ML20189A109

8 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15A. Tables

ML20189A109
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Site:	Oconee
Issue date:	06/29/2020
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
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Oconee Nuclear Station UFSAR Appendix 15A. Tables Appendix 15A. Tables

Oconee Nuclear Station UFSAR Table 15-1 (Page 1 of 1)

(31 DEC 2019)

Table 15-1. Reg. Guide 1.183 Fuel Handling Accident Source Term Isotope Gap Fraction (See Note 1) 72 Hour Gap Inventory (Ci/Fuel Assembly)

Kr-83m 0.05 2.34E-05 Kr-85m 0.10 3.72E-01 Kr-85 0.10 8.53E+02 Kr-87 0.05 2.39E-13 Kr-88 0.05 8.26E-04 Xe-131m 0.05 4.81E+02 Xe-133m 0.05 1.21E+03 Xe-133 0.05 5.26E+04 Xe-135m 0.05 5.38E+00 Xe-135 0.05 7.21E+02 Deleted Row(s) per 2009 Update I-131 0.08 4.35E+04 I-132 0.05 2.59E+04 I-133 0.05 6.44E+03 Deleted Row(s) per 2009 Update I-135 0.05 3.29E+01 Note:

1. For fuel pins that exceed the rod power/burnup criteria of Footnote 11 in RG 1.183, the gap fractions from RG 1.183 are increased by a factor of 4 for Kr-85, Cs-134, and Cs-137. The gap fractions for all other isotopes remain at their pertinent RG 1.183, Table 3 values.

Oconee Nuclear Station UFSAR Table 15-2 (Page 1 of 1)

(31 DEC 2013)

Table 15-2. Rod Ejection Accident Analysis Results Deleted Per 2013 Update Mk-B-HTP with UO2-Gad fuel rods Parameter Value Cycle Exposure BOC BOC BOC EOC EOC EOC Initial core power (% of 2568 MWt) 102 77 0

102 77 0

Number of RCP running 4

3 3

4 3

3 Initial rod position (% wd) 58 31 0

58 31 0

Ejected rod worth ($)

0.164 0.362 1.207 0.202 0.394 1.149 MTC (pcm/°F) 0.0 0.56 7.0

-28.0

-28.0

-12.0 DTC (pcm/°F)

-1.10

-1.16

-1.42

-1.19

-1.22

-1.53 Maximum neutron power (% of 2568 MWt) 118 108 426 122 114 160 Peak UO2 fuel pellet average enthalpy (cal/gm) 115 95 72 103 107 45 Peak UO2 -Gd fuel pellet average enthalpy (cal/gm) 129`

113 91 134 130 45 Percent pins exceeding DNBR (%) <45%

Maximum RCS pressure (psig) 2301 2273 See Note 1 1RCS pressurization is not analyzed for these conditions since they are not limiting.

Oconee Nuclear Station UFSAR Table 15-3 (Page 1 of 1)

(31 DEC 2008)

Table 15-3. Deleted Per 2008 Update

Oconee Nuclear Station UFSAR Table 15-4 (Page 1 of 1)

(31 DEC 2004)

Table 15-4. Deleted Per 2004 Update

Oconee Nuclear Station UFSAR Table 15-5 (Page 1 of 1)

(31 DEC 2003)

Table 15-5. Steam Line Break Accident - With Offsite Power Case Sequence of Events Event Time (sec)

Break opens 0.0 Third CBP starts 0.5 Reactor trip on variable low pressure-temperature 3.0 Control rod insertion begins 3.1 Turbine stop valves closed Control rods fully inserted 3.1 Deleted row(s) per 2003 update HPI actuates 35.5 Deleted row(s) per 2003 update CFT injection begins 97.4 Boron from CFT B starts 110.1 Boron from CFT A starts 115.1 Boron injection from HPI begins 115.8 Deleted row(s) per 2003 update Unaffected SG becomes water-solid 310.0 End of simulation 600.0

Oconee Nuclear Station UFSAR Table 15-6 (Page 1 of 1)

(31 DEC 2000)

Table 15-6. Summary of LOCA Break Spectrum Break Size and Type Parameter CLPD DE CLPD DE CLPD DE CLPD Split CLPS DE Break CD 1.0 0.8 0.6 1.0 1.0 Unruptured node 12 12 13 13 12 PCT, °F 1915.1 1895.9 1851.9 1811.5 1829.9 Time, sec 33.549 41.515 37.100 34.086 32.151 Local oxidation, %

1.7364 1.5650 1.0324 0.9773 1.0277 Ruptured node 11 13 12 12 13 PCT, °F 1957.1 1889.6 1820.9 1745.0 1796.3 Time, sec 28.604 29.845 31.511 31.055 32.284 Local oxidation, %

2.0190 1.8633 1.6000 1.4752 1.5446 Clad rupture time, sec 19.02 20.655 23.21 21.02 19.19 CFTs begin injection, sec 11.80 12.80 14.60 12.20 13.00 End of bypass, sec 18.14 19.29 21.56 18.90 17.70 End of blowdown, sec 20.16 21.46 24.20 21.01 22.94 End of adiabatic heatup, sec 26.562 27.721 29.988 27.475 25.542 Water mass in reactor vessel lower plenum at end of blowdown, lbm 16701.6 17695.6 20418.6 16811.3 36238.7

Oconee Nuclear Station UFSAR Table 15 15-14 (Page 1 of 1)

(31 DEC 2000)

Table 15-7. Deleted Per 1997 Update Table 15-8. Deleted Per 1995 Update Table 15-9. Deleted Per 1995 Update Table 15-10. Deleted Per 1995 Update Table 15-11. Deleted Per 1995 Update Table 15-12. Deleted Per 1995 Update Table 15-13. Deleted Per 1995 Update Table 15-14. Deleted Per 2004 Update

Oconee Nuclear Station UFSAR Table 15-15 (Page 1 of 4)

(31 DEC 2012)

Table 15-15. Total Core Activity for Maximum Hypothetical Accident Isotope Total Ci in Core1 AM241 2.02E+04 AM242M 1.35E+03 AM242 7.66E+06 AM243 3.22E+03 BA139 1.31E+08 BA140 1.27E+08 BA141 1.18E+08 BR83 8.95E+06 BR85 1.93E+07 BR87 3.04E+07 CE141 1.20E+08 CE143 1.12E+08 CE144 9.64E+07 CM242 4.61E+06 CM244 5.84E+05 CS134 1.52E+07 CS136 4.33E+06 CS137 1.07E+07 CS138 1.37E+08 CS139 1.28E+08 EU154 7.08E+05 EU155 2.92E+05 EU156 1.87E+07 I130 1.50E+06 I131 7.20E+07 I132 1.05E+08 I133 1.47E+08 I134 1.65E+08 I135 1.40E+08 KR83M 9.01E+06 KR85M 1.94E+07

Oconee Nuclear Station UFSAR Table 15-15 (Page 2 of 4)

(31 DEC 2012)

Isotope Total Ci in Core1 KR85 1.01E+06 KR87 3.85E+07 KR88 5.17E+07 KR89 6.46E+07 LA140 1.33E+08 LA141 1.19E+08 LA142 1.15E+08 LA143 1.11E+08 MO99 1.33E+08 NB95M 1.41E+06 NB95 1.24E+08 NB97 1.24E+08 ND147 4.74E+07 NP238 3.08E+07 NP239 1.54E+09 PD109 2.68E+07 PM147 1.55E+07 PM148M 3.69E+06 PM148 1.27E+07 PM149 4.16E+07 PM151 1.43E+07 PR143 1.09E+08 PR144M 1.35E+06 PR144 9.69E+07 PU236 3.92E+01 PU238 3.61E+05 PU239 3.42E+04 PU240 4.94E+04 PU241 1.30E+07 PU243 3.30E+07 RB86 1.41E+05 RB88 5.25E+07

