ML13196A255

Updated Final Safety Analysis Report (UFSAR) 2012 Revision

ML13196A255
Person / Time
Site:	Oconee
Issue date:	07/01/2013
From:	Batson S L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13196A255 (44)

Text

~ENERGYe Scott L. Batson Vice President Oconee Nuclear Station 10 CFR 50.71(e) and 10 CFR 50.4(b)(6)

Duke Energy QNOIVP 1 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3274 F 864.873. 4208 Scott.Batson@duke-energy.com July 1, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 Updated Final Safety Analysis Report (UFSAR)2012 Revision Pursuant to 10 CFR 50.71 (e) and 10 CFR 50.4(b)(6), enclosed is a copy of the 2012 revision of the Updated Final Safety Analysis Report (UFSAR) for Oconee Nuclear Station. The effective date of the revision is December 31, 2012.The first part of the enclosure provides instructions for inserting this revision into the existing manuals including a list of effective pages required by 10 CFR 50.71(e).

Changes made in this revision are indicated by a change bar in the margin of the changed page. The attachment provides a list which summarizes information removed from the UFSAR in this revision.

The attachment complies with Regulatory Guide 1.181 (NEI 98-03 Revision 1).Several changes to the summaries of aging management programs credited for license renewal contained in Chapter 18 are included in this 2012 revision.

As required by 10 CFR 54.37(b) and with guidance and clarification provided by an NRC license renewal Frequently Asked Questions (FAQ), aging management reviews supporting changes to these programs are being addressed in a separate submittal.

This submittal document contains no regulatory commitments.

If there are any questions, please contact Susan Perry at (864) 873-4370.I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1st day of July, 2013.Sincerely, Scott L. Batson Enclosure and Attachment 053 Ney www.duke-energy.com U. S. Nuclear Regulatory Commission July 1, 2013 Page 2 xc: Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Boska Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2746 Mr. Ed Crowe Senior Resident Inspector Oconee Nuclear Station U. S. Nuclear Regulatory Commission July 1, 2013 Page 3 Bxc (w/attachment):

Bxc (w/o attachment):

ELL -ECO50 ONS Document Management Information Services Regulatory Affairs K. R. Alter T. L. Patterson R. H. Guy S. C. Perry ONS UFSAR UPDATE INSERTION INSTRUCTIONS Submittal Due Date: 6/30/13 Effective Date: 12/31/12 1. Replace List of Effective Pages (LOEP) for Tables and Figures with the 2012 LOEP Update.2. Replace entire text portions (including the Table of Contents, List of Figures, and List of Tables) for each chapter with the updated text portion.3. Update Tables and Figures according to the following instructions.

Note: Tables and Figures from prior year were re-issued in order to remove all revision bars.Chapter 3 Chapter 4 Remove Table 3-68 (7 pgs)Table 4-3 (2 pgs)Table 4-4 Table 4-6 Table 4-9 Table 4-10 Table 4-11 Table 4-20 Figure 4-5 Figure 4-6 Table 5-16 Table 6-7 (7 pgs)Table 6-25 Table 6-26 (2 pgs)Table 7-1 Table 7-2 Table 7-3 Table 7-4 Insert Table 3-68 (8 pgs)Table 4-3 (2 pgs)Table 4-4 Table 4-6 Table 4-9 Table 4-10 Table 4-11 Table 4-20 Figure 4-5 Figure 4-6 Table 5-16 Table 6-7 (7 pgs)Table 6-25 Table 6-26 (2 pgs)Table 7-1 Table 7-2 Table 7-3 Table 7-4 Chapter 5 Chapter 6 Chapter 7 Figure 7-1 (11 x 17)(1 pg)Figure 7-4 (11 x 17) (1 pg)Figure 7-5 (11 x 17) (1 pg)Figure 7-6 (11 x 17) (1 pg)Figure 7-8 Figure 7-9 Figure 7-10 Figure 8-4 (11 x 17) (3 pgs)Figure 8-5 (11 x 17) (1 pg)Table 9-6 Table 9-16 Figure 9-24 (11 x 17) (lpg)Figure 7-1 (11 x 17 Sht. I of 16 only) (16 pgs)Figure 7-4 (11 x 17) (1 pg)Figure 7-5 (11 x 17 Sht. I of 8 only) (8 pgs)Figure 7-6 (11 x 17) (1 pg)Figure 7-8 Figure 7-9 Figure 7-10 Figure 8-4 (11 x 17) (3 pgs)Figure 8-5 (11 x 17) (1 pg)Table 9-6 Table 9-16 Figure 9-24 (11 x 17) (1 pg)Chapter 8 Chapter 9 Chapter 11 Table 11-6 (7 pgs)Table 11-6 (7 pgs)Page 1 of2 ONS UFSAR UPDATE INSERTION INSTRUCTIONS Submittal Due Date: 6/30/13 Effective Date: 12/31/12 Insert Remove Chapter 13 Chapter 15 Chapter 18 Figure 13-1 Figure 13-3 Figure 13-4 Figure 13-7 Table 15-2 (2 pgs)Table 15-15 (4 pgs)Table 15-16 (2 pgs)Table 15-32 (2 pgs)Table 15-33 Table 15-34 (8 pgs)Table 15-35 (2pgs)Table 15-47 Table 15-60 Table 15-62 (2pgs)Table 15-63 (2pgs)Table 15-64 Figure 15-141 Figure 15-150 Figure 15-151 Figure 15-152 Figure 15-153 Figure 15-154 Figure 15-155 Figure 15-156 Figure 15-170 Figure 15-219 Figure 15-220 Figure 15-221 Figure 15-222 Figure 15-223 Figure 15-224 Figure 15-225 Figure 15-226 Figure 15-227 Figure 15-228 Figure 15-229 Figure 15-230 Figure 15-231 Figure 15-232 Table 18-1 (3pgs)Figure 13-1 Figure 13-3 Figure 13-4 Figure 13-7 (deleted pg)Figure 13-8 (new)Tab 15.18 Table 15-2 (2 pgs)Table 15-15 (4 pgs)Table 15-16 (2 pgs)Table 15-32 (2 pgs)Table 15-33 Table 15-34 (8 pgs)Table 15-35 (2 pgs)Table 15-47 Table 15-60 Table 15-62 (2 pgs)Table 15-63 (2pgs)Table 15-64 Table 15-65 (new)Table 15-66 (new)Figure 15-141 Figure 15-150 Figure 15-151 Figure 15-152 Figure 15-153 Figure 15-154 Figure 15-155 Figure 15-156 Figure 15-170 Figure 15-219 Figure 15-220 Figure 15-221 Figure 15-222 Figure 15-223 Figure 15-224 Figure 15-225 Figure 15-226 Figure 15-227 Figure 15-228 Figure 15-229 Figure 15-230 Figure 15-231 Figure 15-232 Table 18-1 (4 pgs)Page 2 of 2 OCONEE UFSAR -2012 UPDATE List of Effective Pages (LOEP) for Tables The purpose of this list is to assure that the pages in the Tables section of your manual match the most recent issue, as well as to show a full accounting of all tables, including those that have been deleted.The earliest effective date, 12/31/00, was used when all tables were re-issued.

Effective Table Table Title Date No.Chapter 1 12/31/00 1-1 Key Dates in Oconee History 12/31/00 1-2 Engineered Safeguards Equipment 1-3 Deleted Per 1997 Update Chapter 2 12/31/00 2-1 1970 Population Distribution 0-10 Miles 12/31/00 2-2 2010 Projected Population Distribution 0-10 Miles 12/31/00 2-3 1970 Population Distribution 0-50 Miles 12/31/00 2-4 2010 Projected Population Distribution 0-50 Miles 12/31/00 2-5 1970 Cumulative Population Density 0-50 Miles 12/31/00 2-6 2010 Projected Cumulative Population Density 0-50 Miles 12/31/08 2-7 Frequency of Tropical Cyclones in Georgia, South Carolina and North Carolina Plus Coastal Waters 12/31/08 2-8 Mean Monthly Thunderstorm Days and Thunderstorms for Nuclear Plant Site 12/31/08 2-9 Duration and Frequency (in Hours) of Calm and Near-Calm Winds Average of Three Locations*

(1/59 -12/63)12/31/08 2-10 Annual Surface Wind Rose For Greenville, South Carolina (1/59 -12/63)*12/31/08 2-11 Percent Frequency of Wind Speeds at Various Hours Through the Day -Greenville, S. C. (1/59 -12/63)*12/31/08 2-12 Duration and Frequency of Calm and Near-Calm Winds Average of Three Locations*

(1/59 -12/63)12/31/08 2-13 Percentage Distribution of Athens, Georgia Annual Winds at 0630 Eastern Standard Time (800-1300 Feet Above Ground)12/31/08 2-14 Percentage Distribution of Athens, Georgia Annual Winds at 0630 Eastern Standard Time (2300-2800 Feet Above Ground)12/31/08 2-15 Average Wind Direction Change with Height, Athens, Georgia, by Lapse Rates in the Lowest 50 Meters-Two Years of Record *Effective Date 12/31/12 Page 2 of 37 Effective Table Table Title Date No.12/31/08 2-16 67.5i Sector Wind Direction Persistence Duration (in Hours) Greenville, S. C.WBAS 12/31/08 2-17 112.5i Sector Wind Direction Persistence Duration (in Hours) (Greenville, S. C.WBAS)12/31/08 2-18 Surface Temperature (iF) Clemson, S. C. (68 Years of Record)*12/31/08 2-19 Surface Precipitation (Inches) Clemson, S. C. (71 Years of Record)**12/31/08 2-20 Precipitation

-Wind Statistics

-Greenville, S. C. 1959-1963 (By Precipitation Intensities)*

12/31/08 2-21 Pasquill Stability Categories for Greenville, South Carolina 12/31/08 2-22 Pasquill Stability Category and Supplemental Data for Greenville, S. C.12/31/08 2-23 Average Temperature Difference

('F) at Minimum Temperature Time*12/31/08 2-24 Joint Frequency Distribution of Wind Speed and Wind Direction for each Stability Class, for Greenville-Spartanburg, South Carolina for 1975 (Pages 1-8)12/31/08 2-25 Joint Frequency Distribution of Wind Speed and Wind Direction for each Stability Class, for Greenville-Spartanburg, South Carolina for 1968-1972 (Pages 1-8)12/31/08 2-26 Joint Frequencies of Wind Direction and Speed by Stability Class (March 1970-March 1972 (Pages 1-6)12/31/08 2-27 Joint Frequency Tables of Wind Direction and Speed by Atmospheric Stability

