ML20237B092
ML20237B092 | |
Person / Time | |
---|---|
Site: | 05200003 |
Issue date: | 08/13/1998 |
From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
To: | |
Shared Package | |
ML20237B082 | List: |
References | |
NUDOCS 9808180042 | |
Download: ML20237B092 (97) | |
Text
_ _ _ _ _ - - _ - - - - - - -
- s:
En --
O Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment
!O l
Prepared for U.S. Department of Energy
! San Francisco Operations Office DE-AC03-90SF18495
[naina: n" g a i
O
@~ m_ m:\ap600Spratocrev6kott.wpf.lb I
==
3
=:
i~
l i
TABLE OF CONTENTS Section Title Eage CHAPTER 1 INTRODUCTION 1.1 Background and Overview . .. ... .... . .. . ....... . .... 1-1 1.2 Objectives ............ .......... ......... ........ ...... 1-2 1.3 Technical Scope ....... ............. . ... . . .... .. ..... 1-3 1.4 Project Methodology Overview . . .... .. . ........ ............. 1-4 1.5 Results . . . . . . . . . . ............... ............. . .... 1-6 1.6 Plant Definition . . . . . . . . . .... .... ......... . .... ........ 1-7 1.6.1 General Description . . . . . .. .. .......... .......... 1-7 1.6.2 AP600 Design Improvement as a Result of Probabilistic Risk Assessment Studies ... ............. ...... . . .... . 1-12 1.7 References ..... .... ....... .... .............. .. ...... 1-14 CHAPTER 2 INTERNAL INITIATING EVENTS 2.1 Introduction ... . . .... .. .. ... . .... . . .. ...... . 2-1 2.2 Internal Initiating Event Identification and Categorization . . . . . . . ....... 2-1 2.2.1 Logic Diagram for Internal Initiating Events . . . . . . ... . ...... 2-2 2.2.2 Loss-of-Coolant Accidents . . . . ... ..... ................ 2-3 (q
2.2.3 2.2.4 Transients . . . . . . . . . ... ...... ..........
Anticipated Transient without Scram ........ .. .. . .. ..
..... 2-6 2-9 2.2.5 AP600-Specific Initiating Event Analysis . .......... 2-11 2.2.6 Consequential Events . . . . . . . . . ... . ..... . . .... 2-20 2.2.7 Summary of Interaal Initiating Event Categories . . . . . . ......... 2-21 23 Quantification of Internal Initiating Event Frequencies .... ... .... ... . 2-21 2.3.1 Quantification of LOCA Initiating Event Frequencies . . . . . . . . . .. 2-21 2.3.2 Quantification of Transient Initiating Event Frequencies . . . . . . .. 2-27 2.3.3 ATWS Precursor Initiating Event Frequency . . . . . . . . . . .... .. 2-30 l 2.3.4 Summary of Internal Initiating Event Frequencies . . . ...... . . . . 2-30 2.4 References ............. .... ......... ............. ... 2-30 A~ITACHMENT 2A Q~UANTIFICATION OF LOCA 1hTTIATING EVENT FREQUENCIES l 2A.1 Primary System Pipe Break Frequencies . ........ .... .... ... 2A-1 2A.2 l Reactor Coolant System Leakage Initiating Event Frequency . . . . . . . . . . . . 2A-6 l
2A.3 Steam Generator Tube Rupture Initiating Event Frequency . . . . ....... . 2A-15 ;
2A.4 Interfacing System LOCA Initiating Event Frequency . . ............... 2A-19 l 2A.5 - Quantification of Stuck-open Pressurizer Safety Valve and Accumulator !
Interface Break and IRWST Interface Break . . ..... ..... . ...... 2A-29 !
2A.6 Quantification Secondary-side Line Breaks and Stuck-open Main Steam Line Safety Valve Frequencies . . . . . . . . . . ...... ... . ..... . . 2A-34 2A.7 Initiating Events Review Data Summary and INPO Data . ...... . ..... 2A-39 l
\
l
- l (Om) '
ENEl. Revision: 9
[ W85tingt10Use Ets::bm April 11,1997 iii ow60cvavn 9w -tocypt;id
.g. . . =
=
TABLE OF CONTENTS (Cont.)
0 Section Title Eage CHAlrTER 3 MODELING OF SPECIAL INITIATORS 3.1 Introduction .... .. ....... .............. .. ........ . ... 3-1 3.2 Ground Rules for Special Initiating Event Analysis ..................3-1 3.3 Loss of Compon nt Cooling Water System / Service Water System Initiating Event 3-2 3.4 Loss of Compressei and Instrument Air System Initiating Event ............ 3-2 3.5 Spurious Actuation of Automatic Depressurization System ................ 3-3 3.5.1 Evaluation of Automatic Depressurization System Spurious Actuation . . 3-3 3.6 References ..... ... .. ... .. .. ..... ........ .. ... .. 3-8 CHAPTER 4 EVENT TREE MODELS ....... ..... .. . ........ ... .. .. 4-1 4.1 Introduction ...... .... ... ....... ...... . ........ ... 4-1 4.2 Large LOCA Event Tree Model . . . .... ... .. . .............. 4-3 4.2.1 Event Description . , . . ... . ........... .......... 4-3 4.2.2 Event Tree Model and Nodes .... ...... ......... . ... 4-4 4.2.3 Event Tree Success Paths . . . . . . . . . . . . . ...... . ......... 4-5 4.2.4 Operator Actions . . . . . . . . . . . . ........ ...... .. ... 4-6 4.2.5 Event Tre,e End States . . ........... .... . ... .. ..... 4-6 4.3 Medium LOCA Event Tree Model . . . . . . . . ..... . .............. 4-6 4.3.1 Event Description . . . ................... ............. 4-6 4.3.2 Event Tree Model and Nodes ................... .... .... 4-7 4.3.3 Event Tree Success Paths . . . . . . . ...... ............... . 4-9 4.3.4 Operator Actions . ............ ... ... ............... 4-9 4.3.5 Event Tree End States .............. ............. ... 4-9 4.4 Core Makeup Tank Line Break Event Tree Model . . . . . .. ..... ... . . 4-10 4.4.1 Event Description . ... ............... ........... . 4-10 4.4.2 Event Tree Model and Nodes . ....... ......... . . . . . . 4- 10 4.4.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 4-12 4.4.4 Operator Actions . . . ............. ............ . . . . 4-12 4.4.5 Event Tree End States . . . . . . . ....... ......... ..... . 4-13 4.5 Direct Vessel Injection Line Break Event Tree Model . . .. ............ . 4-13 4.5.1 Event Description . . . . . . . . . . . .... ... ....... .. . . 4-13 4.5.2 Event Tree Model and Nodes .... .... . . . ... . . . 4-14 4.5.3 Event Tree Success Paths . . . . . . . .. ..... ........... 4-15 4.5.4 Operator Actions . .. ... . ....... . ..... . . . . . . . 4-15 4.5.5 Event Tree End States . ... ..... .. . ....... . ... 4-15 4.6 Intermediate LOCA Event Tree Model ... ..,.. . .,... . . . 4-16 4.6.1 Event Description . . . . ............................ . . 4-16 4.6.2 Event Tree Model and Nodes ... . ..... . . ...... . . . . . 4-16 4.6.3 Event Tree Success Paths . . .. ... ....... ...... ... . . 4-19 4.6.4 Operator Actions . . .... ......... ........ . . . . . 4-19 4.6.5 Event Tree End States . .... ........ .... ....... . 4-19 O
Revision: 9 April 11,1997 ,f T Westirighouse o%p600$ra\rev 9\pra-toc.wpf.lb iv
1 i
=:
= m A
U TABLE OF CONTENTS (Cont.)
