ML20205R389
| ML20205R389 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/13/1999 |
| From: | Gordon Peterson DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9904220319 | |
| Download: ML20205R389 (64) | |
Text
D (7
Duke Energy Corporation
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h Catawba Nuclear Station 4800 Concord Road York, SC 29745 Gary R. Peterson (803) #314251 mm Vice l>esident I000) #3I'30 "
April 13, 1999 1
U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001
]
i
Subject:
Duke Energy Corporation Catawba Nuclear Station Docket Nos. 50-413 and 50-414 List of Effective Dates for Tables and Figures of the 1998 UFSAR Update Enclosed please find the origincl and ten copies of the List of Effective Dates for Tables and Figures for the 1998 Update of the Final Safety Analysis Report (UFSTR) for Catawba Nuclear Station.
The 1998 Update of the Final Safety Analysis Report (UFSAR) war transmitted separately on April 8, 1999.
If there are any questions concerning this list, please contact J.W. Glenn at (803) 831-3051.
2 Sincerely,
-l /-
G.
R.
Peterson Attachment
)OJbb 9904220319 990413 T
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~U.S.
Nuclear Regulatory Commission Document Control Desk.
-April 73, 1999 Page'2 xc:
L. A.
Reyes, Regional, Administrator USNRC, Region II P.S.
Tam, Project Manager USNRC, ONRR D. J.
Roberts Senior Resident Inspector (CNS) i i
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3 r
Catawba UFSAR List of Effective Dates for Tables Revised to include the 1998 Update (Revision 7)
Chapter 1 Tables 10/1/91 1-1. Shared Facilities and Equipment - page 1 10/1/91 1-1. Shared Facilities and Equipment - page 2 11/30/95 1-1. Shared Facilities and Equipment page 3 5/2/97 1-2. Design Comparison-page 1 5/2/97 1-2. Design Comparison-page 2 10/1/91 1-2. Design Comparison-page 5 10/1/91 1-2. Design Comparison-page 4 10/1/91
- 13. Significant Design Changes 10/24/98 l-4. Piping and Instrumentation Diagrams 5/2/97 1-5. Information Provided on the Subcooling Monitor - page 1 10/1/91 1-5. Information Provided on the Subcooling Monitor - page 2 10/1/91 1-6 Reactor Vessel LevelInstrumentation System 10/1/91 1-7. Criteria for Auxiliary Feedwater System Design Basis 1
Conditions 10/1/91 1-8. Summary of Assumptions Used in AFWs Design Verification Analyses 10/1/91 1-9. Summary of Sensible Heat Source 10/1/91 1-10. Regulatory Guide 1.97, Rev. 2 Review 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page i i
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 2 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 3 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 4 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 5 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 6 5/2/97 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 7 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 8 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review page 9 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 10 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 11 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 12 10/1/93 1-11, Regulatory Guide 1.97, Rev. 2 Review - page 13 10/1/93 1 11. Regulatory Guide 1.97, Rev. 2 Review - page 14 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 15 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 16 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 17 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 18 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 19 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 20 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 21 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 22 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 23 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 24 10/1/93 1 11. Regulatory Guide 1.97, Rev. 2 Review - page 25 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review page 26 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 27 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 28 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 29 10/1/93 1-11 Regulatory Guide 1.97 Rev. 2 Review - page 30 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 31 Page1 10/24/98
l 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 32 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 33 5/2/97 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 34 10/1/93 1-11. Regulatory Guide 1.97 Rev. 2 Review - page 35 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 36 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 37 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 38 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 39 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 40 10/1/93 1-) ! Regulatory Guide 1.97, Rev. 2 Review - page 41 l
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 42 i
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 43 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 4.,
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Revie,v - page 45 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 46 l
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 47 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 48 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 49 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 50 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 51 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 52 10/1/94 1-11. Regulatory Guide 1.97, Rev. 2 Review-page 53 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 54
)
10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 55 10/1/93 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 56 5/2/97 1-11. Regulatory Guide 1.97, Rev. 2 Review - page 57 10/24/98 1-12. NRC Generic Letters and IE Bulletins Response Bases (Note 1)
Chapter 2 Tables 10/1/91 2-1.1977 Population 0-5 Miles (0-8 km) 10/1/91 2-2.1970 Population Distribution 0-10 Miles (0-16.1 km) 10/1/91 2-3. 1980 Projected Population Distribution 0- 10 Miles (0-16.1 km) 10/1/91 2-4. 1981 Projected Population Distribution (Initial Expected Year of Plant Start-up) 0-10 Miles (0-16.1 km) 10/1/91 2-5.1990 Projected Population Distribution 0-10 Miles (0-16.1 km) 10/1/91 2-6. 2000 Projected Population Distribution 0-10 Miles (0-16.1 km) 10/1/91 2-7. 2010 Projected Population Distribution 0-10 Miles (0-16.1 km) 10/1/91 2-8. 2020 Projected Population Distribution 0-10 Miles (0-16.1 km) 10/1/91 2-9. 1970 Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-10. 1980 Projected Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-11. 1981 Projected Population Distribution (Initial Expected Year of Plant Start-up) 0-50 Miles (0-80.4 km) 10/1/91 2-12. 1990 Projected Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-13. 2000 Projected Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-14. 2010 Projected Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-15. 2020 Projected Population Distribution 0-50 Miles (0-80.4 km) 10/1/91 2-16. 1977 Seasonal Recreational Transient Popolation Page 2 10/24/98
10/1/91 2-17.1977 Average Daily Recreational Transient Population 10/1/91 2-18.1977 Daily Industrial Transient Population 10/1/91 2-19. Peak Day Transient Population 0-5 Miles (0-8 km) 10/1/91 2-20.1977 Transient Population Recreation Areas and Facilities 10/1/91 2-21.1977 Transient Population Industrial and Institutional 10/1/91 2-22. Description of Nearby and Significant Industries 10/1/91 2-23. Annual Aircraft Operations Douglas Municipal Airport 10/1/94 2-24. Aviatica Routes - Annual Usage 10/1/91 2-25. Hazardous Chemicals Received at Nearby Facilities 10/1/91 2-26. Hazardous Chemicals Shipped and Received by Nearby Industries 10/1/91 2-27. Tropical Cyclones Affecting the Site Area, 1964-1980 10/1/91 2-28. Tornado Occurrences 1956-1980 (21 Square Centered on Site) 10/1/91 2-29. Catawba Nuclear Station Vicinity Climatology 10/1/91 2-30. Catawba Nuclear Station Onsite Data January 1,1976 - December 31, j
1977 10/1/91 2-31. Structural Design Meteorological Data 10/1/91 2-32. Ultimate Heat Sink Meteorological Data Worst Cooling Periods 10/1/91 2-33. Ultimate Heat Sink Meteorological Data Highest Evaporation Periods 5/2/97 2-34. Catawba Semiannual Calibration Listing - Page 1 5/2/97 2 34. Catawba Semiannual Calibration Listing - Page 2 10/1/91 2-35, 1975 - 1977 Wind Occurrences (10 m) 10/1/91 2 36. Hourly Dilution Factors at the Exclusion Area Boundary for Each j
Sector 10/1/91 2 ~i7. Hourly Dilution Factors at the Low Population Zone Boundary for Selected Sectors 10/1/91 2-38. Cumulative Frequency Distribution at Integer Percentile Levels - 8 Hour Average 10/1/91 2-39. Cumulative Frequency Distribution at Integer Percentile Levels -
16 Hour Average 10/1/91 2-40. Cumulative Frequency Distribution at Integer Percentile Levels -
72 Hour Average 10/1/91 2-41. Cumulative Frequency Distribution at Integer Percentile Levels -
624 Hour Average 10/1/91 2-42. Annual Average X/Q Values to 50 Miles - Sector Average 10/1/91 2-43. Annual Average X/Q Values with Depletion to 50 Miles - Sector Average 10/1/91
%-44.1975 - 1977 Wind Occurrences (40 m) 10/1/91 2-45. Annual Average D/Q Values to 50 Miles - Sector Average 10/1/91 2-46. Catawba Nuclear Station Annual Average X/Q Values at intake Vents Control Room X/Q Values for Accident Conditions 10/1/91 2-47. Dilution Factors for Accident Releases 10/1/91 2-48. Catawba Nuclear Station Dilution Factors for Routine Releases -
Offsite 10/1/91 2-49. Relative Frequency Distribution 10/1/91 2-50. Charlotte, N. C. - Climatic Comparison 10/1/91 2-51. Dams on the Catawba River 10/1/91 2-52. Surface Water Intakes 10/1/92 2-53. Flood Peak Return Period 10/1/92 2-54. Deleted Per 1992 Update 10/1/91 2 55. Maximum Storms in the Southeast 10/1/91 2-56. Deleted Per 1990 Update 10/1/91 2-57. Deleted Per 1990 Update 10/1/91 2-58. Rainfall Subarca Coefficients Page 3 10/24/98
10/1/91 2-59. Parameters Used in Flood Routing 10/1/91 2-60. Storage And Discharge Values For Reservoirs For Rising Reservoir Condition 10/1/91 2-61. Maximum Reservoir Elevations Resulting From PMF 10/1/91 2-62. Reservoir Inflow, Outflow and Elevation for PMF i
10/1/91 2-63. Coincident Wind / Wave Activity 10/1/91 2-64. Maximum Reservoir Elevations Resulting From Seismic Dam Failures With SPF 10/1/91 2-65. Maximum Reservoir Elevations Resulting From Seismic Failure at Cowans Ford Dam With SPS 5/2/97 2-66. Standby Nuclear Service Water Pond 10/1/91 2-67. Low Flow into Lake Wylie j
10/1/91 2-68. Lake Wylie Minimum Surface Water Elevations
(
10/1/90 2-69. Summary of Residential Well Survey Data immediate Vicinity of Site No date available 2-70. Groundwater Intakes No date available 2-71. River Bank Groundwater intakes No date available 2-72. Rock Permeability Test Results No Gte available 2-73. Soil Permeability Test Results No date available 2-74. Summary of Pumping Test No.1 - Test Well A-85TW No date available 2-75. Summary of Pumping Test No. 2 - Test Well A-48TW No date available 2-76. Results of Physical and Chemical Tests on Groundwater No date available 2-77. Ion Exchange Capacity of Soils No date available 2-78. Groundwater Monitoring Program No date available 2-79. Observation Well Monitoring No date available 2-80. Geologic Time Scale No date available 2-81. Summary of Regional Tectonic Structures No date available 2-82. Summary Of Stress Measurements No date available 2 83. Site Geologic History As Related to Regional Geology No date available 2-84. Historic Earthquakes--Southeastern United States No date available 2-85. Earthquakes With Epicenters Located Within 50 Miles of the Catawba Site No date available 2-86. Historic Earthquakes Probably Felt At The Catawba Site No date available 2 87. Summary of Rock And Water Levels In The Test Borings No date available 2-88. Summary of Test Pits No date available 2-89. Laboratory Permeability Test Results Compacted Plant Area Residual Soils No date avaih ble 2-90. Summary of Significant Foundation Engineering Characteristics No date available 2-91. Summary of Significant Foundation Engineering Characteristics No date available 2-92. Summary of Significant Foundation Engineering Characteristics -
Seismic Design Criteria No date available 2-93. Soil and Partially Weathered Rock Permeability Constant Head Field Tests Standby Nuclear Service Water Pond Dam No date available 2-94. Summary of Design Static Shear Strength Parameters For Standby Nuclear Service Water Pond Dam No date available 2-95. Rock Permeability Constant Head Field Tests Standby Nuclear Service Water Pond Dam Foundation No date available 2-96. SNSW Pond Dam - Equipment Used During Dam Construction No date availabh 2-97. Safety Factors of SNSW Pond Dam Under Static Loading No date avai!able 2-98. Laboratory Cyclic Triaxial Tests No date available 2-99. Laboratory Cyclic Triaxial Tests No date available 2-100. Laboratory Cyclic Triaxial Tests Page 4 10/24/98
No date available 2-101. Safety Factors of SNSW Pond Dam Under Earthquake Loading, Pseudo-Dynamic and Newmark Analyses Section Through Borings All7 & All8 No date available 2-102. Soil Permeability Laboratory Test Results No date available 2-103. Soil Permeability Laboratory Test Results No date available 2-104. SNSW Pond Dam Filter Permeability Laboratory Test Results Chapter 3 Tables 10/1/91 3-1. Summary of Criteria - Structures 10/1/91 3-2. Summary of Criteria - Equipment 5/2/97 3-3. Summary of Codes and Standards for Components of Water-Cooled Nuclear P;wer Units 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 1 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 2 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 3 10/24/98 3-4. Summary of Criteria - Mechanical System Components - page 4 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 5 10/1/93 3-4. Summary of Criteria - Mechanical System Components - page 6 11/30/95 3-4. Summary of Criteria - Mechanical System Components - page 7 10/1/93 3-4. Summary of Criteria - Mechanical System Components - page 8 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 9 10/1/94 3-4. Summary of Criteria - Mechanical System Components - page 10 10/24/98 3-4. Summary of Criteria - Mechanical System Components - page 11 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 12 5/2/97 3-4. Summary of Criteria - Mechanical System Components - page 13 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 14 10/1/91 3-4. Summary of Criteria - Mechanical System Components - page 15 10/1/91 3-5. System Piping Classification 10/1/91 3-6. System Valve Classification 10/1/91 3-7. Equipment Generated Missiles Safety Related Structures Design Characteristics 10/1/91 3-8. Summary Of Control Rod Drive Mechanism Missile Analysis 10/1/91 3-9. Piping Temperature Element Assembly - Missile Characteristics 10/1/91 3-10. Characteristics Of Other Missiles Postulated Within Reactor Containment 10/1/91 3-11. Hypothetical Missile Data 43-inch Last Stage Bucket,1800-RPM Low Pressure Turbine 10/1/91 3-12. Turbine Missile Strike Probability High Trajectory Missiles 10/1/91 3-13. Turbine Missile Penetration and Damage Probabilities High Trajectory Missiles - page 1 11/30/95 3-13. Turbine Missile Penetration and Damage Probabilities High Trajectory Missiles - page 2 11/30/95 3-14. Turbine Missile Total Plant Damage Probability High Trajectory Missiles 10/1/91 3-15. Design Basis Tornado Generated Missiles 10/1/91 3-16. Design Basis Tornado Generated Missiles -Minimum Barrier Thickness 10/1/91 3-17. High-Energy Mechanical Piping Systems Analyzed for Consequences of Postulated Piping Breaks 10/1/91 3-18. Moderate-Energy Mechanical Piping Systems Analyzed for Consequences of Postulated Piping Breaks Page 5 10/24/98
l 10/1/91 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) 10/1/91 3-20. Postulated Break Locations For The Main Coolant loop 10/1/91 3-21. Stress Criteria For Reactor Containment Mechanical Penetrations (2)
Duke Class B 10/1/91 3-22. Stress Allowables for Design of Pipe Rupture Restraints 10/1/91 3-23. Deleted Per 1990 Update 5/2/97 3 24. Break Locations with Rigid Rupture Restraints to Negate Jet Impingement Effects 10/1/91 3-25. Summary of Modal Contributions to Total Forces for North South Earthquake 10/1/91 3-26. Comparison Of Response Spectrum And Time-History Responses 10/1/91 3-27. Comparison of two Dimensional Versus Three Dimensional Analysis 10/1/91 3-28. Static and Seismic Incremental Lateral Earth Pressures for Check of Substructure Walls Using Mononobe-Okabe Incremental Lateral Pressure 10/1/91 3-29. Scope Limits for Alternate Seismic Analysis 10/1/91 3-30. Seismic Instrumentation Implementation 10/1/91 3-31. Codes and Specifications for Design of Category 1 Structures 10/1/91 3 32. Load Combinations for Category I Structures 10/1/91 3-33. Concrete Mix Designs 10/1/91 3 34. Quality Control Tests for Aggregates 10/1/91 3-35. Comparison of Concrete Design Criteria 10/1/91 3-36. Shell Walt Design Forces and Reinforcement 10/1/91 3-37. Containment Vessel Loading Combinations 10/1/91 3-38. Containment Stress Limits 5/2/97 3-39. Containment Coatings (deleted per 1997 Update) 5/2197 3-40. Containment Materials 10/1/91 3-41. Containment Allowable Stress Intensities 10/1/91 3-42. Containment Stress Intensities 10/1/91 3-43. Containment Buckling Factors of Safety 10/1/91 3-44. Statistical Containment Material Properto Based on Mill Test Reports 10/1/91 3-45. Ultimate Containment Capacity Analysis Summary 10/1/91 3-46. Design Properties of Seals 10/1/91 3-47. Catawba Compartment Pressurization Analysis 10/1/91 3-48. Maximum Blowdown LOCA Load Resultants For The Containment Interior Structure 10/1/91 3-49. Crane Wall Design 10/1/91 3-50. Design Transients for ASME Code Class I Piping 10/1/91 3-51. Loading Combinations for ASME Class 1 Components and Supports 10/1/91 3-52. Allowable Stresses for ASME Section til Class I Components 10/1/91 3 53. Class I Valve Faulted Condition Criteria 10/1/91 3-54. Maximum Reactor Vessel Displacements at Reactor Vessel Centerline 10/1/91 3-55. Maximum Reactor Vessel Support Loads For Postulated Pipe Rupture Conditions 10/1/91 3-56. Computer Programs Used in Analysis 10/1/91 3-57. Computer Programs Used in Analysis 10/1/91 3-58. Computer Programs Used in Analysis
{
10/1/91 3-59. Computer Programs Used in Analysis 10/1/91 3-60. Computer Programs Used in Analysis j
Page 6 10/24/98
10/1/91 3-61. Computer Programs Used in Analysis 10/1/91 3-62. Computer Programs Used in Analysis 10/1/91 3-63. Computer Programs Used in Analysis 10/1/91 3-64. Computer Programs Used in Analysis 10/1/91 3-65. Computer Programs Used in Analysis 10/1/91 3-66. Computer Programs Used in Analysis 10/1/91 3-67. Computer Programs Used in Analysis 10!!/91 3-68. Computer Programs Used in Analysis 10/1/91 3-69. Computer Programs Used in Analysis 10/1/91 3-70. Computer Programs Used in Analysis 10/1/91 3-71. Computer Programs Used in Analysis 10/1/91 3-72. Computer Programs Used in Analysis 10/1/91 3-73. Computer Programs Used in Analysis 10/1/91 3-74. Computer Programs Used in Analysis 10/1/91 3-75. Computer Programs Used in Analysis 10/1/9!