-Low and High Level (January 1975 -December 1975) (Pages 1-14)12/31/08 2-28 Composite Poorest Diffusion Conditions Observed for Each Hour of Day (Based on 30 Months of Data)12/31/08 2-29 Dispersion Factors Used for Accident and Routine Operational Analyses X/Q 12/31/08 2-30 Determining Appropriate Dispersion Factors (Pages 1-2)12/31/08 2-31 Oconee Nuclear Station X/Q at Critical Receptors to 5 Miles* (Depleted by Dry Deposition) (Pages 1-2)12/31/08 2-32 Oconee Nuclear Station D/Q at Critical Receptors to 5 Miles*12/31/08 2-33 Oconee Nuclear Station X/Q at Critical Receptors to 5 Miles* (Non-Depleted)(Pages 1-2)12/31/08 2-34 Relative Concentration, X/Q, Frequency Distribution Without Wind Speed Correction 12/31/08 2-35 Gas-Tracer Experimental Results From January 15 -March 11, 1970 12/31/08 2-36 Relative Concentration, X/Q, Frequency Distribution With Wind Speed Correction 12/31/08 2-37 Comparative Wind Speed Data (Pages 1-2)12/31/08 2-38 Supplemental Data Oconee Meteorological Survey (Tower Data) For Period of June 1, 1968 Thru May 31, 1969 Effective Date 12/31/12 Page 3 of 37 Effective Table Table Title Date No.12/31/08 2-39 2-40 2-41 2-42 2-43 12/31/08 2-44 2-45 2-46 2-47 2-48 2-49 2-50 2-51 2-52 2-53 2-54 2-55 2-56 2-57 2-58 2-59 2-60 2-61 2-62 2-63 2-64 2-65 2-66 2-67 2-68 2-69 2-70 2-71 Supplemental Data (Pages 1-4)Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Supplemental Data -SF6 Detector Readings -Test Date: January 28, 1970 Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Deleted Per 2008 Update Effective Date 12/31/12 Page 4 of 37 Effective Table Table Title Date No.2-72 Deleted Per 2008 Update 2-73 Deleted Per 2008 Update 2-74 Deleted Per 2008 Update 2-75 Deleted Per 2008 Update 2-76 Deleted Per 2008 Update 2-77 Deleted Per 2008 Update 2-78 Deleted Per 2008 Update 2-79 Deleted Per 2008 Update 2-80 Deleted Per 2008 Update 2-81 Deleted Per 2008 Update 2-82 Deleted Per 2008 Update 2-83 Deleted Per 2008 Update 2-84 Deleted Per 2008 Update 2-85 Deleted Per 2008 Update 2-86 Deleted Per 2008 Update 2-87 Deleted Per 2008 Update 2-88 Deleted Per 2008 Update 2-89 Deleted Per 2008 Update 2-90 Deleted Per 2008 Update 2-91 Deleted Per 2008 Update 2-92 Deleted Per 2008 Update 12/31/00 2-93 Soil Permeability Test Results 12/31/00 2-94 Significant Earthquakes in the Southeast United States (Intensity V or Greater)(Pages 1-6)12/31/00 2-95 Velocity Measurements 12/31/00 2-96 Core Measurements Chapter 3 12/31/04 3-1 System Piping Classification 12/31/10 3-2 System Component Classification (Pages 1-5)12/31/04 3-3 Summary of Missile Equations 12/31/00 3-4 List of Symbols 12/31/04 3-5 Properties of Missiles -Reactor Vessel & Control Rod Drive Effective Date 12/31/12 Page 5 of 37 Effective Table Table Title Date No.12/31/03 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 3-6 3-7 3-8 3-9 3-10 3-11 3-12 3-13 3-14 12/31/00 3-15 12/31/03 3-16 12/31/00 3-17 12/31/03 3-18 12/31/03 3-19 12/31/03 3-20 12/31/03 3-21 12/31/00 3-22 12/31/09 3-23 12/31/00 3-24 3-25 12/31/00 3-26 3-27 3-28 3-29 3-30 3-31 3-32 3-33 3-34 3-35 3-36 3-37 Properties of Missiles -Steam Generator (Pages 1-2)Properties of Missiles -Pressurizer Properties of Missiles -Quench Tank and Instruments Properties of Missiles -System Piping (Pages 1-2)Missile Characteristics Depth of Penetration of Concrete Containment Coatings (Pages 1-5)Service Load Combinations for Reactor Building Accident, Wind, and Seismic Load Combinations and Factors for Class I Concrete Structures (Pages 1-2)Inward Displacement of Liner Plate Stress Analysis Results Stress Analysis Results Stress Analysis Results Stress Analysis Results Stress Analysis Results Stress Analysis Results Bent Wire Test Results Auxiliary Building Loads and Conditions MARK BZ Fuel Assembly Seismic and LOCA Results at 600 degrees F Deleted Per 1996 Update Stress Limits for Seismic, Pipe Rupture and Combined Loads Deleted Per 1999 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Effective Date 12/31/12 Page 6 of 37 Effective Table Table Title Date No.3-38 3-39 3-40 3-41 3-42 3-43 3-44 3-45 3-46 3-47 3-48 3-49 3-50 3-51 3-52 3-53 3-54 3-55 3-56 3-57 3-58 3-59 3-60 3-61 3-62 3-63 3-64 3-65 3-66 3-67 12/31/12 3-68 Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2000 Update Deleted Per 2000 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Deleted Per 2004 Update Electrical Equipment Seismic Qualification (Pages 1-8)Chapter 4 Effective Date 12/31/12 Page 7 of 37 Effective Table Table Title Date No.12/31/09 4-1 Core Design, Thermal, and Hydraulic Data (Pages 1-5)12/31/09 4-2 Fuel Assembly Components (Pages 1-2)12/31/12 4-3 Nuclear Design Data (Pages 1-2)12/31/12 4-4 Typical Eighteen Month Fuel Cycle Excess Reactivity, HFP Samarium 12/31/00 4-5 Effective Multiplication Factor 12/31/12 4-6 Shutdown Margin Calculation for Typical Oconee Fuel Cycle 12/31/09 4-7 Moderator Temperature Coefficient (For the First Cycle)12/31/00 4-8 BOL Distributed-Temperature Moderator Coefficients, 100% Power, 1200 ppm Boron (O1CO I)12/31/12 4-9 BOL Distributed-Temperature Moderator Coefficients, vs. Power, No Xenon 12/31/12 4-10 BOL Distributed-Temperature Moderator Coefficient, 100% Full Power 12/31/12 4-11 Power Coefficients of Reactivity 12/31/00 4-12 pH Characteristics 12/31/00 4-13 Design Methods 4-14 Deleted Per 1999 Update 4-15 Deleted Per 1997 Update 12/31/00 4-16 Internals Vent Valve Materials 12/31/00 4-17 Vent Valve Shaft & Bushing Clearances 12/31/00 4-18 Control Rod Assembly Data 12/31/00 4-19 Axial Power Shaping Rod Assembly Data 12/31/12 4-20 Burnable Poison Rod Assembly Data 12/31/00 4-21 Control Rod Drive Mechanism Design Data 12/31/05 4-22 Fuel Assembly/APSR Compatibility 12/31/09 4-23 Fuel Assembly Design Descriptions 12/3 1/04 4-24 Design Information for Current Demonstration Programs vs. Typical FAs Chapter 5 12/31/00 5-1 Reactor Coolant System Pressure Settings 12/31/04 5-2 Transient Cycles for RCS Components Except Pressurizer Surge Line (Pages 1-3)12/31/10 5-3 Stress Limits for Seismic, Pipe Rupture, and Combined Loads 12/31/04 5-4 Reactor Coolant System Component Codes 12/31/11 5-5 Materials of Construction (Pages 1-2)12/31/00 5-6 Summary of Primary Plus Secondary Stress Intensity for Components of the Effective Date 12/31/12 Page 8 of 37 Effective Table Table Title Date No.Reactor Vessel 12/31/00 5-7 Summary of Cumulative Fatigue Usage Factors for Components of the Reactor Vessel 12/31/04 5-8 Stresses Due to a Maximum Design Steam Generator Tube Sheet Pressure Differential of 2,500 psi at 6507F 12/31/04 5-9 Ratio of Allowable Stresses to Computed Stresses for a Steam Generator Tube Sheet Pressure Differential of 2,500 psi 12/31/04 5-10 Fabrication Inspections (Pages 1-5)12/31/03 5-11 Reactor Vessel Design Data (Pages 1-2)12/31/03 5-12 Reactor Vessel --Physical Properties (Oconee 1) (Pages 1-2)12/31/03 5-13 Reactor Vessel -- Chemical Properties (Oconee 1)12/31/00 5-14 Reactor Vessel -Physical Properties (Oconee 2 & 3) (Pages 1-2)12/31/04 5-15 Reactor Coolant Flow Distribution with Less than Four Pumps Operating 12/31/11 5-16 Reactor Coolant Pump -Design Data (Oconee 1)12/31/01 5-17 Reactor Coolant Pump -Design Data (Oconee 2, 3) (Data Per Pump)12/31/00 5-18 Reactor Coolant Pump Casings -Code Allowables (Applies to Oconee 2 and 3)(Pages 1-3)5-19 Deleted Per 2000 Update 12/31/04 5-20 Steam Generator Design Data (Data Per Steam Generator) (Pages 1-3)12/31/04 5-21 Reactor Coolant Piping Design Data (Pages 1-2)12/31/06 5-22 Pressurizer Design Data 12/31/00 5-23 Operating Design Transient Cycles for Pressurizer Surge Line (Pages 1-3)12/31/00 5-24 Evaluation of Reactor Vessel Pressurized Thermal Shock Toughness Properties at 48 EFPY -Oconee Unit I (Pages 1-2)12/31/00 5-25 Evaluation of Reactor Vessel Pressurized Thermal Shock Toughness Properties at 48 EFPY -Oconee Unit 2 12/31/00 5-26 Evaluation of Reactor Vessel Pressurized Thermal Shock Toughness Properties at 48 EFPY -Oconee Unit 3 (Pages 1-2)12/31/00 5-27 Evaluation of Reactor Vessel Extended Life (48EFPY) Charpy V-Notch Upper-Shelf Energy -Oconee Unit I (Pages 1-2)12/31/00 5-28 Evaluation of Reactor Vessel Extended Life (48EFPY) Charpy V-Notch Upper-Shelf Energy -Oconee Unit 2 12/31/00 5-29 Evaluation of Reactor Vessel Extended Life (48EFPY) Charpy V-Notch Upper-Shelf Energy -Oconee Unit 3 Chapter 6 Effective Date 12/3 1 /) 2 Page 9 of 37 Effective Table Table Title Date No.6-1 Deleted Per 1995 Update 6-2 Deleted Per 2000 Update 12/31/00 6-3 Quality Control Standards for Engineered Safeguards