ML18024A353

Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.11 Table - Analysis of Design Basis Accidents

ML18024A353
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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ML18018A778	List: ML18018A780 ML18018A781 ML18018A783 ML18018A784 ML18018A785 ML18018A787 ML18018A788 ML18018A790 ML18018A792 ML18018A793 ML18018A795 ML18018A796 ML18018A797 ML18018A798 ML18018A800 ML18018A801 ML18018A802 ML18018A804 ML18018A806 ML18018A807 ML18022A114 ML18022A115 ML18022A116 ML18022A117 ML18022A118 ML18022A119 ML18022A120 ML18022A121 ML18022A123 ML18022A124 ML18022A125 ML18022A127 ML18022A128 ML18022A129 ML18022A130 ML18022A131 ML18022A132 ML18022A133 ML18022A148 ML18022A155 ML18022A156 ML18022A157 ML18022A158 ML18022A159 ML18022A161 ML18022A162 ML18022A163 ML18022A164 ML18022A165 ML18022A166 ... further results
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Download: ML18024A353 (11)

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BFN-18 Table 14.11-1 CONTROL ROD DROP ACCIDENT FISSION PRODUCT RELEASE RATE TO ENVIRONS (INITIAL CORE) Fission Product Activity Being Released to Environment Time After Noble Gases Iodines Accident (curies/sec) (curies/sec) 1 min 1.7 X 10° 1.8 X 10-5 30 min 1.1 X 10° 1.7 X 10-5 1 hr 7.4 X 10-1 1.6 X 10-5 2 hr 3.4 X 10-1 1.4 X 10-5 12 hr 1.4 X 10-4 5.0 X 10-6 1 day 1.5 X 10-7 1.7 X 10-6 2 days 1.6 X 10-16 2.4 X 10-7 5 days 7.9 x 10-39 8.4 X 10-10 BFN-18 TABLE 14.11-2 CONTROL ROD DROP ACCIDENT RADIOLOGICAL EFFECTS (INITIAL CORE) Meteorology VS-1 MS-1 N-1 N-5 U-1 U-5 Distance (meters) 0.2 Hour Cloud Gamma Doses (rem) 1,400* 4.4 X 10-3 4.4 X 10-3 5.6 X 10-3 7.8 X 10-4 9.5 X 10-3 1.3 X 10-3 3,000 2.7 X 10-3 2.9 X 10-3 5.1 X 10-3 7.3 X 10-4 4.6 X 10-3 7.6 X 10-3 8,000 1.3 X 10-3 1.4 X 10-3 1.8 X 10-3 4.4 X 10-4 9.5 X 10-4 2.2 X 10-4 16,000 6.4 X 10-4 8.0 X 10-4 5.8 X 10-4 2.0 X 10-4 2.5 X 10-4 8.2 X 10-5 0-2 Hour Thyroid Inhalation Doses (rem) 1,400* a a 1.3 X 10-5 1.4 X 10-7 2.4 X 10-4 2.7 X 10-5 3,000 a 2.5 X 10-10 1.1 X 10-4 9.1 X 10-6 1.2 X 10-5 1.7 X 10-5 8,000 a 8.7 X 10-6 5.8 X 10-5 1.0 X 10-5 2.7 X 10-5 4.9 X 10-6 16,000 a 8.4 X 10-6 2.4 X 10-5 4.7 X 10-6 9.6 X 10-6 1.8 X 10-6 0-24 Hour Cloud Gamma Doses (rem) 1,400 5.4 X 10-3 5.4 X 10-3 7.1 X 10-3 9.8 X 10-4 1.2 X 10-2 1.7 X 10-3 3,000 3.5 X 10-3 3.6 X 10-3 6.4 X 10-3 9.1 X 10-4 5.6 X 10-3 9.6 X 10-4 8,000 1.6 X 10-3 1.8 X 10-3 2.4 X 10-3 5.4 X 10-4 1.2 X 10-3 2.7 X 10-4 16,000 8.0 X 10-4 1.0 X 10-3 7.5 X 10-4 2.4 X 10-4 3.1 X 10-4 9.8 X 10-5 0-24 Hour Thyroid Inhalation Doses (rem) 1,400* a a 5.5 X 10-5 6.0 X 10-7 1.0 X 10-3 1.1 X 10-4 3,000 a 1.1 X 10-9 4.6 X 10-4 3.8 X 10-5 4.9 X 10-4 7.3 X 10-5 8,000 a 3.8 X 10-6 2.7 X 10-4 4.4 X 10-5 1.2 X 10-4 2.2 X 10-5 16,000 a 3.5 X 10-5 1.0 X 10-4 2.0 X 10-5 4.2 X 10-5 7.8 X 10-6 Symbol Definitions: VS-1 - Very stable 1m/sec winds MS-1 - Moderately stable 1m/sec winds N-1 - Neutral 1m/sec winds N-5 - Neutral 5m/sec winds U-1 - Unstable 1m/sec winds * - Nearest site boundary U-5 - Unstable 5m/sec winds a - Dose value 10-10 BFN-18 Table 14.11-3 LOSS-OF-COOLANT ACCIDENT PRIMARY CONTAINMENT RESPONSE SUMMARY Pressure Service Suppression Core Peak Pool Secondary RHR RHR RHR Water Chamber Spray Temperature Peak Pressure Case Loops HX Pumps Pumps Cooling (gpm) (°F) (psig) A 2 4 4 4 30,000 6250 158 8.0 B 2 2 2 2 20,000 6250 169 9.8 C 1 2 2 2 16,000 6250 173 10.7 C* 1 2 2 2 11,700 5600 172 9.0 *Reanalysis based on NEDC-32484P, Revision 2.