3-76. Computer Programs Used in Analysis 10/1/91 3-77. Computer Programs Used in Analysis 10/1/91 3-78. Computer Programs Used in Analysis 10/1/91 3-79. Computer Programs Used in Analysis j
10/1/91 3-80. Computer Programs Used in Analysis 10/1/91 3-81. Computer Programs Used in Analysis 10/1/91 3-82. Computer Programs Used in Analysis 10/1/91 3-83. CRDM Moments - Head Adaptor Location t
10/1/91 3-84. Piping Systems included in Vibration Test Program 10/1/91 3-85. Piping Systems Included In Transient Vibration Test Program 10/1/91 3-86. Piping Systems Included In Thermal Expansion Test Program
}
10/1/91 3-87. Maximum Deflections A!! owed for Reactor Internal Support 1
Structures 10/1/91 3-88. Design Loading Combinations for ASME Code Class 2 and 3 Components and Supports 10/1/91 3-89. Design Loading Combinations for ASME Code Core Support i
Structures 10/1/91 3-90. Stress Criteria for Safety Related ASME Class 2 and Class 3 Tanks 10/1/91 3-91. Stress Criteria for Safety Related Class 2 Tanks 10/1/91 3-92. Stress Criteria for ASME Code Class 2 and Class 3 Inactive Pumps
!C/1/91 3-93. Design Criteria for Active Pumps 10/1/91 3-94. Stress Criteria for Safety Related ASME Code Class 2 and Class 3 Valves 10/1/91 3-95. Stress Criteria and Load Combination Requirements for Duke Class A Piping 10/1/91 3-96. Stress Criteria and Load Combination Requirements for Duke Class B, C, and F Piping 10/1/91 3-97. Stress Limits for Duke Safety Related Equipment and Valves 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. Loading Conditions, Load Combination, and Allowable Stresses for i
Supports, Restraints and Anchors for Duke Classes A, B, C and F(6) 10/1/91 3-102. Loading Conditions and Load Combination Requirements for Snubbers Duke Classes A, B, C, F 10/1/91 3-103. Active Pumps 10/1/94 3-lN. Active Valves - page 1 Page 7 10/24/98
7 10/1/94 3-104. Active Valves - page 2 10/1/94 3-104. Active Valves - page 3 10/164 3-104. Active Valves - page 4 i
10/1/94 3-104. Active Valves - page 5 10/164 3-104. Active Valves - page 6 10/1/94 3-IN. Active Valves - page 7 I
10/1/94 3-104. Active Valves - page 8 l
10/1/94 3-104. Active Valves page 9 i
10/1/94 3-104. Active Valves - page 10 10/1/94 3-104. Active Valves - page 11 10/1/94 3-104. Active Valves - page 12 10/1/94 3-104. Active Valves - page 13 i
10/1/94 3-104. Active Valves - page 14 10/1/94 3-104. Active Valves - page 15 10/1/94 3-104. Active Valves - page 16 10/1/94 3-104. Active Valves - page 17 10/1/94 3-104. Active Valves - page 18 10/1/94 3-104. Active Valves - page 19 10/184 3-104. Active Valves - page 20 10/1/94 3-104. Active Valves - page 21 10/184 3-104. Active Valves - page 22 10/1/94 3-104. Active Valves - page 23 5/2/97 3-104. Active Valves - page 24 10/24/98 3-104. Active Valves - page 25 5/2/97 3-104. Active Valves - page 26 5/2/97 3-104. Active Valves - page 27 10/24 S 8 3-104. Active Valves - page 28 10/1/94 3-104. Active Valves - page 29 10/184 3-104. Active Valves - page 30 5/2/97 3-104. Active Valves - page 31 5/2/97 3-104. Active Valves - page 32 5/2/97 3-104. Active Valves - page 33 5/287-3-104. Active Valves - page 34 5/267 3-104. Active Valves - page 35 5/2/97 3-104. Active Valves - page 36 5/267 3-lN. Active Valves - page 37 5/2/97 3-104. Active Valves - page 38 5/2/97 3104. Active Valves - page 39 5/2/97 3-104. Active Valves - page 40 5/2/91 3-104. Active Valves - page 41 5/2/97 3-104. Active Valves - page 42 11/3085 3-104. Active Valves - page 43 11/30/95 3-104. Active Valves - page 44 10/1/94 3-104. Active Valves - page 45 10/1/94 3-104. Active Valves - page 46 10/184 3104. Active Valves - page 47 l
10/1/94 3-104. Active Valves - page 48 10/1/94 3-104. Active Valves - page 49 10/1/94 3-lN. Active Valves - page 50 10/1/94 3-104. Active Valves - page 51 10/1/94 3-104. Active Valves - page 52 10/164 3-104. Active Valves - page 53 10/1/94 3-104. Active Valves-page 54 10/1/94 3-104. Active Valves - page 55 10/1/94 3-104. Active Valves - page 56 Page 8 -
10/24/98
10/184 3-104. Active Valves - page 57 10/1/94 3-104. Active Valves - page 58 10/1/94 3-IN. Active Valves page 59 10/1/94 3-IN. Active Valves - page 60 10/1/94 3-lM. Active Valves - page 61 10/1/94 3104. Active Valves - page 62 10/1/94 3-104. Active Valves page 63 10/1/94 3-104. Active Valves - page 64 10/1/94 3-104. Active Valves page 65 10/1/94 3-104. Active Valves - page 66 10/1/94 3-104. Active Valves - page 67 10/24/98 3-104. Active Valves - page 68 10/24/98 3-104. Active Valves - page 69 10/24/98 3-IN. Active Valves - page 70 10/1/94 3-IN. Active Valves - page 71 10/184 3-104. Active Valves - page 72 5/2/97 3-104. Active Valves - page 73 10/1/94 3-104. Active Valves - page 74 10/1/94 3-104. Active Valves - page 75 10/1/94 3-104. Active Valves - page 76 10/1/94 3-104. Active Valves - page 77 10/1/94 3-IN. Active Valves - page 78 10/1/94 3-104. Active Valves - page 79 10/1/94 3104. Active Valves - page 80 10/1/94 3-1M. Active Valves - page 81 10/1/94 3-104. Active Valves - page 82 10/1/94 3-IN. Active Valves - page 83 10/1/94 3-104. Active Valves - page 84 10/1/94 3-104. Active Valves - page 85 10/1/94 3-104. Active Valves - page 86 10/1/94 3-104. Active Valves - page 87 10/1/94 3-104. Active Valves - page 88 5/2/97 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 1 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 2 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 3 10/182 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 4 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 5 10/24/98 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 6 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 7 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 8 10/1/92 3 105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 9 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 -page 10 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page ii 10/1/92 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 12 10/1/92 3-105. Electrical Equipment Seismic Qualification Cataviba Unit 1 - page 13 10/1/93 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 14 10/1/93 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 15 10/1/93 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 16 5/2/97 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 17 10/183 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 18 10/183 3-105. Electrical Equipment Seismic Qualification Catawba Unit 1 - page 19 10/1/93 3-105. Elewical Equipment Seismic Qualification Catawba Unit 1 - page 20 10/1/91 3-106. Electrical Equipment Seismic Qualification - page i 10/1/91 3-106. Electrical Equipment Seismic Qualification - page 2 10/1/91 3-106. Electrical Equipment Seismic Qualification - page 3 Page 9 10/24/98
10/1/91 3-106. Electrical Equipment Seismic Qualification - page 4 10/24/98 3-106. Electrical Equipment Seismic Qualification - page 5 10/24/98 3-106. Electrical Equipment Seismic Qualification - page 6 10/1/92 3-106. Electrical Equipment Seismic Qualification - page 7 10/1/93 3-106. Electrical Equipment Seismic Qualification -page 8 10/1/93 3-106. Electrical Equipment Seismic Qualification - page 9 10/1/93 3-106. Electrical Equipment Seismic Qualification - page 10 10/1/93 3-106. Electrical Equipment Seismic Qualification - page 11 10/1/93 3-106. Electrical Equipment Seismic Qualification - page 12 10/1/93 3-106. Electrical Equipment Seismic Qualification - page 13 10/1/93 3-106 Electrical Equipment Seismic Qualification - page 14 10/1/91 3-106. Electrical Equipment Seismic Qualification page 15 10/1/91 3-106. Electrical Equipment Seismic Qualification - page 16 10/24/98 3-106. Electrical Equipment Seismic Qualification - page 17 10/1/91 3-106. Electrical Equipment Seismic Qualification - page 18 10/1/91 3-106. Electrical Equipment Seismic Qualification - page lo 10/1/91 3-106. Electrical Equipment Seismic Qualification - rue e 10/1/91 3-107. Control Complex Areas Ventilation Systems Up Results 10/1/91 3-108. Comparison of Responses: Direct Generation y TMM Versus Time History 0.5% Critical Damping At Elev. 562+0 10/1/91 3-109. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 562+0 10/1/91 3-110. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 595+4 10/1/91 3-111. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 595+4 10/1/91 3-112. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 628+8 10/1/91 3-113. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 628+8 10/1/91 3-114. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 662+0 10/1/91 3-115. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 662+0 10/1/91 3-116. Comparison of Responses: Direct Generation (EDASP) Versus Time History 0.5% Critical Damping At Elev. 691+2 10/1/91 3-117. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 691+2 10/1/91 3-118. Comparison of Responses: Direct Generation (EDASP) Versus Time l
History 0.5% Critical Damping At Elev. 713+1 10/1/91 3-119. Comparison of Responses: Direct Generation (EDASP) Versus Time History 5% Critical Damping At Elev. 713+1 Chapter 4 Tables 10/24/98 4-1, Reactor Design Comparison Table - page 1 10/24/98 4-1. Reactor Design Comparison Table - page 2 10/24/98 4-1. Reactor Design Comparison Table - page 3 5/2/97 4-1. Reactor Design Comparison Table - page 4 10/24/98 4-1. Reactor Design Comparison Table - page 5 10/24/98 4-1. Reactor Design Comparison Table - page 6 10/24/98 4 2. Analytical Techniques In Core Design - page 1 10/1/93 4-2. Analytical Techniques In Core Design - page 2 10/1/91 4-3. Design Loading Conditions For Reactor Core Components 10/24/98 4-4. Reactor Core Description - page 1 Page 10 10/24/98
10/24/98 4-4. Reactor Core Description - page 2 10/24/98 4-4. Reactor Core Description page 3 5/2/97 4-5. Nuclear Design Parameters - page 1 5/2/97 4-5. Nuclear Design Parameters - page 2 5/2/97 4-6. Nuclear Design Parameters 10/1/91 4-7. Reactivity Requirements For Rod Cluster Control Assemblies 11/30/95 4-8. UOd Benchmark Critical Experimentsl3+
10/1/91 4-9. Axial Stability Index Pressurized Water Reactor Core With A 12 Foot Height i
10/1/91 4-10. Typical Neutron Flux Levels (n/cmd-sec) At Full Power 10/24/98 4-11, Comparison Of Measured And Calculated Doppler Defects (Deleted per 1998 Update) 10/24/98 412. Benchmark Critical Experiments 10/1/91 413. Saxton Core 11 Isotopics Rod My, Axial Zone 6 10/1/91 4-14. Critical Baron Concentrations, HZP, BOL 10/1/91 4-15. Benchmark Critical Experiments B4C Control Rod Worth 10/1/91 4-16. Comparison Of Measured And Calculated Moderator Coefficients At HZP, BOL 10/24/98 4-17. Thermal And Hydraulic Comparison Table - page i 10/24/98 4-17. Thermal And Hydraulic Comparison Table page 2 4-18. Deleted Per 1993 Update 10/1/93 4-19. Void Fractions At Nominal Reactor Conditions With Design Hot Channel Factors 10/1/91 4-20. Measurements Required in The Calculation Of Reactet Flow Using A Calorimetric Technique Chapter 5 Tables 10/24/98 5-1. System Design and Operating Parameters - page 1 10/24/98 5-1. System Design and Operating Parameters - page 2 5/2/97 5 2. Applicable Code Addenda for RCS Components 10/24/98 5-3. Code Cases Applicable for Operation, Maintenance, and Testing Activities 10/24/98 5-4. ASME Code Cases Used For Catawba Units 1 &2 Class 1 Components 10/24/98 5-5. Typical Plant Thermal-Hydraulic Parameters - page i 10/24/98 5-5. Typical Plant Thermal-Hydraulic Parameters - page 2 10/1/91 5-6. Class 1 Primary Components Material Specifications - page 1 10/1/91 5-6. Class 1 Primary Components Material Specifications - page 2 j
5/2/97 5-6. Class 1 Primary Components Material Specifications - page 3 10/1/91 5-6. Class 1 Primary Components Material Specifications - page 4 10/1/91 5-6. Class 1 Primary Components Material Specifications - page 5 10/1/91 5-7. Class I and 2 Auxiliary Components Material Specificatior.s 10/24/98 5-8. Reactor Vessels Internals for Emergency Core Cooling 10/24/98 5-9. Reactor Coolant Chemistry Specification (Deleted per 1998 Update) 10/24/98 5-10. Leakage Detection Sensitivity 10/1/91 5-11. Reactor Vessel Quality Assurance Program 10/24/98 5-12. Toughness Properties for the Catawba Unit 1 Reactor Vessel - page 1 10/24/98 5-12. Toughness Properties for the Catawba Unit i Reactor Vessel page 2 10/24/98 5-13. Fracture Toughness Properties for the Catawba Unit 2 Reactor Vessel-page i 10/1/93 5-13. Fracture Toughness Properties for the Catawba Unit 2 Reactor Vessel-page 2 10/24/98 5-14. Fracture Toughness Properties Of The Catawba Unit 1 Reactor Vessel Beltline Region Material Page11 10/24/98
I 10/24/98 5-15. Fracture Toughness Properties Of The Catawba Unit 2 Reactor Vessel Beltline Region Material.
