ML18024A341

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.6 Table - Analysis of Design Basis Accidents

ML18024A341
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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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 Parameter Unit Analysis Value for 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 Initial drywell pressure psia 17.0/15.1(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. response)

°F 95 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 pressure of 1.1 psid) Minimum (at low water level corresponding to 2'-11" downcomer submergence with zero drywell to torus differential pressure) ft 3 ft 3 131,400 121,500 Total pressure suppression chamber volume (including pool) ft 3 250,800 Drywell free volume (including vent system) ft 3 171,000/159,000(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 ft 3 131,400 131,400 131,400 131,400 Drywell Free Volume (including vent system) ft 3 159000 159000 171000 159000 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 Parameter Unit Analysis Value for Power Uprate Core Thermal Power 102% of uprated power (3458 MWt)

MWt 3527 Core Flow (100% of rated) Mlbm/hr 102.5 Initial suppression pool volume ft 3 121,500 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)

- Shell side inlet temperature (Maximum)

- Tube side (RHRSW) flow (Minimum)

- Tube side inlet temperature

- Heat exchanger k-factor gpm °F gpm °F Btu/sec-°F 6500 187.3 (Unit 1), 177 (Units 2 and 3) 4000 95 (Unit 1),

92(1) (Units 2 and 3) 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 t=o Ci/MWt t=24 hr Isotope Ci/MWt t=o Ci/MWt t=24 hr CO58 1.430E+02 1.416E+02 XE131M 3.544E+02 3.487E+-02 CO60 1.425E+02 1.424E+02TE1323.829E+04 3.089E+04KR83M 3.432E+03 1.387E+01I1323.885E+04 3.184E+04KR85 3.601E+02 3.601E+02 I133 5.534E+04 2.559E+04 KR85M 7.329E+03 1.811E+02XE1335.504E+04 5.303E+04RB86 6.372E+01 6.141E+01 XE133M 1.734E+03 1.562E+03 KR87 1.446E+04 3.051E-02I1346.141E+04 1.450E-03KR88 2.009E+04 5.743E+01 CS134 5.703E+03 5.697E+03 KR89 2.521E+04 0.000E+00I1355.250E+04 4.189E+03SR89 2.786E+04 2.748E+04 XE135 1.971E+04 1.429E+04 SR90 3.165E+03 3.165E+03XE135M1.135E+04 6.823E+02Y90 3.283E+03 3.273E+03 CS136 1.941E+03 1.841E+03 SR91 3.487E+04 6.103E+03XE1375.023E+04 0.000E+00Y91 3.583E+04 3.564E+04CS1374.037E+03 4.037E+03SR92 3.677E+04 7.922E+01 BA137M 3.829E+03 3.810E+03 Y92 3.696E+04 1.168E+03XE1384.757E+04 1.172E-26Y93 4.147E+04 8.084E+03 BA139 4.930E+04 4.170E-01 ZR95 4.880E+04 4.822E+04BA1404.909E+04 4.644E+04NB95 4.897E+04 4.897E+04 LA140 5.231E+04 5.079E+04 ZR97 4.953E+04 1.851E+04LA1414.498E+04 7.085E+02MO99 5.088E+04 3.956E+04 CE141 4.535E+04 4.463E+04 TC99M 4.454E+04 3.772E+04LA1424.397E+04 1.035E+00RU103 4.094E+04 4.018E+04 CE143 4.245E+04 2.597E+04 RU105 2.710E+04 6.615E+02PR1434.113E+04 4.075E+04RH105 2.559E+04 1.840E+04CE1443.810E+04 3.810E+04RU106 1.488E+04 1.486E+04 ND147 1.806E+04 1.698E+04 SB127 2.796E+03 2.369E+03NP2395.201E+05 3.902E+05TE127 2.773E+03 2.580E+03 PU238 2.805E+02 2.805E+02 TE127M 3.721E+02 3.719E+02PU2391.234E+01 1.238E+01SB129 8.457E+03 1.952E+02 PU240 1.730E+01 1.730E+01 TE129 8.326E+03 1.236E+03PU2414.450E+03 4.448E+03TE129M 1.615E+03 1.590E+03 AM241 5.449E+00 5.470E+00 TE131M 5.155E+03 2.976E+03CM2421.234E+03 1.234E+03I131 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 (sec/m 3) Site Boundary (sec/m 3) LPZ Boundary (sec/m 3) Top of Stack Releases (LOCA & CRDA)

U1 Intake Unit 3 Intake 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 (sec/m 3) Site Boundary (sec/m 3) LPZ Boundary (sec/m 3) Refueling Vent Releases (FHA and LOCA) ****

U1 Intake Unit 3 Intake 0-2 hrs 4.60E-4 ** Not Used Not Used 2-8 hrs 8-24 hrs 1-4 days 4-30 days Not Used 1.57E-4 1.12E-4 7.90E-5 ** ** ** ** Not Used 4.69E-5 2.23E-5 7.96E-6 **** 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 1 Intake Turbine Building Roof Ventilators Release (Post LOCA MSIV Leakage Units 2/3 Only) 0-2 hrs *** 2.17E-4 2.62E-4 1.31E-4 2-8 hrs *** 1.64E-4 6.61E-5 8-24 hrs *** 7.89E-5 4.69E-5 1-4 days *** 4.33E-5 2.23E-5 4-30 days

• • • 3.35E-5 7.96E-6

• • • Bounded by the Unit 3 Intake BFN-27 Table 14.6-9 (Deleted by Amendment 19)