Systems (Pages 1-2)12/31/04 6-4 Engineered Safeguards Piping Design Conditions (Pages 1-2)12/31/00 6-5 Single Failure Analysis Reactor Building Spray System 12/31/00 6-6 Single Failure Analysis For Reactor Building Cooling System 12/31/12 6-7 Reactor Building Penetration Valve Information (Pages 1-7)12/31/05 6-8 High Pressure Injection System Component Data (Pages 1-2)12/31/09 6-9 Low Pressure Injection System Component Data 12/31/00 6-10 Core Flooding System Components Data 12/31/05 6-1 I Single Failure Analysis -Emergency Core Cooling System (Pages 1-2)12/31/00 6-12 Oconee Nuclear Station Analysis of Valve Motors Which May Become Submerged Following A LOCA 12/31/00 6-13 Equipment Operational During An Accident and Located Outside Containment 12/31/00 6-14 Equipment Operational During an Accident and Located Within the Containment (Pages 1-2)12/31/05 6-15 Emergency Core Cooling Systems Performance Testing 6-16 Deleted Per 1999 Update 6-17 Deleted Per 1999 Update 12/31/00 6-18 Inventory of Iodine Isotopes in Reactor Building (at t = o)12/31/05 6-19 Single Failure Analysis for Reactor Building Penetration Room Ventilation System 12/31/00 6-20 Parameters for Boron Precipitation Analysis 12/31/03 6-21 Summary of Calculated Containment Pressures and Temperatures for LOCA Cases 12/31/06 6-22 Containment Response Analyses Initial Conditions 12/31/00 6-23 Containment Structural Heat Sink Data 12/31/03 6-24 Accident Chronology for Limiting Break for Equipment Qualification 12/31/11 6-25 Minimum Acceptable Combinations of Containment Heat Removal Equipment Performance 12/31/11 6-26 Engineered Safety Feature Assumptions in Containment Response Analyses (Pages 1-2)12/31/08 6-27 Summary of Calculated Containment Pressures and Temperatures for Secondary System Pipe Rupture Cases 12/31/00 6-28 Steam Generator Compartment Pressure Response Flowpath Discharge Effective Date 12/3 1/12 Page 10 of 37 Effective Table Table Title Date No.12/31/03 6-29 12/31/03 6-30 12/31/00 6-31 12/31/03 6-32 12/31/05 6-33 6-34 12/31/03 6-35 Chapter 7 12/31/12 12/31/12 12/31/12 12/31/I1 12/31/06 12/31/05 Chapter 8 12/31/02 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 12/31/00 7-1 7-2 7-3 7-4 7-5 7-6 8-1 8-2 8-3 8-4 8-5 8-6 8-7 Coefficients Peak Pressure Mass and Energy Release Data (Pages 1-15)RELAP5 Long-Term Mass and Energy Release Data (Pages 1-40)BFLOW/FATHOMS Long-Term Mass and Energy Releases (Pages 1-2)Steam Line Break Mass and Energy Releases (Pages 1-5)NPSH Available and Required for LPI and BS Pumps (Limiting Flow Case)Deleted Per 2008 Update ROTSG Peak Pressure Mass and Energy Release Data (Pages 1-18)Reactor Trip Summary Engineered Safeguards Actuation Conditions Engineered Safeguards Actuated Devices Characteristics of Out-of-Core Neutron Detector Assemblies NNI Inputs to Engineered Safeguards (Pages 1-2)ICS Transient Limits Loads to be Supplied from the Emergency Power Source (Pages 1-2)Single Failure Analysis for 125 Volt DC Switching Station Power System (Pages 1-2)Single Failure Analysis for the Keowee Hydro Station Single Failure Analysis for the Emergency Electrical Power Systems Single Failure Analysis for 125 Volt DC Instrumentation and Control Power System (Pages 1-3)Single Failure Analysis for the 120 Volt AC Vital Power System 125 Volt DC Panelboard Fault Analysis Chapter 9 12/31/00 9-1 Spent Fuel Cooling System Data, Units 1, 2 (Pages 1-2)12/31/00 9-2 Spent Fuel Cooling System Data, Oconee 3 (Pages 1-2)12/31/00 9-3 Component Cooling System Performance Data (For Normal Operation on a Per Oconee Basis)12/31/00 9-4 Cooling Water Systems Component Data (Component Data on a Per Unit Basis)Effective Date 12/31/12 Page II of 37 Effective Table Table Title Date No.12/31/06 12/31/11 12/31/05 12/31/00 12/31/09 12/3 1/00 9-5 9-6 9-7 9-8 9-9 9-10 12/31/00 9-11 9-12 12/31/00 9-13 (Pages 1-2)Chemical Addition and Sampling System Component Data (Pages 1-3)High Pressure Injection System Performance Data High Pressure Injection System Component Data (Pages 1-2)Low Pressure Injection System Performance Data Low Pressure Injection System Component Data (Pages 1-2)Coolant Storage System Component Data (Component Quantities for Three Units) (Pages 1-2)Ventilation System Major Component Data (Pages 1-2)Deleted Per 2002 Update Component Cooling System Component Data (Component Data on a per Unit Basis) (Pages 1-2)SSF System Main Components (Pages 1-4)SSF Primary Valves (Pages 1-2)SSF Instrumentation Design Basis Tornado Missiles And Their Impact Velocities Design Basis Tornado Missiles Minimum Barrier Thicknesses Codes and Specifications For Design of Category I Structures 12/31/10 12/31/10 12/31/11 12/31/00 12/31/00 12/31/00 Chapter 10 12/31/00 12/31/09 Chapter I 1 9-14 9-15 9-16 9-17 9-18 9-19 10-1 Condensate/Feedwater Reserves (each unit)10-2 Parameter Indication Location for EFW System 12/31/00 11-1 Estimated Radioactive Waste Quantities from Three Units 12/31/00 11-2 Estimated Maximum Rate of Accumulation Radioactive Wastes per Operation 12/31/00 11-3 Yearly Average Activity Concentrations in the Station Effluent for Three Units, Each Operating with One Percent Defective Fuel 12/31/04 11-4 Escape Rate Coefficients for Fission Product Release 12/31/00 11-5 Reactor Coolant Activity (Pages 1-2)12/31/12 11-6 Waste Disposal System Component Data (Component Quantities for Three Units) (Pages 1-7)12/31/04 11-7 Process Radiation Monitors (Pages 1-4)Chapter 12 Effective Date 12/31/12 Page 12 of 37 Effective Table Table Title Date No.12/31/00 12-1 Parameters Used for Shielding Analyses 12/31/00 12-2 Principal Shielding (Pages 1-2)12/31/04 12-3 Area Radiation Monitors (Pages 1-2)Chapter 13 13-1 Deleted Per 1991 Update 13-2 Deleted Per 1999 Update Chapter 14 12/31/00 14-1 Tests Prior to Initial Fuel Loading 12/31/00 14-2 Postcriticality Tests Chapter 15 12/31/10 15-1 Reg. Guide 1.25 Fuel Handling Accident Source Term 12/31/11 15-2 Rod Ejection Accident Mk-B IOT SIMULATE-3 K Analysis Results (Pages 1-2)15-3 Deleted Per 2008 Update 1-5-4 Deleted Per 2004 Update 12/31/03 15-5 Steam Line Break Accident -With Offsite Power Case Sequence of Events 12/3 1/00 15-6 Summary of LOCA Break Spectrum Break Size and Type 15-7 Deleted Per 1997 Update 15-8 Deleted Per 1995 Update 15-9 Deleted Per 1995 Update 15-10 Deleted Per 1995 Update 15-11 Deleted Per 1995 Update 15-12 Deleted Per 1995 Update 15-13 Deleted Per 1995 Update 15-14 Deleted Per 2004 Update 12/31/12 15-15 Total Core Activity (Oconee 2 Cycle 6 -400 EFPD) (Pages 1-4)12/31/12 15-16 Summary of Transient and Accident Doses Including the Effects of High Burnup Reload Cores with Replacement Steam Generators (Pages 1-2)15-17 Deleted Per 2000 Update 15-18 Deleted Per 2000 Update 15-19 Deleted Per 1995 Update Effective Date 12/31/12 Page 13 of 37 Effective Table Table Title Date No.15-20 Deleted Per 1995 Update 15-21 Deleted Per 1995 Update 15-22 Deleted Per 1995 Update 15-23 Deleted Per 1995 Update 15-24 Deleted Per 1997 Update 15-25 Deleted Per 2001 Update 15-26 Deleted Per 1995 Update 15-27 Deleted Per 2003 Update 12/31/03 15-28 HPI Flow Assumed in Core Flood Line Small Break LOCA Analyses 12/31/03 15-29 HPI Flow Assumed in RCP Discharge Small Break LOCA Analyses 12/31/03 15-30 HPI Flow Assumed in HPI Line Small Break LOCA Analyses 15-31 Deleted Per 2008 Update 12/31/11 15-32 Summary of Transient and Accident Cases Analyzed (Pages 1-2)12/3 I /11 15-33 Methodology Topical Reports and Computer Codes Used in Analyses 12/31/12 15-34 Summary of Input Parameters for Accident Analyses Using Computer Codes (Pages 1-8)12/31/12 15-35 Trip Setpoints and Time Delays Assumed in Accident Analyses (Pages 1-2)12/31/05 15-36 Startup Accident Sequence of Events 122/31/08 15-37 Rod Withdrawal at Power Accident -Peak RCS Pressure Analyses Sequence of Events 12/31/03 15-38 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis Sequence of Events 12/31/08 15-39 Cold Water Accident Sequence of Events 12/31/08 15-40 Loss of Flow Accidents Four RCP Coastdown from Four RCP Initial Conditions Sequence of Events 12/31/03 15-41 Loss of Flow Accidents Two RCP Coastdown from Four RCP Initial Conditions Sequence of Events 12/31/03 15-42 Loss of Flow Accidents One RCP Coastdown from Three RCP Initial Conditions Sequence of Events 12/31/03 15-43 Loss of Flow Accidents Locked Rotor from Four RCP Initial Conditions Sequence of Events 12/31/08 15-44 Loss of Flow Accidents Locked Rotor from Three RCP Initial Conditions Sequence of Events 12/31/10 15-45 Control Rod Misalignment Accidents