10/24/98 5-16. Catawba Unit 1 Closure Head Bolting Material Properties 10/24/98' 5-17. Catawba Unit 2 Closure Head Bolting Material Properties 10/1/91 ~
5-18. Reactor Vessel Design Parameters 10/1/91 5-19. Chemical Composition Of The Catawba Unit 1 Reactor Vessel Beltline Region Material
{
10/24/98 5-20. Chemical Composition Of The Catawba Unit 2 Reactor Vessel Beltline Region Material j
10/1/93 5-21. Catawba Unit i Reactor Vessel Beltline Region Toughness Properties - page 1 10/24/98 5-21. Catawba Unit 1 Reactor Vessel Beltline Region Toughness I
Properties - page 2 10/1/93 5-21. Catawba Unit 1 Reactor Vessel Beltline Region Toughness Properties - page 3 l
10/24/98 5-22. Catawba Unit 2 Reactor Vessel Beltline Region Toughness Properties - page 1 10/24/98 5-22. Catawba Unit 2 Reactor Vessel Beltline Region Toughness Properties - page 2 10/1/93 5-22. Catawba Unit 2 Reactor Vessel Beltline Region Toughness Properties - page 3 10/24/98 5-23. Reactor Coolant Pump Design Parameters 10/1/91 5-24. Reactor Coolant Pump Quality Assurance Program 10/24/98 5-25. Steam Generator Design Data 10/24/98 5-26. Steam Generator Quality Assurance Program - page 1 10/1/91 5-26. Steam Generator Quality Assurance Program - page 2 5/2/97 5-27. Reactor Coolant Piping Design Parameters 10/24/98 5-28. Reactor Coolant Piping Quality Assurance Program 10/24/98 5-29. Design Bases for Residual Heat Removal System Operation 10/24/98 5 30. Residual Heat Removal System Component Data 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page i 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page 2 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page 3 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Hea: Removal System Active Components-Plant Cooldown Operation - page 4 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page 5 '
10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page 6 10/24/98 5-31. Failure Mode and Effects Analysis-Residual Heat Removal System Active Components-Plant Cooldown Operation - page 7 5/2/97 5-32. Pressurizer Design Data -
5/2/97 5-33. Pressurizer Quality Assurance Program 10/24/98 5-34. Pressurizer Relief Tank Design Data 10/24/98 5-35. Relief Valve Discharge To The Pressurizer Relief Tank 5/2/97 5-36. Reactor Coolant System Boundary Valve Design Parameters 5/2/97 5-37. Pressurizer Valves Design Parameters l
10/24/98 5-38. Component Supports 10/24/98 5-39. Materials 10/24/98 5-40. Reactor Vessel Material Surveillance Program - Withdrawal e
- o. ale 10/24/98 5-41. Reactor Coolant System Pressure Isolation Valves i
Page 12 10/24/98
]
1 I
Chapter 6 Tables 10/1/91 6-1. Engineered Safety Feature Materials 10/24/98 6-2. Parameters of Final Post-accident Chemistry 10/24/98 6-3. Protective Coatings on Westinghouse-supplied Equipment inside Containment 10/1/91 6-4. Organic Materials Inside Containment 10/1/93 6-5. Poter.tial Water Traps Inside Containment 10/1/95 6-6. Catawk ice Condenser Design Parameters 5/2/97 6-7. ECCS and Spray Flow Rates Assumed in Peak Containment Pressure Transient 5/2/97 6-8. Structural Heat Sink Data For %ak Containment Temperature Transient - page 1 j
10/24/98 6-8. Structura. Heat Sink Data For Peak Containment Temperature j
Transient - page 2 5/2/97 6-8. Structural Heat Sink Data Fer Peak Containment Temperature Transient - page 3 10/1/91 6-9. Structural Heat Sink Data For Peak Containment Pressure Transient 10/1/93 6-10. Energy Accounting for Peak Containment Pressure Transient (106 i
Btu) 10/1/91 6-11. Mass And Energy Release Rates For Peak Reverse Differential Pressure 10/1/91 6-12. Allowance Leakage Area for Various Reactor Coolant System Break Sizes I
10/1/91 6-13. TMD Element input Data 10/1/91 6-14. TMD Flow Path Input Data 10/1/91 6-15. Calculated Maximum Peak Pressures In Lower Compartment Elements Assuming Unaugmented Flow 4
10/1/91 6-16. Calculated Maximum Peak Pressures In The Ice Condenser Compartment Assuming Unaugmented Flow 10/1/91 6-17. Calculated Maximum Differential Pressures Across The Operating Deck Assuming Unaugmented Flow 10/1N1 6-18. Calculated Maximum Differential Pressures Across The Upper Crane Wall Assuming Unaugmented Flow 10/1/91 6-19. Containment Sump Volume Vs. Time Peak Containment Pressure i
Transient 10/1/91 6-20. Containment Sump Volume Vs. Elevation i
5/2/97 6-21. Sensitivity Studies For D.C. Cook Plant i
5/2/97 6-22. Mass and Energy Releases into Steam Generator Enclosure 1
5/2/97 6-23. TMD Input Data - 2 Node Steam Generator Enclosure 10/1/91 6-24. Peak Differential Pressures-2 Node Steam Generator Enclosure 10/1/91 6-25. TMD. input Data - 9 Node Steam Generator Enclosure 10/1/91 6-26. Peak Differential Pressure-9 Node Steam Generator Enclosure 10/1/91 6 27. Mass and Energy Release Rates into Pressurizer Enclosure 10/1/91 6-28. TMD Input Data - 2 Node Pressurizer Enclosure 10/1/91 6-29. TMD Input Data - 4 Node Pressurizer Enclosure 10/1/91 6-30. Mass and Energy Release Rates into Reactor Cavity 10/1/91 6-31. Reactor Cavity Analysis Volumes - Cold Leg Break 10/1/91 6-32. Reactor Cavity Ana!ysis Flow Paths - Cold Leg Break 10/1/91 6-33. Reactor Cavity Design Pressures 10/1/91 6-34. Mass and Energy Release Rates for Blowdown Page 13 10/24/98
10/1/91 6-35. Mass and Energy Release Rates for Blowdown 10/1/91 6-36. Mass and Energy Release Rates for Blowdown 10/1/91 6-37. Mass and Energy Release Rates for Blowdown 10/1/91 6-38. Mass and Energy Release Rates for Blowdown 10/1/91 6-39. Mass and Energy Release Rates for Blowdown 5/2/97 6-40. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 5/2/97 6-41. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 5/2/97 6-42. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 5/2/97 6-43. Mass and Energy Release Rates for Reflood (Deleted per 1997 Update) 5/2/97 6-44. Mass and Energy Release Rates for Post-Reflood (Deleted per 1997 Update) 5/2/97 6-45. Mass and Energy Releases Rates for Post-Reflood (Deleted per 1997 Update) 5/2/97 6-46. Mass and Energy Release Rates Post Reflood (Deleted per 1997 Update) 5/2/97 6-47. Mass and Energy Release Rates for Peak Containment Temperature Transient for Double Ended Steam Line Rupture 5/2/97 6-48. Mass and Energy Release Rates for Peak Containment Temperature Transient for Double Ended Steam Line Rupture (Deleted per 1997 Update) 5/2/97 6-49. Mass and Energy Release Rates for Peak Containment Temperature Transient (Deleted per 1997 Update) 5/2/97 6-50. Mass and Energy Release Rates for Peak Containment Temperature Transient (Deleted per 1997 Update) 5/2/97 6-51. Mass and Energy Release Rates for Peak Containment Superheat Duration Transient (Deleted per 1997 Update) 5/2,'97 6-52. Mass and Energy Release Rates for Peak Containment Superheat Duration Transient (Deleted per 1997 Update) 5/2/97 6-53. Mass and Energy Balances (Deleted per 1997 Update) 5/2/97 6-54. Mass and Energy Balances (Deleted per 1997 Update) 5/2/97 6-55. Mass and Energy Balances (Deleted per 1997 Update) 5/2/97 6-56. Mass and Energy Balances (Deleted per 1997 Update) 5/2/97 6-57. Mass and Energy Balances (Deleted per 1997 Update) 10/1/91 6-58. Double Ended Pump Suction Guillotine Max SI 10/1/91 6-59. DCP/ Double Ended Pump Suction Guillotine Mini S1 5/2/97 6-60. Basis for Peak Containment Pressure Mass and Energy Release Analysis 10/24/98 6-61. Mass and Energy Release Rates For Minimum Post-LOCA Containment Pressure 10/24/98 6-62. Minimum Post-LOCA Containment Pressure Broken Loop Accumulator Flow to Containment 10/1/91 6-63. Containment and Active Heat Sink Data for Peak Reverse Differential Pressure 10/1/91 6-64. Strut.aral Heat Sink Data For Minimum Post-LOCA Containment Pressure 10/1/91 6-65. Structural Heat Sink Data for Peak Reverse Differential Pressure 10/1/91 6-66. Containment and Active Heat Sink Data for Minimum Post-LOCA Containment Pressure 10/1/91 6-67 Summary Of Steamline and Feedwater Line Isolation Times 10/1/91 6-68. Air Return Fans and Hydrogen Skimmer Fans Failure Analysis 10/1/91 6-69. Deleted Per 1990 Update 10/24/98 6-70. Containment Spray Pump Design Parameters 10/24/98 6-71. Containment Spray Heat Exchanger Operating Parameters 10/1/91 6-72. Containment Spray System Single Failure Analyses 10/1/91 6-73. Failure Mode and Effects Analysis - Containment Spray System -
Active Components 10/24/98 6-74. Potential Bypass Leak Paths Through Containment isolation Valves Page 14 10/24/98
10/1/91 6-75. Typical Annulus Conditions vs. Time Following Design Basis Accident 10/1/91 6-76. Dual Containment Characteristics 10/24/98 6-77. Containment Isolation Valve Data 10/24/98 6-77. Notes to Table 6-77 5/2/97 6-78. Comparison of Containment Purge System With Branch Technical Position CSB 6-4, Revision 2 5/2/97 6-79. Applicable Codes, Standards and Guides Used in the Design of the Electric H2 Recombiner 5/2/97 6-80. Electric Hydrogen Recombiner Typical Parameters 5/2/97 6-81. Containment Hydrogen Sample and Purge System Design Data 5/2/97 6-82. Parameters Used to Determine Hydrogen Generation - page i 10/1/93 6-82. Parameters Used to Determine Hydrogen Generation - page 2 10/1/93 6-83. 'l otal Hydrogen Generation 10/1/91 6-84. Deleted Per 1991 Update 10/1/91 6-85. Deleted Per 1991 Update 10/1/91 6-86. Deleted Per 1991 Update 10/24/98 6-87. Emergency Core Cooling System Component Parameters - page 1 10/24/98 6-87. Emergency Core Cooling System Component Parameters - page 2 11/30/95 6 88. ECCS Relief Valve Data 10/1/91 6-89. Motor Operated Isolation Valves In ECCS - page 1 10/24/98 6-89. Motor Operated Isolation Valves In ECCS - page 2 10/1/91 6-89. Motor Operated Isolation Valves In ECCS - page 3 10/1/91 6-90. Materials Employed For Emergency Core Cooling System Components 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 1 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 2 10/24/98 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 3 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System Active Components - page 4 10/1/91 6-91. Failure Mode and Effects Analysis Emergency Core Cooling System
- Active Components - page 5 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 6 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 7 10/1/91 6-91. Failure Mode and Effects Andysis - Emergency Core Cooling System
- Active Components - page 8 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System Active Components - page 9 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 10 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 11 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 12 10/1/91 6-91. Failure Mode and Effects Analysis - Emergency Core Cooling System
- Active Components - page 13 10/1/91 6-92. Single Active Failure Analysis For Emergency Core Cooling System Components 10/24/98 6-93. Sequence Of Changeover Operation From Injection To Recirculation - page 1 Page 15 10/24/98
c 10/24/98 6-93. Sequence Of Changeover Operation From Injection To Recirculation - page 2 l
5/2/97 6-94. Emergency Core Cooling System Recirculation Piping Passive Failure Analysis 5/2/97 6-95. Safety Related Solenoid Valves Inside Containment Below Elevation 571'O 10/24/98 6-96. Active Valves Inside Containment Below Elevation 571'0" page i 10/1/91 6-96. Active Valves Inside Containment Below Elevation 571'0" - page 2 10/1/91 6-97. Emergency Core Cooling System Shared Functions Evaluation i1/30/95 6-98. Normal Operating Status Of Emergency Core Cooling System Components For Core Cooling iI/30/95 6-99. Parameters for Boron Precipitation Analysis 11/30/95 6-100. Comparison of Control Roocn Protection Against Toxic Gas Hazards With Regulatory Guide 1.95 - page 1 10/24/98 6-100. Comparison of Control Room Protection Against Toxic Gas Hazards With Regulatory Guide 1.95 - page 2 10/1/91 6-101. Comparison of Control Room Protection Against Toxic Gas Hazards With Regulatory Guide 1.78 10/1/91 6-102. Ice Condenser Elementallodine Removal Efficiency 10/1/91 6-103. Process Lines Subject to Augmented Inservice Inspection 10/1/91 6-1(M. Wall Panel Design Loads 10/24/98 6-105. Ice Basket Load Summary 10/24/98 6-106. Summary of Stresses in Basket Due to Design Loads 10/24/98 6107. Ice Basket Material Minimum Yield Stress 10/24/98 6-108. Allowable Stress Limits (D + OBE) For Ice Basket Materials 10/24/98 6-109. Allowable Stress Limits (D + SSE), (D + DB A) For Ice Basket Materials 10/24/98 6-110. Allowable Stress Limits (D + SSE + DBA) For Ice Basket Materials 10/24/98 6-111. Ice Basket Clevis Pin Stress Summary 10/1/91 6-112. Ice Basket Mounting Bracket Assembly Stress Summary 5/2/97 6-113. Ice Basket Plate Stress Summary 5/2/97 6-114. Ice Basket V-Bolt Stress Summary 5/2/97 6-115. Ice Basket - Basket End Stress Summary 5/2/97 6-116. Ice Basket Coupling Screw Stress Summary 5/2/97 6-117. Ice Basket Coupling Screw Stress Summary 5/2/97 6-118. Ice Basket Coupling Screw Stress Summary 5/2/97 6-119. Ice Basket Coupling Screw Stress Summary 5/2/97 6-120. Crane and Rail Assembly Design Loads 10/1/91 6-121. Refrigeration System Parameters 10/1/91 6-122. Lower Inlet Door Design Parameters and Loads 10/1/91 6-123. Top Deck Design Parameters and Loads 10/1/91 6-124. Summary of Results 10/1/91 6-125. Intermediate Deck Design Parameters and Loads 10/1/91 6-126. Summary of Waltz Mill Tests 10/1/91 6-127. Ice Condenser RTD's - page 1 10/24/98 6-127. Ice Condenser RTD's - page 2 10/24/98 6-127. Ice Condenser RTD's - page 3 10/1/91 6-128. Ice Condenser Allowable Limits 10/1/91 6-129. Summary of Catawba Loads-Tangential Case Obtained Using The Two-Mass Dynamic Model 10/1/91 6-130. Summary of Catawba Loads-Radial Case Obtained Using the Two-Mass Dynamic Model Page 16 10/24/98
10/1/91 6-131. Summary of Load Results of Five Non-Linear Dynamic Models 10/1/91 6-132. Summary of Parameters Used In The Seismic Analysis 5/2/97 6-133. Selection of Steels in Relation to Prevention of Non-Ductile Fracture ofIce Condenser Components 5/2/97 6-134. Swivel Bracket Stress Summary (Ref.19) Load Case IV 5/2/97 6-135. Containment Coating 5/2197 6-136. Cruciform Cable Suspension System Designfrest Load Summary 5/2/97 6-137. External Coupling Ring and Rivet Design Load / Stress Summary 5/2/97 6-138. Ice Basket Load Summary - Basic Design Loads (2000 lb. Basket)
Chapter 7 Tables i
10/1/93 7-1. List of Reactor Trips 10/1/91 7-2. Protection System Interlocks i
10/24N8 7-3. Reactor Trip System Instrumentation - page 1 10/24/98 7-3. Reactor Trip System Instrumentation - page 2 10/24/98 7-3. Reactor Trip System Instrumentation - page 3 10/24/98 7-4. Reactor Trip Correlation - page i 10/24/98 7-4. Reactor Trip Correlation - page 2 10/24/98 7-4. Reactor Trip Correlation - page 3 10/24/98 7-4. Reactor Trip Correlation - page 4 5/2/97 7-5. Instrumentation Operating Condition for Engineered Safety Features 5/2/97 7-6. Instrument Operating Conditions for Isolation Functions 5/2/97 7-7. Interlocks for Engineered Safety Features Actuation System
^
10/1/91 7 8. Auxiliary Shutdown Panel A Instrumentation And Controls Available For Hot Shutdown 10/1/91 7-9. Auxiliary Shutdown Panel B Instrumentation And Controls Available For Hot Shutdown 5/2/97 7-10. Auxiliary Feedwater Pump Turbine Control Panel Instrumentation And Controls Available For Hot Shutdown 10/1/91 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 1 10/1/91 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 2 10/1/91 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 3 10/1/91 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 4 5/2/97 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 5 10/1/91 7-11. Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation - page 6 10/1/91 7-12. Plant Control System Interkicks 10/1/91 7-13. Deleted Per 1990 Update 10/24/98 7-14. ESF Bypass Inuication 10/24/98 7-15. ESF Response Times Page 17 10/24/98 4
Chapter 8 Tables 10/1/91 8-1. Class 1E Loads 10/1/91 8-2. Transmission Structures Design Specifications 10/1/93 8-3. Description of Transmission Lines 10/1/91 8-4. Grid Frequency Decay Analysis 10/1/92 8 5. Transmission System Availability 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems page 1 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 2 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 3 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 4 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 5 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 6 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 7 10/24/98 8-6. Catswba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 8 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 9 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 10 10/24/98 8-6. Catawba Nuclear Station: Maximum Loads To Be Supplied From One Of The Redundant Engineered Safety Power Distribution Systems - page 1I (Page 11 was deleted in the 1998 Update) 10/24/98 8-7. Catawba Nuclear Station Switchgear Control Power Sources 10/1/91 8-8. Single Failure Analysis of the Onsite Power Systems - page 1 10/1/91 8-8. Single Failure Analysis of the Onsite Power Systems - page 2 10/1/91 8-8. Single Failure Analysis of the Onsite Power Systems - page 3 10/1/91 8-8. Single Failure Analysis of the Onsite Power Systems - page 4 5/2/97 8-8. Single Failure Analysis of the Onsite Power Systems - page 5 10/1/91 8-9. Deleted Per 1991 Update 5/2/97 8-10. Single Failure Analysis of the 125VDC Vital Instrumentation and Control Power System - page 1 10/1/91 8-10. Single Failure Analysis of the 125VDC VitalInstrumentation and Control Power System - page 2 10/1/91 8-10. Single Failure Analysis of the 125VDC VitalInstrumentation and Control Power System - page 3 10/1/91 8-11. Single Failure Analysis of the 120VAC VitalInstrumentation and Control Power System 10/1/91 8-12. Single Failure Analysis of the 125VDC Diesel Essential Auxiliary Power System Chapter 9 Tables 10/1/91 9-1. Spent Fuel Cooling System Component Design Parameters - page i 10/24/98 9-1. Spent Fuel Cooling System Component Design Parameters - page 2 10/1/91 9-1. Spent Fuel Cooling System Component Design Parameters - page 3 10/1/94 9-2. Nuclear Service Water System Component Design Parameters Page 18 10/24/98 I
10/1/91 9-2. Nuclear Service Water System Component Design Parameters 10/24/98 9-3 Nuclear Service Water System Flow Rates Outside the Nuclear Service Water Pumphouse - page 1 5/2/97 9-3. Nuclear Service Water System Flow Rates Outside the Nuclear Service Water Pumphouse - page 2 10/1/91 9-4. Nuclear Service Water System Failure Analysis - page 1 10/1/91 9-4. Nuclear Service Water System Failure Analysis - page 2 11/30/95 9-4. Nuclear Service Water System Failure Analysis - page 3 10/24/98 9-4. Nuclear Service Water System Failure Analysis - page 4 11/30/95 9-4. Nuclear Service Water System Failure Analysis - page 5 11/30/95 9-5. Nominal Nuclear Service Water System Flow Rates in the Nuclear Service Water Pumphouse 5/2/97 9-6. Component Cooling System Heat Load and Flow Requirements - page 1 i
10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 2 i
5/2/97 9-6. Component Cooling System Heat Load and Flow Requirements - page 3 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 4 5/2/97 9 6. Component Cooling System Heat Load and Flow Requirements - page 5 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 6 5/2/97 9 6. Component Cooling System Heat Load and Flow Requirements - page 7 IWl/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 8 5/2/97 9-6. Component Cooling System Heat Load and Flow Requirements - page 9 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 10 5/2/97 9-6. Component Cooling System Heat Load and Flow Requirements - page 11 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 12 5/2/97 9-6. Component Cooling System Heat Load and Flow Requirements - page 13 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 14 10/24/98 9-6. Component Cooling System Heat Load and Flow Requirements - page 15 10/1/91 9-6. Component Cooling System Heat Load and Flow Requirements - page 16 l
10/1/91 9-7. Component Cooling System Valve Alignment for Various Modes of Operation 5/2/97 9-8. Component Cooling System Component Design Data - page 1 10/24/98 9-8. Component Cooling System Component Design Data - page 2 10/1/91 9-9. Component Cooling System 10/1/91 9-10. Makeup Demineralized Water Sgtem Component Design Parameters - page 1 10/1/91 9-10. Makeup Demineralized Water System Component Design Parameters - page 2 10/1/91 9-10. Makeup Demineralized Water System Component Design Parameters - page 3 10/1/91 9-10. Makeup Demineralized Water System Component Design Parameters - page 4 10/1/91 9-10. Makeup Demineralized Water System Component Design Parameters - page 5 5/2/97 9-10. Makeup Demineralized Water System Component Design Parameters - page 6 5/2/97 9-10. Makeup Demineralized Water System Component Design Parameters - page 7 5/2/97 9-10. Makeup Demineralized Water System Component Design Parameters - page 8 5/2/97 9-10. Makeup Demineralized Water System Component Design Parameters - page 9 10/1/91 9-11. Filtered Water System and Drinking Water System Component Design Parameters - page 1 5/2/97 9-11. Filtered Water System and Drinking Water System Component Design Parameters - page 2 Page 19 10/24/98