Section Title Eage 4.7 Small LOCA Event Tree Model4-20 4.7.1 Event Description . ..................... . . . . . . . . . . . . . 4 20 4.7.2 Event Tree Model and Nodes ................. .......... 4-20 4.7.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . ...... ..... 4-23 4.7.4 Operator Actions . . . ................................. 4-24 4.7.5 Event Tree End States . . . . . . . . . . . ................. . . 4-24 4.8 RCS Leak Event Tree Model . . . . . . . . . . . . . . . . . ... .............. 4-24 4.8.1 Event Description . . . . . . . . . . . . . . . . ......... .. ....... 4-24 4.8.2 Event Tree Model and Nodes ........... . .............. 4-25 4.8.3 Event Tree Success Paths . . . . . .. ..... .. .. .. . . . . . . 4-25 4.8.4 Operator Actions . . . . . . . . . . . . . . . . . . . .. ............. 4-26 4.8.5 Event Tree End States .......... ... . ...............4-26 4.9 PRHR Tube Rupture Event Tree Model . . . . . ......................4-26 4.9.1 Event Description . . . . . . ..... . ............. .... . 4-26 4.9.2 Event Tree Model and Nodes .......... ......... ...... 4-26 4.9.3 Event Tree Success Paths ..... . ..... .. ............ 4-27 4.9.4 Operator Actions ............. ... ... ..... .. .....4-27 4.9.5 Event Tree End States . .... ... ................... . 4-28 n 4.10 Steam Generator Tube Rupture Event Tree Model . . . . . . . ............ 4-28
( ')
4.10.1 4.10.2 Event Description . . .. . .... ........................4-28 Event Tree Model and Nodes ............................4-30 i 4.10.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-34 )
4.10.4 Operator Actions . . . . . . . .......... .................. 4-34 J
4.10.5 Event Tree End States ........... ..................... 4-35 4.11 Reactor Vessel Rupture Event Tree Model ...................... .. . 4-35 4.11.1 Event Description . . . . . . . . . . . . . . . . . . . . ... .. . . . . . . . . . 4-3 5 4.11.2 Event Tree Model and Nodes ....... ...... . . . . . . . . . . . . . 4-3 5 4.11.3 Event Tree Success Paths . . . . . . . . . ...... ........... . 4-36 4.11.4 Operator Actions . . ............ . . . . . . . . . . . . . . . . . . . 4-3 6 4.11.5 Event Tree End States . . . . . . . . . . .... . . . . . . . . . . . . . . . 4-36 4.12 Interfacing System LOCA Event Tree Model . . . . . . . .................4-36 l 4.12.1 Event Description . . . . . . . . . . . . .. ...... .......... . . 4-36 l 4.12.2 Event Tree Model and Nodes ............................4-36 4.12.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . . . .... . 4-36 l 4.12.4 Operator Actions . . . . . . . . . . . . . . . ....... ... .... . .. 4-37 l 4.12.5 Event Tree End States ........... .............. . . . . . . 4-37
- 4.13' Transients with MFW Event Tree Model . . . . .. ... .......... .4-37 4.13.1 Event Description . ... ......... .. ........ ... .. 4-37 4.13.2 Event Tree Model and Nodes ............. ......... . . 4-39 4.13.3 Event Tree Success Paths . . . . . . . . ............... . . . . . . 4-4 3 l 4.13.4 Operator Actions 4-43 4.13.5 Event Tree End States . ...... ..... ............ . . . 4-43 O
O Revision: 9 W
WBStingh00S6 N.m bw APril 11.1997 y oMp600\ prs \rev 9%pra-toc.wpf.lb
=.n Re-I TABLE OF CONTENTS (Cont.)