-Dropped Rod Accident Sequence of Events 12/31/08 15-46 Turbine Trip Accident Sequence of Events Effective Date 12/31/12 Page 14 of 37 Effective Table Table Title Date No.12/31 /11 15-47 Steam Generator Tube Rupture Accident Sequence of Events 12/31/03 15-48 Steam Line Break Accident -Without Offsite Power Case Sequence of Events 12/31/08 15-49 Small Steam Line Break accident Sequence of Events 12/31/09 15-50 Iodine and Noble Gas Inventory in Reactor Core and Fuel Rod Gaps (Pages 1-2)12/31/09 15-51 Reactor Coolant System Fission Product Source Activities

-500 EPFD Equilibrium Cycle [1]15-52 Deleted per 2003 Update 15-53 Deleted per 2003 Update 15-54 Deleted per 2003 Update 15-55 Deleted per 2003 Update 12/31/03 15-56 Results of LOCA Limits Analysis 12/31/08 15-57 Results of Small Break LOCA Break Spectrum Analysis (Pages 1-2)12/31/03 15-58 Parameters Used To Determine Hydrogen Generation 15-59 Deleted Per2001 Update 12/31/11 15-60 Results of Loca Limits Analysis.Mark-B-HTP Mixed Core Time Sequence of Events 12/31/09 15-61 Control Room Atmospheric Dispersion Factors (X/Qs) (Pages 1-2)12/31/11 15-62 Results of LBLOCA Analyses for Mark-B-HTP Full Core Sequence of Events (Pages 1-2)12/31/11 15-63 Results of LBLOCA Analyses for Full Core Mark-B-HTP; Gadolinia Fuel Pins (Pages 1-2)12/31/11 15-64 Results of 102% FP SBLOCA Analyses for Full Core Mark-B-HTP 12/31/12 15-65 Dose Equivalent Iodine (DEI) Calculation 12/31/12 15-66 Dose Equivalent Xenon (DEX) Calculation Chapter 18 12/31/12 18-1 Summary Listing of the Programs, Activities and TLAA (Pages 1-4)Effective Date 12/3 1/12 Page 15 of 37 OCONEE UFSAR -2012 UPDATE List of Effective Pages (LOEP) for Figures The purpose of this list is to assure that the pages in the Figures section of your manual match the most recent issue as well as to show a full accounting of all figures, including those that have been deleted.The earliest effective date, 12/31/00, was used when all figures were re-issued.

Effective Figure Figure Title Date No.Chapter 1 12/31/00 1-1 Duke Power Service Area 12/31/00 1-2 General Arrangement, Floor Plan Elevation 758+0 12/31/00 1-3 General Arrangement, Floor Plan Elevation 771+0 and Elevation 775+0 12/31/00 1-4 General Arrangement, Floor Plan Elevation 783+9 12/31/04 1-5 General Arrangement, Floor Plan Elevation 796+6 12/31/00 1-6 General Arrangement, Floor Plan Elevation 809+3 12/31/07 1-7 General Arrangement, Floor Plan Elevation 8212+0 12/31/00 1-8 General Arrangement, Floor Plan Elevation 838+0 and Elevation 844+0 12/3 1/00 1-9 General Arrangement, Sections Chapter 2 12/31/00 2-1 General Location 12/31/00 2-2 Topography within 5 Miles 12/31/00 2-3 General Area Map 12/31/00 2-4 Site Plan 12/31/11 2-5 Radioactive Effluent Site Boundaries 12/31/00 2-6 Population Centers within 100 Miles 12/31/08 2-7 Forecast of High-Pollution-Potential Days in the U.S 12/31/08 2-8 Annual Surface Wind Rose for Greenville, South Carolina, WBAS (1959-1963) 12/31/08 2-9 Upper Air Wind Rose-Athens, Georgia. 800-1300 ft above ground. (Dec 1954 -Nov 1961)12/31/08 2-10 Upper Air Wind Rose-Athens, Georgia. 2300-2800 ft above ground. (Dec 1959 -Nov 1961)12/31/08 2-I 1 Cumulative Probability of Wind Direction Persistence Duration at Grenville, SC 12/31/08 2-12 Precipitation Surface Wind Rose for Greenville, South Carolina, WBAS (1959 -1963)Effective Date 12/31/12 Page 16 of 37 Effective Figure Figure Title Date No.12/31/08 2-13 Surface Wind Direction Frequency Distribution During Low-Level Temperature Inversion Conditions 12/31/08 2-14 Maximum Topographic Elevation versus Distance (NNE and N sectors)12/31/08 2-15 Maximum Topographic Elevation versus Distance (NE sector)12/31/08 2-16 Maximum Topographic Elevation versus Distance (ENE sector)12/31/08 2-17 Maximum Topographic Elevation versus Distance (ESE and E sectors)I2/3 1/08 2-1 8 Maximum Topographic Elevation versus Distance (SSE and SE sectors)12/31/08 2-19 Maximum Topographic Elevation versus Distance (SSW and S sectors)12/31/08 2-20 Maximum Topographic Elevation versus Distance (WSW and SW sectors)12/31/08 2-21 Maximum Topographic Elevation versus Distance (WNW and W sectors)12/31/08 2-22 Maximum Topographic Elevation versus Distance (NW sector)12/31/08 2-23 Maximum Topographic Elevation versus Distance (NWW sector)12/31/08 2-24 Relative Elevations of Meteorological Instruments 12/31/08 2-25 Annual Surface Wind Rose (October 19, 1966 -October 31, 1967)12/3 1/08 2-26 Precipitation Surface Wind Rose (October 19, 1966 -October 3 1, 1967)12/31/08 2-27 Surface Wind Frequency Distribution during Low-Level Temperature Inversion Conditions (October 19, 1966 -October 3 1, 1967)12/31/08 2-28 Wind Rose for Tower Winds (June 19, 1967 -May 31, 1968)12/31/08 2-29 Frequency Distribution for Tower Winds During Low-Level Temperature Inversion Conditions (June 19, 1967 -May 31, 1968)12/31/08 2-30 Precipitation Wind Rose for Tower Winds (June 19, 1967 -May 31, 1968)12/31/08 2-31 General Building Arrangements 12/31/08 2-32 Plot Plan and Site Boundary During Early Meteorological Studies 12/31/08 2-33 SF6 Gas Tracer Test Background Sample Points 12/31/08 2-34 SF6 Gas Tracer Test Release Point 2-35 Deleted Per 2008 Update 2-36 Deleted per 2008 Update 12/31/08 2-37 SF6 Gas Tracer Test Release and Sample Stations 12/31/08 2-38 Approximate Terrain at Nuclear Site 12/31/00 2-39 Location of Municipal Water Supply Intakes 12/31/00 2-40 Areal Groundwater Survey 12/31/00 2-41 Groundwater Survey at Station Site 12/31/00 2-42 Well Pernearneter Test Apparatus 12/31/00 2-43 Formulae for Determining Permeability Effective Date 12/31/12 Page 17 of 37 Effective Figure Figure Title Date No.12/31/00 2-44 Regional Geologic Map 12/31/00 2-45 Topographic Map of Area 12/31/00 2-46 Location and Topographic Map 12/31/00 2-47 Strike and Dip of Joint Pattern 12/31/00 2-48 Earthquake Epicenters 12/31/00 2-49 Regional Techtonics 12/31/00 2-50 Ground Motion Spectra 12/31/00 2-51 Recommended Response Spectra 12/31/00 2-52 Ground Motion Spectra 12/31/00 2-53 Recommended Response Spectra 12/31/00 2-54 Ground Motion Spectra 12/31/00 2-55 Recommended Response Spectra 12/31/00 2-56 Subsurface Profile 12/31/00 2-57 Subsurface Profile 12/31/00 2-58 Subsurface Profile 12/31/00 2-59 Subsurface Profile 12/31/00 2-60 Subsurface Profile 12/31/00 2-61 Subsurface Profile 12/31/00 2-62 Subsurface Profile 12/31/00 2-63 Subsurface Profile 12/3 1/00 2-64 Subsurface Profile 12/31/00 2-65 Boring Plan 12/31/00 2-66 Core Boring Record, Boring Log NA- I 12/31/00 2-67 Core Boring Record, Boring Log NA-I 12/31/00 2-68 Core Boring Record, Boring Log NA-2 12/31/00 2-69 Core Boring Record, Boring Log NA-2 12/3 1/00 2-70 Core Boring Record, Boring Log NA-3 12/31/00 2-71 Core Boring Record, Boring Log NA-3 12/31/00 2-72 Core Boring Record, Boring Log NA-4 12/31/00 2-73 Core Boring Record, Boring Log NA-4 12/31/00 2-74 Core Boring Record, Boring Log NA-5 12/31/00 2-75 Core Boring Record, Boring Log NA-5 12/31/00 2-76 Core Boring Record, Boring Log NA-6 Effective Date 12/31/12 Page 18 of 37 Effective Figure Figure Title Date No.12/31/00 2-77 Core Boring Record, Boring Log NA-6 12/31/00 2-78 Core Boring Record, Boring Log NA-7 12/31/00 2-79 Core Boring Record, Boring Log NA-7 12/31/00 2-80 Core Boring Record, Boring Log NA-8 12/31/00 2-81 Core Boring Record, Boring Log NA-8 12/31/00 2-82 Core Boring Record, Boring Log NA-9 12/31/00 2-83 Core Boring Record, Boring Log NA-9 12/31/00 2-84 Core Boring Record, Boring Log NA-9 12/31/00 2-85 Core Boring Record, Boring Log NA- 10 12/31/00 2-86 Core Boring Record, Boring Log NA-10 12/31/00 2-87 Core Boring Record, Boring Log NA-10 12/31/00 2-88 Core Boring Record, Boring Log NA- Il 12/31/00 2-89 Core Boring Record, Boring Log NA- 11 12/31/00 2-90 Core Boring Record, Boring Log NA- 12 12/31/00 2-91 Core Boring Record, Boring Log NA- 12 12/31/00 2-92 Core Boring Record, Boring Log NA- 13 12/31/00 2-93 Core Boring Record, Bor.ing Log NA-13 12/31/00 2-94 Core Boring Record, Boring Log NA- 14 12/31/00 2-95 Core Boring Record, Boring Log NA- 14 12/31/00 2-96 Core Boring Record, Boring Log NA-15 12/31/00 2-97 Core Boring Record, Boring Log NA-15 12/31/00 2-98 Core Boring Record, Boring Log NA- 16 12/31/00 2-99 Core Boring Record, Boring Log NA- 16 12/31/00 2-100 Core Boring Record,, Boring Log NA- 16 12/31/00 2-101 Core Boring Record, Boring Log NA-17 12/31/00 2-102 Core Boring Record, Boring Log NA- 17 12/31/00 2-103 Core Boring Record, Boring Log NA- 17 12/31/00 2-104 Core Boring Record, Boring Log NA- 18 12/31/00 2-105 Core Boring Record, Boring Log NA- 18 12/31/00 2-106 Core Boring Record, Boring Log NA-18 12/31/00 2-107 Core Boring Record, Boring Log NA-18 12/31/00 2-108 Core Boring Record, Boring Log NA-19 12/31/00 2-109 Core Boring Record, Boring Log NA- 19 Effective Date 12/31/12 Page 19 of 37 Effective Figure Figure Title Date No.12/31/00 2-110 Core Boring Record, Boring Log NA-19 12/31/00 2-111 Core Boring Record, Boring Log NA- 19 12/31/00 2-1 12 Core Boring Record, Boring Log NA-20 12/31/00 2-113 Core Boring Record, Boring Log NA-20 12/31/00 2-114 Core Boring Record, Boring Log NA-20 12/31/00 2-115 Core Boring Record, Boring Log NA-21 12/31/00 2-I 16 Core Boring Record, Boring Log NA-21 12/31/00 2-117 Seismic Field Work Location Map 12/31/00 2-118 Diagrammatic Cross Section through Seismic Lines Chapter 3 12/31/00 3-1 Frequency and Mode Shapes -Auxiliary Building -North South Direction (Sheet I of 2)12/31/00 3-2 Frequency and Mode Shapes -Auxiliary Building -East West Direction (Sheet 2 of-2)12/31/00 3-3 Auxiliary Building Mass Model 12/31/00 3-4 Auxiliary Building -East West Direction