10/1/94 9-12. Deleted Per 1994 Update i
10/1/94 9-13. Deleted Per 1994 Update 10/1/94 9-14. Condensate Storage System Design Parameters 10/24/98 9-15. Refueling Water System Component Design Data 10/24/98 9-16. Conventional Low Pressure Service Water System Component Design l
Parameters i
l1/30/95 9-17. Compressed Air Systems Component Design Parameters - page 1 11/30/95 9-17. Compressed Air Systems Component Design Farameters page 2 10/1/91 9-17. Compressed Air Systems Component Design Parameters - page 3 10/1/91 9-17. Compressed Air Systems Component Design Parameters - page 4 10/1/91 9-17. Comnressed Air Systems Component Design Parameters - page 5 10/1/91 9-18. Nuclear Sampling System Sample Locations and Data - page 1 10/1/91 9-18. Nuclear Sampling System Sample Locations and Data - page 2 10/1/93 9-18. Nuclear Sampling System Sample Locations and Data - page 3 10/1/93 9-19. Temperature and Pressure Reduction for Samples in the Conventional Systems Sample Panel 10/1/94 9-20. Types of Analyses Provided in the Conventional Sampling Lab 10/1/91 9 21. Chemical and Volume Control System Design Parameters 10/1/93 9-22. CVCS Principal Component Data Summary 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 1 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 2 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 3 10/1/94 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 4 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 5 5/2/97 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 6 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control j
System - page 7 5/2/97 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 8 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 9 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 10 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 11 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 12 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 13 j
10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control i
System - page 14 10/1/94 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 15 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 16 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 17 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 18 Page 20 10/24/98
7 1
10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 19 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 20 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 21 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 22 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 23 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control j
System - page 24 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control l
System - page 25 j
10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 26 10/1/91 9-23. Failure Mode and Effects Analysis Chemical t.,d Volume Control System - page 27 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 28 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Wlume Control System - page 29 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 30 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 31 10/24/98 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 32 10/24/98 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 33 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 34 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 35 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 36 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 37 10/1/94 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 38 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 39 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 40 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 41 10/1/91 9-23. Failure Mode and Effects Analysis Chemical and Volume Control System - page 42 10/1/91 9-24. Boron Recycle System Component Data Summary 10/1/91 9-25. Boron Thermal Regeneration System Component Data 10/1/93 9-26. Control Room Area Ventilation System Failure Analysis 10/1/93 9-27. Fuel Handling Area Exhaust System Failure Analysis 10/24/98 9-28. Auxiliary Building Ventilation System Failure Analysis 10/24/98 9-29. Purge System isolation Valve Design and Test Criteria 10/24/98 9-30. Annulus Ventilation System Page 21 10/24/98 I
k
10/24N8 9-31. Summary of Fire Protection Documents Submitted to the NRC 10/24/98 9-32. Communications Available for Transient and Accident Conditions 10/24/98 9-33. Communications and Lighting Available for Safe Shutdown of Plant 10/1/91 9-34. Single Failure Analysis of the Emergency Lighting Systems 10/1/91 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 1 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 2 10/24N8 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 3 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 4 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 5 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 6 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 7 10/24N8 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 8 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment - page 9 10/24/98 9-35. Lighting Systems Available to illuminate Safety Related Equipment page 10 10/24/98 9-36. 8-Hour Lighting for Post-Fire Alternate Shutdown Utilizing the Standby Shutdown System 10/24/98 9-37. Diesel Generator Engine Fuel Oil System Single Failure Analysis 10/24N8 9-38. Diesel Generator Fuel Oil Specifications 10/24/98 9-39. Diesel Generator Engine Cooling Water System Single Failure Analysis 10/24/98 9-40. Diesel Generator Engine Cooling Water System Alarm and Shutdown Setpoints 10/1/91 9-41. Diesel Generator Engine Starting Air System Single Failure Analysis 10/1/91 9-42. Diesel Generator Engine Lube Oil System Single Failure Analysis 10/1/91 9-43. Diesel Generator Engine Lube Oil System Alarm and Shutdown Setpoints i
10/1/91 9-44. Diesel Generator Engine intake and Exhaust System Single Failure Analysis 10/1/91 9-45. Comparison of VQ System to B FP CSB 6-4 10/1/91 9-46. Groundwater Drainage System Component Design Parameters Chapter 10 Tables 10/1/91 10-1. Design and Performance Characteristics of the Major Equipment and Tanks 10/1/91 10-2. Turbine Speed Control System Protection Devices 10/1/91 10-3. Turbine Speed Control System Valve Closure Time 10/1/91 10-4. Turbine Speed Control System Component Failure Analysis Page 22 10/24/98
10/1/91 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 10/24/98 10-6. Main Condenser Design Parameters 10/1/91 10-7. Main Condenser Evacuation System Component Design Parameters 10/1/91 10-8. T.arbine Bypass System Failure Mode And Effects Analysis 10/1/91 10-9. Condenser Circulating Water System Component Design Parameters 10/1/91 10-10. Condensate Cleanup System Component Design Parameters 10/1/91 10-11. Condensate and Feedwater System Component Design Parameters - page 1 10/24/98 10-11. Condensate and Feedwater System Component Design Parameters - page 2 10/1/91 10-11. Condensate and Feedwater System Component Design Parameters - page 3 5/2/97 10-12. Maximum Allowance Blowdown Flowrate 10/1/91 10-13. Steam Generator Blowdown System Component Design Parameters 10/1/91 10-14. Failure Analysis, Steam Generator Blowdown System - page 1 10/24/98 10-14. Failure Analysis, Steam Generator Blowdown System - page 2 10/1/91 10-15. Auxiliary Feedwater System Motor Driven Pump Design Data 10/1/91 10-16. Auxiliary Feedwater System Tt'rbine Driven Pump Design Data 10/1/91 10-17. Auxiliary Feedwater System Component Failure Analysis 10/1/91 10-18. Auxiliary Feedwater System Instrumentation and Control - page I 11/30/95 10-18. Auxiliary Feedwater System Instrumentation and Control - page 2 10/1/91 10-18. Auxiliary Feedwater System Instrumentation and Control - page 3 10/1/91 10-19. Moisture Separator / Reheater and Feedwater Heater Drains System C Feedwater Heater Drain Tank Pump Design Data Chapter 11 Tables 10/1/90 Il-l. Parameters Used in Calculating Maximum Reactor Coolant Activities 10/1/90 11-2. Design Basis Reactor Coolant Radioactivity Concentrations 10/1/90 11-3. Parameters Used in Calculating Normal Primary and Secondary Coolant Activities 10/1/90 11-4. Primary and Secondary Activity During Normal Operation 10/1/90 11-5. Tritium Source Terms 10/1/90 11-6. Maximum Expected Daily Flows to Liquid Radwaste System 10/1/90 11-7. Makeup Demineralized Water Chemistry 10/1/90 11-8. Liquid Radwaste System Component Design Parameters 10/1/90 11-9. Normal Expected Daily Flows to Liquid Radwas" Ntem (2 Units) 10/1/90 11-10. Tanks Outside Containment Which Contain Potentially Rad'aactive Liquids 10/1/90 11-11. Catawba Nuclear Station Estimated Radioactive Releases in ' iquid Effluents (curies / year / unit) 10/1/90 11-12. Estimated Doses from Radioactive Liquid Effluents Released from the Station 10/24/98 11-13. Waste Gas System Component Data 10/1/90 11-14. Estimated Annual Airborne Effluent Releases 10/1/90 11-15. Estimated Doses from Gaseous Effluent Releases from the Station 10/1/90 Il-16. Estimated Maximum Specific Activities Input to Nuclear Solid Waste Disposal System 10/1/90 11-17. Solid Radwaste System Component Data 10/1/92 11-18. Estimated Maximum Volumes Discharged from Solid Radwaste System (Two Units)(Deleted per the 1997 Update)
Page 23 10/24/98
r 10/1/94 11-19. Liquid Process Radiation Monitoring Equipment 10/1/90 1120. Airborne Process Radiation Monitoring Equipment - page 1 10/1/94 11-20. Airborne Process Radiation Monitoring Equipment - page 2 10/1/90 11-21. System Component Design Parameters 5/2/97 1 -22. Adjacent-to-Line Radiation Monitoring System Chapter 12 Tables 10/1/91 12-1. Design Basis Source Strengths for Fluids 10/1/91 12-2. Design Basis Source Strengths for Demineralizers Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/ gamma) 10/1/91 12-3. Design Basis Source Strengths for Filters Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/ gamma) 10/1N1 12-4. Reactor Coolant System Nitrogen-16 Activity 10/1/91 12-5. Fluxes on Inside Surface of Primary Concrete 10/1/91 12-6. Design Source Strengths for Outside Storage Tanks 10/1/91 12-7. Spent Fuel Source Term -(MeV/cc - sec) 10/1/91 12-8. Source Terms for Calculating Airborne Radioactivity in Auxiliary Building Cubicles 10/1/92 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 1 10/1/92 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 2 10/1/91 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 3 10/1/92 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 4 10/1/91 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 5 10/182 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 6 10/1/92 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (+Ci/ml)- page 7 10/1/92 12-10. Concentration Estimates of Airborne Radioactivity in Turbine Building 10/1/92 12-11. Concentration Estimates of Airborne Radioactivity in Upper Containment During Operation 10/1/92 12-12. Concentration Estimates of Airborne Radioactivity in the Administration Building 10/1/92 12-13. Concentration Estimates of Airborne Radioactivity in the Control Room 10/1/92 12-14. Concentration Estimates of Airborne Radioactivity in Fuel Handling Area 5/2/97 12-15. Design Radiation Zones 5/2/97 12-16. Present W E-Specs On Cobalt Content of Materials 10/1/91 12-17. Catawba Radiation Zones - Reactor Building 10/1/91 12-18. Catawba Radiation Zones - Auxiliary Buildiag 10/1/91 12-19. Design Shield Thickness 10/1/91 12-20. Primary Shield Description 10/1/91 12-21. Parameters Used for Design Basis Accident Analysis of Control Room Direct Dose 10/1/91 12-22. Design Basis Accident Containment Source Strength 10/1/91 12-23. Comparison of Control Room Area Pressurizing Air Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 Page 24 10/24/98
l 10/1/91 12-24. Comparison Of Auxiliary Building Filtered Exhaust System With Regulatory Guide 1.52 Revision 2, March 1978 10/1/91 12-25. Comparison Of Fuel Handling Area Exhaust Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 10/1/91 12-26. Comparison Of Annulus Ventilation Filtration System With Regulatory Guide 1.52 Revision 2, March 1978 10/1/91 12-27. Filter System Design Parameters 10/1/91 12-28. Comparison of Containment Purge Filter System With Regulatory Guide 1.52 Revision 2. March 1978 11/30/95 12-29. Area Radiation Monitoring System - page 1 11/30/95 12-29. Area Radiation Monitoring System - page 2 11/30/95 12-29. Area Radiation Monitoring System - page 3 10/1/91 12-30. Estimated - Station Organization and Work Area j
10/1/91 12-31. Dose Assessment - Number of Personnel and Times of Occupancy in l
Radiation Areas 10/1/91 12-32. Routine Operation Dose Assessment 10/1/91 12-33. Total Occupational Radiation Exposure Estimates (for one I
unit) 10/1/91 12-34. Occupational Radiation Exposure Estimate for Reactor Operations and Surveillance (for one unit) 10/1/91 12-35. Occupational Radiation Exposure Estimate For Routine Maintenance (For One Unit) 10/1/91 12-36. Occupational Radiation Exposure Estimate For Waste Processing (For One Unit) 10/1/91 12-37. Occupational Radiation Exposure Estimate For Refueling (For One Unit) 10/1/91 12-38. Occupational Radiation Exposure Estimate For Inservice Inspection (For One Unit) 10/1/91 12-39. Occupational Radiation Exposure Estimate For Special Maintenance *
(For One Unit) 5/2/97 12-40. RCA Description and RCA Control Points 5/2/97 12-41. Design Source Strengths for the Retired Steam Generator Storage Facility Chapter 13 Tables 10/1/91 13-1. To be provided i
10/1/91 13-2. Deleted per 1990 Update Chapter 14 Tables 10/1/91 14-1. Compliance with Regulatory Guides 10/1/91 14 2. Preoperational and Startup Test Schedule Chapter 15 TaMa 10/1/92 15-1. Deleted Per 1992 Update 5/2/97 15-2. Summary of Accidents Analyzed With Computer Codes 5/2/97 15-3. Summary of Computer Codes and Methodologies Used in Accident Analyses 5/2/97 15-4. Summary ofinput Parameters for Accident Analyses - page i 10/24/98 15-4. Summary ofinput Parameters for Accident Analyses - page 2
$/2/97 15-4. Summary ofinput Parameters for Accident Analyses - page 3 Page 25 10/24/98
5/2/97 15-4. Summary ofInput Parameters for Accident Analyses - page 4 5/2/97 15-4. Summary ofInput Parameters for Accident Analyses - page 5 10/24/98 15-5. Deleted Per 1992 Update 10/24/98 15-6. Rod Drop Times Used in FSAR Analyses 10/24/98 15-7. Trip Points and Time Delays to Trip Assumed in Accident Analyses 10/1/92 15-8. Deleted Per 1992 Update 10/IS2 15-9. Deleted Per 1992 Update 10/1/92 15-10. Deleted Per 1992 Update 10/1/92 15-11. Deleted Per 1992 Update 10/1/91 15-12. lodine and Noble Gas Inventory in Reactor Core and Fuel Rod Gaps 10/1/91 15-13. Reactor Coolant Specific Activities for lodine and Noble Gas Isotopes 10/1/94 15-14. Offsite Doses (Rem)- page 1 10/1/91 15-14. Offsite Doses (Rem)- page 2 5/2/97 15-15. Time Sequence of Events for incidents Which Cause an Increass in Heat Removal By The Secondary System - page 1 5/2/97 15-15. Time Sequence of Events for Incidents Which Cause an Increase In Heat Removal By The Secondary System - page 2 10/1/92 15-16. Deleted Per 1992 Update 101/91 1517. Parameters for Postulated Main Steam Line Break Offsite Dose Analysis 10/24/98 15-18. Time Sequence Of Events For Incidents Which Cause A Decrease in Heat Removal By The Secondary System - page 1 10/24/98 15-18. Time Sequence Of Events For Incidents Which Cause A Decrease In Heat Removal By The Secondary System - page 2 5/2/97 15-18. Time Sequence Of Events For Incidents Which Cause A Decrease In Heat Removal By The Secondary System - page 3 10/1/91 15-19. Parameters for Loss of Offsite Power Offsite Dose Analysis 5/2/97 15-20. Time Sequence of Events for Incidents Which Cause in a Decrease in Reactor Coolant System Flow 10/1/92 15-21. Deleted Per 1992 Update 10/1/91 15-22. Parameters for Postulated Locked Rotor Offsite Dose Analysis 5/2/97 15-23. Time Sequence of Events for Incidents which Cause Reactivity and i
Power Distribution Anomalies - page 1 10/24/98 15-23. Time Sequence of Events for incidents which Cause Reactivity and Power Distribution Anomalies - page 2 5/2/97 15-23. Time Sequence of Events for Incidents which Cause Reactivity and Power Distribution Anomalies-page 3 5/2/97 15-23. Time Sequence of Events for Incidents which Cause Reactivity and Power Distribution Anomalies - page 4 10/1/92 15-24. Deleted Per 1992 Update 5/2/97 15-25. Parameters Used in the Analysis of the Rod Cluster Control Assembly Ejection Accident 10/1/91 15-26. Parameters for Postulated Rod Ejection Offsite Dose Analysis 10/1/91 15 27. Deleted Per 1995 Update 5/2/97 15-28. Time Sequence of Events For inadvertent Opening of a Pressurizer Safety Valve 10/1/91 15-29. Parameters for Postulated Instrument Line Break Offsite Dose Analysis 10/1/91 15-30. Deleted Per 1990 Update 10/1/93 15-31. Parameters for Postulated Steam Generator Tube Rupture Offsite Dose Analysis 5/2/97 15-32. Input Parameters Used in the Small Break LOCA Analyses Page 26 10/24/98
l 11/30/95 15-33. Deleted Per 1994 Update 11/30/95 15-34. Deleted Per 1994 Update 11/30/95 15-35. Deleted Per 1995 Update 11/30/95 15-36. Deleted Per 1994 Update 11/30/95 15-37. Deleted Per 1995 Update 10/24/98 15-38. Small Break LOCA Time Sequence of Events (Westinghouse Evaluation Model) 10/24/98 15-39. Small Break LOCA Results Del Cladding Data (Westinghouse Evaluation Model) 10/1/91 15-40. Parameters for LOCA Offsite Dose analysis 10/1/91 15-41. Para,neters for LOCA Control Room Dose Analysis 5/2/97 15-42. Parameters for Postulated Liquid Storage Tank Rupture Evaluation 5/2/97 15-43. Parameters for Postulated Refue!ing Water Storage Tank Rupture Accident 5/2/97 15-44. Activities for Postulated Refueling Water Storage Tank Rupture Accident 5/2/97 15-45. Activities in Highest inventory Discharged Assembly for Postulated Fuel Handling Accidents 5/2/97 15-46. Parameters for Postulated Fuel Handling Accident Outside Containment 5/2/97 15-47. Parameters for Postulated Fual Handling Accident inside Containment 5/2/97 15-48. Parameters for Post-LOCA Subcriticality Analysis 10/1/91 15-49. Time Sequence of Events For Steam Generator Tube Rupture 5/2/97 15-50. Input Parameters Used in the Large Break LOCA Analyses (B&W Evaluation Model) 5/2/97 15-51. Large Break LOCA Time Sequence of Events (B&W Evaluation Model) 5/2/97 15-52. Large Break LOCA Results Fuel Cladding Data (B&W Evaluation Model) 11/30/95 15-53. Maximum Injected ECCS Flows Assumed in LDLOCA Analyses - Two Trains Operational S/2/97 15-54. Minimum ECCS Flow Assumed in SBLOCA Analyses (Westinghouse Evaluation Model) 5/2/97 15-55. SBLOCA Reanalyses PCT Results, Summary (Westinghouse Evaluation Model) 10/24/98 15-56. SBLOCA Reanalyses PCT Results,(B&W Evaluation Model, Unit 2) 5/2/97 15-57. Minimum ECCS Flow Assumed in SBLOCA Analyses - One Train Operational (B&W Evaluation Model) 5/2/97 15-58. Parameters for Postulated Weir Gate Drops 5/2/97 15-59. Input Parameters Used in the Small Break LOCA Analyses (Unit 1) 5/2/97 15-60. Small Break LOCA Time Sequence of Events (Unit 1) 10/24/98 15-61. Small Break LOCA Results Fuel Cladding Data (Unit 1) 5/2/97 15-62. Input Parameters Used in the Large Break LOCA Analyses (Unit 1) 10/24/98 15-63. Large Break LOCA Sequence of Events, Maximum Safeguards, DECLG, CD = 1.0 (Unit 1) 10/24/98 15.64. Large Break LOCA Results Fuel Cladding Data, Maximum Safeguards, DECLG, CD = 1.0 (Unit 1)
Page 27 10/24/98
Catawba UFSAR List of Effective Dates for Figures Chapter 1 Figures 10/1/91 1-1. Duke Power Company Service Area No Date Available 1-2. General Arrangement Plan @ EL. 522 +0 No Date Available 1-3. General Arrangement Plan @ EL. 543 +0 No Date Available 1-4. General Arrangement Plan @ EL. 560 +0 No Date Available 1-5. General Arrangement Plan @ EL. 577 +0 No Date Available 1-6. General Arrangement Plan @ EL 594 +0 No Date Available 1-7. General Arrangement Plan @ EL. 619 +0 No Date Available 1-8. General Arrangement Roof Plan No Date Available 1-9. General Arrangement longitudinal Section No Date Available 1-10. General Arrangement Containment and Reactor Building Plan @ EL.
