ML18024A341
| ML18024A341 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/05/2017 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18018A778 | List:
|
| References | |
| Download: ML18024A341 (11) | |
Text
BFN-27 Table 14.6-1 Sheet 1 of 2 Iodine-131 Activity (Ci) by Location as Function of Time for CRDA Time - hrs Main Cond Stack Rm Control Rm Environment 0 2.99E+04 0.00E+00 0.00E+00 0.00E+00 0.4 2.35E+04 3.39E+00 2.32E-02 6.27E+02 0.5 2.22E+04 4.11E+00 2.57E-02 7.60E+02 0.8 1.8TE+04 6.03E+00 1.45E-02 1.12E+03 1.1 1.55E+04 7.62E+00 8.20E-03 1.42E+03 1.4 1.29E+04 8.93E+00 4.65E-03 1.67E+03 1.7 1.08E+04 1.00E+01 2.65E-03 1.88E+03 2 9.05E+03 1.09E+01 1.52E-03 2.06E+03 2.3 7.56E+03 1.16E+01 8.60E-04 2.20E+03 2.6 6.32E+03 1.22E+01 4.89E-04 2.33E+03 2.9 5.29E+03 1.27E+01 2.80E-04 2.43E+03 3.2 4.42E+03 1.31E+01 1.62E-04 2.51E+03 3.5 3.69E+03 1.34E+01 9.49E-05 2.59E+03 3.8 3.09E+03 1.36E+01 5.65E-05 2.65E+03 4.1 2.58E+03 1.38E+01 3.44E-05 2.70E+03 4.4 2.16E+03 1.40E+01 2.16E-05 2.74E+03 4.7 1.80E+03 1.41E+01 1.40E-05 2.77E+03 5 1.51E+03 1.41E+01 9.44E-06 2.80E+03 5.3 1.26E+03 1.42E+01 6.62E-06 2.83E+03 5.6 1.05E+03 1.42E+01 4.82E-06 2.85E+03 5.9 8.81E+02 1.42E+01 3.62E-06 2.86E+03 6.2 7.37E+02 1.42E+01 2.80E-06 2.88E+03 6.5 6.16E+02 1.42E+01 2.22E-06 2.89E+03 6.8 5.15E+02 1.41E+01 1.78E-06 2.90E+03 7.1 4.30E+02 1.41E+01 1.45E-06 2.91E+03 7.4 3.60E+02 1.40E+01 1.19E-06 2.92E+03 7.7 3.01E+02 1.40E+01 9.81E-07 2.92E+03 8 2.51E+02 1.39E+01 8.13E-07 2.93E+03 8.3 2.10E+02 1.39E+01 5.80E-07 2.93E+03
BFN-27 Table 14.6-1 Sheet 2 of 2 Iodine-131 Activity (Ci) by Location as Function of Time for CRDA Time - hrs Main Cond Stack Rm Control Rm Environment 8.6 1.76E+02 1.38E+01 4.29E-07 2.93E+03 8.9 1.47E+02 1.37E+01 3.28E-07 2.94E+03 9.2 1.23E+02 1.36E+01 2.56E-07 2.94E+03 9.5 1.03E+02 1.36E+01 2.04E-07 2.94E+03 9.8 8.58E+01 1.35E+01 1.65E-07 2.94E+03 10.1 7.17E+01 1.34E+01 1.35E-07 2.94E+03 10.4 6.00E+01 1.33E+01 1.11E-07 2.94E+03 24 1.78E-02 1.01E+01 0 2.95E+03 96 0 2.22E+00 0 2.95E+03 720 0 0 0 2.95E+03
BFN-27 TABLE 14.6-2 (Deleted by Amendment 19)
BFN-27 TABLE 14.6-3
SUMMARY
OF POWER UPRATE INPUT PARAMETERS USED FOR ALL CONTAINMENT ANALYSES Analysis Value for Parameter Unit Power Uprate Core Thermal Power 102% of uprated power (3458 MWt) MWt 3527 Initial Reactor Core Flow (100% rated) Mlbm/hr 102.5 Vessel dome pressure At 102% of uprated power (3458 MWt) psia 1053 (1)
Initial drywell pressure psia 17.0/15.1 Initial drywell temperature (Maximum value used to maximize the drywell temp. response) °F 150 Initial drywell relative humidity (Minimum) % 20 Initial wetwell pressure psia 15.9/15.1(1)
Initial wetwell airspace temperature (Maximum) °F 95 Initial wetwell airspace relative humidity (Maximum) % 100 Initial pressure suppression pool temperature (Maximum value used to maximize the suppression pool temp. °F 95 response)
Downcomer submergence at high water level ft. 3.83 Initial pressure suppression pool volume:
Maximum (at high water level corresponding to 3-10 downcomer submergence with a drywell to torus differential 3
pressure of 1.1 psid) ft 131,400 Minimum (at low water level corresponding to 2-11 downcomer submergence with zero drywell to torus 3
differential pressure) ft 121,500 3
Total pressure suppression chamber volume (including ft 250,800 pool) 3 Drywell free volume (including vent system) ft 171,000/159,000(1)
Torus-to-drywell vacuum breaker full open p psid 0.5 Number of downcomers 96 Downcomer I.D. ft. 1.956 Vent flow loss coefficient - 5.32 (1): The value that was most limiting for a specific analysis was used.