Oconee Nuclear Station UFSAR Table 15-15 (Page 3 of 4)

(31 DEC 2012)

Isotope Total Ci in Core1 RB89 6.90E+07 RB90 6.26E+07 RH103M 1.19E+08 RH105 7.97E+07 RU103 1.19E+08 RU105 8.59E+07 RU106 4.69E+07 SB127 6.90E+06 SB129 2.12E+07 SM153 3.44E+07 SR89 7.18E+07 SR90 8.05E+06 SR91 9.02E+07 SR92 9.61E+07 SR93 1.06E+08 TC99M 1.18E+08 TC101 1.24E+08 TE127M 1.15E+06 TE127 6.79E+06 TE129M 3.82E+06 TE129 1.99E+07 TE131 6.09E+07 TE132 1.02E+08 TE133M 6.95E+07 TE133 7.87E+07 TE134 1.33E+08 XE131M 9.62E+05 XE133M 4.57E+06 XE133 1.43E+08 XE135M 3.11E+07 XE135 5.33E+07 XE137 1.32E+08

Oconee Nuclear Station UFSAR Table 15-15 (Page 4 of 4)

(31 DEC 2012)

Isotope Total Ci in Core1 XE138 1.26E+08 Y90 8.26E+06 Y91M 5.23E+07 Y91 9.32E+07 Y92 9.72E+07 Y93 1.09E+08 Y94 1.14E+08 Y95 1.18E+08 ZR95 1.23E+08 Z R97 1.23E+08 U237 6.61E+07 Note:

1. Core activity values bound both 18-month and 24-month cycle scenarios.

Oconee Nuclear Station UFSAR Table 15-16 (Page 1 of 2)

(31 DEC 2019)

Table 15-16. Summary of Transient and Accident Doses Including the Effects of High Burnup Reload Cores with Replacement Steam Generators Doses (rem)

Fuel Handling Accident for Single Fuel Assembly Event TEDE at EAB 1.18 TEDE at LPZ 0.13 TEDE in Control Room 2.19 Deleted row(s) per 2016 update Steam Generator Tube Rupture Case 1 Case 2 Thyroid at EAB 4.24E+1 2.80E+2 Whole body at EAB 1.46E-1 1.82E-1 Thyroid at LPZ 1.00E+1 6.93E+1 Whole body at LPZ 3.04E-2 4.00E-2 Waste Gas Tank Failure TEDE at EAB 4.4E-1 Rod Ejection Containment Release Secondary Side Release TEDE at EAB 5.23 2.66 TEDE at LPZ 2.00 1.35 TEDE in Control Room 4.46 4.92 Deleted row(s) per 2009 update Large Main Steam Line Break Preaccident Iodine Spike Concurrent Iodine Spike TEDE at EAB 0.18 0.70 Deleted row(s) per 2012 Update TEDE at LPZ 0.05 0.22 TEDE in Control Room 0.76 1.30

Oconee Nuclear Station UFSAR Table 15-16 (Page 2 of 2)

(31 DEC 2019)

Doses (rem)

Small Main Steam Line Break Preaccident Iodine Spike Concurrent Iodine Spike TEDE at EAB 0.29 0.68 Deleted row(s) per 2012 Update TEDE at LPZ 0.06 0.24 TEDE in Control Room 1.29 1.69 Deleted row(s) per 2004 update Maximum Hypothetical Accident TEDE at EAB 10.86 TEDE at LPZ 2.74 TEDE in Control Room 4.39 Deleted row(s) per 2008 update Fuel Cask Handling Accident for Multiple Fuel Assembly Event TEDE at EAB 1.93 TEDE at LPZ 0.21 TEDE in Control Room 3.62 Deleted row(s) per 2008 update Deleted row(s) per 2004 update Deleted row(s) per 2008 update

Oconee Nuclear Station UFSAR Table 15 15-27 (Page 1 of 1)

(31 DEC 2000)

Table 15-17. Deleted Per 2000 Update Table 15-18. Deleted Per 2000 Update Table 15-19. Deleted Per 1995 Update Table 15-20. Deleted Per 1995 Update Table 15-21. Deleted Per 1995 Update Table 15-22. Deleted Per 1995 Update Table 15-23. Deleted Per 1995 Update Table 15-24. Deleted Per 1997 Update Table 15-25. Deleted Per 2001 Update Table 15-26. Deleted Per 1995 Update Table 15-27. Deleted Per 2003 Update

Oconee Nuclear Station UFSAR Table 15-28 (Page 1 of 1)

(31 DEC 2015)

Table 15-28. HPI Flow Assumed in Core Flood Line Small Break LOCA Analyses 102% Full Power SBLOCA Flow rates prior to credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

HPI Flow (gpm) 0 428 600 428 1200 333 1500 294 1600 280 1800 250 2400 127 Flow rates after credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

HPI Flow (gpm) 0 817 600 817 1200 653 1500 573 1600 544 1800 482 2400 230 52% Full Power SBLOCA RCS Pressure (psig)

HPI FLow (gpm) 0 389 600 389 1200 303 1500 262 1600 248 1800 216 2400 84

Oconee Nuclear Station UFSAR Table 15-29 (Page 1 of 1)

(31 DEC 2015)

Table 15-29. HPI Flow Assumed in RCP Discharge Small Break LOCA Analyses 102% Full Power SBLOCA Flow rates prior to credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

Broken Leg Flow (gpm)

Intact Leg Flow (gpm) 0 243 185 600 243 185 1200 189 144 1500 167 127 1600 159 121 1800 142 108 2400 69 53 Flow rates after credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

Broken Leg Flow (gpm)

Intact Leg Flow (gpm) 0 243 574 600 243 574 1200 189 464 1500 167 406 1600 159 385 1800 142 340 2400 72 158 52% Full Power SBLOCA RCS Pressure (psig)

Broken Leg FLow (gpm)

Intact Leg Flow (gpm) 0 223 167 600 223 167 1200 174 130 1500 151 113 1600 142 106 1800 124 93 2400 48 36

Oconee Nuclear Station UFSAR Table 15-30 (Page 1 of 1)

(31 DEC 2015)

Table 15-30. HPI Flow Assumed in HPI Line Small Break LOCA Analyses 102% Full Power SBLOCA Flow rates prior to credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

Broken Leg/Spill Flow (gpm)

Intact Leg Flow (gpm) 0 259 181 600 320 124 1200 382 47 1500 408 0

Flow rates after credit for operator realignment of HPI at 10 minutes RCS Pressure (psig)

Broken Leg/Spill Flow (gpm)

Intact Leg Flow (gpm) 0 259 570 600 320 513 1200 383 366 1500 407 279 52% Full Power SBLOCA RCS Pressure (psig)

Broken Leg Flow (gpm)

Intact Leg Flow (gpm) 0 236 165 300 269 134 600 303 101 1200 377 15 1500 385 0

1600 385 0

1800 385 0

2400 385 0

Oconee Nuclear Station UFSAR Table 15-31 (Page 1 of 1)

(31 DEC 2008)

Table 15-31. Deleted Per 2008 Update

Oconee Nuclear Station UFSAR Table 15-32 (Page 1 of 2)

(31 DEC 2015)

Table 15-32. Summary of Transient and Accident Cases Analyzed UFSAR Section Description of Transient Summary of Cases Analyzed 15.2 Startup Accident Peak RCS pressure 15.3 Rod Withdrawal at Power