523 +11 No Date Available 1-11. General Arrangement Containment and Reactor Building Plan @ EL.
552 +0 No Date Available 1-12. General Arrangement Containment and Reactor Building Plan @ EL.
565 +3 No Date Available 1-13. General Arrangemerit Containment and Reactor Building Plan @ EL.
594 +10 3/4 No Date Available 1-14. General Arrangement Containment and Reactor Building Plan @ EL.
605 +10 No Date Available 1-15. General Arrangement Containment and Reactor Building Plan @ EL.
652 +71/2 No Date Available 1-16. General Arrangement Containment and Reactor Building Section (Laydown Space) i No Date Available 1-17. General Arrangement Containment and Reactor Building Section No Date Available 1-18. General Arrangement Containment and Reactor Building Refueling Canal Layout Longitudinal Section 5/2/97 1-19. Site Plan No Date Available 120. Plot Plan 10/1/91 1-21. Electrical SymbolIdentification 10/24/98 1-22. Symbols for Flow Diagrams 10/24/98 1-23. Symbols for Flow Diagrams j
No Date Available 1-24. Catawba Symbols and Abbreviations for Flow Diagraras No Date Available 1-25. Post-accident Radiation Zones @ EL. 522+0 No Date Available 1-26. Post-accident Radiation Zones @ EL. 543+0 No Date Available 1-27. Post-accident Radiation Zones @ EL. 560+0 No Date Available 1-28. Post-accident Radiation Zones @ EL. 577+0 No Date Available 1-29. Post-accident Radiation Zones @ EL. 594+0 No Date Available 1-30. Post-accident Radiation Zones @ EL. 605+10 & 619+0 10/1/91 1J L Inadequate Core Cooling Instrumentation Configuration 10/1/91 1-32. Loss of Offsite Power 10/1/91 133. Feedline Rupture with Offsite Power 10/1/91 134. Feedline Rupture without Offsite Power 10/1/91 1-35. Incore Thermocouple System Configuration Chapter 2 Figures (no dates on all Chapter 2 Figures are available) 2-1. Regional Location 2-2. Site Location 2 3. Site Area Page 28 10/24/98
o 2-4. Release Points 2-5. Significant Population Groupings, Ten Miles 2-6. Significant Population Groupings, Fifty Miles 2-7. VicinityTopography 2-8. Five Mile (Eight Kilometer) Area 2-9. Population Centers 2-10. Cumulative Population, Year of Plant Start-Up 2-11. Cumulative Population, End of Plant Life 2-12. Locations and Routes 2-13. Tornado Frequency 1916 - 1955 2-14. Visible Plume Length Frequency (June - November) 2-15. Visible Plume Length Frequency (December - May) 2-16. Vicinity Topography - Profile 2-17. Relative Elevations of Meteorological Instruments 2-18. Cumulative Frequency Distribution of Hourly Dilution Factors at the Exclusion Area Boundary (Northeast Sector) 2-19. Cumulative Frequency Distribution of Hourly Dilution Factors at the Low Population Zone Boundary (Northeast Sector) 2-20. Site Earthwork 2-21. Plan-Profile of Catawba River 2-22. Surface Water Users 2-23. Yard Drainage 2 24. Power Block Area Features 2-25. Catch Basin Inlet Details 2-26. Administratian and Security Fence Base Details 2-27. Local Intense Precipitation PMP Floor Routing Using Puls Graphical 2-28. P P ood Routing; Type ! Inlets - 100% Efficient; Type II Inlets
- 100% Efficient 2-29. PMP Flood Routing; Type I Inlets - 100% Efficient; Type II Inlets
- 50% Efficient 2-30. PMP Flood Routing; Type i Inlets - 100% Efficient; Type II Inlets
- 0% Efficient 2-31. PMP Flood Routing; Switchyard 2-32. PMP Flood Routing; Cooling Tower Yard 2-33. Exterior Door Entrances to Safety Related Structures 2-34. Probable Maximum Precipitation 2-35. Basin Subarcas and Thiessen Polygons and Isohyetal Map for Probable Maximum Precipitation 2-36. Lag Time 2-37. Basin Subarca Unit Hydrographs 2-38. Reservoir Inflows, Outflows, and Elevations for Wylie Reservoir 2-39. PMF Hydrograph, Lake Wylie 2-40. Fetch Map 2-41. Wylie Reservoir Inflows, Outflows and Elevations i
2-42. SNSW PMF Hydrographs 2-43. NSW Pump House Sections 2-44. LPSW Intake Structure 2-45. NSW and SNSW Discharge Structures 2-46. SNSW Intake Structure 2-47. Location of Wells Surveyed 2-48. Groundwater Users 2-49. River Bank Wells 2-50. Reconstruction Groundwater Contour Map Page 29 10/24/98
2-51. Site Cross-Section 2-52. Monthly Groundwater flydrograph (October,1973 to September, 1977) 2-53. Groundwater 1evel, Daily Rainfall and Lake Level 2-54. Schematic Equipment Arrangement for Rock Permeability Testing 2-55. Schematic Equipment Arrangement for Soil Permeability Testing 2-56. Pumping Test No.1 - A85-TW Location, Plan 2-57. Pumping Test No. 2 - A48TW Location, Plan 2-58. Core of Depression - Pumping Test 1 2-59. Core of Depression - Pumping Test 2 2-60. Auxiliary and Reactor Building Groundwater Drainage System 2-61. Auxiliary and Reactor Building Groundwater Drainage System 2-62. Plot of Water Level at Structure Versus Rebound Time 2-63. Auxiliary and Reactor Building Groundwater Drainage System 2-64. Auxiliary and Reactor Building Groundwater Drainage System 2-65. Powerhouse Foundation 2-66. Location of Compacted Backfill (Powerhouse Area) 2-67. Regional Physiographic Map 2-68. Regional Geologic Map 2-69. Regional Tectonic Map 2-70. Regional Geologic Cross-Section 2-71. Regional Aeromagnetic Map 2-72. Regional Bouguer Gravity Anomaly Map 2-73. Subregional Geologic Index 2-74. Regional Linear Features Map 2-75. Subregional Geologic Map 2 76. Subregional Drainage Map with Linear Stream Segments 2-77. RegionalIn Situ Stresses 2-78. Boring Location Plan 2-79. Boring Location Plan 2-80. Subsurface Profiles
. 2-81. Subsurface Profiles 2-82. Subsurface Profiles 2-83. Subsurface Profiles 2-84. Subsurface Profiles 2-85. Subsurface Profiles 2-86. Subsurface Profiles 2-87. Subsurface Profiles 2-88. Subsurface Profiles 2-89. Subsurface Profiles 2-90. Subsurface Profiles 2-91. Subsurface Profiles I
2-92. Subsurface Profiles i
2-93. Subsurface Profiles I
2-94. Seismic Refraction Traverses 2-95. Seismic Refraction Traverses 2-96. Seismic Refraction Traverses 2-97. Scismic Refraction Traverses 2-98. Uphole Seismic Data, Boring A-61 2-99. Uphole Seismic Data, Boring A-63 2100. Contours on Top of Continuous Rock 2-101. Equal Area Projections of Poles to Planes - Powerhouse Excavation Page 30 10/24/98
F l
l l
2-102. Equal Area Projections of Poles to Planes - SNSW Pond Dam i
Excavations l
2-103. Geologic Map of Powerhouse Excavation - Reactor and Auxiliary l
Building Area 2-lfM. Geologic Map of Powerhouse Excavation - Turbine and Service Building Area i
2-105. Geologic Map of SNSW Pond Dam Excavation i
2-106. RegionalEpicenterMap l
2-107. Epicenters of Earthquakes Located Within 50-Mile Radius of the Site l
2-108. Epicenters of Earthquakes Probably Felt at the Catawba Site l
2-109. Acceleration - Intensity Relationships 2-110. Design Response Spectra,.08g 2-111. Design Response Spectra,.08g 2-112. Design Response Spectra,.15g 2-113. Design Response Spectra,25 feet of Overburden,.08g at Rock 2-114. Actual Foundation Conditions at Structures Designed Using Response Spectrum Computed for 25 Fr. of Overburden (Fill) 2-115. Soil Columns for Unit 2 Fuel Oil Storage Tanks and Unit 2 Above Ground Storage Tank 2-116. Comparison of Computed Response Spectra and Design Response Spectrum j
2-117. Location Plan for Seismic Refraction Lines on Rock In Powchouse l
Excavation 2-118. Results of Seismic Refraction Lines - NSW Intake Structure and NSW Pump Structure 2-119. Seismic Refraction Profiles - NSW Pipe Lines 2-120. Results of Seismic Refraction Lines in Powerhouse Excavation 2-121. Summary of Grain Size Distribution of Residual Soils from Adamellite 2-122.,cummary of Optimum Moisture and Maximum Dry Density of Residual Soils from Plant Area 2-123. Typical Consolidation Test Results of Compacted Residual Soils from Plant Area 2-124. Summary of Consolidation Characteristics of Partially Weathered Rock Materials 1
2-125. Summary of Mohr Diagrams of Compacted Residual Soils from Plant l
Area 2-126. Summary of Mohr Diagrams for Partially Weathered Rock Materials 2-127. Summary of Stress-Strain Data on Rock Core 2-128. Summary of Rock Test Data From Plant Area Substructure Excavation 2-129. Dynamic Moduli of Foundation Materials - Plant Area 2-130. Contours of Plant Excavation Bottom at Start of Blasting 2-131. Soil Column Analysis - NSW Pipeline 2-132. Sections Through Powerhouse 2-133. Cross Sections Through NSW and SNSW Pump Structure and Diesel Fuel Oil Storage Tanks 2-134. Selected Subsurface Profiles Through NSW Pipe Lines 2-135. Earth Pressure Distribution on Subsurface Walls 2-136. Number of Moisture Tests Versus Moisture Content for Compacted Group I Backfill 2-137. Number of Compaction Tests Versus Percent Compaction for Group I Backfill Page 31 10/24/98 l
e-2-138. Number of Compaction Tests Versus Relative Density for Granular Backfill 2-139. Nuclear Service Water System Yard Layout - Longitudinal Profiles 2-140. Typical Section, Standby Nuclear Service Water Pond Dam 2-141. Standby Nuclear Service Water Pond Dam, Details 2-142. Plan, Standby Nuclear Service Water Pond Dam 2-143. Profile of Standby Nuclear Service Water Pond Outlet Works l
2144. Boring Location Plan, Standby Nuclear Service Water Pond Dam 2-145. Section Along Axis of Standby Nuclear Service Water Pond Dam 2-146. Section A-87 Through A-96, South of Standby Nuclear Service Water Pond Dam 2-147. Section A-103 S1 Through A-103 S2, Standby Nuclear Service Water Pond Dam 2-148. Standby Nuclear Service Water Pond Dam, Section A-116 Through A-119 2-149. Standby Nuclear Service Water Pond Dam, Section A 117 Through A-118 2-150. Summary of Grain Size Distribution, Residual Soils at Standby Nuclear Service Water Pond Dam - Foundation Saprolites 2-151, Summary of Mohr Diagrams for Foundation Soils, Standby Nuclear Service Water Pond Dam 2-152. Cyclic Triaxial Strength Results 2-153. Cyclic Strength of Soils 2-154. Summary of Consolidation Characteristics for Residual Soils, Standby Nuclear Service Water Pond Dam 2-155. Cross Hole Seismic Data, Boring A-103 2-156. Cross Hole Seismic Data, Boring A-105 2-157. Dynamic Tests on Foundation Soils l
2-158. Summary of Mohr Diagrams of Partially Weathered Rock l
2-159. Standby Nuclear Service Water Pond Dam Foundation Plan 2-160. Standby Nuclear Service Water Pond Dam Fow,ilation Bedrock-South Abutment 2-161. Standby Nuclear Service Water Pond Dam Fad 1 Sources and Quantities Placed Versus Date 2-162. Summary Grain Size Distribution, Residual Samis - General Borrow i
l Areas Investigated for PSAR l
2-163. Summary Grain Size Distribution Residual Soils-Silty Sands, SNSW l
Pond Dam Embankment Borrow Area Utilized l
2-164. Earth Embankment Material, Grain Size Distribution. Standby l
Nuclear Service Water Pond Dam 2-165. Optimum Moisture, Maximum Dry Density for Soil During PSAR Investigation and Borrow Area Studies, Standby Nuclear Service Water Pond Dam 2-166. Dry Density versus Optimum Moisture Content From Proctor Tests on Soils Placed on SNSW Pond Dam l
2-167. Summary of Mohr Diagrams of Structural Fill Obtained During PSAR Investigations 2-168. Summary of Mohr Diagrams of Structural Fill from Borrow Areas Used for Standby Nuclear Service Water Pond Dam Embankment 2-169. Summary of Mohr Diagrams for Structural Fill Sampled from Standby Nuclear Service Water Pond Embankment 2-170. Distribution of Field Density Tests with Percent Compaction on Standby Nuclear Service Water Pond Dam Embankment Page 32 10/24/98
I l
l 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 2 172. Slope Protection, Filter layer, Grain Size Distribution 2-173. Number of Moisture Tests Versus Moisture Content for Standby Nuclear Service Water Pond Dam 2-174. Number of Moisture Tests Versus Moisture Content for Standby Nuclear Service Water Pond Dam 2-175. Number of Compaction Tests Versus Percent Compaction for Standby Nuclear Service Water Pond Dam 2-176. Blanket Drain Course. Filter, Density Test Distribution 2-177. Blanket Drain Top Layer Fine Filter Density Test Distribution 2-178. Blanket Drain, Coarse Fitler, Grain Size Distribution 2-179. Blanket Drain, Fine Filter-Top Layer, Grain Size Distribution 2-180. Blanket Drain, Fine Filter-Bottom Layer, Grain Size Distribution 2-181. Cross-Section for Stability Analysis 2-182. Dynamic Modulus for Embankment and Foundation Materials 2-183. Dynamie Modulus and Combining Pressure for Foundation Soils -
Saprolites 2-184. Failure Surfaces of Lowest Safety Factor - Static Analysis 2-185. Finite Element Representation 2-186. Static Finite Element Analysis, Vertical Effective Normal Stress in Embankment 2-187. Static Finite Element Analysis, Horizontal Shear Stressin Embankment 2188. Static Finite Element Analysis, Principal Stress Ratios in Embankment 2-189. Cyclic Triaxial Tests - Typical Strain and Pore Pressure Data (Remolded Samples) 2-190. Variation of Damping for Embankment and Foundation Materials 2-191. Variation of Modulus for Embankment and Foundation Materials 2-192. Dynamic Tests on Embankment Materials 2-193. Time History of Synthetic EQ-1 2-194. Time History of Synthetic EQ-2 l
2-195. Time History of Synthetic EQ-3 2-196. Time History of Synthetic EQ-4 2-197. Failure Potential Under Cyclic Loading 2-198. Seismic Coefficient SNSW Pond Dam 2-199. Standby Nuclear Service Water Pond Dam Instrumentation Details 2-200. Local Safety Factors Against 5% Strain 2-201. SNSW Pond Dam Piezometric Readings 2-202. SNSW Pond Dam Settlement Versus Time 2-203. SNSW Pond Dam Crest Elevation 2-204. Design Response Spectrum for Direct Generation Chapter 3 Figures l
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 Page 33 10/24/98
i I
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 10/1/91 3-7. Imation Of Postulated Breaks in Main Reactor Coolant Loop 10/1/91 3-8. Analytical Method For Resolving Pipe Break Consequences 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 i
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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 l'pdate 10/1/91 3-2(M. Deleted Per 1990 Update 10/1/91 3-205. Deleted Per 1990 Update 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 10/1/91 3-221. Nuclear Service Water Pump Structure Elevation l
Page 37 10/24/98
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 (Ib/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 10/1/91 3-228. Reactor Building Hoop Force N& phi. (Ib/in) Due To SSE 10/1/91 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 No Date Available 3-245. Reactor Building Top Radial Bars No Date Available 3-246. Reactor Building Circular Bars No Date Available 3-247. Cotitainment Vessel And Equipment Anchorage Details No Date Available 3-248. Reactor Building Shell Wall Developed Elevation No Date Available 3-249. Reactor Building Shell Walt Developed Elevation No Date Available 3-250. Reactor Building Shell Wall Developed Elr : tion 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. Contr.inment Geometry No Date Available 3-260. Containment Personnel And Equipment Hatch Typical Details Page 38 10/24/98
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 5/2/97 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. Locr.hzed "Nastran" Model For Stability Analysis 10/1/91 3-277. Containment Vessel Model For " Marc" Ultimate Capacity Analysis 10/1/91 3-278. Repetor Buildine Pressure Seals And Gaskets 10/1/91 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 10/1/91 3-282. Fixed End Supports 10/1/91 3-283. Pinned End Supports 10/1/91 3-284. Fixed End Supports 10/1/91 3 285. Pinned End Supports 10/1/91 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 Varial.les 10/1/91 3-291. Pre And Post Hot Functional Examination Points For Internals And Integrity 10/1/91 3-292. Auuliary Building Auxiliary Feedwater System 10/1/91 3-293. Fu'.I 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 Tempera %re 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 Schene Flow Chart 5/2/97 3-301. Reactor Coolant Loop Model for Steam Generator Replacement
$/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 Page 39 10/24/98 I
l