Title .Pajte Section 4.14 Transients with Loss of RCS Flow Event Tree Model . . ... ........... 4-44 4.14.1 Event Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-44 4.14.2 Event Tree Model and Nodes ................ ........... 4-44 4.14.3 Event Tree Success Paths . . . . .. .......... . . . . . . . . . . . . 4-47 4.14.4 Operator Actions . . . . . . . . . . . . ............. . . . . . . . . . 4-4 8 4.14.5 Event Tree End States ...... .. ....... ...... . . . . . . . . 4-4 8 4.15 Transients with Loss of MFW to One SG Event Tree Model . . . . . . . . . . . . . . 4-48 4.15.1 Event Description . . . . . . . . ............... ... . . . . . . . 4-48 4.15.2 Event Tree Model and Nodes . ....... .. ... .. . . . . . . . 4-49 4.15.3 Event Tree Success Paths . . . . . . ... ..... . . . . . . . . . . . 4-5 2 4.15.4 Operator Actions . . . . . .. .. ........ .. ........... 4-52 4.15.5 Event Tree End States ... . .. ...... ........ ...... 4-53 4.16 Transients with Core Power Excursion Event Tree Model . . . . .. ...... 4-53 4.16.1 Event Description . . . . . . . . . . . . . ............... ...... 4-53 4.16.2 Event Tree Model and Nodes . ...... ................... 4-53 4.16.3 Event Tree Success Paths .............. . ... ....... . 4-57 4.16.4 Operator Actions . . . . . . . . . . . . . . . . . . .. ..... ........,4-57 4.16.5 Event Tree End States .... ......... .... .. ......... 4-57 4.17 Transients with Loss of CCS/SWS Event Tree Model . . . . . . . . . . . . . . . . . . 4-5 8 4.17.1 Event Description . . . . . . . . . ...........................4-58 4.17.2 Event Tree Model and Nodes ........ .... . .. ........ 4-58 4.17.3 Event Tree Success Paths . .... ............... ...... 4-61 4.17.4 Operator Actions . . . . . . . . .. ................. .. . . 4-62 4.17.5 Event Tree End States .... . ...... ..... ... . .. .. 4-62 4.18 Loss of Main Feedwater Event Tree Model ............ ............ 4-62 4.18.1 Event Description . . . . . . . . ... ......... ............ 4-62 4.18.2 Event Tree Model and Nodes .... ............. . . . . . . . 4 64 4.18.3 Event Tree Success Paths .............................. 4-68 4.18.4 Operator Actions . . . . . ............... ............... 4-68 4.18.5 Event Tree End States ............... ................ 4-68 4.19 Loss of Condenser Event Tree Model . . . . . . .... ........... ...... 4-69 4.19.1 Event Description . . . . . . . .......... .... . .. ..... 4-69 4.19.2 Event Tree Model and Nodes . .... . ............ ... . 4-69 4.19.3 Event Tree Success Paths . .. . ...... ..... . . ..... 4-72 4.19.4 Operator Actions . ........ . ..... .... ... . . . . . . . . . 4-7 2 4.19.5 Event Tree End States . . . .. ....... . . . ...... 4-73 O
,1997 6 W85tiligh0038 ohp600\pravev.ppra-toc.wpf:1b vi
%E w
i J
TABLE OF CONTENTS (Cont.)
Section Title P.!yte 4.20 Loss of Compressed Air Event Tree Model . . . . . . . . . . . . . . . . . . . . . . . . . 4-7 3 4.20.1 Event Description . ...... ................. ..... . . . . 4-73 4.20.2 Event Tree Model and Nodes .. ............ .. . ... . 4-74 4.20.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . ...... 4-77 4.20.4 Operator Actions . . . . . . . . . . ................. . . . . . . 4-77 4.20.5 Event Tree End States ........... .... ...... .. .. . . 4-77 4.21 Loss of Offsite Power Event Tree Model ......................... . 4-78 i 4.21.1 Event Description . . . . . . . . .. .... . .. ..... . . . . . 4-7 8 4.21.2 Event Tree Model and Nodes ....... ...... .... . ... . . 4-78 4
4.21.3 Event Tree Success Paths .. ....... ................. 4-82 1 1
4.21.4 Operator Actions . . . . . . . . . . .. .............. .... . 4-82 l 4.21.5 Event Tree End States ............. .............. ... 4-83 4.22 Main Steam Line Break Downstream of MSIVs Event Tree Model .. . ... 4-83 4.22.1 Event Description . . . . .. .......... . . ... . .. . 4-83 4.22.2 Event Tree Model and Nodes ............ ....... . .... 4-84 4.22.3 Event Tree Success Paths . . . . . . . . . . . ..... . . . . 4-87 4.22.4 Operator Actions . . . . . . . . . . . . . ... ...... ............ 4-87 s 4.22.5 Event Tree End States .... . ....... ...... ..... ..... 4-88 4.23 Main Steam Line Break Upstream of MSIVs Event Tree Model . . . . . . ..... 4-88 v ) 4.23.1 Event Description . . . . . . . . . . ................ ......... 4-88 4.23.2 Event Tree Model and Nodes . ....................... .. 4-89 4.23.3 Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-92 4.23.4 Operator Actions . ....... . ... . ... .......... . . 4-92 ,
4.23.5 Event Tree End States ............ ......... .. ....... 4-93 1 4.24 Stuck-Open Secondary-Side Safety Valve Event Tree Model .. . ....... 4-93 4.24.1 Event Description . . . ..... ..... .................... . 4-93 4.24.2 Event Tree Model and Nodes ................... ..... . . 4-94 4.24.3 Event Tree Success Paths . ............ ........... ... 4-97 4.24.4 Operator Actions . . . . . . . . . . . . . . . ................. .. 4-97 4.24.5 Event Tree End States . . ..... ............... .. .. . 4-97 4.25 ATWS Precursors without MFW Event ~ree Model . . . . . . . . ........... 4-98 4.25.1 Event Description . . . . . . . . . . . . . . . . . . . . ..... ........ . 4-98 4.25.2 Event Trev Model and Nodes ... ......... . ... . . . 4-100 4.25.3 Event Tree Success Paths . . . . . . . .. ..... ...... .. . 4-104 4.25.4 Operator Actions . . . . . . .. ...... ............. .. 4-104 4.25.5 Event Tree End States .. ... ..... .......... ...... 4-105 b
V Revision: 9
[ WB5ti!1gt100se E m M um. April 11,1997 vil c$ap60opaVev,9Wtoc wpf:lb l
l
I M
TABLE OF CONTENTS (Cont.)