1. Core cooling capability

2. Peak RCS pressure 15.4 Moderator Dilution Accidents

1. Power operation

2. Refueling 15.5 Cold Water Accident Core cooling capability 15.6 Loss of Coolant Flow Core cooling capability:

1. Four RCP trip from four-RCPs

2. Two RCP trip from four-RCPs

3. One RCP trip from three-RCPs

4. Locked rotor from four-RCPs

5. Locked rotor from three-RCPs 15.7 Control Rod Misalignment Accidents Core cooling capability

1. Dropped rod from four-pumps

2. Dropped rod from three-pumps

3. Statically misaligned rod 15.8 Turbine Trip Peak RCS pressure 15.9 Steam Generator Tube Rupture Offsite dose 15.10 Waste Gas Tank Rupture Offsite dose 15.11 Fuel Handling Accidents Offsite dose

1. Fuel handling accident in Spent Fuel Pool

2. Fuel handling accident in containment

3. Fuel shipping cask drop

4. Dry storage canister cask drop

Oconee Nuclear Station UFSAR Table 15-32 (Page 2 of 2)

(31 DEC 2015)

UFSAR Section Description of Transient Summary of Cases Analyzed 15.12 Rod Ejection Peak fuel enthalpy 1/4. Four-pump BOC and EOC 2/5.Three-pump BOC and EOC 3/6.Three-pump BOC and EOC, HZP Core cooling capability 1/4.Four-pump BOC and EOC 2/5.Three-pump BOC and EOC 3/6.Three-pump BOC and EOC, HZP Peak RCS pressure

7. Three-pump BOC

8. Four-pump BOC 15.13 Steam Line Break Core cooling capability

1. With offsite power

2. Without offsite power 15.14 Loss of Coolant Accidents 10CFR50.46 and offsite dose

1. Large-break LOCA spectrum Full-core Mk-B-HTP LOCA limits

2. Small-break LOCA spectrum (full power)

Full-core Mk-B-HTP LOCA limits

3. Small-break LOCA spectrum (reduced power)

Full-core Mk-B-HTP LOCA limits 15.15 Maximum Hypothetical Accident Large Break LOCA - offsite dose 15.16 Post-Accident Hydrogen Control Large Break LOCA - flammability limit 15.17 Small Steam Line Break Core cooling capability

Oconee Nuclear Station UFSAR Table 15-33 (Page 1 of 1)

(31 DEC 2013)

Table 15-33. Methodology Topical Reports and Computer Codes Used in Analyses UFSAR Section Topical Reports Computer Codes 15.2 Startup Accident DPC-NE-3005-PA RETRAN-3D SIMULATE-3 15.3 Rod Withdrawal at Power Accident DPC-NE-3005-PA RETRAN-3D VIPRE-01 SIMULATE-3 15.4 Moderator Dilution Accidents DPC-NE-3005-PA N/A 15.5 Cold Water Accident DPC-NE-3005-PA RETRAN-3D 15.6 Loss of Coolant Flow Accidents DPC-NE-3005-PA RETRAN-3D VIPRE-01 SIMULATE-3 15.7 Control Rod Misalignment Accidents DPC-NE-3005-PA RETRAN-3D VIPRE-01 SIMULATE-3 15.8 Turbine Trip Accident DPC-NE-3005-PA RETRAN-3D 15.9 Steam Generator Tube Rupture Accident DPC-NE-3005-PA RETRAN-3D 15.12 Rod Ejection Accident DPC-NE-3005-PA SIMULATE-3K SIMULATE-3 RETRAN-3D VIPRE-01 15.13 Steam Line Break Accident DPC-NE-3005-PA RETRAN-3D VIPRE-01 SIMULATE-3 15.14 Loss of Coolant Accident Large Breaks BAW-10192-PA RELAP5/MOD2-B&W CONTEMPT REFLOD3 BEACH Small Breaks BAW-10192-PA RELAP5/MOD2-B&W CONTEMPT 15.17 Small Steam Line Break Accident DPC-NE-3005-PA RETRAN-3D VIPRE-01 SIMULATE-3

Oconee Nuclear Station UFSAR Table 15-34 (Page 1 of 8)

(31 DEC 2016)

Table 15-34. Summary of Input Parameters for Accident Analyses Using Computer Codes UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

15.2 N/A 1.0E-7 532 2155 272,624 285

+7.0E-5 Note 15 0.0065 0

15.3 1

102 579 2125 378,400 195 0.0 Note 2 0.0065 0

2 102 581 2155 371,360 285 0.0 Note 2 0.0065 5

15.5 N/A 80 579 2125 282,665 195

-35.0E-5 Note 3 0.0049 0

15.6 1

102 579 2125 378,400 195 0.0 Note 2 0.0065 0

2 102 579 2125 378,400 195 0.0 Note 2 0.0065 0

3 80 579 2125 282,665 195 0.0 Note 2 0.0065 0

4 102 579 2125 378,400 195 0.0 Note 2 0.0065 0

5 75 579 2125 282,665 195

+0.56E-5 Note 2 0.0065 0

15.7 1

102 579 2125 381.920 195 0.0 Note11

.0058 0

2 75 579 2125 282,665 195

+0.56E-5 Note 11

.0058 0

15.8 N/A 102 581 2185 374,493 285 0.0 Note 2 0.0065 5

15.9 N/A 102 577 2185 371,360 285

-35.0E-5 Note 4 0.0049 5

15.12 (Note

7) 1 102 581 2095 374,880 N/A 0.0

-1.10E-5 0.0058 N/A 2

77 581 2095 275,614 N/A

+0.56E-5

-1.16E-5 0.0058 N/A 3

0 540 2095 275,614 N/A

+7.0E-5

-1.42E-5 0.0058 N/A 4

102 581 2095 374,880 N/A

-28.0E-5

-1.19E-5 0.0047 N/A 5

77 581 2095 275,614 N/A

-28.0E-5

-1.22E-5 0.0047 N/A 6

0 540 2095 275,614 N/A

-12.0E-5

-1.53E-5 0.0047 N/A

Oconee Nuclear Station UFSAR Table 15-34 (Page 2 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

7 77 581 2095 275,614 285

+0.56E-5

-1.16E-5 0.0058 5

8 102 581 2095 374,880 285 0.0

-1.10E-5 0.0058 5

15.13 1

102 577 2095 371,360 195 Note 8 Note 5 0.0 0

2 102 579 2125 378,400 285 0.0 Note 6 0.0065 0

15.14 1

102 579 2155 374,880(10) 220 0.0 Note 4 0.007 7

2 102 579 2155 374,880(10) 220 0.0 Note 4 0.007 7

3 52 579 2155 374,880(10) 220

+5.0 Note 4 0.007 7

15.17 N/A 102 579 2125 381,902(17) 195

-7.0 Note 14 0

Note:

1. This flow rate corresponds to 105.5% of Design Flow.

2. Doppler Reactivity assumption as function of average fuel temperature:

Accident Analyses: 15.3, 15.6 (Cases 1-5), 15.8 Average Fuel Temperature Doppler Coefficient

(°F) k/k-°F (x10-5) 230.0

-1.89 450.0

-1.58 750.0

-1.27 1450.0

-1.02 Note:

3. Doppler reactivity assumption as function of average fuel temperature:

Accident Analyses: 15.5

Oconee Nuclear Station UFSAR Table 15-34 (Page 3 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

Average Fuel Temperature Doppler Coefficient

(°F) k/k-°F (x10-5) 472.18

-1.7290 632.60

-1.5926 889.68

-1.3738 1358.65

-1.2662 Note:

