ML18024A353

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

ML18024A353
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Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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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