e i t
Section Title fate 4.26 ATWS Precursor with SI Event Tree Model ..... . ..... ..... .. 4-105 l 4.26.1 Event Description . ............. .. ............... 4-105 4.26.2 Event Tree Model and Nodes ......... ...... . . . . . . . . . . 4- 106 4.26.3 Event Tree Success Paths . . . . . . . . . . . ....... .. .. . . . . 4-109 4.26.4 Operator Actions , . . . . .... ....... ... . . .... . . . 4-109 4.26.5 Event Tree End States . .......... .... .... . . . . . . 4-110 4.27 ATWS Precursor Transients with MFW Event Tree Model . . . ... . . 4-110 4.27.1 Event Description . ... . ... .. ... . . . . . . . . . 4- 1 10 4.27.2 Event Tree Model and Nodes ............ ....... . .. 4-111 4.27.3 Event Tree Success Paths . . .......... ........... . . . . 4-114 4.27.4 Operator Actions . ... . ............ .. . ......... 4-114 4.27.5 Event Tree End States . ....... . . ..... . .. 4-114 4A Event Tree Analysis Methodology . . . ........ .... ...... . . . . . 4A- 1 4A.1 Overview . . . . . . ...... ..... .. ...... . ........ . . 4A-1 4A.2 Event Tree Terminology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 A- 1 4A.3 Event Tree Development . . . . .... . .. . .. . . . . 4A-2 4A.4 Success Criteria . . . . . . . . . . . . . . . . . . . . ........... ........... 4A-4 4 A.4.1 Time Frame ... . ... ............. . .. . .... . 4A-4 4A.5 Consequential Events . . . . .................. .. ..... . . . . 4 A-5 4A.6 Definition of Core Damage Categories . . . . ......... . . . . . . . . . . 4 A -5 CHAPTER 5 SUPPORT SYSTEMS 5.1 Introduction . ..... .. . .... . .. . ....................... 51 5.2 Support Systems and Their Interdependencies . . . . ..... .. . .. ... . 5-1 5.3 Front-Line Systems and Their Dependencies . . . . . . . . . . ...... ...... . 5-1 CHAPTER 6 SUCCESS CRITERIA ANALYSIS 6.1 Introduction . .......... .. . ........ ... .. .. ..... 6-1 6.2 Acceptance Criteria and Critical Functions for Success Criteria . . ......... 6-1 6.3 Event Sequences and Timing, Passive / Active System Interactions . .. ..... 6-3 6.3.1 General Sequence Success Criteria . . . . . . . .. ..... . ..... 6-3 6.3.2 Timing of Events and Key Operator Actions . .... ........ 6-8 6.3.3 Passive / Active System Interactions ..... . . .. . . . . . . . . 6- 17 6.3.4 Sequence Success Criteria Summary . . . . . . . . . ... .. . .. . 6-19 6.4 Event Tree Top Events Success Criteria .......... . .. ....... . 6-20 6.4.1 Accumulators ........ . . .......... .. . ....... 6-21 6.4.2 Full RCS Depressurization . . .... ........ . . ..... 6-22 6.4.3 Partial RCS Depressurization . . . . . . . . . . . .. .... ........ . 6-33 6.4.4 Location of Main Steam Line Break Upstream of MSIVs . . . . . . . 6-40 6.4.5 Large LOCA Break Size Sufficient for IRWST Injection with Failed Containment Isolation . . .. .......... ... ... 6-41 e
Revision: 9 April 11,1997 h,, ,,,. [ Westiflgt10Use o%p6005praVev.yspra-tocwpf:Ib viij
g i t V
TABLE OF CONTENTS (Cont.)
Section Title Page 6.4.6 Main Steam Line Isolation Following Steam Line Break . . . . . . . . . 6-41 6.4.7 Steam Generator Isolation Following SGTR ... .......... . . 6-43 6.4.8 Containment Isolation for Large LOCA .. ........... . . . . 6-44 6.4.9 Core Makeup Tank System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 5 6.4.10 Turbine Bypass and Main Condenser Available - SGTR . . ... . 6-50 6.4.11 Auxiliary Pressurizer Spray . . . . . .. ......... ... . . . . . 6-51 6.4.12 RCS Boration Following ATWS . . . . . . . . . . . . ... ... . . . 6-52 6.4.13 RCS Makeup From the Chemical and Volume Control System . . . . . 6-53 6.4.14 Inventory and Reactivity Control Following Steam Line Break . . . . . 6-5 5 6.4.15 Diverse Actuation System Operation for ATWS . . ... . . . . . 6-5 6 6.4.16 Emergency Diesel Generators Operate . . .... . . . . . . . . . . 6-5 8 6.4.17 Main Feedwater Available . . . . . . . . . ... ... ... . .... . 6-59 6.4.18 Gravity Injection . . . . . . . . . . . .... ...... .. ....... 6-62 6.4.19 Motor Generator Sets Tripped . . . . . ...... ............... 6-67 6.4.20 RCS Pressure Relief Via Pressurizer Safety Valves . . . . .. .. . . 6-68 6.4.21 Patsive Residual Heat Removal System Isolation Following PRHR Tube Rupture ...... . ..................... . . 6-69 6.4.22 Passive Residual Heat Removal System Operatica . . . . . . . . . . . . . 6-70 l] 6.4.23 Pressurizer Safety Valves Reclose . .......... . . . . . . . . . . . . 6-74 v 6.4.24 Offsite Power Recovered Within One-half Hour . . . . . . . . . . . . . . . 6-75 6.4.25 Reactor Coolant Pumps Trip . ......... ...... . . . . . . . . . 6-7 6 6.4.26 Water Recirculation to the RCS . . .. ........... . . . . . . . . . 6-7 8 6.4.27 Normal 14esidual Heat Removal System . . ............ . . . . . 6-80 6.4.28 Reactor Trip . . . . . . . . . . . . . .... ... ... . ........ 6-84 6.4.29 Manually Step-In Control Rods Following ATWS .. ... ...... 6-87 6.4.30 Manual Controlled Shutdown .. .......... .... . . . . . . . . 6-8 8 6.4.31 Startup Feedwater System ............... . . . . . . . . . . . . 6- 8 8 6.4.32 Steam Generator Overfilling Protection . . . . . . . .... ......... 6-93 6.4.33 Steamline Break-Induced Steam Generator Tube Rupture ... . . . . 6-94 6.4.34 Reclosure of the Main Steamline Relief Valves . ........ ... . 6-95 6.5 ATWS Modeling Considerations . . ............... ....... . . . . 6-98
- 6.5.1 Background . .. .. ......... .. ... . ..... . . 6-98 6.5.2 Success Criteria for Shutdown . . . . . . . . . . . . . . . . . . . 6-98 6.5.3 Success Criteria to Achieve Zero UET . . . ... . . .. . . . . . 6-99 6.5.4 Success Criteria Credit for Reactor Coolant Pump Trip ... ... . 6-100 6.6 References .....................................6-101 CHAPTER 7 FAULT TREE GUIDELINES 7.1 Purpose .......... ...... .. ... . ... ... ........ ..... 7-1 7.2 Fault Tree Development . . . . . . . . .... ......... ... .. . ... 7-1 7.2.1 Procedural Steps for Fault Tree Preparation . . . .. ......... 7-1 7.2.2 Procedural Steps for Fault Tree Construction . . . .. .... ..... 7-2 O
V Revision: 9
[ Westilighouse fh_ o:\np600\pra\ ret9\pra. toc.wpf:lb April 11,1997 iX I
___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . a
=
1 I
TABLE OF CONTENTS (Cont.)