BFN-18 Table 14.11-4 INVENTORY IN PRIMARY CONTAINMENT AVAILABLE FOR LEAKAGE Isotope Activity (Ci) (hr-1)Isotope Activity (Ci) (hr-1) 131I 7.7173E7 3.59E-3 85Kr 1.3977E6 7.34E-6 132I 1.1455E8 3.01E-1 87Kr 7.6039E7 5.47E-1 133I 1.8416E8 3.30E-2 88Kr 1.0720E8 2.48E-1 134I 2.0719E8 7.88E-1 89Kr 1.4002E8 1.31E1 135I 1.7438E8 1.03E-1 131Xem 1.1873E6 2.41E-3 131I* 3.3922E6 3.59E-3 133Xem 5.7251E6 1.28E-2 132I* 5.0351E6 3.01E-1 133Xe 2.0252E8 5.48E-3 133I* 8.0945E6 3.30E-2 135Xem 3.1599E7 2.65E0 134I* 9.1072E6 7.88E-1 135Xe 1.9842E8 7.57E-2 135I* 7.6652E6 1.03E-1 137Xe 1.8343E8 1.09E1 85Krm 3.8936E7 1.58E-1 138Xe 1.8795E8 2.93E0

Note:

• denotes organic form, m denotes metastable state BFN-18 Table 14.11-5 (Deleted by Amendment 17)

BFN-18 Table 14.11-6 (Deleted by Amendment 17)

BFN-18 Table 14.11-7 (Deleted by Amendment 17)

BFN-18 Table 14.11-8 VALUES FOR X/Q FOR ACCIDENT DOSE CALCULATIONS Time Period Control Room (sec/m3) Site Boundary (sec/m3) LPZ Boundary (sec/m3)

Top of Stack Releases Note 1 U1 Intake Note 2 Note 1 Unit 3 Intake 0-0.5 hrs* 3.40E-5 3.31E-5 3.02E-5 2.40E-5 1.30E-5 0.5-2 hrs 5.90E-15 5.90E-15 9.64E-7 9.70E-7 8.00E-7 2-8 hrs 4.29E-15 3.80E-15 1.89E-7 8.00E-7 8-24 hrs 3.65E-15 3.02E-15 8.37E-8 4.00E-7 1-4 days 2.58E-15 1.90E-15 1.43E-8 2.00E-7 4-30 days 1.57E-15 9.60E-16 1.13E-9 6.50E-8 *Fumigation Base of Stack Releases Note 1 Note 2 Note 1 0-2 hrs 3.70E-3 8.89E-4 1.20E-3 1.22E-4 5.65E-5 2-8 hrs 2.38E-3 7.30E-4 7.91E-4 5.65E-5 8-24 hrs 1.91E-3 6.60E-4 6.42E-4 2.24E-5 1-4 days 1.19E-3 5.40E-4 4.09E-4 7.94E-6 4-30 days 5.97E-4 4.00E-4 2.14E-4 1.71E-6 Refuel Floor Damper Bypass (FHA Only) 0-15 secs 1.46E-4 1.22E-4 5.65E-5 Turb. Bldg.

Release (MSLB only) 6.56E-4 2.70E-4 1.32E-4 Note 1: The control room X/Q values used in these columns are for the LOCA analysis only. Note 2: The control room X/Q values used in this column is for all other radiological evaluations.

BFN-18 Table 14.11-9 (Deleted by Amendment 17)

BFN-18 Table 14.11-10 (Deleted by Amendment 17)

BFN-18 Table 14.11-11 STEAM LINE BREAK ACCIDENT RADIOLOGICAL EFFECTS Distance (m) Gamma Dose (rem) Thyroid Dose (rem) 1465 (EAB) 0.657 32.05 3200 (LPZ) 0.321 15.67