15-253. Deleted per 2000 Update 4/8/00 15-254. RCCA Position Versus Time to Dashpot 5/2/97 15-255. Normalized Rod Worth Versus Percent Inserted 4/8/00 15-256. Normalized RCCA Bank Reactivity Worth Versus Normalized Drop Time 4/18/09 15-257. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-258. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-259. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-260. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-261. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-262. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 4/18/09 15-263. Unit 2 Loss of Normal Feedwater Short-Term Core Cooling Analysis 03/27/03 15-264. Unit 2 Loss of Normal Feedwater Long-Term Core Cooling Analysis 03/27/03 15-265. Unit 2 Loss of Normal Feedwater Long-Term Core Cooling Analysis 03/27/03 15-266. Unit 2 Loss of Normal Feedwater Long-Term Core Cooling Analysis 03/27/03 15-267. Unit 2 Loss of Normal Feedwater Long-Term Core Cooling Analysis 03/27/03 15-268. Unit 2 Loss of Normal Feedwater Long-Term Core Cooling Analysis 10/24/04 15-269. Partial Loss of Forced Reactor Coolant Flow 4/24/06 15-270. Complete Loss of Forced Reactor Coolant Flow Attachment I Page 55 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 4/8/00 15-271. Locked Rotor Offsite Power Maintained 4/8/00 15-272. Locked Rotor Offsite Power Maintained 4/8/00 15-273. Locked Rotor Offsite Power Maintained 4/8/00 15-274. Locked Rotor Offsite Power Maintained 10/24/04 15-275. Locked Rotor - Peak RCS Pressure 4/24/06 15-276. Deleted per 2006 Update 4/24/06 15-277. Uncontrolled RCCA Bank Withdrawal from 10% Power-Westinghouse Fuel 4/24/06 15-278. Uncontrolled RCCA Bank Withdrawal from 50% Power-Westinghouse Fuel 4/24/06 15-279. Uncontrolled RCCA Bank Withdrawal from 100% Power-Westinghouse Fuel 10/24/04 15-280. Deleted Per 2004 Update 4/24/06 15-281. Uncontrolled RCCA Bank Withdrawal from 98% Power- Westinghouse Fuel 10/22/01 15-282. Power Distribution Assumed for Small Break LOCA Analyses 11/15/07 15-283. Catawba-2 SBLOCA 4-Inch Pressurizer Pressure 11/15/07 15-284. Catawba-2 SBLOCA 4-Inch Core Mixture Level 11/15/07 15-285. Catawba-2 SBLOCA 4-Inch Core Exit Vapor Temperature 11/15/07 15-286. Catawba-2 SBLOCA 4-Inch Break Vapor Flow 11/15/07 15-287. Catawba-2 SBLOCA 4-Inch Break Liquid Flow 11/15/07 15-288. Catawba-2 SBLOCA 4-Inch Peak Clad Temperature 11/15/07 15-289. Catawba-2 SBLOCA 4-Inch Hot Spot Fluid Temperature 11/15/07 15-290. Catawba-2 SBLOCA 2-Inch Pressurizer Pressure 11/15/07 15-291. Catawba-2 SBLOCA 2-Inch Core Mixture Level 11/15/07 15-292. Catawba-2 SBLOCA 2-Inch Core Exit Vapor Temperature 11/15/07 15-293. Catawba-2 SBLOCA 2-Inch Peak Clad Temperature 11/15/07 15-294. Catawba-2 SBLOCA 3-Inch Pressurizer Pressure 11/15/07 15-295. Catawba-2 SBLOCA 3-Inch Core Mixture Level 11/15/07 15-296. Catawba-2 SBLOCA 3-Inch Core Exit Vapor Temperature 11/15/07 15-297. Catawba-2 SBLOCA 3-Inch Peak Clad Temperature 11/15/07 15-298. Catawba-2 SBLOCA 6-Inch Pressurizer Pressure 11/15/07 15-299. Catawba-2 SBLOCA 6-Inch Core Mixture Level 11/15/07 15-300. Catawba-2 SBLOCA 6-Inch Core Exit Vapor Temperature 11/15/07 15-301. Catawba-2 SBLOCA 6-Inch Peak Clad Temperature 10/22/01 15-302. Lower Bound Containment Pressure used for Best Estimate Large Break LOCA 10/22/01 15-303. LBLOCA Peak Clad Temperature (Reference Transient) 10/22/01 15-304. LBLOCA Liquid Mass Flowrate at Inlet to Hot Assembly 10/22/01 15-305. LBLOCA Vapor Mass Flowrate at Blowdown PCT Location 10/22/01 15-306. LBLOCA Entrained Liquid Mass Flowrate at Blowdown PCT Location 10/22/01 15-307. LBLOCA Accumulator Discharge Flowrate 10/22/01 15-308. LBLOCA Pumped Safety Injection 10/22/01 15-309. LBLOCA Collapsed Liquid Level in the Lower Plenum 10/22/01 15-310. LBLOCA Collapsed Liquid Level in Hot Assembly 10/22/01 15-311. LBLOCA Collapsed Liquid Level in Downcomer 10/22/01 15-312. Best-Estimate LBLOCA PBOT/PMID Operating Limits 10/22/01 15-313. LBLOCA Axial Power Distribution for Reference Transient 11/15/07. 15-314. McGuire Unit 1 4-Inch Pressurizer Pressure 11/15/07 15-315. McGuire Unit 1 4-Inch Core Mixture Level 11/15/07 15-316. McGuire Unit 1 4-Inch Core Exit Vapor Temperature 11/15/07 15-317. McGuire Unit 1 4-Inch Break Vapor Flow 11/15/07 15-318. McGuire Unit 1 4-Inch Break Liquid Flow 11/15/07 15-319. McGuire Unit 1 4-Inch Peak Clad Temperature Attachment I Page 56 of 57