BFN-27 Table 14.6-4
SUMMARY
OF POWER UPRATE INPUT PARAMETERS USED FOR DBA-LOCA SHORT TERM CONTAINMENT RESPONSE Parameter Units Case 1(1) Case 2 Case 3(2) Case 4 Initial Reactor Thermal Power MWt 3527 3527 3527 2179 Initial Reactor Thermal Power % of uprated 102 102 102 63 Initial Reactor Core Flow Mlb/hr 102.5 102.5 83.0 39.0 Initial Reactor Core Flow % of uprated 100 100 81 38 Feedwater Temperature °F 384 328 328 328 Initial suppression pool volume ft3 131,400 131,400 131,400 131,400 Drywell Free Volume (including vent ft3 159000 159000 171000 159000 system)
Initial Drywell Pressure psia 15.1 17.0 17.0 17.0 Drywell-Wetwell Pressure difference psid 0.0 1.1 1.1 1.1 (1): This is the most limiting case for hydrodynamic loads.
(2): This is the most limiting case for DBA-LOCA drywell pressure and temperature response.
BFN-27 Table 14.6-5
SUMMARY
OF POWER UPRATE INPUT PARAMETERS USED FOR DBA-LOCA LONG-TERM CONTAINMENT RESPONSE Analysis Value for Parameter Unit Power Uprate Core Thermal Power 102% of uprated power (3458 MWt) MWt 3527 Core Flow (100% of rated) Mlbm/hr 102.5 3
Initial suppression pool volume ft 121,500 Decay Heat Model - ANS/ANSI 5.1 + 2 uncertainty RHRS Heat Exchanger Heat Removal Rate (BTU per hr) calculated at the following containment spray mode conditions:
- Shell side (RHR) flow (Minimum) gpm 6500
- Shell side inlet temperature (Maximum) °F 187.3 (Unit 1), 177 (Units 2 and 3)
- Tube side (RHRSW) flow (Minimum) gpm 4000
- Tube side inlet temperature °F 95 (Unit 1),
92(1) (Units 2 and 3)
- Heat exchanger k-factor Btu/sec-°F 223 (1) Operation with inlet temperature above 92°F is governed by Technical Specification limits for the Ultimate Heat Sink.
BFN-27 Table 14.6-6 DBA-LOCA SHORT TERM PRESSURE AND TEMPERATURE RESPONSE Parameter Units Case 1(1) Case 2 Case 3(2) Case 4 Peak Drywell Pressure psig 48.6 47.1 50.6 44.2 Peak Drywell Gas Temperature °F 295 294 297 290 (1): This is the most limiting case for hydrodynamic loads.
(2): This is the most limiting case for DBA-LOCA drywell pressure and temperature response for Unit 2 and 3. For Unit 1 the peak drywell pressure and peak drywell gas temperature are 48.5 psig and 295.2°F, respectively.
