ML21286A565
| ML21286A565 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/2021 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21286A574 | List:
|
| References | |
| Download: ML21286A565 (9) | |
Text
BFN-29 PLANT SAFETY ANALYSIS TABLE OF CONTENTS Page No 14.0 PLANT SAFETY ANALYSIS ..................................................................................................... 14.1-1 14.1 Analytical Objective ................................................................................................................... 14.1-1 14.2 Unacceptable Safety Results for Abnormal Operational Transients .......................................... 14.2-1 14.3 Unacceptable Safety Results For Accidents.............................................................................. 14.3-1 14.4 Approach to Safety Analysis...................................................................................................... 14.4-1 14.4.1 General ...................................................................................................................... 14.4-1 14.4.2 Abnormal Operational Transients .............................................................................. 14.4-2 14.4.3 Accidents ................................................................................................................... 14.4-4 14.4.4 Barrier Damage Evaluations ...................................................................................... 14.4-6 14.5 Analyses of Abnormal Operational Transients ......................................................................... 14.5-1 14.5.1 Objective .................................................................................................................... 14.5-1 14.5.2 Events Resulting in a Nuclear System Pressure Increase ......................................... 14.5-9 14.5.3 Events Resulting in a Reactor Vessel Water Temperature Decrease ........................ 14.5-18 14.5.4 Events Resulting in a Positive Reactivity Insertion..................................................... 14.5-18 14.5.5 Events Resulting in a Reactor Vessel Coolant Inventory Decrease ........................... 14.5-26 14.5.6 Events Resulting in a Core Coolant Flow Decrease .................................................. 14.5-34 14.5.7 Events Resulting in a Core Coolant Flow Increase .................................................... 14.5-38 14.5.8 Event Resulting in Excess of Coolant Inventory......................................................... 14.5-42 14.5.9 Loss of Habitability of the Control Room .................................................................... 14.5-45 14.6 Analysis of Design Basis Accidents .......................................................................................... 14.6-1 14.6.1 Introduction ................................................................................................................ 14.6-1 14.6.2 Control Rod Drop Accident (CRDA) ........................................................................... 14.6-2 14.6.3 Loss of Coolant Accident (LOCA) .............................................................................. 14.6-10 14.6.4 Refueling Accident ..................................................................................................... 14.6-26 14.6.5 Main Steam Line Break Accident ............................................................................... 14.6-32 14.7 Conclusions ............................................................................................................................... 14.7-1 14.8 Analytical Methods .................................................................................................................... 14.8-1 14.8.1 Nuclear Excursion Analysis........................................................................................ 14.8-1 14.8.2 Reactor Vessel Depressurization Analysis................................................................. 14.8-2 14.8.3 Reactor Core Heatup Analysis ................................................................................... 14.8-9 14.8.4 Containment Response Analysis ............................................................................... 14.8-13 14.8.5 Analytical Methods for Evaluating Radiological Effects .............................................. 14.8-16 14.0-i
BFN-29 PLANT SAFETY ANALYSIS TABLE OF CONTENTS (Cont'd)