Catawba UFSAR List of Effective Dates for Figures Revised to Include the 2009 Update (Revision 14) 11/15/07 15-320. McGuire Unit 1 4-Inch Hot Spot Fluid Temperature 11/15/07 15-32 1. McGuire Unit 1 3-Inch Pressurizer Pressure 11/15/07 15-322. McGuire Unit 1 3-Inch Core Mixture Level 11/15/07 15-323. McGuire Unit 1 3-Inch Peak Clad Temperature 11/15/07 15-324. McGuire Unit 1 6-Inch Pressurizer Pressure 11/15/07 15-325. McGuire Unit 1 6-Inch Core Mixture Level 11/15/07 15-326. McGuire Unit 1 6-Inch Peak Clad Temperature 11/15/07 5-327. Catawba Unit 1 4-Inch Pressurizer Pressure 11/15/07 15-328. Catawba Unit 1 4-Inch Core Mixture Level 11/15/07 15-329. Catawba Unit 1 4-Inch Peak Clad Temperature Chapter 16 Figures No figures Chapter 17 Figures No Figures Chapter 18 Figures No Figures Attachment I Page 57 of 57

ATTACHMENT 2

SUMMARY

OF INFORMATION REMOVED FROM REVISION 14 OF THE UFSAR

Catawba UFSAR 2009 Update List of Items Removed UFSAR Figure 2-33: Plant modification CN-50500 revised the yard area grade and the PMP flood analysis resulting in this table being deleted. UFSAR Table 5-40: Note 5 of Table 5-40 was deleted as the result of the review completed by the Hukari Completeness Review Team. UFSAR Section 7.3.1.2.2: Item 2c of this section was deleted as this variable (NC Syste'm Tavg) is not monitored for automatic initiation of SI. UFSAR Section 7.3.2.2.5: Deleted "Time Required for Testing" paragraph. Tech Spec contains the required test times and out of service timnes. UFSAR Section 7.3.2.2.5: Excessive detail information was deleted concerning what is included in typical maintenance procedures. UFSAR Section 8.3.1.1.2.1: Removed details of Load Sequencer from this section (4160 VAC Essential Power System) and relocated to 8.3.1.1.3.6 (Load Shedding and Sequencing). UFSAR Table 10-12: Table 10-12, Maximum Allowance Blowdown Flowrate, is unnecessary as the Unit I blowdown is no longer a function of load. Unit I and 2 blowdown rates relocated to UFSAR Section 10.4.8.2. UFSAR Section 13.1.3.1: Deleted Regulatory Compliance Manager and attendant qualifications as this job description is not included in ANSI N18.1, which is the standard used to describe job qualifications. UFSAR Section 15.0: CASMO-3 and SIMULATE-3P are obsolete and no longer used. References to these programs have been deleted. UFSAR Section 18.2.1.3: Removed paragraph discussing circumferential cracking as this is no longer applicable. Page I of Il}}