Chapter 4 Figures 10/1/93 4-1.17 x 17 Fuel Assembly Cross Section 10/1/93 4-2.17 x 17 Optimized Fuel Assembly Outline 10/24N8 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 10/1/93 4-6. Elevation Vicw of Mid Grid to Guide Thimble Joint l'Vl/93 4 7. Top Grid to Nozzle Attachment 10/1/93 4-8. Guide Thimble to Bottom Nozzle Joint 10/lNI 4-9. Full Length Rod Cluster Control and Drive Rod Assembly with Interfacing Components 10/24N8 4-10. Rod Cluster Control Assembly Outline 10/1/91 4-11. Hybrid B4C Absorber Rod 10/1/94 4-12. Composite Core Component Rods and Assembly Outline 10/1/94 4-13. Burnable Poison Rod (Pyrex) Cross Section 10/lN4 4-14. Deleted Per 1994 Update 10/1/91 4-15. Secondary Source Assembly 10/1/91 4-16. Thimble Plug Assembly 5/2/97 4-17. Fuel Loading Arrangement j
5/2/97 4-18. Fuel Loading Arrangement
)
10/1/91 4-19. Production and Consumption of Higher Isotopes 10/24/98 4-20. Boron Concentration Versus Typical Cycle Burnup With and Without Burnable Poison Rods 5/2/97 4-21. Typical Burnable Poison Rod Arrangement Within An Assembly 5/2/97 4-22. Typical Burnable Poison Loading Pattern 5/2/97 4-23. Typical Burnable Poison Loading Pattern 5/2/97 4 24. Normalized Power Density Distribution Near Beginning-Of-Life, Unrodded Core, Hot Full Power, No Xenon 5/2/97 4-25. Normalized Power Density Distribution Near Beginning-Of-Life, Unrodded Core. Hot Full, Equilibrum Xenon 5/2/97 4-26. Normalized Power Density Distribution Near Beginning-Of-Life, Group D 28% inserted, Hot Full Power, Equilibrum Xenon 5/2/97 4-27. Normalized Power Density Distribution Near Middle-Of-Life, Hot Full Power, Equilibrum Xenon 5/2N7 4-28. Normalized Power Density Distribution Near End-Of-Life, Unrodded Core, Hot Full Power, Equilibrum Xenon 5/2/97 4-29. Normalized Power Density Distribution Near End-Of-Life, Group D 28% Inserted, Hot Full Power, Equilibrum Xenon 10/1/91 4-30. Rodwise Power Distribution in a Typical Assembly (G-9) Near Beginning-Of-Life, Hot Full Power, Equilibrium Xenon, Unrodded Core 10/1/91 4-31. Rodwise Power Distribution in a Typical Assembly (G-9) Near End-Of-Life, Hot Full Power, Equilibrium Xenon, Unrodded j
Core i
10/1/91 4-32. Typical Axial Power Shapes Occurring at Beginning-Of-Life i
10/1/91 4-33. Typical Axial Power Shapes Occurring at Middle.Of-Life j
10/1/91 4-34. Typical Axial Power Shapes Occurring at End-Of Life i
10/1/91 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 10/1/91 4 37. Predicted Power Spike Due To Single Non0attened Gap in Adjacent Fuel 10/1/91 4-38. Power Spike Factor as a Function of Axial Position Page 40 10/24/98
5/2/97 4 39. Maximum FQX Power Versus Axial Height During Normal Operation 10/1/91 4-40. Peak Linear Power During Control Rod Malfunction Overpower Transient 10/1/91 4-41. Peak Linear Power During Boration/ Dilution Overpower Trans4nts 5/2/97 4-42. Typical Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution 10/1/91 4-43. Comparison of Calcuiated and Measured Axial Shape 10/1/91 4-44. Comparison of Calculated and Measured Peaking Factors, FQX PREL MAX Envelope as a Function of Core Height 10/1/91 4-45. Doppler Temperature Coefficient at BOL and EOL, Cycle 1 10/1/91 4-46. Doppler - Only Power Coefficient - BOL. EOL, Cycle 1 10/1/91 4-47. Doppler - Only Power Defect Coefficient - BOL, EOL, Cycle 1 10/1/91 4-48. Moderator Temperature Coefficient - BOL Cycle 1, No Rods 10/1/91 4-49. Moderator Temperature Coefficient - EOL Cycle 1 10/1/91 4-50. Moderator Temperature Coefficient as a Function of Boron Concentration - BOL Cycle 1, No Rods 10/1/91 4-51. Hot Full Power Temperature Coefficient During Cycle I for the Critical Boron Concentration 10/1/91 4-52. Total Power Coefficient - BOL, EOL, Cycle 1 10/1/91 4 53. Total Power Defect - BOL, EOL, Cycle 1
-10/1/91 4-54. Rod Cluster Control Assembly Pattern 10/1/91 4-55. Accidental Simultaneous Withdrawal of Two Control Banks, EOL, HZP, Banks C and B Moving in the Same Plane 10/24/48 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 10/1/91 4-61. Comparison of Calculated r.nd 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 Assemblics,12-Foot Core 10/1/91 4-64. Improved Thermal Design Procedure 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 10/1/91 4-67. Normalized Radial Flow and Enthalpy Distribution at 4-ft Elevation 10/1/91 4-68. Normalized Radial Flow and EnthalpyDistributionat8-ft Elevation 10/1/91 4-69. Normalized Radial Flow and Enthalpy Distribution at 12 ft Elevation Core Exit 10/1/91 4 70. Void Fraction Versus Themodynamic Quality H Hsat/Hg-Hsat 10/1/91 4-71. Thermal Conductivity of UO2 (Data Corrected to 95% Theoretical l
Density) 11/30/95 4-72. Deleted Per 1995 Update 10/1/92 4-73. Deleted Per 1992 Update 10/1/91 4-74. Distribution ofincore Instrumentation 10/24/98 4-75. Typical 17 X 17 Mark-BW Fuel Assembly with Debris Filter Bottom Nozzle 10/24/98 4-76. Unitt Reactor Coolant System Temperature - Percent Power Map Page 41 10/24/98
11/30/95 4-77. Unit 2 Reactor Coolant System Temperature - Percent Power Map 10/24/98 4-78. Replacement of Secondary Sources Chapter 5 Figures 5/10/97 5-1. Flow Diagram of Reactor Coolant System ( Unit 1 Only )
10/24/98 5-2. Flow Diagram of Reactor Coolant System ( Unit 2 Only )
10/24/98 5-3. Flow Diagram of Reactor Coolant System 5/2/97 5-4. Simplified Schematic of Reactor Vessel Head Vent System 10/1/92 5-5. Flow Diagram of Reactor Coolant System ( Unit i Only )
10/24/98 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/I/91 5-9. Reactor Vessel (Part 2 of 2) 10/1/91 5-10. Reactor Vessel Head View Showing Top-Mounted Control Rod Mechanism Housing Locations and UH1 Head Adaptors 10/1/91 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. Ste un Generator (Unit 1) 10/1/91 5-15. Counter Flow Preheat Steam Generator (Unit 2) 10/24/98 5-16. Flow Diagram of Conventional Chemical Addition System 10/24/98 5-17. Flow Diagram of Residual Heat Removal System 10/24/98 5-18. Flow Diagram of Residual Heat Removal System 10/1/91 5-19. Normal RHR Cooldown 10/1/91 5-20. Single Train Cooldown 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 5/2/97 5-32. Typical Unit i Steam Generator Upper Support 10/24/98 5-33. Flow Diagram of the Reactor Coolant System 10/24/98 5-34. Flow Diagram of the Reactor Coolant System Chapter 6 Figures 10/1/91 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 Page 42 10/24/98 1
l
10/1/91 6-6. Peak Containment Pressure Transient 10/1/91 6-7. Peak Containment Pressure Transient 10/1/91 6-8. Peak Containment Pressure Transient 10/1/91 6-9. Peak Containment Pressure Transient 10/1/91 6-10. Peak Containment Pressure Transient 10/1/91 6-11. Containment Spray Return Drains from Air Return Pit Fans 10/1/91 6-12. Containment Spray Return Drains from Air Return Pit Fans 10/1/91 613. 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 10/1/91 6-20. Peak Containment Temperature Transient for Double Ended Steam Line Breaks 10/1/91 6-21. Peak Containment Superheat Duration Transient j
10/1/91 6-22. Peak Containment Temperature Transient
{
10/1/91 6-23. Typical Upper and Lower Compartment Pressure Transient for Break j
Compartment Having a DEHL Break l
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 10/1/91 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 Page 43 10/24/98
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 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 j
10/1/91 6-73. Reactor Cavity Analysis, Element 42 i
10/1/91 6-74. Reactor Cavity Analysis, Element 43 10/1/91 6-75. Reactor Cavity Analysis, Element 44 3
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 Sir.gle Ended Split Break 10/1/91 6-87. Cold leg Single Ended Split Break j
10/1/91 6-88. Cold Leg Single Ended Split Break 10/1/91 6-89. Comparison of Satan to Henry Fauske j
10/1/91 6-90. Comparison of Satan to Moody Subcooled 10/1/91 6-91. Zaloudek Measured Data Versus Modified Zaloudek Correlation j
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 10/24/98 6-96. Minimum Pressure Analysis 10/1/91 6-97. Minimum Pressure Analysis 10/1/91 6-98. Minimum Pressure Analysis 10/1/91 6-99. Minimum Pressure Analysis 10/1/91 6-100. Minimum Pressure Analysis 10/1/91 6-101. Minimum Pressure Analysis 10/1/91 6-102. Illustration of Choked Flow Characteristics 10/1/92 6-103. Flow Diagram of Containment Air Return Exchange & Hydrogen Skimmer System No Date Available 6-104. Reactor Building Plan at Elev. 565 + 3 Hydrogen Skimmer System Page 44 10/24/98
No Date Available 6-105. Reactor Building Hydrogen Skimmer System 10/1/91 6-106. Contaimnent 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 -
10/24/98 6-109. Flow Diagram of Containment Spray System 10/1/91 6-110. Containment Spray Pump Performance Curve 10/i/91 6-111. Recirculation Sump Screen Assembly 10/1/91 6-112. Containment Piping Penetration Valve Arrangements 10/1/91 6-113. Containment Piping Penetration Valve Arrangements 10/1/91 6-114. Containment Piping Penetration Valve Arrangements 10/24/98 6-115. Containment Piping Penetration Valve Arrangements 10/24/98 6-116. Flow Diagram of Containment Valve Injection Water System 10/1/91 6117. Fuel Transfer Tube 10/1/91 6-118. Model B Electric Hydrogen Recombiner-Cutaway 10/1/91 6-119. Recombiner Control System Schematic 10/1/91 6-120. Flow Diagram of Containment Hydrogen Sample & Purge System 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 10/1/91 6-124. Aluminum Corrosion DBA Environment 10/1/91 6-125. Zine Corrosion in DBA Environment 10/1/91 6-126. Comparison of ANS 5.1 and Westinghouse Decay Energy Values 10/1/91 6-127. Results of Westinghouse Irradiation Tests 10/24/98 6-128. Flow Diagram of Safety Injection System 10/24/98 6-129. Flow Diagram of Safety injection System 10/24/98 6130. Flow Diagram of Safety Injection System 10/24/98 6-131. Flow Diagram of Safety Injection System No Date Available 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 Cceve 10/1/91 6-136. Safety Injection / Residual Heat 7emoval Spem Process Flow Diagram 10/1/91 6-137. Ice Condenser 10/1/91 6-138. Isometric ofIce Condenser 10/1/91 6-139. Floor Structure 10/1/91 6-140. Wear Slab Top Surface A.w 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. LowerInlet Door Assembly 10/1/91 6-155. Details of Lower Inlet Door Showing Hinge, Proportioning Mechanism limit Switches and Seals Page 45 10/24/98-
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 Ixg Break 10/1/91 6-165. DLF Spectra Hot leg Break Force Transient 10/1/91 6-166. Top Deck Test Assembly 10/1/91 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 10/1/91 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 10/1/91 6-175. Ice Condenser RTD Location 10/24/98 6-176. Block Diagram: Ice Condenser Temperature Monitoring System 10/1/91 6-177. Door Monitoring Zones 10/1/91 6-178. Wiring Diagram: "X" Switch 10/1/91 6-179. Wiring Diagram: "Y" Switches Lower Inlet Doors and Personnel Access Doors 10/1/91 6-180. Wiring Diagram: Access Door Switches 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 RadialIce Basket Model 10/1/91 6-188. 48 Foot Beam Mod =1 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 Walt Displacement 10/1/91 6-192. TypicalIce 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 5/2/97 6-199. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses 5/2/97 6-200. CNS-1 Double. Ended LDLOCA Mass and Energy Release Analyses 5/2/97 6-201. CNS-1 Double-Ended LBL,0CA Mass and Energy Release Analyses Page 46 10/24/98
5/2/97 6-202. CNS-1 Double-Ended LBLOCA Mass and Energy Release Analyses I
10/24/98 6-203. Containment Backpressure for ECCS Analysis (Unit 2)
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 - pr.ge 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 10/1/91 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 6 5/2/97 7-2. Instrumentation and Control System Diagrams - Index and Symbols - page 7 5/2/97 7 2. Instrumentation and Control System Diagrams - Index and Symbols - page 8 5/2/97 7-2. 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 10/1/91 7-2. 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. Instrumentation and Control System Diagrams Index and i
Symbols - page 16 10/1/91 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 10/1/93 7-6. Motc>r-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 10/1/91 7-13. Cold Leg Accumulator Isolation Valves Control and Alarm Logic 10/1/94 7-14. Containment Pressure Control System Logic Page 47 10/24/98
10/1/91 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 10/1/91 717. Reactor Coolant System Overpressure Protection System for Low Pressure / Temperature Water Solid Conditions Logic Diagram 10/1/91 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 10/1/91 7 21. Pressurizer Pressure Control System Block Diagram 10/1/91 7-22. Pressurizer Level Control System Block Diagram 10/1/91 7-23. Steam Generator Water Level Control System Block Diagram 10/1/91 7-24. Main Feedwater Pump Speed Control System Block Diagram 10/1/91 7 25. Steam Dump Control System Block Diagram 10/1/91 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 10/1/91 7-30. Boron Concentration Measurement System Linearity Curve Over Normal Plant Operating Range of Boron Concentrations 10/1/91 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 10/24/98 8-1. Onsite Power System 10/1/93 8-2. Duke Transmission System No Date Available 8-3. VACAR Subregion of the Southeastern Electric Reliability Council 10/1/93 8-4. Site Plan of Transmission Lines 10/1/93 8-5. Newport Transmission Line Plan 10/1/93 8-6. Allison Creek Transmission Line Plan 10/1/93 8-7. Roddey Transmission Line Plan 10/1/93 8-8. Clay Hill Transmission Line Plan 10/1/93 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 10/1/93 8-14. Stability Analysis Diagram I
10/1/93 8-15. Stability Analysis Swing Curve-Case A 10/1/93 8-16. Stability Analysis Swing Curve-Case B 10/1/93 8-17. Stability Analysis Swing Curve-Case C j
10/1/93 8-18. Frequency Decay Rate Case D
~
10/1/93 8-19. Non-Class 1E AC Power Systems 5/2/97 8-20.13.8KV Normal Auxiliary Power System and 600 VAC Cooling Tower Auxiliary Power System 10/24/98 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 10/1/93 8-24.125 VDC and 120 VAC Vital Instrumentation and Control Power System 5/2/97 8-25.125 VDC Vital Instrumentation and Control Battery Duty Cycle Page 48 10/24/98
5/2/97 8-26.125 VDC Diesel Essential Auxiliary Power System 10/1/93 8-27.125 VDC Diesel Auxiliary Power Battery Duty Cycle 10/1/93 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 10/1/91 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 10/1/91 9-8. Spacer for Spent Fuel Storage 10/1/91 9-9. Spent Fuel Pool Racks - General Arrangement 10/1/91 9-10. Spent Fuel Pool Racks - Details 5/10/97 9-11. Flow Diagram of Spent Fuel Cooling System 10/24/98 9-12. Flow Diagram of Spent Fuel Cooling System j
10/24/98 9-13. Spent Fuel Pool Temperature Versus Time
{
5/2/97 9-14. Refueling Machine 10/1/91 9-15. Fuelliandling Machine 10/1/91 9-16. New Fuel Elevator 10/1/91 9-17. Fuel Transfer System 5/2/97 9-18. Rod Control Cluster Changing Fixture (Deleted per 1997 Update) 10/1/91 9-19. Reactor Vessel Head Lifting Device 10/1/91 9-20. Reactor Internals Lifting Device j
10/1/91 9-21. Reactor Vessel Stud Tensioner 10/24/98 9-22. Flow Diagram of Nuclear Service Water System 10/24/98 9-23. Flow Diagram of Nuclear Service Water System 10/24/98 9 24. Flow Diagram of Nuclear Service Water System 10/24/98 9-25. Flow Diagram of Nuclear Service Water System 10/24/98 9-26. Flow Diagram of Nuclear Service Water System 10/24/98 9-27. Flow Diagram of Nuclear Service Water System 10/24/98 9-28. Flow Diagram of Nuclear Service Water System 10/1/92 9-29. Flow Diagram of Nuclear Service Water System 10/24/98 9-30. Flow Diagram of Nuclear Service Water System 10/24/98 9-31. Flow Diagram of Nuclear Service Water System 5/10/97 9-32. Flow Diagram of Nuclear Service Water System No Date Available 9-33. Flow Diagram of Nuclear Service Water System i