O I
Section Title Page 7.3 Primary Events to be Considered in Fault Trees . . .................... 7-3 7.3.1 Random Component Failure ........................ .. . 7-4 7.3.2 Outage for Maintenance and Testing ................ ...... 7-6 7.3.3 Common Cause Failures . . . . . . . . . . . . . . . . . . . . ....... .. 7-7 7.3.4 Human Errors . . . . . ............. ..... .............. 7-7 7.3.5 Power and Control Model . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-10 7.4 Data Base . ..... . . ......... ................... ......... 7-11 7.5 Fault Tree Model: Identification Codes .... ............ ........ 7-11 7.5.1 Identification Code for Fault Tree Names ... ............... 7-11 7.5.2 Identification Code for Support Systems . . . .. . . . . . . . . . . . . 7- 12 7.5.3 Identification Code for Primary Event Names ... ...... ... . . 7-12 7.5.4 Identification Code for Common Cause Failures . .. . . . . . . . . . . 7- 12 7.5.5 Identification Code for Undeveloped Events (Modules) .... ..... 7-13 7.5.6 Identification Code for Operator Errors . .. ................7-14 7.6 Fault Tree Quantification .... ........ . .... .................7-14 7.7 References ...... ........ ... .. ... ....... ............ 7-15 P SS IDU T VkL 8.1 System Description ...... ..... ................ . .......... 8-1 8.1.1 Support Systems . . . . . . . . . . . . . . . . . . ................. . 8-1 8.1.2 Instmmentation and Control .. ........ ...... ........... 8-1 8.1.3 Test and Maintenance Assumptions ....... ................ 8-2 8.2 System Operation . . . ...................... ... ............. 8-2 8.3 Pe:formance during Accident Conditions . . . . .......... ............. 8-3 ,
8.3.1 Non-Loss-of-Coolant Accident Transients . . . . . . . ..... ..... 8-3 8.3.2 Loss-of-Coolant Accidents . . . . . . . . . . . . . . . . .... ... ...... 8-3 8.3.3 Passive Residual Heat Removal Heat Exchanger Tube Rupture ...... 8-4 8.4 Initiating Event Review ............................... ....... 8-4 8.4.1 Initiating Events Impacting the Passive Residual Heat Removal System . . . .... .. ........... .... ........ . ... 8-4 8.4.2 Initiating Events Due to Loss of the Passive Residual Heat Removal System ...... .. . ........... .. .. . ............ 8-5 8.5 System Logic Models . . . . . ......... ..... . ... ......... . 8-5 8.5.1 Assumptions and Boundary Conditions ... .. ......... ..... 8-5 8.5.2 Fault Tree Models . . . . ..... ...... . ............. 8-6 l 8.5.3 Human Intertetions ................. . .............. 8-7 ,
8.5.4 Common Cause Failures . . . . . . . . . . . . .... ... ......... 8-7 l 8.6 References . . . . . . . . . . . . ........ .......... . ..... . .... 8-7 Revision: 9 9
April 11,1997 6 WB5tingt100S6 o:\ap600\pra\rev 9%pra-toc.wpf:lb X
Q
\ >
v TABLE OF CONTENTS (Cont.)
Section Title P, age CHAPTER 9 PASSIVE CORE COOLING SYSTEM - CORE MAKEUP TANK 9.1 System Description ............................ .. ........... 9-1 9.1.1 S upport Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ... 9-1 9.1.2 Instrumentation and Control . . . . . . . . . . . . . . . . . . . . . . . ...... 9-1 9.1.3 Test and Maintenance Assumptions .. ...................... 9-2 9.2 System Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . ............. ... 9-2 9.3 Performance during Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-3 9.3.1 'nadvertent Opening of a Steam Generator Relief or Safety Valve
. . . 9-3 9.3.2 Steam Line Break . . . . . . . . . . . . . .................... .. 9-3 9.3.3 Steam Generator Tube Rupture . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-3 9.3.4 Reactor Coolant System Heatup Transients . . . . . . . . . . . . . . . . . .. 9-4 9.3.5 Loss-of-Coolant Accidents . . ........... ............. .. 9-4 9.3.6 Loss of 0ffsite Power . . . . . . . . . . . . .......... ........... 9-4 9.3.7 Anticipated Transient without Trip . . . . . . . . . . . . . ... ........ 9-4 9.4 Initiating Event Review ........................................ 9-5 9.4.1 Initiating Events Impacting the Core Makeup Tank Subsystem . . . . . . 9-5 9.4.2 Initiating Events Due to Loss of the Core Makeup Tank Subsystem . . . 9-5 9.5 System Logic Models . . . . . . . ... ... .......................... 9-5 (g)v 9.5.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . . . . . . . . . . . 9-5 9.5.2 Fault Tree Models . ................................... 9-7 9.5.3 Human Interactions .. ................................. 9-8 9.5.4 ( 'nmon Cause Failures . . . . . . . . . . . . . . .................. 9-8 9.6 References ................................................ 9-8 CHAPTER 10 PASSIVE CORE COOLING SYSTEM - ACCUMULATOR 10.1 System Description .................................. . . . . . . 10-1 10.1.1 Support Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10- 1 10.1.2 Instrumentation and Control . ........... . . . . . . . . . . . . . . . 10- 1 10.1.3 Test and Maintenance Assumptions ....................... . 10-1 10.2 System Operation . . . . . . . . . . . . . . ........... ..... . . . . . . . . . . . 10-2 10.3 Performance during Accident Conditions . . ....... . . . . . . . . . . . . . . . . 10-2 10.3.1 Steam Line Break ...... ................... ........ . 10-2 10.3.2 Loss-of-Coolant Accidents or Non-Loss-of-Coolant Accidents with Automatic Depressurization System . . . . . . . ...... . . . . 10-2 10.4 Initiating Event Review ............ ............. . . . . . . . . . . . . 10-3 10.4.1 Initiating Events Impacting the Accumulator Subsystem . . . . . . . . . . 10-3 10.4.2 Initiating Events Due to Loss of the Accumulator Subsystem . . . . . . . 10-3 r
(
Revision: 9 r
T Westinghouse @b gj o:\ap600\pra\rev 9\pra-toc.wpf.lb April 11,1997 1
t._____ . . _ . _ _ . _ _ _ _ __ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE OF CONTENTS (Cont.)
