|
---|
Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23144A3052023-05-23023 May 2023 Updated Final Safety Analysis Report, Revision 34 ML22144A1282022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22144A1162022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22144A1142022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22144A1312022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Featres ML22144A1302022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22144A1362022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22144A1172022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22144A1192022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22144A1202022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22144A1292022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML22144A1222022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, List of Effective Pages ML22144A1212022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22144A1262022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22144A1332022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22144A1322022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML22144A1242022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22144A1232022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22144A1182022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report2022-05-18018 May 2022 Submittal of Revision 26 to Updated Final Safety Analysis Report ML21334A0292021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, List of Effective Pages ML21334A0262021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21334A0352021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Wastes and Radiation Protection ML21334A0312021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 3, Reactor ML21334A0252021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 16, Managing the Effects of Component Aging ML21334A0202021-11-22022 November 2021 Submittal of the Updated Final Safety Analysis Report, Revision 33 ML21334A0222021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML21334A0272021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix B, Seismic Design ML21334A0232021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ML21334A0332021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis ML21334A0212021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operation ML21334A0362021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix a, Quality Assurance ML21334A0372021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML21334A0242021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 5, Containment Systems ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases L-21-164, 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations2021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations ML21334A0322021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency System ML21334A0392021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML21334A0282021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20335A1382020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20335A1412020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML20335A1402020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML20335A1252020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations L-20-186, 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection2020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20335A1392020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML20335A1202020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20335A1302020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20335A1362020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20335A1372020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML20335A1222020-11-23023 November 2020 Submittal of Revision 25 to Updated Final Safety Analysis Report 2023-05-23
[Table view] |
Text
)(
Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting
v v-v x VR 4h F spray sed spray w sp m spray = 3 spray = F m = h = = R sp = w =
V = v spray = v sed =
dri where ird 1.214 -Stk )Stk (2 ln 0.75 + 1 1 = 2 i R 9) - ( C r 2 Stk sp sedsprayc pvv 2 = p 0.7 +Stk Stk = 2 i
R r 3 1 - 1 x R r 2 3 sp sp 2 r Pe 3.5 = -2/3 d r 6 C = B c
Parameter Value
Description of Aerosol
,
,
)
Secondary Side Parameters CR Emergency Ventilation: Initiation Signal/Timing
°
Secondary Side Parameters CR emergency Ventilation: Initiation Signal/Timing
Secondary System Release Parameters
CR Emergency Ventilation: Initiation Signal/Timing
Secondary System Release Parameters CR emergency Ventilation: Initiation Signal/TimingManual
Containment Pathway Parameters Secondary Side Pathway Parameters CR Emergency Ventilation: Initiation Signal/Timing
TABLE 14.3-6 (CONTD)
BEAVER VALLEY MAAP-DBA PARAMETER FILE
SUMMARY
OF JUNCTION FLOW AREAS
CR Emergency Ventilation: Initiation Signal/Timing
Time (sec) Pressure (psia) Time (sec) Temp ( F) Time (sec) Steam Condensing Rates (gm/sec)
Time (sec) Relative Humidity Fraction Time (sec) Pressure (psia) Time (sec) Temp ( F) Time (sec) Steam Condensing Rates (gm/sec)
Time (sec) Relative Humidity Fraction Time (sec) Pressure (psia) Time (sec) Temp ( F) Time (sec) Steam Condensing Rates (gm/sec) Time (sec) Relative Humidity Fraction
Single Failures - Failed Equipment
Parameter Analyzed Value or Range
1.0 Plant
Physical Description 2.0 Plant Initial Operating Conditions ~
Parameter Analyzed Value or Range
3.0 Accident
Boundary Conditions Notes:
Net Free Volume Initial Conditions Spray System Containment Fan Coolers RWST Level (feet) Containment Pressure (psig) Maximum Two Pump Spray Flow Rate (Delivered to Spray Headers)
Gallons per minute Wall TAir ( F) Area (ft 2) Height (ft) Tinit ( F) Thickness (in)
Wall TAir ( F) Area (ft 2) Height (ft) Tinit ( F) Thickness (in)
RCS Pressure (psig) Total Injected Flow Rate (gpm)
ASTRUM Result Value Criteria
Time [s] Mass Flow Rate [lb m/s] Energy Flow [BTU/s]
Time [s] Mass Flow Rate [lb m/s] Energy Flow [BTU/s]
Time [s] Mass Flow Rate [lb m/s] Energy Flow [BTU/s]
Time [s] Mass Flow Rate [lb m/s] Energy Flow [BTU/s]
Event Time (sec)
%
"%%
"
"
%%
"
% "% "
%
%
% " " "%%%
%%%
%&f
" "
" "%%
%
" "% " " " " " "
"
%%%
%º
"
"
%
"
Nuclide Group Regulatory Guide 1.183 Gap Fraction for Non-LOCA Events excluding the CREA (Note 1)
Nuclide Group Regulatory Guide 1.183 Gap Fraction for Non-LOCA Events excluding the CREA (Note 1)
)(!"
)(!"")(!"
dtuALdtsALQ t T t T)()(0 0$$
dtALQ t T 0$
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
Isotope Parent Relationship Parent Isotope Activity (Curies) Isotope Parent Relationship Parent Isotope Activity (Curies)
0EEZZwZZwsuussu 2!AAVwZwZAVEwZEVww 2's ou 1 u 2uoss 2 u s t 1 2!!AAVwZwZAVEwZEVww 2'u os 1 s 2souu 2 s u t 1 2!!AEAVwZAVwZwZEVww 1'ssos 1uou 2 u 1 u s t 1 2!AEAVwZAVwZwZEVww 1'uuou 1sos 2 s 1 s u t 1 2!At 1twEXP i s i'21i A%twEXP i u i i'2 1 A%At 21twEXP wAA L i i s i u i i 12 1!%
i j'AIntegrationconstantsforsprayedandunsprayedregionsofprimarycontainment,i=1,2;j=s,u1 j AActivityinsprayedandunsprayedregionofprimarycontainment(Ci)j=u,s2 j AActivitytoenvironmentfromleakagefromsprayedandunsprayedregionsofprimarycontainment(Ci)j=u,s
L 1Z uZ sE
V tVV us Nuclide Primary Coolant (1) (Ci/gm) Secondary Coolant (2) (Ci/gm)
Notes:
&
% " " "
'
P/P EE200Mevc1aewatts/watt 1 o 1 1 1 t!"watts/watt2e1e2ea1cMev200EEP/P][ttt21 222 o 2"!!!!!
""""
" " " " " "
% "
%
%