4. Doppler reactivity assumption as function of average fuel temperature:

Accident Analyses: 15.9, 15.14 Case 1 Average Fuel Temperature Doppler Coefficient

(°F) k/k-°F (x10-5) 452.38

-2.1782 754.3

-1.8795 1149.79

-1.6651 1350

-1.5566 Note:

5. Doppler reactivity assumption as function of average fuel temperature:

Accident Analysis: 15.13 Case 1 Average Fuel Temperature Doppler Reactivity

(°F)

%k/k 953.8 0

940.55 0.0221

Oconee Nuclear Station UFSAR Table 15-34 (Page 4 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

950.0 0.0 938.59 0.0169 918.39 0.0477 532 0.8804 512 0.9194 500 0.9419 450 1.0398 400 1.1398 Average Fuel Temperature Doppler Reactivity 350 1.2423 300 1.3480 250 1.4571 200 1.570 Note:

6. Doppler reactivity assumption as function of average fuel temperature:

Accident Analysis 15.13 Case 2 Average Fuel Temperature Doppler Reactivity

(°F)

%k/k/°F 1450

-1.02E-5 750

-1.27E-5 450

-1.58E-5

Oconee Nuclear Station UFSAR Table 15-34 (Page 5 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

230

-1.89E-5 Deleted Row(s) Per 2008 Update Note:

7. Actual physics parameter values determined from code cross section library for 15.12 Cases 1-7, target values listed for moderator and doppler reactivities and -effective

8. Moderator reactivity assumption as a function of moderator density.

Accident Analysis: 15.13 Case 1 Moderator Density Moderator Reactivity (lbm/ft3)

%k/k 44.6590 0

45.2758 0.2253 Moderator Density Moderator Reactivity 46.0125 0.4866 47.6731 0.6991 47.6658 1.0369 47.8133 1.0824 49.1185 1.6595 49.5917 1.8547 51.5476 2.6327 52.0171 2.8095 53.7633 3.4392 54.1503 3.5729

Oconee Nuclear Station UFSAR Table 15-34 (Page 6 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

55.7105 4.0921 56.0313 4.1950 Deleted Row(s) Per 2008 Update

9. Deleted Row(s) Per 2008Update Note:

10. This flow rate corresponds to 106.5% of Design Flow.

11. Doppler reactivity assumption as a function of average fuel temperature:

Accident Analyses: 15.7 Average Fuel Temperature Doppler Coefficient

(°F) k/k-°F (x10-5) 230.0

-1.89 450.0

-1.58 Average Fuel Temperature Doppler Coefficient 750.0

-1.27 1450.0

-1.02

12. Deleted Row(s) per 2008 Update Note:

13. Doppler reactivity assumption as a function of average fuel temperature:

Accident Analysis: 15.17 Average Fuel Temperature Doppler Coefficient

(°F) k/k-°F (x10-5)

Oconee Nuclear Station UFSAR Table 15-34 (Page 7 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

230.0

-1.89 450.0

-1.58 750.0

-1.27 1450.0

-1.02 Note:

14. Doppler reactivity assumption interpolated between the following:

BOC EOC Average Fuel Temperature Doppler Coefficient Average Fuel Temperature Dopler Coefficient

(°F) k/k-°F (x10-5)

(°F) k/k-°F (x10-5) 230.0

-1.89 472.18

-1.7290 450.0

-1.58 632.60

-1.5926 750.0

-1.27 889.68

-1.3738 1450.0

-1.02 1358.65

-1.2662 Average Fuel Temperature Doppler Coefficient Average Fuel Temperature Dopler Coefficient eff interpolated between the following BOC EOC

.0065

.0054 Note:

15. Doppler reactivity assumption as a function of temperature:

Accident Analysis: 15.2 Average Fuel Temperature Doppler Coefficient

Oconee Nuclear Station UFSAR Table 15-34 (Page 8 of 8)

(31 DEC 2016)

UFSAR Section Case Identifier Power Level

(%FP)

RCS T-ave

(°F)

(Note 16)

RCS Pressure (psig)

RCS FLOW (gpm)

Pressuriz er Level (inches)

MTC (k/k./°F)

DTC (k/k./°F) effective SG Tube Pluggin g (%)

(°F) k/k-°F (x10-5) 231.4

-2.0174 452.47

-1.6873 743.78

-1.3838 1434.14

-1.1136 Note:

16. All accident analyses have been evaluated for an end-of-cycle T-ave reduction of up to 10°F lower than the T-ave values shown in this table.

17. This flow rate corresponds to 108.5% of Design Flow.

Oconee Nuclear Station UFSAR Table 15-35 (Page 1 of 2)

(31 DEC 2016)

Table 15-35. Trip Setpoints and Time Delays Assumed in Accident Analyses Trip Functions Nominal Setpoint Limiting Trip Setpoint Assumed in Analyses Time Delay (seconds)

RPS:

High Flux (8)

High Flux(11) 107.5% FP 80.5% FP 108.5%

112.0% (10) 81.5%

0.4 0.4 High Pressure 2355 psig 2362 psig 0.5 Low Pressure 1800 psig 1793 psig(2) 0.5 Variable Low Pressure-Temperature Trip if: (1)

P<11.14 Thot-4706 Trip if: (1)

P<11.14 Thot-4716 0.7 High Temperature 618°F 618.85°F 0.7 Flux/Flow (8)

Trip if: (3)

> 109.4%FP/flow Fm Trip if: (3)

> 109.4%FP/flow Fm

+2.2%FP 1.2 Pump Monitor NA 0.9

Oconee Nuclear Station UFSAR Table 15-35 (Page 2 of 2)

(31 DEC 2016)

ESPS:

HPI Trip Setpoint HPI Time Delay (seconds)

LPI Time Delay (Seconds)

CFT Setpoint Nominal Setpoint 1590 psig 2 psid Transient LBLOCA N/A N/A 38 + 36 sec. ramp (Note 7)

SBLOCA 1500 psig 48 (LOOP)

N/A (Note 7)

Large Steam Line Break 1400 psig 15 (no LOOP) 38 (LOOP)

N/A

+6.5 psid (CFT A)

-2.5 psid (CFT B)

Small Steam Line Break 1450 psig 15 (no LOOP) 38 (LOOP)

N/A N/A Rod Ejection (Note 5)

(Note 5)

N/A N/A SGTR (Note 6)

(Note 6)

N/A N/A Notes:

1. P is gauge pressure.

2. SBLOCA assumes 1765 psig.

3. "Fm" is measured flow.

4. Deleted per 2003 update.

5. Rod ejection assumes HPI actuation 5 seconds after the event begins.

6. SGTR assumes HPI actuation coincident with the tube rupture.

7. LOCA analyses assume a CFT nitrogen pressure of 550 psig. The CFT line break case considers a pressure of 547 psig to account for check valve leakage.

8. %FP is % of 2568 mwth.

9. Deleted per 2010 update.

10. Rod Ejection at 102% FP.

11. 3 RCP Small Steam Line Break.