e Section Title hge 10.5 System Logic Models . . . . . ....... ....................... . . . 10-3 10.5.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . . . . . ... . 10-3 10.5.2 Fault Tree Models . . . . . . . . ....... .............. . 10-4 10.5.3 Human Interactions .... . ... ................ . . . . . . 10-5 10.5.4 Common Cause Failures . ............................. . 10-5 10.6 References ...... ............. ......... ............. .. . 10-5 CHAPTER 11 PASSIVE CORE COOLING SYSTEM - AUTOMATIC DEPRESSURIZATION SYSTEM 11.1 System Description .................... ................. ... 11-1 11.1.1 Suppost Systems . . . . . . . . . .. .. ................. .. 11-1 11.1.2 Instrumentation and Control .......... ..... ... .. . . 11-2 11.1.3 Test and Maintenance . . . . .... .............. ..... ... 11-3 11.2 System Operation . . . . . . ......... .................. .... . 11-3 11.3 Perfonnance during Accident Conditions . . . . . . . . . . . . . . . ....... .... 11-3 11.3.1 Loss-of-Coolant Accidents . . . . . . . . . . . . .... . .. ..... . 11-3 11.3.2 Tran sients . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 11-4 11.4 Initiating Event Review ........... .. ...... ...... ....... . 11-4 11.4.1 Initiating Events Impacting the Automatic Depressurization System . . 11-4 11.4.2 Initiating Events Due to Loss of the Automatic Depressurization System . . ... .. ........... .. ................... 11-4 11.5 System Logic Models . . . . . . ......... ... .................... 11-4 11.5.1 Assumptions and Boundary Conditions . .............. .... 11-4 11.5.2 Fault Tree Models . ......... ....... ..... .......... 11-5 11.5.3 Human Interactions ......... .... ................... 11-7 11.5.4 Common Cause Failures . . .. ....................... 11-8 11.6 References ................... ..... . ..... ...... . . . . 11-8 CHAPTER 12 PASSIVE CORE COOLING SYSTEM - IN-CONTAINMENT REFUELING WATER STORAGE TANK 12.1 System Description .. ... . ........ ..... .... . . . . . . . . . . . 12- 1 12.1.1 Support Systems . . . . . . . . . . . ...... .... ..... ...... 12-1 12.1.2 Instrumentation and Control ....... .. .... ... . ... 12 1 l 12.1.3 Test and Maintenance Assumptions . . . . . . . . . . . . .... .. . 12-2 12.2- System Operation . . . . ...... .... ... ... ..... ... ... . . . 12 2 12.3 Performance during Accident Conditions . . ........... ..... .. 12-2 12.3.1 Transients . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. .. 12-4 12.3.2 Loss-of-Coolant Accidents .. . ........ . . . . . . . . . . . . . . . 1 2 -4
( 12.3.3 Severe Accident Core Damage Mitigation . ...... .... ... 12-5 l
l 1
e A ,1997 _
W85tl!1gh00S8 o$ap600\pra\rev_9%pra-toc *pf.Ib xii
+ -w b *O tO) w TABLE OF CONTENTS (Cont.)
i 1
Section Title _P,. age 12.4 Initiating Event Review ......... ...... ....... .... . . . . . . . 12-5 12.4.1 Initiating Events Impacting the IRWST Subsystem . . ...... .... 12-5 12.4.2 Initiating Events Due to Loss of the IRWST Subsystem . . ...... . 12-6 12.5 System Logic Models ........... .... ....... .... ......... 12-6 l 12.5.1 Assumptions and Boundary Conditions . ... . .. . .... 12-6 l
12.5.2 Fault Tree Medels . . .. . .... ..................... . 12-8 l 12.5.3 Human Interactions ....... ......... . ... .. ...... . 12-9 12.5.4 Common Cause Failures . . . .. ........... ..... .... . 12-10 12.6 References . . . . . . . . .......... ................ ........ 12-10 CHAPTER 13 PASSIVE CONTAINMENT COOLIM SYSTEM 13.1 System Description . ........... . ... .... . . . . . . . . . . . . 13- 1 13.1.1 Support Systems ........ .. .. ... .. .. ... ..... . 13-1 13.1.2 Instrumentation and Control . . .. ........ .. . . . . . 13-1 13.1.3 Test and Maintenance Assumptions .... ....... .......... 13-2 13.2 System Operation . . . . ....... ........ ...... ....... .. .. 13-2 13.3 Performance during Accident Conditions . . . . . . . ... .. . .......... 13-2 13.3.1 Post-Reactor Trip with Loss of All ac Power . . . . . . . . . . . . . . . . . . 13-2 (n) 13.3.2 13.3.3 Automatic Depressurization System (ADS) Actuation . . . . . . . . . . . . 13-2 Post-Loss-of-Coolant Accident . . ........ ... ..... ... . 13-3 13.3.4 Post-Main Steam Line Break . . . . . . . . .................... 13-3 13.4 Initiating Event Review ..................... . . . . . . . . . . . . . . 13-3 13.4.1 Initiating Events Impacting the Passive Containment Cooling System . . . . . . . . . . . . . . . . .... ...... . . . . . . . . 13-3 13.4.2 Ir.itiating Events Due to Loss of the Passive Containment Cooling System . . . . ........ .. ....... . . . . . . . . . . . 13 -4 13.5 System Logic Model . ....... ...... ..... .... . .. .. . . . 13-4 13.5.1 Assumptions and Boundary Conditions . . . .............. 13-4 13.5.2 Fault Tree Model . . . . . . . .. .... ......... ..... ..... 13-6 13.5.3 Human Interactions ..... .. .. ........ ............ 13-6 13.5.4 Common Cause Failures . . .... . .... ..... .. . . . . . . 13-6 )
13.6 References . . ..... ...... ......... ....... .. .. . . . . . . . 13-7 )
CHAPTER 14 MAIN AND STARTUP FEEDWATER SYSTEM i 14.1- System Description . .. ... .. .. . .... ..... . ..... ... 14-1 14.1.1 Support Systems ..... .... ............. . .. . . . . . . 14-1 14.1.2 Instrumentation and Control .... .. ....... . . .. ..... 14-1 14.1.3 Test and Maintenance Assumptions . . . . . . . . . ........ ..... 14-2 l (D
U Revision: 9 3 WBStirighouse ENE Wh April 11,1997 xiii o:\ap600Nprairev.9\pra-toc.wpf; 1 b l
1 l
t L_____________.__._.._
=
TABLE OF CONTENTS (Cont.)