-Seismic Model Results (Sheet I of 2)12/31/00 3-5 Auxiliary Building -North South Direction

-Seismic Model Results (Sheet 2 of 2)12/31/00 3-6 Example Spectrum Curves 12/31/00 3-7 Reactor Building -Seismic Model Results (Sheet 1 of 2)12/31/00 3-8 Reactor Building -Seismic Model Results (Sheet 2 of 2)12/31/06 3-9 Main Steam System West Generator Problem Number 1-01-08 12/31/06 3-10 Core Flooding Tank IA Problem Number 1-53-9 12/31/06 3-11 Low Pressure Injection System West Generator Problem Number 1-53-9 12/31/06 3-12 RCP Piping to HPI Letdown Coolers Problem Number 1-55-03 12/31/06 3-13 RCP Piping to HP! Letdown Coolers Problem Number 1-55-03 12/31/06 3-14 RCP Piping to HPI Letdown Coolers Problem Number 1-55-03 12/31/06 3-15 RCP Piping to HPI Letdown Coolers Problem Number 1-55-03 12/31/00 3-16 Seismic Analysis of Component Coolers 12/31/00 3-17 Seismic Analysis of Component Coolers 12/31/00 3-18 Seismic Analysis of Component Coolers 12/31/00 3-19 Reactor Building Typical Details -(Sheets 1-3)12/31/11 3-20 Typical Electrical and Piping Penetrations 12/31/00 3-21 Details of Equipment Hatch and Personnel Hatch Effective Date 12/31/12 Page 20 of 37 Effective Figure Figure Title Date No.12/31/00 3-22 Reactor Building Finite Element Mesh 12/31/00 3-23 Reactor Building Finite Element Mesh 12/31/00 3-24 Reactor Building Thermal Gradient 12/31/00 3-25 Reactor Building Isostress Plot Wall and Dome (Parts 1-4)12/31/00 3-26 Reactor Building Isostress Plot Wall and Base (Parts 1-6)12/31/00 3-27 Reactor Building Finite Element Mesh Wall Buttresses 12/31/00 3-28 Reactor Building Isostress Plot for Buttresses (Pages 1-2)12/31/00 3-29 Temperature Gradient at Buttress 12/31/00 3-30 Buttress Reinforcing Details 12/31/00 3-31 Reactor Building Equipment Hatch Mesh 12/31/00 3-32 Reactor Building Penetration Loads 12/31/00 3-33 Reactor Building Model for Liner Plate Analysis for Radial Displacement 12/3 1/00 3-34 Reactor Building Model for Liner Analysis for Anchor Displacement 12/31/00 3-35 Reactor Building -Results firom Tests on Liner Plate Anchors 12/31/00 3-36 Location of Plugged Sheaths 12/3 1/00 3-37 Reactor Building Instrumentation for Unit I (Parts 1-4)12/31/00 3-38 Turbine Building Cross-Section at Line 21 3-39 Deleted Per 1996 Update 3-40 Deleted Per 1996 Update 3-41 Deleted Per 1996 Update 3-42 Deleted Per 1996 Update 3-43 Deleted Per 1996 Update 3-44 Deleted Per 1996 Update 3-45 Deleted Per 1996 Update 3-46 Deleted Per 1996 Update 3-47 Deleted Per 1996 Update 3-48 Deleted Per 1996 Update 3-49 Deleted Per 2004 Update 3-50 Deleted Per 2004 Update 3-51 Deleted Per 2004 Update 12/31/03 3-52 Seismic, Thermal, and Dead Load Analytical Model for the Pressurizer Surge Line Piping (Units 2 and 3)3-53 Deleted Per 2003 Update Effective Date 12/31/12 Page 21 of 37 Effective Figure Figure Title Date No.3-54 Deleted Per 2003 Update 3-55 Deleted Per 2004 Update 3-56 Deleted Per 2004 Update 12/31/00 3-57 Directions and Velocities of the Coolant Flow in the Reactor 12/31/00 3-58 Location of Instrumentation Surveillance Speciman Holder Tubes and the Plenum Cylinder Tubes 12/31/00 3-59 Location of the Instrumentation in the Specimen Holder Tube 12/31/00 3-60 Location of the Accelerometer in Plenu, m Cylinder Tube Chapter 4 12/31/00 4-1 Burnable Poison Rod Assembly 4-2 Deleted Per 1999 Update 4-3 Deleted Per 1999 Update 12/31/00 4-4 Typical Pressurized Fuel Rod 12/31/12 4-5 Typical Boron Concentration Versus Core Life 12/31/12 4-6 Typical BPRA Concentration and Distribution 12/31/00 4-7 Typical Control Rod Locations and Groupings 12/31/00 4-8 Typical Uniform Void Coefficient 4-9 Deleted Per 1995 Update 12/31/00 4-10 Typical Rod Worth Versus Distance Withdrawn 12/31/00 4-11 Percent Neutron Power Versus Time Following Trip 12/31/00 4-12 Power Spike Factor Due to Fuel Densification 12/31/00 4-13 Power Peaking Caused by Dropped Rod (Oconee Unit 1, Cycle 1)12/31/00 4-14 Azimuthal Stability Index Versus Moderator Coefficient From Three Dimensional Case (Oconee Unit 1, Cycle 1)12/31/00 4-15 Azimuthal Stability Index with Compounded Error Versus Moderator Coefficient Calculated From Three Dimensional Case (Oconee Unit 1, Cycle 1)12/31/00 4-16 Azimuthal Stability Index Versus Moderator Coefficient From Three Dimension Case (Oconee Unit 2, Cycle 1)12/31/00 4-17 Azimuthal Stability Index with Compounded Error Versus Moderator Coefficient From Three Dimensional Case (Oconee Unit 2, Cycle 1)4-18 Deleted Per 1997 Update 4-19 Deleted Per 1995 Update 4-20 Deleted Per 1995 Update 12/31/00 4-21 Flow Regime Map for the Hot Unit Cell Effective Date 12/31/12 Page 22 of 37 Effective Figure Figure Title Date No.12/31/00 4-22 12/31/00 4-23 12/31/00 4-24 4-25 12/31/00 4-26 12/31/00 4-27 12/31/00 4-28 12/31/00 4-29 12/31/00 4-30 12/31/00 4-31 12/31/00 4-32 4-33 12/31/00 4-34 4-35 4-36 12/31/00 4-37 12/31/04 4-38 Flow Regime Map for the Hot Control Rod Cell Flow Regime Map for the Hot Wall Cell Flow Regime Map for the Hot Corner Cell Deleted Per 1996 Update Reactor Vessel and Internals General Arrangement Reactor Vessel and Internals Cross Section Core Flooding Arrangement Internals Vent Valve Clearance Gaps Internals Vent Valve Control Rod Assembly Axial Power Shaping Rod Assembly Deleted Per 1999 Update Control Rod Drive -General Arrangement Deleted Per 1999 Update Deleted Per 1999 Update Typical Fuel Assembly Westinghouse 177 Fuel Assembly Reactor Coolant System (Unit I)Reactor Coolant System (Units 2 & 3)Reactor Coolant System, Arrangement Plan (Unit 1)Reactor Coolant System, Arrangement Elevation (Unit 1)Reactor Coolant System, Arrangement Plan (Unit 2)Reactor Coolant System, Arrangement Elevation (Unit 2)Reactor Coolant System, Arrangement Plan (Unit 3)Reactor Coolant System, Arrangement Elevation (Unit 3)Reactor and Steam Temperatures versus Reactor Power (Replacement Steam Generators) (Pages 1-2)Points of Stress Analysis for Reactor Vessel Location of Replacement Steam Generator Weld Deleted Per 1991 Update Deleted Per 1991 Update Chapter 5 12/31/00 12/31/00 12/31/00 12/31/00 12/31/04 12/31/04 12/31/04 12/31/04 12/31/04 12/31/00 12/31/04 5-1 5-2.5-3 5-4 5-5 5-6 5-7 5-8 5-9 5-10 5-11 5-12 5-13 Effective Date 12/31/12 Page 23 of 37 Effective Figure Figure Title Date No.12/31/03 5-14 Reactor Vessel Outline (Unit 1) (Shown with original reactor vessel head)12/31/03 5-15 Reactor Vessel Outline (Unit 2) (Shown with original reactor vessel head)12/31/03 5-16 Reactor Vessel Outline (Unit 3) (Shown with original reactor vessel head)12/31/00 5-17 Reactor Coolant Controlled Leakage Pump (Unit 1)12/31/00 5-18 Reactor Coolant Pump Estimated Perfonmance Characteristic (Unit 1)12/31/00 5-19 Reactor Coolant Pump (Units 2, 3)12/31/00 5-20 Reactor Coolant Pump Estimated Performance Characteristic (Units 2, 3)12/31/04 5-21 Flow Diagram of Bingham Reactor Coolant Pump 2A I Piping Diagram (Pages I-4)12/31/04 5-22 Flow Diagram of Bingham Reactor Coolant Pump 3A I Piping Diagram (Pages 1-4)12/31/00 5-23 12/31/00 5-24 12/31/04 5-25 5-26 12/31/00 5-27 12/31/00 5-28 12/31/08 5-29 12/31/03 5-30 12/31/03 5-31 5-32 12/31/03 5-33 Code Allowables and Reinforcing Limits Nozzles and Bowls Code Allowables, Cover Steam Generator Outline Deleted Per 2004 Update Turbine Generator Speed Response Following Load Rejection Pressurizer Outline Reactor Coolant System Arrangement Elevation (Typical)Reactor Coolant System Arrangement