Page No 14.9 (Deleted) 14.10 (Deleted) 14.11 (Deleted) 14.12 Analysis of the Primary Containment Response ...................................................................... 14.12-1 14.12.1 Methodology ............................................................................................................ 14.12-1 14.12.2 Short-Term Containment Pressure Response .......................................................... 14.12-2 14.12.3 Drywell and Wetwell Temperature ........................................................................... 14.12-4 14.12.4 Long-Term Bulk Suppression Pool Temperature Response - Design Basis Accidents ........................................................................................................ 14.12-5 14.12.5 Long-Term Bulk Suppression Pool Temperature Response - Special Events .......... 14.12-16 14.13 Anticipated Transient Without Scram With Instability (ATWSI) ................................................. 14.13-1 14.0-ii
BFN-29 PLANT SAFETY ANALYSIS LIST OF TABLES Table Title 14.4-1 Summary of Abnormal Operational Transients 14.4-2 Results of Design Basis Accidents 14.5-1 (Deleted) 14.5-2 Transient Analyses Initial Conditions 14.6-1 Iodine-131 (Ci) by Location as Function of Time of CRDA 14.6-2 (Deleted) 14.6-3 (Deleted) 14.6-4 (Deleted) 14.6-5 (Deleted) 14.6-6 (Deleted) 14.6-7 Inventory in Primary Containment Available for Leakage 14.6-8 Values for X/Q for Accident Dose Calculations 14.6-9 (Deleted) 14.8-1 Characteristics of Nuclear Excursions - Water-Moderated Oxide Cores 14.8-2 Dose Computational Methods Wind Direction Persistence 14.8-3 Meteorology Applicable to Design Basis Accidents 14.8-4 Calculated Air Concentration for 183 Meter Release Height 14.8-5 Calculated Air Concentration for 183 Meter Release Height 14.8-6 Thyroid Dose Conversion Factors 14.9-1 (Deleted) 14.9-2 (Deleted) 14.11-1 (Deleted) 14.11-2 (Deleted) 14.11-3 (Deleted) 14.11-4 (Deleted) 14.11-5 (Deleted) 14.11-6 (Deleted) 14.11-7 (Deleted) 14.11-8 (Deleted) 14.11-9 (Deleted) 14.11-10 (Deleted) 14.11-11 (Deleted) 14.12-1 DBA Containment Response Key Analysis Input Values 14.12-2 Non-Accident Unit Containment Response Key Analysis Input Values 14.0-iii
BFN-29 PLANT SAFETY ANALYSIS LIST OF TABLES Table Title 14.12-3 Station Blackout Containment Response Key Analysis Input Values 14.12-4 Fire Event Containment Response Key Analysis Input Values 14.12-5 ATWS Event Containment Response Key Analysis Input Values 14.12-6 Containment Response Results 14.13-1 Results of BFN ATWSI Evaluation 14.0-iv
BFN-29 PLANT SAFETY ANALYSIS LIST OF ILLUSTRATIONS Figure Title 14.4-1 Plant Safety Analysis - Method for Identifying and Evaluating Abnormal Operational Transients 14.4-2 Plant Safety Analysis - Method for Identifying and Evaluating Accidents 14.5-1 (Deleted) 14.5-2 (Deleted) 14.5-3 (Deleted) 14.5-4 (Deleted) 14.5-5 (Deleted) 14.5-5a EOC LRNB at 100P/105F with TSSS - Key Parameters 14.5-5b EOC LRNB at 100P/105F with TSSS - Sensed Water Level 14.5-5c EOC LRNB at 100P/105F with TSSS - Vessel Pressures 14.5-6 (Deleted) 14.5-6a LRNB with EOC-RPT-OOS at 100P/105F with TSSS - Key Parameters 14.5-6b LRNB with EOC-RPT-OOS at 100P/105F with TSSS - Sensed Water Level 14.5-6c LRNB with EOC-RPT-OOS at 100P/105F with TSSS - Vessel Pressures 14.5-7a (Deleted) 14.5-7b (Deleted) 14.5-8 (Deleted) 14.5-9 (Deleted) 14.5-9a TTNB at 100P/105F with TSSS - Key Parameters 14.5-9b TTNB at 100P/105F with TSSS - Sensed Water Level 14.5-9c TTNB at 100P/105F with TSSS - Vessel Pressures 14.5-10a (Deleted) 14.5-10b (Deleted) 14.5-11 (Deleted) 14.5-11a MSIV Closure Overpressurization Event at 102P/105F - Key Parameters 14.5-11b MSIV Closure Overpressurization Event at 102P/105F - Sensed Water Level 14.5-11c MSIV Closure Overpressurization Event at 102P/105F - Vessel Pressures 14.5-11d MSIV Closure Overpressurization Event at 102P/105F - Safety/Relief Valve Flow Rates 14.5-12a One MSIV Closure at 100P/105F with TSSS - Key Parameters 14.5-12b One MSIV Closure at 100P/105F with TSSS - Sensed Water Level 14.5-12c One MSIV Closure at 100P/105F with TSSS - Vessel Pressures 14.5-13a (Deleted) 14.5-13b (Deleted) 14.5-14a (Deleted) 14.5-14b (Deleted) 14.0-v
