RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems

Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems

ML16357A521
Person / Time
Site:	Byron, Braidwood
Issue date:	12/15/2016
From:	Exelon Generation Co
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML16357A264	List: ML16357A507 ML16357A508 ML16357A509 ML16357A521 ML16357A523 ML16357A524 ML16357A526 ML16357A529 ML16357A530 ML16357A532 ML16357A533 ML16357A534 ML16357A535 ML16357A536 ML16357A537 ML16357A540 ML16357A545 ML16357A549 ML16357A579 ML16357A580 ML16357A583 ML16357A584 ML16357A591 ML16357A592 ML16357A593 ML17086A588 ML17086A589 ML17086A590 ML17086A591 ML17086A592 ML17086A593 ML17086A595 ML17086A596 ML17086A597 ML17086A598 ML17086A599 ML17086A600 ML17086A601 ML17094A865 ML17095A852 ML17095A866 RS-16-248, Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix B - Construct Material Standards and Quality Control Procedures RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix C - Deleted RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix D - Computer Programs ... further results
References
RS-16-248
Download: ML16357A521 (261)

Text

REVISION 16 DECEMBER 2016 Normal Cooldown 370.00 350.00 [ 330.00 Cll :; 310.00 290.00 Cll a. E 270.00 Cll I-250.00 .... c .!!! 230.00 0 8 210.00 190.00 Ill ::#. 170.00 I (l \ '----.... ' ---* . ---Min SFP Heat Load -No SFP Heat Load 150.00 130.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 Time (hours after shutdown)

Time to reach 140 °F, from start of event, 2 RHR Trains: No SFP Heat Load= 57.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Min SFP Heat Load = 64.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> BRAIDWOOD STATION UPDATED FINAL SAFElY ANALYSIS REPORT FIGURE 5.4-6 REACTOR COOLANT TEMPERATURE VS TIME (NORMAL COOLDOWN) 360 Li:' 340 !-(lj 320 ... ::s .... "' 300 ... (lj Q. E 280 (lj I-.... 260 i:: "' 0 0 240 u ... 0 220 .... u "' (lj a: 200 180 Single Train Cooldown Time to Reach 200°F No SFP Heat Load = 50.3 Hours REVISION 16 DECEMBER 2016 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50 52 Time (hours after shutdown)

BYRON STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 5.4-7 SINGLE RHR TRAIN REACTOR COOLANT TEMPERATURE VERSUS TIME 360 Li:' a.. 340 a 320 l'G ... 300 E 280 .... lij 260 0 8 240 ... .s 220 .c v m 200 a:: 180 0 10 Single Train Cooldown 20 30 40 50 Time (hours after shutdown) 60 70 REVISION 16 DECEMBER 2016 -No SFP Heat Load Time to reach 200 °F, from start of event: No SFP Heat Load= 58.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 5.4-7 SINGLE RHR TRAIN REACTOR COOLANT TEMPERATURE VERSUS TIME