BFN-27 Table 14.6-7 BOUNDING CORE INVENTORY Isotope Ci/MWt Ci/MWt Isotope Ci/MWt Ci/MWt t=o t=24 hr t=o t=24 hr CO58 1.430E+02 1.416E+02 XE131M 3.544E+02 3.487E+-02 CO60 1.425E+02 1.424E+02 TE132 3.829E+04 3.089E+04 KR83M 3.432E+03 1.387E+01 I132 3.885E+04 3.184E+04 KR85 3.601E+02 3.601E+02 I133 5.534E+04 2.559E+04 KR85M 7.329E+03 1.811E+02 XE133 5.504E+04 5.303E+04 RB86 6.372E+01 6.141E+01 XE133M 1.734E+03 1.562E+03 KR87 1.446E+04 3.051E-02 I134 6.141E+04 1.450E-03 KR88 2.009E+04 5.743E+01 CS134 5.703E+03 5.697E+03 KR89 2.521E+04 0.000E+00 I135 5.250E+04 4.189E+03 SR89 2.786E+04 2.748E+04 XE135 1.971E+04 1.429E+04 SR90 3.165E+03 3.165E+03 XE135M 1.135E+04 6.823E+02 Y90 3.283E+03 3.273E+03 CS136 1.941E+03 1.841E+03 SR91 3.487E+04 6.103E+03 XE137 5.023E+04 0.000E+00 Y91 3.583E+04 3.564E+04 CS137 4.037E+03 4.037E+03 SR92 3.677E+04 7.922E+01 BA137M 3.829E+03 3.810E+03 Y92 3.696E+04 1.168E+03 XE138 4.757E+04 1.172E-26 Y93 4.147E+04 8.084E+03 BA139 4.930E+04 4.170E-01 ZR95 4.880E+04 4.822E+04 BA140 4.909E+04 4.644E+04 NB95 4.897E+04 4.897E+04 LA140 5.231E+04 5.079E+04 ZR97 4.953E+04 1.851E+04 LA141 4.498E+04 7.085E+02 MO99 5.088E+04 3.956E+04 CE141 4.535E+04 4.463E+04 TC99M 4.454E+04 3.772E+04 LA142 4.397E+04 1.035E+00 RU103 4.094E+04 4.018E+04 CE143 4.245E+04 2.597E+04 RU105 2.710E+04 6.615E+02 PR143 4.113E+04 4.075E+04 RH105 2.559E+04 1.840E+04 CE144 3.810E+04 3.810E+04 RU106 1.488E+04 1.486E+04 ND147 1.806E+04 1.698E+04 SB127 2.796E+03 2.369E+03 NP239 5.201E+05 3.902E+05 TE127 2.773E+03 2.580E+03 PU238 2.805E+02 2.805E+02 TE127M 3.721E+02 3.719E+02 PU239 1.234E+01 1.238E+01 SB129 8.457E+03 1.952E+02 PU240 1.730E+01 1.730E+01 TE129 8.326E+03 1.236E+03 PU241 4.450E+03 4.448E+03 TE129M 1.615E+03 1.590E+03 AM241 5.449E+00 5.470E+00 TE131M 5.155E+03 2.976E+03 CM242 1.234E+03 1.234E+03 I131 2.669E+04 2.481E+04 CM244 5.697E+01 5.697E+01
BFN-27 Table 14.6-8 (Sheet 1)
VALUES FOR X/Q FOR ACCIDENT DOSE CALCULATIONS Time Period Control Room Site Boundary LPZ Boundary 3 3 3 (sec/m ) (sec/m ) (sec/m )
Top of Stack Releases U1 Intake Unit 3 Intake (LOCA & CRDA) 0-0.5 hrs* 3.40E-5 3.02E-5 2.35E-5 1.26E-5 0.5-2 hrs 9.08E-13 1.41E-7 1.19E-6 1.13E-6 2-8 hrs 3.41E-13 4.50E-8 5.75E-7 8-24 hrs 2.09E-13 2.54E-8 4.10E-7 1-4 days 7.21E-14 7.36E-9 1.97E-7 4-30 days 1.57E-14 1.24E-9 6.88E-8 Base of Stack Releases (LOCA & CRDA) 0-2 hrs 2.00E-4 8.60E-5 2.62E-4 1.31E-4 2-8 hrs 1.28E-4 6.46E-5 6.61E-5 8-24 hrs 5.72E-5 2.80E-5 4.69E-5 1-4 days 4.05E-5 2.00E-5 2.23E-5 4-30 days 3.09E-5 1.53E-5 7.96E-6
BFN-27 Table 14.6-8 (Sheet 2)
VALUES FOR X/Q FOR ACCIDENT DOSE CALCULATIONS Time Period Control Room Site Boundary LPZ Boundary 3 3 3 (sec/m ) (sec/m ) (sec/m )
Refueling Vent Releases U1 Intake Unit 3 Intake (FHA and LOCA) ****
Not Used Not Used 0-2 hrs 4.60E-4 **
Not Used 2-8 hrs Not Used **
4.69E-5 8-24 hrs 1.57E-4 **
2.23E-5 1-4 days 1.12E-4 **
7.96E-6 4-30 days 7.90E-5 **
- Control room 0-2 hr for FHA only; values 8 hr+ for control room and LPZ Boundary used as surrogate for HCVS release Turbine Building Exhaust Release (MSLB - EAB/LPZ; Post-LOCA MSIV Leakage - Unit 1 Only) 0-2 hrs 3.22E-4 ** 2.62E-4 1.31E-4 2-8 hrs 2.77E-4 ** 6.61E-5 8-24 hrs 1.31E-4 ** 4.69E-5 1-4 days 7.91E-5 ** 2.23E-5 4-30 days 6.10E-5 ** 7.96E-6
- Bounded by the Unit 3 Intake
BFN-27 Table 14.6-9 (Deleted by Amendment 19)