Oconee Nuclear Station UFSAR Table 15-36 (Page 1 of 1)

(31 DEC 2013)

Table 15-36. Startup Accident Sequence of Events Event Time(sec)

Rod withdrawal begins 0.0 Pressurizer control heaters de-energize 49.3 High power reactor trip 50.6 Control rod insertion begins 51.0 Pressurizer safety valves open 53.3 Peak RCS pressure occurs 53.7 Pressurizer safety valves reseat 55.5 End of simulation 100.0

Oconee Nuclear Station UFSAR Table 15-37 (Page 1 of 1)

(31 DEC 2008)

Table 15-37. Rod Withdrawal at Power Accident - Peak RCS Pressure Analysis Sequence of Events Event Time (sec)

Rod withdrawal begins 0.0 High RCS pressure reactor trip setpoint reached 36.7 Control rod insertion begins 37.2 Turbine trip on reactor trip 37.2 Main steam safety valves lift 39.8 - 41.2 Peak RCS pressure occurs 41.0 Main steam safety valves begin to reseat 47.3 End of simulation 47.3

Oconee Nuclear Station UFSAR Table 15-38 (Page 1 of 1)

(31 DEC 2003)

Table 15-38. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis Sequence of Events Event Time (sec)

Rod withdrawal begins 0.0 Pressurizer spray actuates 92.7 High temperature reactor trip setpoint reached 204.4 Control rod insertion begins 205.1 Turbine trip on reactor trip 206.1 Main steam safety valves lift 208.4 - 210.4 Pressurizer spray terminates 211.2 End of simulation 215.2

Oconee Nuclear Station UFSAR Table 15-39 (Page 1 of 1)

(31 DEC 2015)

Table 15-39. Cold Water Accident Sequence of Events Event Time (sec)

Fourth RCP starts 0.1 RCP reaches full speed 5.1 Maximum heat flux occurs (97.5%)

6.9 End of simulation 15.0

Oconee Nuclear Station UFSAR Table 15-40 (Page 1 of 1)

(31 DEC 2008)

Table 15-40. Loss of Flow Accidents Four RCP Coastdown from Four RCP Initial Conditions Sequence of Events Event Time (sec)

All RCPs trip 0.0 Pump monitor reactor trip 0.0 Rod motion begins 0.9 Turbine trip on reactor trip 1.1 Pressurizer spray initiates 2.7 MSSVs lift 3.9 - 4.7 Pressurizer spray terminates 11.4 End of simulation 20.0

Oconee Nuclear Station UFSAR Table 15-41 (Page 1 of 1)

(31 DEC 2003)

Table 15-41. Loss of Flow Accidents Two RCP Coastdown from Four RCP Initial Conditions Sequence of Events Event Time (sec)

Two RCPs trip 0.0 Flux/flow reactor trip setpoint reached 3.0 Rod motion begins 4.2 Turbine trip on reactor trip 4.4 Pressurizer spray initiates 5.4 MSSVs lift 6.5 - 11.2 End of simulation 20.0

Oconee Nuclear Station UFSAR Table 15-42 (Page 1 of 1)

(31 DEC 2003)

Table 15-42. Loss of Flow Accidents One RCP Coastdown from Three RCP Initial Conditions Sequence of Events Event Time (sec)

One RCPs trip 0.0 Flux/flow reactor trip setpoint reached 3.8 Rod motion begins 5.0 Turbine trip on reactor trip 5.2 MSSVs lift 7.4 - 9.8 End of simulation 20.0

Oconee Nuclear Station UFSAR Table 15-43 (Page 1 of 1)

(31 DEC 2003)

Table 15-43. Loss of Flow Accidents Locked Rotor from Four RCP Initial Conditions Sequence of Events Event Time (sec)

Locked rotor occurs 0.0 Flux/flow reactor trip setpoint reached 0.5 Rod motion begins 1.7 Turbine trip on reactor trip 1.8 Pressurizer spray initiates 2.8 MSSVs lift 3.9 - 7.8 End of simulation 10.0

Oconee Nuclear Station UFSAR Table 15-44 (Page 1 of 1)

(31 DEC 2008)

Table 15-44. Loss of Flow Accidents Locked Rotor from Three RCP Initial Conditions Sequence of Events Event Time (sec)

Locked rotor occurs 0.0 Flux/flow reactor trip setpoint reached 0.4 Rod motion begins 1.6 Turbine trip on reactor trip 1.8 Pressurizer spray initiates 3.5 MSSVs lift 4.8 - 8.8 End of simulation 10.0

Oconee Nuclear Station UFSAR Table 15-45 (Page 1 of 1)

(31 DEC 2010)

Table 15-45. Control Rod Misalignment Accidents - Dropped Rod Accident Sequence of Events Event Time (sec)

Control rod drops 0.01 ICS initiates control rod withdrawal 0.6 Control rod withdrawal terminates 12.9 Pressurizer spray initiates 21.6 Terminate Pressurizer Spray 68.2 End of Simulation 90.0

Oconee Nuclear Station UFSAR Table 15-46 (Page 1 of 1)

(31 DEC 2013)

Table 15-46. Turbine Trip Accident Sequence of Events Event Time (sec)

Turbine trip 0.01 MFW isolation 0.01 Main steam safety valves start to lift 2.5 High RCS pressure reactor trip 3.6 Control rod insertion begins 4.1 Peak RCS pressure occurs 6.0 Main steam safety valves start to reseat 11.3 End of simulation 40.0

Oconee Nuclear Station UFSAR Table 15-47 (Page 1 of 1)

(31 DEC 2011)

Table 15-47. Steam Generator Tube Rupture Accident Sequence of Events Event Seconds SGTR occurs 0.1 HPIS injection flow starts 0.1 Reactor trip 1,200 Turbine trip on reactor trip 1,200 MFW pumps trip 1,200 MSSVs lift and begin cycling 1,202 EFW flow to ruptured SG begins 1,380 Operator identifies EFW control valve is failed closed 1,980 EFW to both SG is restored 2,580 Operator identifies ruptured SG 3,180 Operator begins minimizing subcooled margin 3,900 Operator begins cooldown to 532°F with ADVs 6,300 All MSSVs have reseated 6,300 RCS cooled down to 532°F 7,040 Operator completes isolation of the ruptured SG 8,240 Operator trips one RCP in loop without pressurizer 8,240 Shift changeover begins 8,240 Steaming of ruptured SG due to high SG level begins 10,621 Shift changeover completed 11,840 Operator begins RCS cooldown to 450°F.

12,140 RCS temperature reaches 450°F. - RCS Boron Concentration is determined and boration to cold shutdown initiated.

15,191 Operator begins cooldown to LPIS conditions 22,691 Operator trips one RCP in loop with the pressurizer 24,605 LPIS conditions reached 31,455 Start cooldown with LPIS 36,855 Plant cooled down to 212°F 40,725

Oconee Nuclear Station UFSAR Table 15-48 (Page 1 of 1)

(31 DEC 2003)

Table 15-48. Steam Line Break Accident - Without Offsite Power Case Sequence of Events Event Time (sec)

Break initiates, offsite power lost, reactor trips 0.0 RCPs begin to coast down Deleted row(s) per 2003 update Control rod insertion begins 0.14 Turbine stop valves closed 1.72 Control rods fully inserted 2.54 End of simulation 5

Oconee Nuclear Station UFSAR Table 15-49 (Page 1 of 1)

(31 DEC 2016)

Table 15-49. Small Steam Line Break Accident Sequence of Events Event Time (sec)

Break occurs 10 Pressurizer heater backup banks energize, makeup flow starts 10.6 Third Condensate Booster Pump actuates 18.7 Pressurizer heater control and backup banks de-energize on low pressurizer level 174.5 MDNBR occurs 195 Pressurizer heater control and backup banks energize 248.6 Peak neutron power 610.0 Problem termination 610

Oconee Nuclear Station UFSAR Table 15-50 (Page 1 of 2)

(31 DEC 2009)

Table 15-50. Failed Fuel Source Term for the Rod Ejection Accident (Curies)

Nuclide Single DNB Assembly Activity Release Fraction Failed Fuel Gap Release Source Term1 I--130 2.14E+04 10%