-Plan (Typical)Jet Impingement Load on the Replacement Steam Generator Deleted per 2003 Update Replacement Reactor Vessel Closure Head Outline Flow Diagram of Emergency Core Cooling System Flow Diagram of Reactor Building Spray System Reactor Building Cooling Schematic Reactor Building Purge and Penetration Ventilation System Reactor Building Spray Pump Characteristics Reactor Building Cooler Heat Removal Capacity Reactor Building Cooler Heat Removal Capability as a Function of Air-Steam Mixture Flow Reactor Building Post-Accident Steam-Air Mixture Composition Reactor Building Isolation Valve Arrangements (Pages 1-3)Chapter 6 12/31/05 12/31/02 12/31/06 12/31/06 12/31/00 12/31/00 12/31/00 12/31/00 12/31/09 6-1 6-2 6-3 6-4 6-5 6-6 6-7 6-8 6-9 Effective Date 12/3 1/12 Page 24 of 37 Effective Figure Figure Title Date No.6-10 6- 1 6-12 6-13 6-14 6-15 12/31/00 6-16 12/31/00 6-17 12/31/00 6-18 12/31/07 6-19 12/31/00 6-20 12/31/00 6-21 12/31/00 6-22 12/31/00 6-23 12/31/00 6-24 12/31/00 6-25 12/31/00 6-26 12/31/00 6-27 12/31/03 6-28 12/31/03 6-29 12/31/03 6-30 12/31/03 6-31 12/31/03 6-32 12/31/03 6-33 12/31/03 6-34 12/31/03 6-35 12/31/11 6-36 12/31/03 6-37 6-38 6-39 6-40 6-41 12/31/08 6-42 Deleted Per 1993 Update Deleted Per 1993 Update Deleted Per 1993 Update Deleted Per 1999 Update Deleted Per 1999 Update Deleted Per 1991 Update High Pressure Injection Pump Characteristics Low Pressure Injection Pump Characteristics Low Pressure Injection Cooler Capacity Control Rooms 1-2 And 3 Locations General Arrangement Control Room 1-2 General Arrangement Control Room 3 Penetration Room Ventilation Fan And System Characteristics Penetrations In Penetration Room 809'3" Floor And Wall Areas Penetrations In Penetration Room 838'0" Floor Penetration Rooms Details, Mechanical Openings Penetration Rooms Details, Electrical Openings Penetration Rooms Details Construction Details ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis ONS ROTSG Peak Pressure Analysis Oconee Large Break LOCA Long-term Containment Response Oconee Large Break LOCA Long-term Containment Response Deleted per 2003 Update Deleted per 2003 Update Deleted per 2003 Update Deleted per 2003 Update Oconee Steam Line Break: Containment Pressure Effective Date 12/31/12 Page 5 of 37 Effective Figure Figure Title Date No.12/3 1/08 6-43 Oconee Steam Line Break: Containment Temperature 12/31/00 6-44 LOCA-Mass Release for the Subcompartment Pressure Response Analysis 12/3 1/00 6-45 LOCA-Energy Release Rate for the Subcompartment Pressure Response Analysis 12/3 1/00 6-46 LOCA-Reactor Compartment Pressure Response 12/31/00 6-47 LOCA-Steam Generator Compartment Vent Discharge Coefficient 12/3 1/00 6-48 LOCA-Steam Generator Compartment Pressure Response 6-49 Deleted per 2003 Update 12/31/00 6-50 LOCA-Mass Released to the Reactor Building 12/31/00 6-51 LOCA-Energy Released to the Reactor Building 12/31/00 6-52 LOCA-Reactor Building Pressure 6-53 Deleted Per 1997 Update Chapter 7 12/3 1/09 7-1 Reactor Protective System (pages I -16)12/31/00 7-2 Typical Pressure Temperature Boundaries 12/31/03 7-3 Typical Power Imbalance Boundaries 12/3 /12 7-4 Rod Control Drive Controls 12/31/12 7-5 Engineered Safeguards Protection System (pages 1-8)12/31/12 7-6 Nuclear Instrumentation System 12/3, /00 7-7 Nuclear Instrumentation Flux Range 12/31/12 7-8 Nuclear Instrumentation Detector Locations 12/31/I1 7-9 Nuclear Instrumentation Detector Locations

-(Unit 1)12/31/12 7-10 Nuclear Instrumentation Detector Locations

-(Unit 2 & 3)12/31/00 7-11 Automatic Control Rod Groups -Typical Worth Value Versus Distance Withdrawn 12/31/09 7-12 Control Rod Drive Logic Diagram 12/31/09 7-13 Control Rod Electrical Block Diagram 12/31/00 7-14 Integrated Control System 12/31/00 7-15 Core Thermal Power Demand -Integrated Control System 12/31/00 7-16 Integrated Master -Integrated Control System 12/31/00 7-17 Feedwater Control -Integrated Control System 12/31/04 7-18 Reactor and Steam Temperatures Versus Reactor Power (Replacement Steam Generator) 12/3 1/00 7-19 Reactor Control -Integrated Control System Effective Date 12/31/12 Page 26 of 37 Effective Figure Figure Title Date No.12/31/00 7-20 Incore Detector Locations 12/31/00 7-21 Incore Monitoring Channel 7-22 Deleted Per 1997 Update 7-23 Deleted Per 1997 Update 7-24 Deleted Per 1997 Update 7-25 Deleted Per 1997 Update 12/31/00 7-26 Control Room Layout Chapter 8 12/31/11 8-1 Single Line Diagram 12/31/00 8-2 Site Transmission Map 12/31/06 8-3 Typical 6900 Volt and 4160 Volt Unit Auxiliary

-Single Line Diagram (Pages 1-2)12/31/12 8-4 Typical 600 Volt and 208 Volt ESG Auxiliaries

-Single Line Diagram (Pages 1-3)12/31/12 8-5 Typical DC and AC Vital Power System -Single Line Diagram 12/31/06 8-6 Keowee DC Power System -Single Line Diagram 12/31/06 8-7 230 KV SWYD One Line 125V DC 8-8 Deleted Per 1997 Update 12/31/00 8-9 125/250 VDC Station Aux. Circuits Chapter 9 12/31/00 9-1 Fuel Storage Rack (Module)12/31/00 9-2 Fuel Storage Rack (Assembly) 12/31/00 9-3 Spent Fuel Pool Outline Oconee 1,2 12/31/00 9-4 Spent Fuel Pool Outline Oconee 3 12/31/00 9-5 Spent Fuel Cooling System 9-6 Deleted Per 1990 Update 12/31/00 9-7 Fuel Handling System (Units l&2 -Sheet I and Unit 3 -Sheet 2) (Sheets 1-2)12/31/00 9-8 Component Cooling System 12/31/00 9-9 Condenser Circulating Water System 12/31/06 9-10 High Pressure Service Water System 12/31/07 9-11 Low Pressure Service Water System 12/31/09 9-12 Low Pressure Service Water System (Pages 1-2)Effective Date 12/3 1/12 Page 27 of 37 Effective Figure Figure Title Date No.12/31/00 9-13 9-14 12/31/03 9-15 12/31/07 9-16 12/31/05 9-17 12/31/00 9-18 12/31/04 9-19 12/31/04 9-20 12/31/01 9-21 12/31/00 9-22 12/31/00 9-23 12/31/12 9-24 12/31/00 9-25 12/31/00 9-26 12/31/11 9-27 12/31/01 9-28 9-29 12/31/00 9-30 12/31/00 9-31 12/31/00 9-32 12/31/00 9-33 12/31/00 9-34 12/31/00 9-35 12/31/00 9-36 12/31/00 9-37 12/31/00 9-38 12/31/00 9-39 12/31/08 9-40 12/31/00 9-41 12/31/00 9-42 12/31/00 9-43 Recirculated Cooling Water System Deleted Per 1997 Update Chemical Addition and Sampling System Chemical Addition and Sampling System High Pressure Injection System (Pages 1-2.)High Pressure Injection System Low Pressure Injection System Coolant Storage System Coolant Treatment System Post-Accident Liquid Sample System Post-Accident Containment Air Sample System Control Room Area Ventilation and Air Conditioning System Spent Fuel Pool Ventilation System Unit I and 2 Spent Fuel Pool Ventilation System Unit 3 Auxiliary Building Ventilation System Unit I and 2 Auxiliary Building Ventilation System Unit 3 Deleted Per 1998 Update SSF General Arrangements Longitudinal Section SSF General Arrangements Plan Elevation 777' and 754'SSF General Arrangements Plan Elevation 797+0 SSF General Arrangements Plan Elevation 817+0 SSF General Arrangements Transverse Section SSF RC Makeup System SSF Auxiliary Service Water System SSF HVAC Service Water System & SSF Diesel Cooling Water System SSF Diesel Air Starting System SSF Sump System SSF 4160V/600V/208V Electrical Distribution SSF 125 VDC Auxiliary Power Systems Essential Siphon Vacuum System Siphon Seal Water System Effective Date 12/31/12 Page 28 of 37 Effective Figure Figure Title Date No.Chapter 10 12/31/07 10-1 Main Steam and Auxiliary Steam System 12/31/00 10-2 High Pressure Turbine Exhaust and Steam Seal System 12/31/00 10-3 High Pressure Turbine Exhaust and Steam Seal System 12/31/02 10-4 Moisture Separator and Reheater Heater and Drain System 12/31/00 10-5 Vacuum System 12/31/07 10-6 Condensate System 12/31/00 10-7 Main Feedwater System 12/31/00 10-8 Emergency Feedwater System 12/31/04 10-9 OTSG Recirculation System (Pages 1-2)Chapter 11 12/31/00 11-1 3" Liquid Waste Discharge 12/31/00 11-2 Liquid Waste Disposal System 12/31/00 11-3 Gaseous Waste Disposal System 12/31/11 11-4 Waste Water Collection Basin 11-5 Deleted Per 1999 Update 11-6 Deleted Per 1997 Update Chapter 13 12/31/12 13-1 Duke Energy Corporation Structure 13-2 Deleted Per 1999 Update 12/31/12 13-3 Nuclear Generation Department 12/31/12 13-4 Nuclear Generation