0 Section Title f.aye 14.2 System Operation .................... ...... ............... 14-2 14.3 Performance during Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-2 14.4 Initiating Event Review .... ............................. ... . 14-4 14.4.1 Initiating Events Impacting the Main and Startup Feedwater and Condensate Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-4 14.4.2 Initiating Events Due to Loss of the Main and Startup Feedwater and Condensate Systems . . . . ................... 14-5 14.5 System Logic Models . . . ........................ ....... . . . . 14-5 14.5.1 Assumptions and Boundary Conditions . . . . . . . ... ...... . 14-5 14.5.2 Fault Tree Models . . . . ............. .... .. . . . . . . 14-7 14.5.3 Human Interactions . ............... . .............. 14-8 14.5.4 Common Cause Failures . . . . . .. ......... ....... .... 14-8 14.6 References .. ........... . ..... ...... . ....... ..... 14-8 CHAPTER 15 CHEMICAL AND VOLUME CONTROL SYSTEM 15.1 System Description ..... .. ... .......... . ......... .. . 15-1 15.1.1 Support Systems . . . ........ ................... .. 15-1 15.1.2 Instrumentation and Control Assumptions . . ............ . . . . 15-1 15.1.3 Test and Maintenance Assumptions ......... .. ....... . . 15-2 15.2 System Operation ......... .. ................ ...... . . . . . 15-3 15.3 Performance during Accident Conditions . . . . .. . .... . .... 15-3 l 15.4 Initiating Event Review ... .......... ....... ... ... . . . . . . . . 15-5 15.4.1 Initiating Events Impacting the Chemical and Volume Control System .15-5 15.4.2 Initiating Events Due to Loss of the Chemical and Volume Contro1 System . . . . . . . . . . . . . ... .. ........ .. . . . 15-5 i 15.5 System Logic Models . . . . . . . . . ....... . .. .... ...... ...... 15-5 15.5.1 Assumptions and Boundary Conditions . . . . ........... ..... 15-5 l 15.5.2 Fault Tree Models . . . . . . . . . . . . . . . . . . . . . . . . ..... . . . 15-7 i 15.5.3 Human Interactions ...................... .. . ... 15-8 1 15.5.4 Common Cause Failures . . ..... .. .. . .. ......... 15-8 l 15.6 References . . . . . . . . . . . . .................... . ...... . . . . 15-8 i
CHAPTER 16 CONTAINMENT HYDROGEN CONTROL SYSTEM l 16.1 System Description .. .... ..... .. .... .. .. . . 16-1 l 16.1.1 Support Systems . . . ... .............. ............ 16-1 16.1.2 Instrumentation and Control .. . ..... . . .. . . . . . . 16-1 l 16.1.3 Test and Maintenance . . ............ .. ...... . . . . . 16-2 l 1
i 1
Revision: 9
~
Oll l
l April 11,1997 '6 [ WBStingh00SO o: sap 60%rasrev 9spra-ioc.wpf:tb xiv
. . _ _ _ _ __-__- -___ - __ - ____ __ - _ _ ____- --_- ___ - __ _ ____________ _________ _________ - ____ O
t.:--r o
\ i v
TABLE OF CONTENTS (Cont.)