BFN-29 PLANT SAFETY ANALYSIS LIST OF ILLUSTRATIONS Figure Title 14.5-15a Pressure Regulator Failure Open 2075 MWt/100F 14.5-15b Pressure Regulator Failure Open 2075 MWt/100F 14.5-16a (Deleted) 14.5-16b (Deleted) 14.5-17a (Deleted) 14.5-17b (Deleted) 14.5-17c (Deleted) 14.5-18a (Deleted) 14.5-18b (Deleted) 14.5-19a (Deleted) 14.5-19b (Deleted) 14.5-20a (Deleted) 14.5-20b (Deleted) 14.5-21a (Deleted) 14.5-21b (Deleted) 14.5-22a (Deleted) 14.5-22b (Deleted) 14.5-22c (Deleted) 14.5-22d (Deleted) 14.5-22e (Deleted) 14.5-22f (Deleted) 14.5-23a (Deleted) 14.5-23b (Deleted) 14.5-24a (Deleted) 14.5-24b (Deleted) 14.5-24c Fast Recirculation Pump Runup at 66P/52F - Key Parameters 14.5-24d Fast Recirculation Pump Runup at 66P/52F - Sensed Water Level 14.5-24e Fast Recirculation Pump Runup at 66P/52F - Vessel Pressures 14.5-24f Fast Recirculation Pump Runup at 66P/52F - Recirculation Pump Speed 14.5-25a (Deleted) 14.5-25b (Deleted) 14.5-25c 105% OLTP Idle Recirculation Loop Startup at 75P/52F - Key Parameters 14.5-25d 105% OLTP Idle Recirculation Loop Startup at 75P/52F - Sensed Water Level 14.5-25e 105% OLTP Idle Recirculation Loop Startup at 75P/52F - Core Inlet Enthalpy 14.0-vi
BFN-29 PLANT SAFETY ANALYSIS LIST OF ILLUSTRATIONS Figure Title 14.5-25f 105% OLTP Idle Recirculation Loop Startup at 75P/52F - Loop Flows 14.5-26a (Deleted) 14.5-26b (Deleted) 14.5-27a (Deleted) 14.5-27b (Deleted) 14.5-28 (Deleted) 14.5-28a FWCF at 77.6P/109F with TSSS - Key Parameters 14.5-28b FWCF at 77.6P/109F with TSSS - Sensed Water Level 14.5-28c FWCF at 77.6P/109F with TSSS - Vessel Pressures 14.5-29 (Deleted) 14.5-30 (Deleted) 14.5-30a FWCF with EOC-RPT-OOS at 100P/105F with TSSS - Key Parameters 14.5-30b FWCF with EOC-RPT-OOS at 100P/105F with TSSS - Sensed Water Level 14.5-30c FWCF with EOC-RPT-OOS at 100P/105F with TSSS - Vessel Pressures 14.5-31 (Deleted) 14.5-31a FWCF with TBVOOS at 100P/105F with TSSS - Key Parameters 14.5-31b FWCF with TBVOOS at 100P/105F with TSSS - Sensed Water Level 14.5-31c FWCF with TBVOOS at 100P/105F with TSSS - Vessel Pressures 14.6-1 (Deleted) 14.6-2 (Deleted) 14.6-3 (Deleted) 14.6-4 (Deleted) 14.6-5 (Deleted) 14.6-6 (Deleted) 14.6-7 Main Steamline Break Accident, Break Location 14.6-8 Main Steamline Break Accident, Mass of Coolant Lost Through Break 14.6-9 Main Steamline Break Accident, Normalized Core Inlet Flow 14.6-10 Main Steamline Break Accident - Minimum Critical Heat Flux Ratio 14.6-11 (Deleted) 14.6-12 (Deleted) 14.6-13 (Deleted) 14.6-14 (Deleted) 14.6-15 (Deleted) 14.6-16 (Deleted) 14.0-vii
BFN-29 PLANT SAFETY ANALYSIS LIST OF ILLUSTRATIONS Figure Title 14.6-17 (Deleted) 14.6-18 (Deleted) 14.8-1 Fuel Rod and Fuel Bundle Details 14.10-1 (Deleted) 14.10-2 (Deleted) 14.10-3 (Deleted) 14.10-4 (Deleted) 14.10-5 (Deleted) 14.10-6 (Deleted) 14.10-7 (Deleted) 14.10-8 (Deleted) 14.10-9 (Deleted) 14.10-10 (Deleted) 14.10-10a (Deleted) 14.10-10b (Deleted) 14.10-11 (Deleted) 14.10-12 (Deleted) 14.10-13 (Deleted) 14.10-14 (Deleted) 14.10-15 (Deleted) 14.10-16 (Deleted) 14.10-17 (Deleted) 14.10-18 (Deleted) 14.10-19 (Deleted) 14.10-20 (Deleted) 14.11-1 (Deleted) 14.11-2 (Deleted) 14.11-3 (Deleted) 14.11-4 (Deleted) 14.11-5 (Deleted) 14.11-6 (Deleted) 14.11-7 (Deleted) 14.11-8 (Deleted) 14.11-9 (Deleted) 14.11-10 (Deleted) 14.0-viii
BFN-29 PLANT SAFETY ANALYSIS LIST OF ILLUSTRATIONS Figure Title 14.11-11 (Deleted) 14.11-12 (Deleted) 14.11-13 (Deleted) 14.11-14 (Deleted) 14.11-15 (Deleted) 14.11-16 (Deleted) 14.11-17 (Deleted) 14.11-18 (Deleted) 14.12-1 Short-Term RSLB DBA-LOCA Containment Pressure Response - Design Case 14.12-2 Short-Term RSLB DBA-LOCA Containment Temperature Response - Design Case 14.12-3 Short-Term RSLB DBA-LOCA Containment Pressure Response - Bounding Case 14.12-4 Short-Term RSLB DBA-LOCA Containment Temperature Response - Bounding Case 14.12-5 Short-Term RSLB DBA-LOCA Containment Pressure Response - Reference Case 14.12-6 Short-Term RSLB DBA-LOCA Containment Temperature Response - Reference Case 14.12-7a Drywell Temperature Response - Small Steam Line Break LOCA 14.12-7b Drywell Pressure Response - Small Steam Line Break LOCA 14.12-8 Suppression Pool Temperature Response - RSLB DBA LOCA 14.12-9 Drywell and Wetwell Airspace Temperature Response - RSLB DBA LOCA 14.12-10 Long-Term Small Steam Line Break LOCA Suppression Pool Temperature Response - 0.01 ft2 Break with HPCI Available 14.12-11 Suppression Pool Temperature Response - Non-Accident Unit Shutdown (CST Available) 14.12-12 Station Blackout Suppression Pool Temperature Response 14.12-13 Fire Event Suppression Pool Temperature Response 14.12-14 ATWS Suppression Pool Temperature and Containment Pressure Response - LOOP 14.0-ix