-Oconee Nuclear Site 12/31/00 13-5 "At the Controls" Definition

-Unit I & 2 12/31/00 13-6 "At the Controls" Definition

-Unit 3 13-7 Deleted Per 2012 Update 12/31/12 13-8 Nuclear& PMC Organizational Structure Chapter 15 12/31/05 15-1 Startup Accident 12/31/05 15-2 Startup Accident 12/31/05 15-3 Startup Accident Effective Date 12/31/12 Page 29 of 37 Effective Figure Figure Title Date No.12/31/05 15-4 Startup Accident 12/31/05 15-5 Startup Accident 12/31/05 15-6 Startup Accident 15-7 Deleted Per 1998 Update 15-8 Deleted Per 1998 Update 15-9 Deleted Per 1998 Update 15-10 Deleted Per 1998 Update 12/31/03 15-11 Rod Withdrawal at Power Accident -Peak RCS Pressure Analysis Power 12/31/03 15-12 Rod Withdrawal at Power Accident -Peak RCS Pressure Analysis RCS Temperatures 12/31/03 15-13 Rod Withdrawal at Power Accident -Peak RCS Pressure Analysis Pressurizer Level]2/31/03 15-14 Rod Withdrawal at Power Accident -Peak RCS Pressure Analysis RCS Pressure 12/31/03 15-15 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis Power 12/31/03 15-16 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis RCS Temperatures 12/31/03 15-17 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis Pressurizer Level 12/31/08 15-18 Cold Water Accident -RCS Flow 12/31/08 15-19 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP Initial Conditions Analysis -RCS Flow 12/31/08 15-20 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP Initial Conditions Analysis -Power 12/31/08 15-21 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP. Initial Conditions Analysis -RCS Temperature 12/31/08 15-22 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP Initial Conditions Analysis -Pressurizer Level 12/31/08 15-23 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP Initial Conditions Analysis -RCS Pressure 12/31/08 15-24 Loss of Coolant Flow Accidents

-Four RCP Coastdown From Four RCP Initial Conditions Analysis -DNBR 12/31/03 15-25 Loss of Coolant Flow Accidents

-Two RCP Coastdown From Four RCP Initial Conditions Analysis -RCS Flow 12/31/10 15-26 Control Rod M isalignment Accidents

-Dropped Rod Analysis-Neutron Power 12/31/10 15-27 Control Rod Misalignment Accidents

-Dropped Rod Analysis -RCS Temperatures 12/31/10 15-28 Control Rod Misalignment Accidents

-Dropped Rod Analysis -Pressurizer Level Effective Date 12/31/12 Page 30 of 37 Effective Figure Figure Title Date No.12/31/08 15-29 Rod Ejection Accident -BOC Four RCPs -Power 12/31/08 15-30 Rod Ejection Accident -BOC Three RCPs -Power 12/31/08 15-31 Rod Ejection Accident -BOC HZP -Power 12/31/08 15-32 Rod Ejection Accident-EOC Four RCPs -Power 12/31/08 15-33 Rod Ejection Accident -EOC Three RCPs -Power 12/31/08 15-34 Rod Ejection Accident -EOC HZP -Power 12/31/08 15-35 Rod Ejection Accident -BOC Four RCPs -Core Power Distribution 12/3 1/08 15-36 Rod Ejection Accident -BOC Three RCPs -RCS Pressure 15-37 Deleted Per 1999 Update 15-38 Deleted Per 1999 Update 15-39 Deleted Per 1999 Update 12/31/03 15-40 Steam Line Break Accident -With Offsite Power -Steam Line Pressure 12/31/03 15-41 Steam Line Break Accident -With Offsite Power- Break Flowrate 12/31/03 15-42 Steam Line Break Accident -With Offsite Power- RCS Temperature 12/31/03 15-43 Steam Line Break Accident -With Offsite Power -Reactivity 12/31/00 15-44 LOCA -Large Break Analysis Code Interfaces 15-45 Deleted Per 2000 Update 15-46 Deleted Per 1990 Update 15-47 Deleted Per 1997 Update 15-48 Deleted Per 1997 Update 15-49 Deleted Per 2000 Update 12/31/08 15-50 LOCA -Peak Cladding Temperature vs. Break Size for LBLOCA Spectrum 15-51 Deleted Per 1997 Update 15-52 Deleted Per 1995 Update 15-53 Deleted Per 1995 Update 15-54 Deleted Per 1995 Update 15-55 Deleted Per 1995 Update 15-56 Deleted Per 1995 Update 15-57 Deleted Per 1995 Update 15-58 Deleted Per 1995 Update 15-59 Deleted Per 1995 Update 15-60 Deleted Per 1995 Update 15-61 Deleted Per 1995 Update Effective Date 12/31/12 Page 31 of 37 Effective Figure Figure Title Date No.15-62 15-63 15-64 15-65 15-66 15-67 15-68 15-69 15-70 15-71 15-72 15-73 15-74 15-75 15-76 15-77 15-78 15-79 12/31/00 15-80 15-81 15-82 15-83 15-84 15-85 15-86 15-87 15-88 12/31/03 15-89 15-90 15-91 15-92 15-93 15-94 Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update MHA -Integrated Direct Dose Deleted Per 1995 Update Deleted Per 2000 Update Deleted Per 1995 Update Deleted Per 2000 Update Deleted Per 2000 Update Deleted Per 1997 Update Deleted Per 2000 Update Deleted Per 1995 Update Post-Accident Hydrogen Control -Reactor Building Arrangement Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Deleted Per 1995 Update Effective Date 12/31/12 Page 32 of 37 Effective Figure Figure Title Date No.15-95 Deleted Per 1995 Update 15-96 Deleted Per 1995 Update 15-97 Deleted Per 1995 Update 15-98 Deleted Per 1995 Update 15-99 Deleted Per 1995 Update 15-100 Deleted Per 1995 Update 15-101 Deleted Per 1995 Update 15-102 Deleted Per 1995 Update 15-103 Deleted Per 1995 Update 15-104 Deleted Per 1995 Update 15-105 Deleted Per 1995 Update 15-106 Deleted Per 1995 Update 15-107 Deleted Per 1995 Update 15-108 Deleted Per 1995 Update 15-109 Deleted Per 1995 Update 15-110 Deleted Per 2001 Update 15-I1l Deleted Per 2003 Update 12/31/08 15-112 LOCA kW/ft Limits vs. Core Elevation for MK-B1OT Fuel 12/31/03 15-113 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis RCS Pressure 12/31/08 15-114 Rod Withdrawal at Power Accident -Core Cooling Capability Analysis DNBR 12/31/08 15-115 Cold Water Accident -Core Average Temperature 12/31/08 15-116 Cold Water Accident -Power 12/31/08 15-117 Cold Water Accident -Cold Leg Temperature 12/31/08 15-118 Cold Water Accident -RCS Pressure 12/31/03 15-119 Loss of Coolant Flow Accidents

-Two RCP Coastdown from Four RCP Initial Conditions Analysis -Power 12/31/03 15-120 Loss of Coolant Flow Accidents

-Two RCP Coastdown from Four RCP Initial Conditions Analysis -RCS Temperature 12/31/03 15-121 Loss of Coolant Flow Accidents

-Two RCP Coastdown fi'om Four RCP Initial Conditions Analysis -Pressurizer Level 12/31/03 15-122 Loss of Coolant Flow Accidents

-Two RCP Coastdown from Four RCP Initial Conditions Analysis -RCS Pressure 12/31/08 15-123 Loss of Coolant Flow Accidents

-Two RCP Coastdown from Four RCP Initial Conditions Analysis -DNBR Effective Date 12/31/12 Page 33 of 37 Effective Figure Figure Title Date No.12/31/03 15-124 Loss of Coolant Flow Accidents-One RCP Coastdown firom Three RCP Initial Conditions Analysis -RCS Flow 12/31/03 15-125 Loss of Coolant Flow Accidents

-One RCP Coastdown from Three RCP Initial Conditions Analysis -Power 12/31/03 15-126 Loss of Coolant Flow Accidents

-One RCP Coastdown firom Three RCP Initial Conditions Analysis -RCS Temperature 12/31/03 15-127 Loss of Coolant Flow Accidents

-One RCP Coastdown fiom Three RCP Initial Conditions Analysis -Pressurizer Level 12/31/03 15-128 Loss of Coolant Flow Accidents

-One RCP Coastdown from Three RCP Initial Conditions Analysis -RCS Pressure 12/31/08 15-129 Loss of Coolant Flow Accidents

-One RCP Coastdown from Three RCP Initial Conditions Analysis -DNBR 12/31/03 15-130 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -RCS Flow 12/31/03 15-131 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -Power 12/31/03 15-132 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -RCS Temperature 12/31/03 15-133 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -Pressurizer Level 12/31/03 15-134 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -RCS Pressure 12/31/08 15-135 Loss of Coolant Flow Accidents

-Locked Rotor From Four RCP Initial Conditions Analysis -DNBR 12/31/08 15-136 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -RCS Flow 12/31/08 15-137 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -Power 12/31/08 15-138 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -RCS Temperatures 12/31/08 15-139 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -Pressurizer Level 12/31/08 15-140 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -RCS Pressure 12/31/11 15-141 Loss of Coolant Flow Accidents

-Locked Rotor From Three RCP Initial Conditions Analysis -DNBR 12/3 1/00 15-142 Intentionally Blank 12/31/10 15-143 Control Rod Misalignment Accidents-Dropped Rod -RCS Pressure Effective Date 12/31/12 Page 34 of 37 Effective Figure Figure Title Date No.12/31/10 15-144 Control Rod Misalignment Accidents