1.70E+05 I--131 6.20E+05 10%

4.94E+06 I--132 9.14E+05 10%

7.28E+06 I--133 1.33E+06 10%

1.06E+07 I--134 1.55E+06 10%

1.23E+07 I--135 1.26E+06 10%

1.00E+07 BR--83 1.04E+05 5%

4.16E+05 BR--85 2.41E+05 5%

9.59E+05 BR--87 3.96E+05 5%

1.58E+06 KR--83M 1.04E+05 10%

8.32E+05 KR--85M 2.42E+05 10%

1.92E+06 KR--85 8.30E+03 10%

6.61E+04 KR--87 4.93E+05 10%

3.93E+06 KR--88 6.72E+05 10%

5.35E+06 KR--89 8.58E+05 10%

6.84E+06 XE131M 8.02E+03 10%

6.39E+04 XE133M 4.01E+04 10%

3.19E+05 XE-133 1.27E+06 10%

1.01E+07 XE135M 2.64E+05 10%

2.10E+06 XE-135 4.20E+05 10%

3.34E+06 XE-137 1.21E+06 10%

9.65E+06 XE-138 1.23E+06 10%

9.83E+06 RB--86 1.68E+03 12%

1.60E+04 RB--88 6.77E+05 12%

6.47E+06 RB--89 8.98E+05 12%

8.58E+06 RB--90 8.46E+05 12%

8.09E+06 CS-134 1.94E+05 12%

1.85E+06 CS-136 4.67E+04 12%

4.46E+05 CS-137 9.61E+04 12%

9.19E+05 CS-138 1.32E+06 12%

1.26E+07

Oconee Nuclear Station UFSAR Table 15-50 (Page 2 of 2)

(31 DEC 2009)

Nuclide Single DNB Assembly Activity Release Fraction Failed Fuel Gap Release Source Term1 CS-139 1.24E+06 12%

1.19E+07 Note:

1. Assumes 45% failed fuel.

Oconee Nuclear Station UFSAR Table 15-51 (Page 1 of 1)

(31 DEC 2009)

Table 15-51. Reactor Coolant System Fission Product Source Activities - 500 EPFD Equilibrium Cycle1 Nuclide Maximum Specific Activity 2

(µCi/gm)

Maximum Total Coolant 3 Activity (Curies)

I-131 5.80E+0 1.39E+3 I-132 8.36E+0 1.68E+3 I-133 7.03E+0 1.42E+3 I-134 7.76E-1 1.55E+2 I-135 3.32E+0 6.63E+2 Xe-131m 6.04E+0 1.21E+3 Xe-133m 6.42E+0 1.28E+3 Xe-133 4.67E+2 9.32E+4 Xe-135m 7.06E-1 1.41E+2 Xe-135 1.34E+1 2.67E+3 Xe-138 7.40E-1 1.48E+2 Kr-83m 5.34E-1 1.06E+2 Kr-85m 2.23E+0 4.44E+2 Kr-85 1.72E+2 3.43E+4 Kr-87 1.21E+0 2.42E+2 Kr-88 3.81E+0 7.60E+2 Note:

1. Reactor coolant activities at equilibrium assuming 1 percent failed fuel randomly distributed throughout the core.

2. Based on steady-state operation with no RCS leakage and no continuous pressurizer spray flow. Used for calculating doses arising from reactor coolant leaks to the secondary systems.

3. Based on steady-state operation with no RCS leakage and 1 gpm continuous pressurizer spray flow.

Oconee Nuclear Station UFSAR Table 15 15-55 (Page 1 of 1)

(31 DEC 2003)

Table 15-52. Deleted Per 2003 Update Table 15-53. Deleted Per 2003 Update Table 15-54. Deleted Per 2003 Update Table 15-55. Deleted Per 2003 Update

Oconee Nuclear Station UFSAR Table 15-56 (Page 1 of 1)

(31 DEC 2014)

Table 15-56. Deleted Per 2014 Update Table 15-57. Deleted per 2014 Update

Oconee Nuclear Station UFSAR Table 15-57 (Page 1 of 1)

(31 DEC 2014)

Table 15-57. Deleted Per 2014 Update

Oconee Nuclear Station UFSAR Table 15-58 (Page 1 of 1)

(31 DEC 2003)

Table 15-58. Parameters Used To Determine Hydrogen Generation Reactor Thermal Power (102%)

2,568 MWt Reactor Operating Time (average cycle length) 980 Days Containment Free Volume 1.79E+06 ft3 Weight Of Zirconium Surrounding The Fuel 41,000 lbm Hydrogen Generated From 5.0% Zr-Water Reaction 17,435 scf Hydrogen Dissolved In Primary Coolant And Pressurizer Gas Space 450 scf Corrodable Metals Aluminum, Zinc Hydrogen Generated From Radiolysis Sources Core Radiolysis Sump Radiolysis Percent of total halogens retained in solution 50 50 Percent of total noble gases retained in solution 0

0 Percent of other fission products retained in solution 99 1

Energy Distribution Percent of total decay energy -

Gamma 50 50 Percent of total decay energy -

Beta 50 50 Energy Absorption by the Solution Percent of gamma energy absorbed 10 100 Percent of beta energy absorbed 0

100 Molecules of H2 Produced per 100 ev Energy Absorbed 0.45 0.3

Oconee Nuclear Station UFSAR Table 15-59 (Page 1 of 1)

(31 DEC 2001)

Table 15-59. Deleted Per 2001 Update

Oconee Nuclear Station UFSAR Table 15-60 (Page 1 of 1)

(31 DEC 2014)

Table 15-60. Deleted per 2014 Update

Oconee Nuclear Station UFSAR Table 15-61 (Page 1 of 2)

(31 DEC 2009)

Table 15-61. Control Room Atmospheric Dispersion Factors (/Qs)

Release Type Bounding /Q (sec/m3)

Units Vent Releases 0 to 2 hr 9.43E-04 2 to 8 hr 6.00E-04 8 to 24 hr 2.41E-04 1 to 4 days 1.87E-04 4 to 30 days 1.54E-04 Main Steam Penetration Releases 0 to 2 hr 5.76E-04 2 to 8 hr 4.09E-04 8 to 24 hr 1.72E-04 1 to 4 days 1.34E-04 4 to 30 days 1.08E-04 Equipment Hatch Releases 0 to 2 hr 6.59E-04 2 to 8 hr 4.86E-04 8 to 24 hr 2.13E-04 1 to 4 days 1.65E-04 4 to 30 days 1.28E-04 ADV Releases 0 to 2 hr 1.79E-03 2 to 8 hr 1.25E-03 8 to 24 hr 5.45E-04 1 to 4 days 4.17E-04 4 to 30 days 3.34E-04 MSSV Releases 0 to 2 hr 1.91E-03 2 to 8 hr 1.33E-03 8 to 24 hr 5.86E-04 1 to 4 days 4.52E-04 4 to 30 days 3.54E-04

Oconee Nuclear Station UFSAR Table 15-61 (Page 2 of 2)

(31 DEC 2009)

Release Type Bounding /Q (sec/m3)

MSLB Releases 0 to 2 hr 1.21E-03 2 to 8 hr 8.39E-04 8 to 24 hr 3.70E-04 1 to 4 days 2.81E-04 4 to 30 days 2.23E-04 Fuel Handling Building Roll-up Door Releases 0 to 2 hr 3.19E-04 2 to 8 hr 2.50E-04 8 to 24 hr 1.04E-04 1 to 4 days 7.89E-05 4 to 30 days 6.10E-05 BWST Releases 0 to 2 hr 4.76E-04 2 to 8 hr 3.27E-04 8 to 24 hr 1.35E-04 1 to 4 days 1.05E-04 4 to 30 days 8.99E-05