10/1/91 9-34. Nuclear Service Water System Yard Layout 12/31/95 9-35. Fiow Diagram of Component Cooling System 10/24/98 9-36. Flow Diagram of Component Cooling System 10/1/92 9 37. Flow Diagram of Ccmponent Cooling System 10/24/98 9-38. Flow Diagram of Component Cooling System 10/24/98 9-39. Flow Diagram of Component Cooling System 10/24/98 9-40. Flow Diagram of Component Cooling System 10/1/93 9-41. Flow Diagram of Component Cooling System 10/24/98 942. Flow Diagram of Component Cooling System 10/24/98 9-43. Flow Diagram of Component Cooling System 10/24/98 9-44. Flow Diagram of Makeup Demineralized Water System 10/24/98 9-45. Flow Diagram of Makeup Demineralized Water System 10/24/98 9-46. Flow Diagram of Makeup Demineralized Water System 10/24/98 9-47. Flow Diagram of Makeup Demineralized Water System 10/24/98 9-48. Flow Diagram of Makeup Demineralized Water System 10/24/98 9-49. Flow Diagram of Makeup Demineralized Water System Page 49 10/24/98 l
5/10/97 9-50. Flow Diagram of Filtered Water System 10/24/98 9-51. Flow Diagram of Filtered Water System 10/24/98 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/IS4 9-55. Deleted Per 1994 Update 10/1/94 9-56. Deleted Per 1994 Update 10/24/98 9-57. Total Heat Rejected to Standby Nuclear Service Water Pond 10/24/98 9-58. Residual Decay Heat 10/24/98 9-59. Flow Diagram of Condensate Storage System 10/1/92 9-60. Flow Diagram of Condensate Storage System 10/24/98 9-61. Flow Diagram of Condensate Storage System 10/24/98 9-62. Flow Diagram of Refueling Water System 10/24/98 9-63. Flow Diagram of Conventional LPSW System 10/24/98 9-64. Flow Diagram of Conventional LPSW System 10/24/98 9-65. Flow Diagram of Conventional LPSW System 10/24/98 9-66. Flow Diagram of Conventional LPSW System 5/10/97 9-67. Flow Diagram of Conventional LPSW System 10/24/98 9-68. Flow Diagram of Conventional LPSW System 10/24/98 9-69. Flow Diagram of Conventional LPSW System 10/24/98 9-70. Flow Diagram ofInstrument Air System 10/24/98 9-71. Flow Diagram ofInstrument Air System 10/24/98 9-72. Flow Diagram ofInstrument Air System 10/24/98 9-73. Flow Diagram of Station Air System No Date Available 9-74. Flow Diagram of Station Air System 10/24/98-9-75. Flow Diagram of Breathing Air System 10/24/98 9-76. Flow Diagram of Breathing Air System 10/24/98 9-77. Flow Diagram of Breathing Air System 10/24/98 9-78. Flow Diagram of Nuclear Sampling System 10/24/98 9-79. Flow Diagram of Nuclear Sampling System 10/24/98 9-80. Flow Diagram of Nuclear Sampling System 10/24/98 9-81. Flow Diagram of Nuclear Sampling System 10/24/98 9-82. Flow Diagram cf Nuclear Sampling System
. No Date Available 9-83. Flow Diagram of Conventional Sampling System 10/24/98 9-84. Flow Diagram of Conventional Sampling System 10/24/98 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 10/1/93 9-88. Post-Accident Liquid Sampling System Schematic 10/24/98 9-89. Flow Diagram of Chemical and Volume Control System 10/24/98 9-90. Flow Diagram of Chemical and Volume Control System 10/24/98 9-91. Flow Diagram of Chemical and Volume Control System 10/1/94 9-92. Flow Diagram of Chemical and Volume Control System 10/24/98 9-93. Flow Diagram of Chemical and Volume Control System 10/24/98 9-94. Flow Diagram of Chemical and Volume Control System 10/24/98 9-95. Flow Diagram of Chemical and Volume Control System 10/24/98 9-96. Flow Diagram of Chemical and Volurne Control System No Date Available 9-97. Flow Diagram of Chemical and Volume Control System 10/24/98 9-98. Flow Diagram of Boron Recycle System 10/24/98 9-99. Flow Diagram of Boron Recycle System 10/1/92 9-100. Flow Diagram of Boron Recycle System 10/24/98 9-101. Flow Diagram of Boron Recycle System 1/2/96 9-102. Flow Diagram of Boren Recycle System 10/24/98' 9-103. Flow Diagram of Boron Recycle System 10/1/92 9-104. Flow Diagram of Boron Recycle System Page 50 10/24/98
g 10/1/92 9-105. Flow Diagram of Boron Recycle System 10/24/98 9-106. Flow Diagram of Boron Thermal Regeneration System 12/31/95 9-107. Flow Diagram of Boron Thermal Regeneration System 10/24/98 9-108. Flow Diagram of Control Room Area Ventilation System 10/24/98 9-109. Flow Diagram of Control Room Area Ventilation System 10/24N8 9-110. Flow Diagram of Control Room Area Ventilation System 10/24/98 9-111. Flow Diagram of Battery Room Area Ventilation System EL 554' + 0' 10/24/98 9-112. Flow Diagram of Control Area Chilled Water System 10/24/98 9-113. Flow Diagram of Control Area Chilled Water System 10/24/98 9-114. Flow Diagram of Control Area Chilled Water System 10/24/98 9-115. Flow Diagram of Control Area Chilled Water System 10/24/98 9-116. Flow Diagram of Control Area Chilled Water System 10/24/98 9-117. Flow Diagram of Control A.ea Chilled Water System 10/24/98 9-118. Flow Diagram of Fuel Handling Ventilation System 10/24/98 9-119. Flow Diagram of Fuel Handling Ventilation System 5/10/97 9-120. Flow Diagram of Unit i Vent Stack 10/24/98 9-121. Flow Diagram of Auxiliary Building Ventilation System 10/24/98 9-122. Flow Diagram of Auxiliary Building Ventilation System 10/24/98 9-123. Flow Diagram of Auxiliary Building Ventilation System 10/24/98 9-124. Flow Diagram of Auxiliary Building Ventilation System 1
10/24/98 9-125. Flow Diagram of Auxiliary Building Ventilation System i
10/1/91 9-126. Auxiliary Shutdown Panel Air Conditioning System 10/INI 9-127; Auxiliary Shutdown Panel Air Conditioning System 10/24/98 9-128. Flow Diagram of Diesel Building Ventilation System 10/24N8 9-129. Flow Diagram of Containment Purge System No Date Available 9-130. Flow Diagram of Containment Purge System 10/24/98 9-131. Flow Diagram of Containment Ventilation System No Date Available 9-132. Flow Diagram of Turbine Buildiag Ventilation System No Date Available 9-133. Flow Diagram of Turbine Building Ventilation System 5/10/97 9-134. Flow Diagram of Nuclear Service Water Pump Structure Ventilation System 10/24/98 9-135. Flow Diagram of Annulus Ventilation System 10/24/98 9-136. Flow Diagram of Exterior Fire Protection System 10/1/92 9-137. Flow Diagram of Exterior Fire Protection System 10/24/98 9-138. Flow Diagram ofInterior Fire Protection System 10/24/98 9-139. Flow Diagram ofInterior Fire Protection System 10/24/98 140. Flow Diagram ofInterior Fire Protection System
)
10/24/98 9-141. Flow Diagram ofInterior Fire Protection System 10/24/98 9-142. Flow Diagram of Fire Protection System 10/1/92 9-143. Flow Diagram ofInterior Fire Protection System 10/24N8 9-144. Flow Diagram ofInterior 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 10/1N1 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 10/1/91 9-152. Deleted Per 1990 Update 10/1/91 9153. 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/l!91 9-157. Deleted Per 1990 Update Page 51 10/24/98 i
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 5/10/97 9-169. Flow Diagram of Diesel Generator Engine Fuel Oil System 5/10/97 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 Na Date Available 9-173. Diesel Generator Building Plan @ Elevation 556+0 No Date Availai'le 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. I'iesel 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 No Date Available 9-181. HVAC Diesel Generator Rooms 10/24/98 9-182. Flow Diagram of Diesel Generator Engine Cooling Water System 10/24/98 9-183. Flow Diagram of Diesel Generator Engine Starting Air S stem 3
10/24/98 9-184. Flow Diagram of Diesel Generator Engine Starting Air System 10/24/98 9-185. Flow Diagram of Diesel Generator Engine Lube Oil System 10/24/98 9-186. Row Diagram of Diesel Generator Engine Lube Oil System 10/24/98 9-187. Flow Diagram of Diesel Generator Engine Lube Oil System No Date Available 9-188. Flow Diagram of Diesel Generator Engine Air Intake and Exhaust System No Date Available 9-189. Diesel Generator Area Unit 1 General Arrangement No Date Avr.ilable 9-190. Diesel Generator Area Unit i General Arrangement No Date Available 9-191. Diesel Generator Area Unit 1 General Arrangement No Date Available 9-192. Diesel Generator Rooms HVAC 10/1/92 9-193. Flow Diagram of Diesel Generator Room Sump Pump System 10/1/92 9-194. Flow Diagram of Containment Air Release and Addition System 12/31/95 9-195. Flow Diagram of Groundwater System 10/1/92 9-196. Flow Diagram of Groundwater System 5/10/97 9-197. Flow Diagram of the Makeup Demineralized Water System 5/10/97 9-198. Flow Diagram of the Makeup Demineralized Water System 5/10/97 9-199. Flow Diagram of the Makeup Demineralized Water System 10/24/98 9-200. Flow Diagram of the Boron Recycle System 10/24/98 9-201. Flow Diagram of the Nuclear Sampling System 10/24/98 9-202. How Diagram of the Nuclear Sampling System 10/24/98 9-203. Flow Diagram of the Nuclear Sampling System 10/24/98 9-204. Flow Diagram of the Component Cooling System 10/24/98 9-205. Flow Diagram of the Component Cooling System 10/24/98 9-206. Flow Diagram of the Component Cooling System 10/24/98 9-207. Flow Diagram of the Component Cooling System 10/24/98 9-208. Flow Diagram of the Nuclear Service Water System 10/24/98 9-209. Flow Diagram of the Nuclear Service Water System 10/24/98 9-210. How Diagram of the Nuclear Service Water System 10/24/98 9-211. Flow Diagram of the Containment Ventilation System Page 52 10/24/98
10/24N8 9-212. Flow Diagram of the Auxiliary Buildmg Ventilation System 10/24/98 9-213. Flow Diagram of the Auxiliary Building Ventilation System 10/24/98 9-214. Flow Diagram of the Auxiliary Building Ventilation System 10/24/98 9-215. How Diagram of the Auxiliary Building Ventilation System 10/24/98 9-216. Flow Diagram of the Auxiliary Building Ventilation System 10/24N8 9 217. How Diagram of the Auxiliary Building Ventilation System 10/24/98 9-220. Flow Diagrsm of the Fire Protection System 10/24/98 9-221. Flow Diagram of the Fire Protection System 10/24/98 9-222. Flow Diagram of the Interior Fire Protection System 10/24N8 9-223. Flow Diagram of the Makeup Demineralized Water System 10/24/98 9-224. Flow Diagrarn of the Makeup Demineralized Water System 10/24/98 9-225. Flow Diagram of the Makeup Demineralind Water System 10/24/98 9-226. Flow Diagram of the Instrument Air System 10/24/98 9-227. Flow Diagram of the Instrument Air System 10/24/98 9-228. Flow Diagram of the Instrument Air System 10/24N8 9-229. Flow Diagram of the Instrument Air System 10/24/98 9-230. Flow Diagram of the Instrument Air System 10/24/98 9-231. Flow Diagram of the Instrument Air System 10/24/98 9-232. Flow Diagram of the Instrument Air System 10/24/98 9-233. Flow Diagram of the 10/24/98 9-234. Flow Diagram of the Instrument Air System 10/24/98 9-235. Flow Diagram of the Instrument Air System 10/24/98 9-236. Flow Diagram of the Instrument Air System 10/24/98 9-237. How Diagram of the Instrument Air System 10/24/08 9-238. Flow Diagram of the Instrument Air System 10/24N8 9-239. Flow Diagram of the Instrument Air System 10/24/98 9-240. Flow Diagram of the Instrument Air System 10/24/98 9-241. Flow Diagram of the Instrument Air System 10/24/98 9 242. Flow Diagram of the Instrument Air System 10/24/98 9-243. Flow Diagram of the Instrument Air System 10/24/98 9-244. Flow Diagram of the Instrument Air System 10/24N8 9-245. Flow Diagram of the Instrument Air System 10/24/98 9-246. Flow Diagram of the Instrument Air System 10/24/98 9-247. Flow Diagram of the Instrument Air System 10/24/98 9-248. Flow Diagram of ti.e Station Air System 10/24/98 9-249. How Diagram of the Conventional Sampling System 10/24/98 9-250. Flow Diagram of the Station Air System 10/24/98 9-251. Flow Diagram of the Station Air System 10/24/98 9-252. How Diagram of the Station Air System 10/24/98 9-253. Flow Diagram of the Station Air System 10/24/98 9-254. How Diagram of the Station Air System 10/24/98 9-255. Row Diagram of the Turbine Building Ventilation System 10/24/98 9-256. Flow Diagram of the Turbine Building Ventilation System 10/24/98 9-257. Flow Diagram of the Turbine Building Ventilation System 10/24/98 9-258. Flow Diagram of the Turbine Building Ventilation System 10/24N8 9-259. Flow Diagram of the Turbine Building Ventilation System 10/24/98 9-260. Flow Diagram of the Conventional Sampling System 10/24/98 9-261. Flow Diagram of the Conventional Sampling System 10/24/98 9-262. Flow Diagram of the Conventional Sampling System 10/24/98 9-263. Flow Diagram of the Conventional Sampling System 10/24/98 9-264. Flow Diagram of the Boron Recycle System i
Page 53 10/24/98
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)
No Date Available 10-4. Block Diagram of Control System 10/24/98 10-5. Flow Diagram of Main Steam System-Main Steam Vent to ATMOS 5/10/97 10-6. Flow Diagram of Main Steam to Auxiliary Equipment - Main Steam Bypass to Condenser 10/24/98 10-7. Flow Diagram of FDWP Turbine Exhaust 10/24/98 10-8. Flow Diagram of Main Steam System 5/10/97 10-9. Flow Diagram of Steam Supply to FWP Turbine System 10/24/98 10-10. Flow Diagram of Steam Supply to FWP Turbine System 5/10/97 10-11. Flow Diagram of Main Steam System - Main Steam to Atmosphere System 10/24/98 10-12. Flow Diagram of Main Steam System 10/24/98 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 10/24/98 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 10/24/98 10-18. Flow Diagram of Condensate System 10/24/98 10-19. Flow Diagram of Condensate System No Date Available 10-20. Flow Diagram of Condensate System 10/1/94 10-21. Flow Diagram of Condensate System 10/24/98 10-22. Flow Diagram of Condensate System 10/24/98 10-23. Flow Diagram of Condensate System 10/24/98 10-24. Flow Diagram of Condensate System j
10/24/98 10-25. Flow Diagram of Condensate System 10/24/98 10-26. Flow Diagram of Condensate System 10/24/98 10-27. Flow Diagram of Feedwater System 10/24/98 10-28. Flow Diagram of Feedwater System 10/24/98 10-29. Flow Diagram of Steam Generator Blowdown System 5/10/97 10-30. Flow Diagram of Steam Generator Blowdown System 10/24/98 10-31. Flow Diavam of Steam Generator Blowdown System 5/10/97 10-32. Flow Diagram of Steam Generator Blowdown System 10/24/98 10-33. Flow Diagram of Auxiliary Feedwater System 10/24/98 10-34. Flow Diagram of Auxiliary Feedwater System 10/24/98 10-35. Flow Diagram of Heater Drain System (HW) 10/24/98 10-36. Flow Diagram of Heater Drain System (HW) 10/24/98 10-37. Flow Diagram of Moisture Separator Reheater Drain System (HS) 10/24/98 10-38. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 10/24/98 10-39. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 10/24/98 10-40. Flow Diagram of Moisture Separator-Reheater Drain System (HS) 10/1/91 10-41. System Overview of Control Room System Chapter 11 Figures 5/10/97 11-1. Liquid Radwaste System i
10/24/98 11-2. Liquid Radwaste System Page 54 10/24/98
{
10/24/98 11-3. Flow Diagram of Liquid Radwaste System 10/24/98 11-4. Flow Diagram of Liquid Radwaste System 10/24/98 11-5. Flow Diagram of Liquid Radwaste System 1/2196 11-6. Flow Diagram of Liquid Radwaste System 10/24/98 11-7. Flow Diagram of Liquid Radwaste System 10/1/92 11-8. Flow Diagram of Liquid Radwaste System 10/24/98 Il-9. Flow Diagram of Liquid Radwaste System I