-Dropped Rod -DNBR 12/31/08 15-145 Turbine Trip Accident -Steam Generator Pressure 12/31/08 15-146 Turbine Trip Accident -RCS Temperatures 12/3 1/08 15-147 Turbine Trip Accident -Pressurizer Level 12/31/08 15-148 Turbine Trip Accident -RCS Pressure 12/31/08 15-149 Turbine Trip Accident -Power 12/31/11 15-150 Steam Generator Tube Rupture -Power 12/31 /11 15-151 Steam Generator Tube Rupture -Break Flow 12/31/11 15-152 Steam Generator Tube Rupture -RCS Pressure 12/31/11 15-153 Steam Generator Tube Rupture -Pressurizer Level 12/31/11 15-154 Steam Generator Tube Rupture -Steam Generator Pressure 12/31/11 15-155 Steam Generator Tube Rupture -Steam Generator Level 12/31/11 15-156 Steam Generator Tube Rupture -RCS Temperatures 12/31/03 15-157 Steam Line Break Accident -With Offsite Power -Power 12/3 1/03 15-158 Steam Line Break Accident -With Offsite Power -RCS Pressure 12/31/03 15-159 Steam Line Break Accident -With Offsite Power -Core Inlet Flow 15-160 Deleted per 2003 Update 12/3 1/03 15-161 Steam Line Break Accident -Without Offsite Power -Steam Line Pressure 12/31/03 15-162 Steam Line Break Accident -Without Offsite Power- RCS Temperatures 12/31/03 15-163 Steam Line Break Accident -Without Offlsite Power -RCS Flow 12/31/03 15-164 Steam Line Break Accident -Without Offsite Power -Reactivity 12/31/03 15-165 Steam Line Break Accident -Without Offsite Power- Power 12/31/03 15-166 Steam Line Break Accident -Without Offsite Power -RCS Pressure 12/31/08 15-167 Steam Line Break Accident -Without Offsite Power- DNBR 12/31/03 15-168 Small Steam Line Break -Steam Mass Flows 12/31/03 15-169 Small Steam Line Break -Steam Line Pressures 12/31/11 15-170 Small Steam Line Break -Main Feedwater Mass Flows 12/31/03 15-171 Small Steam Line Break -RCS Temperatures 12/31/03 15-172 Small Steam Line Break -Core Average Power 12/31/03 15-173 Small Steam Line Break- RCS Hot Leg Pressure 12/31/03 15-174 LOCA kW/ft Limits vs. Core Elevation for MK-BI I and MK-BI I A Fuel 12/31/03 15-175 Oconee -No CHRS Flow 15-176 Deleted Per 2001 Update Effective Date 12/3 1/12 Page 35 of 37 Effective Figure Figure Title Date No.12/31/03 15-177 Lower Bound Containment Pressure Used in Large Break LOCA 12/31/03 15-178 BOL LBLOCA Limit Case -2.506-ft, Mk-BI I (M5) Reactor Vessel Upper Plenum Pressure 12/31/03 15-179 BOL LBLOCA Limit Case -2.506 -ft, Mk 11 (M5) Break Mass Flow Rates 12/31/03 15-180 BOL LBLOCA Limit Case -2.506 -ft, Mk I I (M5) Hot Channel Mass Flow Rates 12/31/03 15-181 BOL LBLOCA Limit Case -2.506 -ft, Mk 1 I(M5) Core Flooding Rate 12/31/03 15-182 BOL LBLOCA Limit Case -2.506 -ft, Mk1 I(M5) HP Fuel & Clad Temperatures at Ruptured Location 12/31/03 15-183 BOL LBLOCA Limit Case -2.506 -ft, Mkl 1(M5) HP Fuel & Clad Temperatures at Peak Unruptured Location 12/31/03 15-184 BOL LBLOCA Limit Case-2.506

-ft, Mkl I(M5) HC Filtered Heat Transfer Coefficients 12/31/03 15-185 BOL LBLOCA Limit Case -2.506 -ft, Mk 1 I(M5) Quench Front Advancement 12/31/03 15-186 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA -Pressure 12/31/03 15-187 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA -Break and ECCS Mass Flow Rates 12/31/03 15-188 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA-Hot Channel Levels 12/31/03 15-189 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA -Peak Cladding Temperature 12/31/03 15-190 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA -HC Vapor Temperature at Core Exit 12/31/03 15-191 0.15 ft2 CLPD, 102% of 2568 MWt SBLOCA -HC Heat Transfer Coefficient 12/31/03 15-192 0.15 ft2 CLPD, 77% of 2568 MWt SBLOCA -Pressure 12/31/03 15-193 0.15 ft2 CLPD, 77% of 2568 MWt SBLOCA -Break and ECCS Mass Flow Rates 12/31/03 15-194 0.15 ft2 CLPD, 77% of 2568 MWt SBLOCA -Hot Channel Levels 12/31/03 15-195 0.15 ft2 CLPD, 77% of 2568 MWt SBLOCA -Peak Cladding Temperature 12/31/03 15-196 0.15 ft2 CLPD, 77% of 2568 MWt SBLOCA -HC Vapor Temperature at Core Exit 12/31/03 15-197 0. 15 ft2 CLPD, 77% of 2568 MWt SBLOCA -HC Heat Transfer Coefficient 12/31/08 15-198 2.506-ft Mark-B-HTP Mixed-Core Bol LBLOCA Case -Reactor Vessel Upper Plenum Pressure 12/31/08 15-199 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -Break Mass Flow Rates 12/31/08 15-200 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -Hot Channel Mass Flow Rates 12/31/08 15-201 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -Core Flooding Rate 12/31/08 15-202 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -HP Fuel & Clad Temperatures at Ruptured Location Effective Date 12/31/12 Page 36 of 37 Effective Figure Figure Title Date No.12/31/08 15-203 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -HP Fuel & Clad Temperature at Unruptured Location 12/31/08 15-204 2.506-ft Mark-B-HTP Mixed-Core BOL LBLOCA Case -Quench Front Advancement 12/31/08 15-205 2.506-ft Mark-B-HTP Mixed-Core MOL LBLOCA Case -HP Fuel & Clad Temperatures at Ruptured Locations 12/31/08 15-206 2.506-ft Mark-B-HTP Mixed-Core MOL LBLOCA Case -HP Fuel & Clad Temperatures at Unruptured Location 12/31/08 15-207 102% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Spectrum Analysis 12/31/08 15-208 0.15 fit 2 CLPD, 102% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Pressure 12/31/08 15-209 0.15 ft 2 CLPD, 102% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Break and ECCS Mass Flow Rates 12/31/08 15-210 0.15 ft 2 CLPD, 10 2% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Hot Channel Levels 12/31/08 15-211 0.15 ft 2 CLPD, 102% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Peak Cladding Temperature 12/31/08 15-212 0.15 ft 2 CLPD, 102% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-HC Vapor Temperature at Core Exit 12/31/08 15-213 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Spectrum Analysis 12/31/08 15-214 0.075 ft 2 CLPD, 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Pressure 12/31/08 15-215 0.075 ftW CLPD, 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Break and ECCS Mass Flow Rates 12/31/08 15-216 0.075 ft 2 CLPD, 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Hot Channel Levels 12/31/08 15-217 0.075 ft 2 CLPD, 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-Peak Cladding Temperature 12/31/08 15-218 0.075 ft 2 CLPD, 77% of 2568 MWt, Mark-B-HTP Mixed-Core SBLOCA Case-HC Vapor Temperature at Core Exit 12/31/11 15-219 Mark-B-HTP Full-Core BOL LBLOCA -Reactor Vessel Upper Plenum Pressure 12/31/11 15-220 Mark-B-HTP Full-Core BOL LBLOCA -Break Mass Flow Rates 12/31/11 15/221 Mark-B-HTP Full-Core BOL LBLOCA -Hot Channel Mass Flow Rates 12/31/11 15-222 Mark-B-HTP Full-Core BOL LBLOCA -Core Flooding Rates 12/31/11 15-223 Mark-B-HTP Full-Core BOL LBLOCA -Hot Pin Fuel & Clad Temperatures at Ruptured Location 12/31/11 15-224 Mark-B-HTP Full-Core BOL LBLOCA -Hot Pin Fuel & Clad Temperatures at Effective Date 12/31/12 Page 37 of 37 Effective Figure Figure Title Date No.Unruptured Location 12/31/1I 15-225 Mark-B-HTP Full-Core BOL LBLOCA -Quench Front Advancement 12/31/11 15-226 Mark-B-HTP Full-Core BOL LBLOCA -Hot Pin Heat Transfer Coefficients 12/31/1 15-227 102% of 2568 MWt., Full Core Mark-B-HTP SBLOCA Break Spectrum Analysis 12/31/11 15-228 0.15ft 2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -Pressure 12/3 Il I 15-229 0.15ft 2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -Break and ECCS Mass Flow Rates 12/31/11 15-230 0.15ft 2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -RV Collapsed Liquid Level & Hot Channel Mixture Level 12/31/11 15-231 0.15ft 2 CLPD, 102% of 2568 MWt., Full Core Mark-B-HTP SBLOCA -Hot Pin Peak Clad Temperature 12/31/11 15-232 0.15ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -Hot Channel Vapor Temperature at Core Exit Effective Date 12/31/12 ATTACHMENT

SUMMARY

OF INFORMATION REMOVED FROM REVISION 22 OF THE UFSAR 4 Attachment Oconee Nuclear Station UFSAR 2012 Update List of Removed Items UFSAR Table 7-3 Notes 4 & 5 concerning Low Pressure Service Water (LPSW) valves 1055 & 1061, and LPSW-1054 & -1062 respectively, were deleted as a result of the Engineered Safeguards Protective System/Reactor Protective System modification.

UFSAR Section 9.5.1 Section 9.5.1 was re-written as a result of National Fire Protection Association (NFPA) 805 implementation.

Sections 9.5.1.3 -9.5.1.7.4 were removed/replaced by NFPA 805 information.

UFSAR Section 9.6.4.6.1 During re-write resulting from NFPA 805 implementation, information related to cold shutdown was deleted.UFSAR Section 9.6.5 During re-write resulting from NFPA 805 implementation, unnecessary information concerning Appendix R events was deleted.UFSAR Section 9.6.6 During re-write resulting from NFPA 805 implementation, references that were no longer applicable were deleted.Table 15-16 Irrelevant entries, associated with the Large Main Steam Line Break and Small Main Steam Line Break, were deleted as a result of the Table update to include calculated Total Effective Dose Equivalent (TEDE) doses in accordance with AST methodology.

UFSAR Section 18.3.1.2 Deleted paragraph that referenced EA-03-009 since it no longer applies.UFSAR Table 18-1 The "Boric Acid Corrosion Program" entry that was listed after "Flow Accelerated Corrosion Program" was deleted; the "Boric Acid Corrosion Program" was then placed in the correct location in the Table.Page I of I