Oconee Nuclear Station UFSAR Table 15-62 (Page 1 of 2)

(31 DEC 2014)

Table 15-62. Results of LBLOCA Analyses for Mark-B-HTP Full Core Sequence of Events BOL Conditions Core Elevation, ft 2.506 4.264 6.021 7.779 9.536 Allowable peak linear heat rate, kW/ft 17.8 17.8 17.8 17.8 17.3 End of blowdown, sec 22.3 22.3 22.2 22.2 22.1 LPI begins injecting, sec 42.1 42.1 42.1 42.1 42.1 CFTs empty, sec 48.9 48.9 48.9 48.8 48.8 Unruptured node:

Peak cladding temperature, °F 1849.5 1867.4 1887.0 1905.7 1864.5 Time, sec 35.1 37.7 36.9 39.1 74.7 Local oxidation, %

1.10 1.43 1.58 1.83 1.87 Rupture node:

Peak cladding temperature, °F 1913.2 1897.2 1907.0 1857.6 1841.7 Time, sec 29.8 29.8 31.2 29.7 36.2 Local oxidation, %

1.89 1.99 2.39 2.08 2.01 Rupture time, sec 22.3 23.1 22.8 23.7 25.5 Hot pin initial pressure, psia 683 681 679 678 670 Whole core hydrogen generation, %

<0.14

<0.14

<0.15

<0.16

<0.15 MOL Conditions Core Elevation, ft 2.506 4.264 6.021 7.779 9.536 Allowable peak linear heat rate, kW/ft

[Note 1]

17.8 17.8 17.8 17.8 17.3 End of blowdown, sec 22.4 22.3 22.2 22.2 22.1 LPI begins injecting, sec 42.1 42.1 42.1 42.1 42.1 CFTs empty, sec 48.9 48.8 48.9 48.8 48.7 Unruptured node:

Peak cladding temperature, °F 1879.0 1858.3 1863.9 1863.3 1805.2 Time, sec 31.9 37.0 36.8 36.3 72.1 Local oxidation, %

1.85 2.03 2.11 2.33 2.27 Rupture node:

Peak cladding temperature, °F 1864.3 1776.3 1873.6 1766.7 1707.7 Time, sec 31.7 31.7 31.6 36.1 38.4 Local oxidation, %

2.11 1.88 2.31 1.93 1.74 Rupture time, sec 19.7 21.3 20.8 22.2 24.4 Hot pin initial pressure, psia 1898 1853 1817 1818 1792 Whole core hydrogen generation, %

<0.07

<0.07

<0.08

<0.09

<0.08 Note 1: The allowable peak linear heat rates shown above at MOL were used in the Analysis of Record.

To account for fuel pellet thermal conductivity degradation, the MOL values for all core elevations are penalized (reduced) by 2 kW/ft. See Sections 15.14.4.1.6 and 15.14.4.4.

Oconee Nuclear Station UFSAR Table 15-62 (Page 2 of 2)

(31 DEC 2014)

EOL Conditions Core Elevation, ft 2.506 4.264 6.021 7.779 9.536 Allowable peak linear heat rate, kW/ft 12.3 N/A N/A N/A N/A End of blowdown, sec 22.3 N/A N/A N/A N/A LPI begins injecting, sec 42.1 N/A N/A N/A N/A CFTs empty, sec 48.9 N/A N/A N/A N/A Unruptured node:

Peak cladding temperature, °F 1577.0 N/A N/A N/A N/A Time, sec 31.8 N/A N/A N/A N/A Local oxidation, %

1.81 N/A N/A N/A N/A Rupture node:

Peak cladding temperature, °F 1618.3 N/A N/A N/A N/A Time, sec 31.6 N/A N/A N/A N/A Local oxidation, %

1.92 N/A N/A N/A N/A Rupture time, sec 24.8 N/A N/A N/A N/A Hot pin initial pressure, psia 2971 N/A N/A N/A N/A Whole core hydrogen generation, %

<0.03 N/A N/A N/A N/A

Oconee Nuclear Station UFSAR Table 15-63 (Page 1 of 2)

(31 DEC 2014)

Table 15-63. Results of LBLOCA Analyses for Full Core Mark-B-HTP; Gadolinia Fuel Pins 2 w/o Gadolinia Concentration BOL MOL EOL Burnup, GWd/mtU 0

34 62 Allowable peak linear heat rate, kW/ft

[Note 1]

16.9 16.9 11.6 Axial Peak Elevation, ft 2.506 2.506 2.506 End of blowdown, sec 22.3 22.4 22.3 LPI begins injecting, sec 42.1 42.1 42.1 CFTs empty, sec 48.9 48.9 48.9 Unruptured node:

Peak cladding temperature, °F 1814.4 1833.4 1556.4 Time, sec 35.1 31.9 31.8 Local oxidation, %

0.97 1.72 2.10 Rupture node:

Peak cladding temperature, °F 1858.6 1793.8 1581.8 Time, sec 29.8 31.7 31.5 Local oxidation, %

1.57 1.84 2.18 Rupture time, sec 23.2 20.5 25.0 Pin initial pressure, psia 676 1745 2694 4 w/o Gadolinia Concentration BOL MOL EOL Burnup, GWd/mtU 0

34 62 Allowable peak linear heat rate, kW/ft

[Note 1]

16.1 16.1 11.1 Axial Peak Elevation, ft 2.506 2.506 2.506 End of blowdown, sec 22.3 22.4 22.3 LPI begins injecting, sec 42.1 42.1 42.1 CFTs empty, sec 48.9 48.9 48.9 Unruptured node:

Peak cladding temperature, °F 1812.2 1856.2 1566.7 Time, sec 35.1 31.9 31.8 Local oxidation, %

0.95 1.76 2.34 Rupture node:

Peak cladding temperature, °F 1862.7 1826.0 1581.3 Time, sec 29.8 31.7 31.5 Local oxidation, %

1.58 1.95 2.41 Rupture time, sec 23.2 20.3 25.0 Pin initial pressure, psia 675 1823 2706

Oconee Nuclear Station UFSAR Table 15-63 (Page 2 of 2)

(31 DEC 2014) 6 w/o Gadolinia Concentration BOL MOL EOL Burnup, GWd/mtU 0

34 62 Allowable peak linear heat rate, kW/ft

[Note 1]

15.6 15.6 10.8 Axial Peak Elevation, ft 2.506 2.506 2.506 End of blowdown, sec 22.3 22.4 22.3 LPI begins injecting, sec 42.1 42.1 42.1 CFTs empty, sec 48.9 48.9 48.9 Unruptured node:

Peak cladding temperature, °F 1813.8 1848.8 1578.7 Time, sec 35.1 31.9 31.8 Local oxidation, %

0.95 1.73 2.34 Rupture node:

Peak cladding temperature, °F 1874.3 1821.9 1598.0 Time, sec 29.8 31.7 31.5 Local oxidation, %

1.63 1.93 2.42 Rupture time, sec 23.1 20.4 24.8 Pin initial pressure, psia 675 1770 2797 8 w/o Gadolinia Concentration BOL MOL EOL Burnup, GWd/mtU 0

34 62 Allowable peak linear heat rate, kW/ft

[Note 1]

15.1 15.1 10.4 Axial Peak Elevation, ft 2.506 2.506 2.506 End of blowdown, sec 22.3 22.4 22.3 LPI begins injecting, sec 42.1 42.1 42.1 CFTs empty, sec 48.9 48.9 48.9 Unruptured node:

Peak cladding temperature, °F 1814.2 1806.0 1575.8 Time, sec 35.1 31.9 31.8 Local oxidation, %

0.94 1.62 2.22 Rupture node:

Peak cladding temperature, °F 1881.1 1771.9 1594.5 Time, sec 29.8 31.7 31.5 Local oxidation, %

1.66 1.75 2.30 Rupture time, sec 23.1 21.1 24.9 Pin initial pressure, psia 675 1697 2749 Note 1: The allowable peak linear heat rates shown above at MOL were used in the Analysis of Record.