10/24/98 11-10. Flow Diagram of Liquid Radwaste System 10/24/98 11-11. Flow Diagram of Liquid Radwaste System 10/24/98 11-12. Flow Diegram of Liquid Radwaste System 10/24/98 11-13. Flow Diagram of Liquid Radwaste System 10/24/98 11-14. Flow Diagram of Liquid Radwaste System 10/24/98 11-15. Flow Diagram of Liquid Radwaste System No Date Available 11-16. Flow Diagram of Liquid Radwaste System 10/24/98 11-17. Flow Diagram of Liquid Radwaste System 10/24/98 11-18. Flow Diagram of Liquid Radwaste System 10/24/98 11-19. Flow Diagram of Liquid Radwaste System 10/24/98 11-20. Flow Diagram of Liquid Radwaste System 10/1/93 11-21. Fic,w Diagram of Liquid Radwaste System 10/24/98 11-22. Flow Diagram of Liquid Radwaste System 10/24/98 11-23. Flow Dierram of Liquid Radwaste System 10/24/98 11-24. Flow Diagram of Liquid Radwaste System 10/24/98 11-25. Flow Diagram of Waste Gas System 10/24/98 1126. Flow Diagram of Waste Gas System 10/24/98 11-27. Flow Diagram of Waste Gas System 10/24/98 11-28. Flow Diagram of Waste Gas System No Date Available 11-29. Flow Diagram of Waste Gas System 10/24/98 1130. Flow Diagram of Solid Radwaste System No Date Available Il-31. Flow Diagram of Solid Radwaste System No Date Available Il 32. Flow Diagram of Solid Radwaste System 12/31/95 11-33. Flow Diagram of Solid Radwaste System No Date Available 11-34. Flow Diagram of Solid Radwaste System 10/1/92 11-35. Flow Diagre.m of Solid Radwaste System No Date Available Il-36. Waste Solidification Facility Interim General Arrangement 10/24/98 1137. Flow Diagram of Liquid Waste Recycle System No Date Available 11-38. Flow Diagram of Liquid Waste Recycle System 10/24/98 11-39. Flow Diagram of Liquid Waste Recycle System 10/24/98 11-40. Flow Diagram of Liquid Waste Recycle System 10/24/98 11-41. Flow Diagram of Liquid Waste Recycle System 10/24/98 11-42. Flow Diagram of Liquid Waste Recycle System 10/24/98 Il-43. Flow Diagram of Liquid Waste Recycle 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 i Elevation 594 + 10 3/4 l
10/1/91 12-5. Containment and Reactor Building - Unit I at Operating Floor l
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 i Elevation 669 + 5 I
Page 55 10/24/98
10/1/91 12-8. Containment and Reactor Building Sections 10/1/91 12-9. Auxiliary Building Unit I and 2 Elevation 522 + 0 10/1/91 12-10. Auxiliary Building Unit I and 2 Elevation 522 + 0 10/1/91 12-11. Auxiliary Building Unit I and 2 Elevation 543 + 0 10/1/91 12-12. Auxiliary Building Unit 1 and 2 Elevation 543 + 0 10/1/91 12-13. Auxiliary Building Unit I and 2 Elevation 543 + 0 10/1/91 12-14. Auxiliary Building Unit 1 and 2 AuxiliaryFeedwaterPump 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 1218. 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 1 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. Aviliary Building Elevation 594 + 0
]
10/1/91 12-28. Auxiliary Building Elevation 594 + 0 Cable Room i
10/1/91 12-29. Primary Shield Neutron Flux Distribution 10/1/91 12 30. Typical Nuclear Safety Related Air Clean-Up System i
Chapter 13 Figures 5/10/97 13-1. Duke Power Corporate Organization 10/1/94 13-2. Power Generation Group Organization 10/24/98 13-3. Nuclear Generation Organization 10/24/98 13-4. Typical Nuclear Site Organization 11/30/95 13-5. Deleted Per 1995 Update 10/1/91 13-6. "At the Controls" Definition Chapter 14 Figures i
10/1/91 141, Major Testing Milestone Schedule i
10/1/91 14-2. Testing Following Initial Fuel Loading Chapter 15 Figures 10/1/92 151. Illustration of Overtemperature and Overpower & Delta. T Protection i
5/2/97 15-2. Minimum Moderator Density Coefficient Used in Analysis (Deleted per 1997 Update) 5/2/97 15-3. Doppler Power Coefficient Used in Accident Analysis (Deleted per 1997 Update) 5/2/97 15-4. RCCA Position Versus Time to Dashpot 10/1/91 15-5. Normalized Rod Worth Versus Percent Inse1ed 10/1/91 15-6. Normalized RCCA Bank Reactivity Worth Versus Nma!ned Drop Time 5/2/97-15-7. Feedwater Control Valve Malfunction Page 56 10/24/98
1 l
5/2/97 15-8. Feedwater Control Valve Malfunction 5/20/97 15-9. Ten Percent Step Load increase, Minimum Reactivity Feedback, Manual Reactor Control 5/2N7 15-10. Ten Percent Step Load increase, Minimum Reactivity Feedback, Manual Reactor Control 5/2/97 15-11. Ten Percent Step Load increase, Maximum Reactivity Feedback, Manual Reactor Control 5/2/97 15-12. Ten Percent Step Load increase, Maximum Reactivity Feedback, Manual Reactor Control 5/2/97 15-13. Ten Percent Step Load Increase, Minimum Reactivity Feedback, Automatic Reactor Control 5/2/97 15-14. Ten Percent Step Load Increase, Minimum Reactivity Feedback, Automatic Reactor Control (Deleted per 1997 Update) 5/2/97 15-15. Ten Percent Step Load increase, Maximum Reactivity Feedback, Automatic Reactor Control (Deleted per 1997 Update) 5/2/97 15-16. Ten Percent Step Load Increase, Maximur Reactivity Feedback, Automatic Reactor Control (Deleted per 19s Update) 5/2/97 15-17. KEFF Versus Temperature 5/2/97 15-18. Failure of a Steam Generator Safety or Dump Valve j
5/2/97 15-19. Failure of a Steam Generator Safety or Dump Valve 5/2/97 15-20. Doppler Power Feedback (Deleted per 1997 Update) 5/2/97 15-21. Steamline Break, Offsite Power Maintained 5/2/97 15-22. Steamline Break, Offsite Power Maintained 5/2/97 15-23. Steamline Break.Offsite Power Maintained 5/2/97 15-24. Steamline Break, Offsite Power Maintained 5/2/97 15-25. Steamline Break, Offsite Power Maintained 5/2/97 15-26. Steamline Break, Offsite Power Maintained 5/2/97 15-27. Excessive Increase in Feedwater Flow 5/2/97 15-28. Turbine Trip, Maximum Secondary Pressure Case 5/2/97 15-29. Turbine Trip, Maximum Secondary Pressure Case 5/2/97 15-30. Turbine Trip, Maximum Secondary Pressure Case 5/2/97 15-31. Turbine Trip, Maximum Secondary Pressure Case 10/1/93 15-32. Turbine Trip, Maximum Secondary Pressure Case 5/2/97 15-33. Turbine Trip, Maximum Primary Pressure Case 5/2/97 15-34. Feedwater System Pipe Break 10/1/91 15-35. Feedwater System Pipe Break 10/1/94 15-36. Loss of Offsite Power 10/1/94 15-37. Loss of Offsite Power 10/1/94 15-38. Loss of Offsite Power 10/1/94 15-39. Loss of Offsite Power 10/1/94 15-40. Loss of Offsite Power 10/24/98 15-41. Part I of 2, Loss of Normal Feedwater 10/24/98 15-41. Part 2 of 2,less of Normal Feedwater 10/24/98 15-42. Part 1 of 2, Loss of Normal Feedwater 10/24/98 15-42. Part 2 of 2,less of Nonnal Feedwater 10/24/98 15-43. Loss of Normal Feedwater
$/2/97 15-44. Loss of Norm-t Feedwater (Deleted per 1997 Update) 5/2/97 15-45. Loss of Normal Feedwater
$/2/97 15-46. Feedwater System Pipe Break 5/2/97 15-47. Feedwater System Pipe Break 5/2/97 15-48. Feedwater System Pipe Break
(
5/2/97 15-49. Feedwater System Pipe Break j
5/2/97 15-50. Feedwater System Pipe Break 5/2/97 15-51. Feedwater System Pipe Break 10/1/92 15-52. Feedwater System Pipe Break l
Page 57 10/24/98 l
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10/1/92 15-53. Deleted Per 1992 Update 10/1/91 15-54. Reserved for Future Use 10/1/92 15-55. Partial Loss of Forced Reactor Coolant Flow 10/1/92 15-56. Partial Loss of Forced Reactor Coolant Flow 10/1/92 15-57. Partial Loss of Forced Reactor Coolant Flow 10/IN2 15-58. Partial Loss of Forced Reactor Coolant Flow 10/IN2 15-59. Partial Loss of Forced Reactor Coolant Flow 10/1/92 15-60. Partial Loss of Forced Reactor Coolant Flow 10/1/92 15-61. Complete Loss of Forced Reactor Coolant Flow 10/IN2 15-62. Complete Loss of Forced Reactor Coolant Flow 10/1/92 15-63. Complete Loss of Forced Reactor Coolant Flow 1(VIN 2 15-64. Complete Loss of Forced Reactor Coolant Flow 10/1/92 15-65. Complete Loss of Forced Reactor Coolant Flow 5/2/97 15-66. Complete Loss of Forced Reactor Coolant Flow 5/2/97 15-67. Locked Rotor 5/2/97 15-68. Bank Withdrawal at IIZF 5/2/97 15-69. Bank Withdrawal at liZP 5/2/97 15-70. Bank Withdrawal at liZP 5/2/97 15-71. Bank Withdrawal at 11ZP 10/1/92 15-72. Bank Withdrawal at liZP 10/1/92 15-73. Bank Withdrawal at liZP 10/1/92 15-74. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/1/92 15-75. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/1/92 15-76. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/1/92 15-77. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/1/92 15-78. Uncontrolled RCCA Bank Withdrawal from 10% Power 10/1/92 15-79. Uncontrolled RCCA Bank Withdrawal from 50% Power 10/1/92 15-80. Uncontrolled RCCA Bank Withdrawal from 100% Power 10/1/92 15-81. Single RCCA Withdrawal (Deleted per 1992 Update) 10/24/98 15-82. Startup of a Reactor Coc,lant Pump at an Incorrect Temperature
'0/24/98 15-83. Startup of a Reactor Coolant Pump at an Incorrect Temperature 10/24/98 15-84. Startup of a Reactor Coolant Pump at an incorrect Temperature 10/24/98 15-85. Startup of a R: actor Coolant Pump at an Incorrect Temperature 10/24/98 15-86. Startup of a Reactor Coolant Pump at an incorrect Temperature 10/1/91 15-87. Improper Startup of an Inactive Reactor Coolant Pump 10/1/91 15-88. Interchange Between Region 1 and Region 3 Assembly 10/1/91 15-89. Interchange Between Region I and Region 2 Assembly. Burnable Poison Rods Being Retained by the Region 2 Assembly 10/1/91 15-90. Interchange Between Region I and Region 2 Assembly Burnable Poison Rod Being Transferred to the Region i Assembly 10/1/91 15-91. Enrichment Error: A Region 2 Assembly Loaded into the Core Central Position 10/1/92 15-92. Loading A Region 2 Assembly into a Region 1 Position Near Core Periphery 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 1992 Update 11/30/95 15-98. Deleted Per 1995 Update 11/30/95 15-99. Deleted Per 1995 Update 5/2/97 15-100. Inadvertent Opening of a Pressurizer Safety Valve 5/2/97 15-101. Inadvertent Opening of a Pressurizer Safety Valve 5/2/97 15-102. Deleted per 1997 Update 10/1/91 15-103. Steam Generator Tube Rupture r
Page 58 10/24/98
10/1/91 15-104. Steam Generator Tube Rupture 10/1/91 15-105. Steam Generator Tube Rupture 10/1/91 15-106. Steam Generator Tube Rupture 10/1/91 15-107. Steam Generator Tube Rupture 10/1/91 15-108. Steam Generator Tube Rupture 5/2/97 15-109. Sequence of Events for Large Break Loss-of-Coolant Analysis 11/30/95 15-110. Deleted Per 1995 Update l
5/2/97 15-111. Code Interface Description for Large Break Model
)
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 i
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 i
10/1/94 15-126. Delet:d 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 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 5/2/97 15-154. Catawba-2 Power Distribution Assumed for Small Break LOCA Analyses 11/30/95 15-155. Deleted Per 1995 Update 10/1/94 15-156. SBLOCA Safety Injection Flowrate VS. Pressure 10/1/94 15-157. RCS Pressure,3" Break 10/1/94 15-158. Core Mixture Height,3" Break Page 59 10/24/98 l
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10/IN4 15-159. Hot Spot Cladding Temperature,3" Break 10/1/94 15-160. RCS Pressure,4" Break 10/1/94 15-161. Core Mixture Height,4" Break 10/1/94 15-162. Hot Spot Cladding Temperature,4" Break 10/1/94 15-163. RCS Pressure,2" Break 10/1/91 15-164. Core Mixture Height,2" Break 10/1/94 15-165. Hot Spot Clad Temperature 2 Inch Cold Leg Break 10/1/94 15-166. Core Steam Flowrate,3" Break 10/1/94 15-167. Core Heat Transfer Coefficient,3" Break 10/1/94 15-168. Hot Spot Fluid Temperature 3" Break i1/30/95 15-169. B&W Large Break Analysis Code Interface 5/2/97 15-170. Catawba - 2 LBLOCA,6.3 ft. Peak, Reactor Vessel Upper Plenum Pressure 5/2/97 15-171. Catawba - 2 LBLOCA,6.3 ft. Peak, Hot Spot Mass Flow Rate 5/2/97 15-172. Catawba - 2 LBLOCA,6.3 ft. Peak, Core Flooding Rate 5/2/97 15-173. Catawba - 2 LBLOCA,6.3 ft. Peak, Hot Channel Quench Front &
Liquid Level 5/2/97 15-174. Catawba - 2 LBLOCA,6.3 ft. Peak, Hot Channel Peak Cladding Temperature 5/2/97 15-175. Catawba - 2 LBLOCA,6.3 ft. Peak, Hot Channel Outlet Temperature 5/2/97 15-176. Catawba - 2 LBLOCA,6.3 ft. Peak, Hot Channel Maximum Local Oxidation 5/2/97 15-177. Catawba - 2 LBLOCA,9.7 ft. Peak, Reactor Vessel Upper Plenum Pressure 5/2/97 15-178. Catawba - 2 LBLOCA,9.7 ft. Peak, Hot Spot Mass Flow Rate 5/2/97 15-179. Catawba - 2 LBLOCA,9.7 ft. Peak, Core Flooding Rate 5/2/97 15-180. Catawba - 2 LBLOCA,9.7 ft. Peak, Hot Channel Quench Front &
Liquid Level 5/2N7 15-181. Catawba-2 LBLOCA,9.7 ft. Peak, Hot Channel Peak Cladding Temperature 11/30/95 15182. Deleted Per 1995 Update 11/30/95 15-183. Deleted Per 1995 Update 11/30/95 15-184. Deleted Per 1995 Update j
11/30/95 15-185. Deleted Per 1995 Update i1/30/95 15-186. Deleted Per 1995 Update 11/30/95 15-187. Deleted Per 1995 Update 5/2N7 15-188. Licensing Summary of FTI LBLOCA Methods Topical Reports 5/2/97 15-189. RELAPS Large Break LOCA Loop Noding 5/2/97 15-190. RELAP5/ BEACH Large Break LOCA Reactor V*ssel Noding 5/2/97 15-191. REFLOD3B Large Break LOCA Model 5/2/97 15-192. Locked Rotor Core Average Heat Flux (Fraction of Nominal) 5/2/97 15-193. Locked Rotor Loop Average Temperature (Deg F) 5/2/97 15-194. Locked Rotor Pressurizer Pressure (psig) 10/1/92 15-195. Locked Rotor RCS Pressure (psig) 5/2/97 15-196. Locked Rotor RCS Neutron Power (% of Nominal)
I 10/1/92 15-197. Dropped Rod Accident 10/1/92 15-198. Dropped Rod Accident I
10/1/92 15-199. Dropped Rod Accident i
10/1/92 15-200. Dropped Rod Accident 5/2/97 15-201. Rod Ejection Accident (BOC, HFP) 5/2/97 15-202. Rod Ejection Accident (BOC, HFP) 5/2/97 15-203. Uncontrolied RCCA Bank Withdrawal at HZP Max. NC Pressure 0
P8 10/1/92 15-204. Uncontrolled RCCA Bank Withdrawal @10% Power Pressure (psia)
Page 60 10/24/98
l 5/2/97 15-205. Steamline Break, Offsite Power Maintained 5/2/97 15-206. Steamline Break, Offsite Power Maintained 5/2/97 15-207. Steamline Break. Offsite Power Maintained 5/2/97 15-208. Steamline Break, Offsite Power Maintained 5/2/97 15-209. Steamline Break. Offsite Power Maintained 5/2/97 15-210. Steamline Break, Offsite Power Lost 5/2/97 15-211. Steamline Break. Offsite Power Lost 5/2/97 15-212. Steamline Break. Offsite Power Lost 5/2/97 15-213. Steamline Break, Offsite Power Lost 5/2/97 15-214. Steamline Break, Offsite Power Lost 5/2/97 15-215. Steamline Break, Offsite Power Lost 5/2/97 15-216. Steamline Break, Offsite Power Lost 5/2/97 15-217. Steamline Break. Offsite Power Lost 5/2/97 15-218. Steamline Break, Offsite Power Lost 5/2/97 15-219. Steamline Brett. Offsite Power Lost 5/2/97 15-220. Steamline Break, Offsite Power Lost 5/2/97 15-221. Deleted per 1997 Update 5/2/97 15-222. FeeJwater System Pipe Break - Unit 1 5/2/97 15-223. Feedwater System Pipe Break - Unit 1 5/2/97 15-224. Feedwater System Pipe Break - Unit 1 5/2/97 15-225. Feedwater System Pipe Break - Unit 1 5/2/97 15-226. Feedwater System Pipe Break - Unit 1 5/2/97 15-227. Feedwater System Pipe Break - Unit 1 5/2/97 15-228. Feedwater System Pipe Break - Unit 1 5/2/97 15-229. Steam Generator Tube Rupture 5/2/97 15-230. Licensing Summary of FTI SBLOCA Methods Topical Reports 5/2/97 15-231. RELAP5 Small Break LOCA Loop Noding 5/2/97 15-232. RELAP5 Small Break LOCA Reactor Vessel Noding 5/2/97 15-233. Catawba - 1 LBLOCA,9.7 ft Peak, Reflooding Rate - Core Entrance Location 5/2/97 15-234. Catawba - 1 LBLOCA,9.7 ft Peak, Hot Channel Quench Front and Collapsed Liquid Level 5/2/97 15-235. Catawba - 1 LBLOCA,9.7 ft Peak, Cladding Temperature 5/2/97 15-236. Catawba - 1 LBLOCA,9.7 ft Peak, Hot Channel Local Oxidation 5/2/97 15-237. Catawba - 1 LBLOCA,9.7 ft Peak, Downcomer Water Level 5/2/97 15-238. Catawba - 1 LBLOCA,9.7 ft Peak, ECCS Flows 5/2/97 15-239. Catawba - 1 LBLOCA,9.7 ft Peak, Hot Channel Fluid Temperaturt.
8.6 ft. Elevation 5/2/97 15-240. Catawba - 1 SBLOCA,2.5 Inch Break, RCS Pressure 5/2/97 15-241. Catawba - 1 SBLOCA,2.5 Inch Break, Break Flow Rate 5/2/97 15-242. Catawba - 1 SBLOCA,2.5 Inch Break, Hot Channel Froth and Collapsed Level 5/2/97 15-243. Catawba - 1 SBLOCA,2.5 Inch Break, Cladding Temperature PCT Location 5/2/97 15-244. Catawba - 1 SBLOCA,2.5 Inch Break, Vapor Temperature at PCT Location 5/2/97 15-245. Catawba - 1 SBLOCA,3 Inch Break, RCA Pressure 5/2/97 15-246. Catawba - 1 SBLOCA,3 Inch Break, Break Flow Rate 5/2/97 15-247. Catawba - 1 SBLOCA,3 Inch Break Hot Channel Froth and Collapsed Level 5/2/97 15-248. Catawba - 1 SBLOCA,3 Inch Break, Cladding Temperature PCT Locatio 5/2/97 15-249. Catawba - 1 SBLOCA,3 Inch Break, Vapor Temperature at PCT Location 5/2/97 15-250. Catawba - 1 Power Distribution Assumed for Small Break LOCA Analyses 5/2/97 15-251. Catawba - 2, LBLOCA,9.7 ft. Peak, Hot Channel Outlet Temperature Page 61 10/24/98
5/2/97 15-252. Catawba - 2. LBLOCA,9.7 ft. Peak, Hot Channel Outlet Maximum Local Oxidation 5/2/97 15 253. Catawba - 2, LBLOCA, Containment Backpressure
- 5/2/97 15-254. RCCA Position Versus Time to Dashpot 5/2/97 15-255. Normalized Rod Worth Versus Percent Inserted 4
5/2/97 15-256. Normalized RCCA Bank Reactivity Worth Versus Normalized Drop Time 1
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