To account for fuel pellet thermal conductivity degradation, the MOL values for all core elevations are penalized (reduced) by 2 kW/ft. See Sections 15.14.4.1.6 and 15.14.4.4.

Oconee Nuclear Station UFSAR Table 15-64 (Page 1 of 1)

(31 DEC 2011)

Table 15-64. Results of 102% FP SBLOCA Analyses for Full Core Mark-B-HTP Break Size and Description PCT (°F)

Time of PCT (sec)

Local Oxidation (%)

Whole Core H2 Generation (%)

0.01 ft2 CLPD with LOOP 711.9 (1) 0.005 0.08

<0.01 0.04 ft2 CLPD with LOOP 711.9 (1) 0.005 0.08

<0.01 0.07 ft2 CLPD with LOOP 711.9 (1) 0.005 0.08

<0.01 0.1 ft2 CLPD with LOOP 1288.2 959.8 0.16

<0.01 0.125 ft2 CLPD with LOOP 1515.4 739.0 0.48

<0.02 0.15 ft2 CLPD with LOOP 1597.5 641.6 0.88

<0.04 0.175 ft2 CLPD with LOOP 1565.9 557.7 0.70

<0.03 0.2 ft2 CLPD with LOOP 1474.1 498.9 0.34

<0.02 0.3 ft2 CLPD with LOOP 1310.3 330.2 0.13

<0.01 0.4 ft2 CLPD with LOOP 1126.3 214.4 0.08

<0.01 0.5 ft2 CLPD with LOOP 1103.5 126.9 0.08

<0.01 0.3 ft2 CLPD with 2 Min RCP Trip 711.9 (1) 0.005 0.08

<0.01 0.4 ft2 CLPD with 2 Min RCP Trip 1175.9 233.1 0.09

<0.01 0.5 ft2 CLPD with 2 Min RCP Trip 1255.5 210.0 0.10

<0.01 0.02464 ft2 HPI with LOOP 711.9 (1) 0.005 0.08

<0.01 0.44 ft2 CFT with LOOP 711.9 (1) 0.005 0.08

<0.01 0.44 ft2 CFT with 2 Min RCP Trip 1072.8 215.9 0.08

<0.01 Notes:

1.

Indicates initial steady-state cladding temperature.

Oconee Nuclear Station UFSAR Table 15-65 (Page 1 of 1)

(31 DEC 2012)

Table 15-65. Dose Equivalent Iodine (DEI) Calculation Isotope Concentration

(µCi/gm)

FGR No. 11, Table 2.1 DCFs (Sv/Bq)

DEI

(µCi/gm)

I-131 9.55E-01 8.89E-09 9.55E-01 I-132 1.42E-01 1.03E-10 1.64E-03 I-133 2.48E-01 1.58E-09 4.40E-02 I-134 1.32E-02 3.55E-11 5.27E-05 I-135 7.38E-02 3.32E-10 2.76E-03 DEI 1.00E+00

Oconee Nuclear Station UFSAR Table 15-66 (Page 1 of 1)

(31 DEC 2012)

Table 15-66. Dose Equivalent Xenon (DEX) Calculation Isotope Concentration

(µCi/gm)

FGR No. 12, Table III.1 DCFs (Sv-s/Bq-m3)

DEX (µCi/gm)

KR-85M 2.15E+00 7.48E-15 1.03E+01 KR-85 1.82E+01 1.19E-16 1.39E+00 KR-87 1.18E+00 4.12E-14 3.11E+01 KR-88 3.69E+00 1.02E-13 2.41E+02 XE-131M 4.39E+00 3.89E-16 1.09E+00 XE-133M 5.76E+00 1.37E-15 5.06E+00 XE-133 3.93E+02 1.56E-15 3.93E+02 XE-135M 4.47E-01 2.04E-14 5.84E+00 XE-135 1.14E+01 1.19E-14 8.67E+01 XE-138 7.19E-01 5.77E-14 2.66E+01 DEX 8.02E+02

Oconee Nuclear Station UFSAR Table 15-67 (Page 1 of 1)

(31 DEC 2014)

Table 15-67. Peak Cladding Temperature Results of LBLOCA Reanalyses for Mark-B-HTP Full Core to Address Error Corrections, UO2 Fuel Pins Time in Life (GWd/mtU)

BOL (0)

MOL (34)

EOL (62)

Peaking Elevation (ft)

Node Peaking Cladding Temperature (°F) 0.0 Both

<1836.9

<1851.9

<1688.3 2.506 Ruptured 1834.6 1750.9 1618.3 2.506 Unruptured 1836.9 1851.9 1618.3 4.264 Ruptured 1821 1700 1618 4.264 Unruptured 1844 1835 1618 6.021 Ruptured 1833 1799 1618 6.021 Unruptured 1847 1824 1618 7.779 Ruptured 1785.5 1695 1618 7.779 Unruptured 1848.0 1806 1618 9.536 Ruptured 1772 1638 1618 9.536 Unruptured 1789 1730 1618 12.0 Both

<1789

<1730

<1738 Notes: PCT estimates are shown in italics. EOL values are conservatively set to the base analysis values per Table 15-62, and are not split between and unruptured nodes.

Oconee Nuclear Station UFSAR Table 15-68 (Page 1 of 2)

(31 DEC 2014)

Table 15-68. Peak Cladding Temperature Results of LBLOCA Reanalyses for Mark-B-HTP Full Core to Address Error Corrections, Gadolinia Fuel Pins Time in Life (GWd/mtU)

BOL (0)

MOL (34)

EOL (62)

Peaking Elevation (ft)

Gadolinia w/o Peaking Cladding Temperature (°F) 0.0 2

<1801.0

<1783.4

<1688.3 0.0 4

<1802.6

<1806.1

<1688.3 0.0 6

<1813.6

<1790.8

<1688.3 0.0 8

<1820.5

<1736.8

<1688.3 2.506 2

1801.0 1783.4 1618.3 2.506 4

1802.6 1806.1 1618.3 2.506 6

1813.6 1790.8 1618.3 2.506 8

1820.5 1736.8 1618.3 4.264 2

1808 1767 1618 4.264 4

1810 1789 1618 4.264 6

1821 1774 1618 4.264 8

1828 1720 1618 6.021 2

1811 1756 1618 6.021 4

1813 1778 1618 6.021 6

1824 1763 1618 6.021 8

1831 1709 1618 7.779 2

1812 1738 1618 7.779 4

1814 1760 1618 7.779 6

1825 1745 1618 7.779 8

1832 1691 1618 9.536 2

1753 1662 1618 9.536 4

1755 1684 1618 9.536 6

1766 1669 1618 9.536 8

1773 1615 1618 12.0 2

<1753

<1662

<1738 12.0 4

<1755

<1684

<1738 12.0 6

<1766

<1669

<1738 12.0 8

<1773

<1615

<1738

Oconee Nuclear Station UFSAR Table 15-68 (Page 2 of 2)

(31 DEC 2014)

Notes: PCT estimates are shown in italics. EOL values are conservatively set to the base analysis values for UO2 pins, as none of the EOL cases for gadolinia pins were explicitly reanalyzed.