Section Title Page 16.2 System Operation . . . . . . . . . . . . . . . . . . ..... ..... . . . . . . . . . . . . 16-2 16.3 Performance during Accident Conditions . ........... ......... . . . . 16-2 16.4 Initiating Event Review ...... ....... ... ... . .... . . . . . 16-2 16.5 System Logic Model . . . . . . . . . . . . . . . . . ........ ..... . . . . . . 16-2 16.5.1 Assumptions and Boundary Conditions . ................ . . . 16-3 16.5.2 Fault Tree Model . . . ..... .. . . . . . . . . . . . . . . . . . . . . . . 1 6-3 16.5.3 Human Interactions ....... ... ... .... . . . . . . . . . . . . 16-4 16.6.4 Common Cause Failures . . . . . . . . . . . . . .. . ....... . . 16-4 16.6 References .........................................16-4 CHAPTER 17 NORMAL RESIDUAL HEAT REMOVAL SYSTEM 17.1 System Description ... .. .. ........ ..... . .. ..... . . 17-1 17.1.1 Support Systems . . . . . . . .... . .. . .. . . 17-1 17.1.2 Instrumentation and Control ... .. ... ............. .... 17-1 17.1.3 Test and Maintenance Assumptions . . . . . . . ... . . . . . . 17-1 17.2 System Operation . . . . . . . . . . . . . . . . .. .. .... ..... .... .. 17-2 17.3 Performance during Accident Conditions . .. . ..... . ... .. .... 17-2 c 17.4 Initiating Event Review . ......... . .. ... ...... ... ...... . 17-3 3
( 17.4.1 Initiating Events Impacting the Normal Residual Heat {
b Removal System . . . . . .... .... . .............. 17-3 17.4.2 Initiating Events Due to Loss of the Noanal Residual Heat Removal System . . . . . . ......... ...... . .... . 17-4 17.5 System Logic Models . . . . ..... .. ..... .............. ... 17-4 17.5.1 Assumptions and Boundary Conditions .. ......... .... . . 17-4 17.5.2 Fault Tree Models . . . . . . . . . . . ........... ...... .. 17-6 17.5.3 Human Interactions ...... . ..... .... . . . . . . . . . . . . . . . 1 7-7 17.5.4 Common Cause Failures . . . . . . . ... .................... 17-7 17.6 References ....... .. ........... ... ................. . 17-7 CHAPTER 18 COMPONENT COOLING WATER SYSTEM 18.1 System Description ................ .........................18-1 18.1.1 Support Systems .......... ......... . ..... . . . . . 18- 1 18.1.2 Instrumentation and Control ... .......... .. .. .. . . . . I 8-1 18.1.3 Test and Maintenance Assumptions . .. ...... ...... . . . 18-1 18.2 System Operation . . . . . . . . . . . . . . . . . . ................... ...... 18-2 18.3 Performance during Accident Conditions . . . . ...... .. . . . . . . . . . . 18-2 18.4 Initiating Event Review .... ........ . . .............. ... . 18-2 18.4.1 Initiating Events Impacting the Component Cooling Water System . . . 18-3 18.4.2 Initiating Events Due to Loss of the Component Cooling Water System . . . . . . . ........ ....... .. ......... . . . 18-3
/m N.)i Revision: 9 3 W85tingh00S8 hh_ XV o:\ap600\prairev 9%pra-toc.wpf.lb April 11,1997
TABLE OF CONTENTS (Cont.)
e Title f, age Section 18.5 System Logic Models . . . . . . . . . . . . . . . . . . . ...... . . . . . . . . . . . . . 18-3 18.5.1 Assumptions and Boundary Conditions . . . . . ......... . . . . . 18-3 18.5.2 Fault Tree Models . . . . . . . . .......... . . . . . . . . . . . . . . . 1 8-4 18.5.3 Human Interactions ... . .. ............ ....... ... . 18-5 18.5.4 Common Cause Failures . . . . .... ............... . . . . . 18-5 18.6 References .................... ..................... ..... 18-5 CHAPTER 19 SERVICE WATER SYSTEM 19.1 System Description ........... . ........... ................ 19-1 19.1.1 Support Systems . . . .... .. ....... ..... . . . . . . 19-1 19.1.2 Instrumentation and Control .................. ........ . 19-1 19.1.3 Test and Maintenance Assumptions ...... ... . .. ... . . 19-1 19.2 System Operation . . . . . . . . ... ...... .... ......... .. .. . 19-2 19.3 Performance during Accident Conditions . . . . . . . . . . .. ..... ... . 19-2 19.4 Initiating Event Review ....... ....... .... . . ..... ... . 19-2 19.4.1 Initiating Events Impacting the Service Water System . . . . . . . . . . 19-3 19.4.2 Initiating Events Due to Loss of the Service Water System . . . . . . . 19-3 19.5 System Logic Models . . . . . . ....... ........ . . . ...... 19-3 19.5.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . . . . . . . . . . 19-3 19.5.2 Fault Tree Models . . . . . . . .. .......... .. ...... .. 19-5 19.5.3 Human Interactions .. ....... .......... ...... . . . 19-5 19.5.4 Common Cause Failures . .. .... .... . ....... . . . . . 19-5 19.6 References . . . . . . . . . . . . . . . . ... .............. .......... . 19-5 CHAPTER 20 CENTRAL CHILLED WATER SYSTEM 20.1 System Description ....... ...... ... ...... ....... ... . . 20-1 20.1.1 Support Systems . .. ........ .. ... .. ....... . . 20-1 20.1.2 Instrumentation and Control .... ....... ... . . . . . . . . . . . 20- 1 20.1.3 Test and Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . 20-1 20.2 System Operation . . . . . . . . ............. . ... ... ........ 20-2 20.3 Performance during Accident Conditions . . . . . . . . . . . . . . . . .. . .. .. 20-2 20.4 Initiating Event Review ... .......... .. ..... . .... ...... 20-2 20.4.1 Initiring Evem Im: acting the Central Chilled Water System . . . . . . 20-3 20.4.2 Initinting Events Due to Loss of the Central CC.ed Water Syst m . . ..... .. ............... . .... .. .... 20-3 20.5 System Logic Model ..... ............ ...... . . . . . . . . . . . . . . 20-3 20.5.1 Assur iptions and Boundary Conditions . . . . . . . ... . . . . . 20-3 20.5.2 Fault Tree Mcdel . .. .......... . . . . . . . . . . . . . . . . . . . . . 2 0-4 20.5.3 Humn Interactions . .......... ... ... ......... . . 20-4 20.5.4 Common Cause Failures . . . ...... . ... ....... ... 20-4 p ,1997 - WB5tiligt100SB o$ap6005pra\rev_9% pre-tocMlb xvi
==_
R_ _
/
\v\/
TABLE OF CONTENTS (Cont.)
Section Title Eage 20.6 References .......... ...... .............. ....... . . . . . . 20-5 CHAPTER 21 AC POWER SYSTEM 21.1 System Description ........... . . ...... .... .... . . 21-1 21.1.1 Support Systems ........... .............. .. ....... 21-2 21.1.2 Instrumentation and Control . ..... ......... ....... 21-2 21.1.3 Test and Maintenance Assumptions . . . . . . . . . . .. ..... . 21-2 21.2 System Operation .. .. . ... ...... ............. ... ...... 21-2 21.3 Performance during Accident Conditions . . ......... . .. . .... ... 21-3 21.3.1 Automatic Load Shedding .... . ... .... .. ...... .. 21-3 21.3.2 Manual Transfer . . . .... . ...... . ... ........ . 21-3 21.3.3 Electric Circuit Protection .......... ... . ... . 21-3 21.4 Initiating Event Review ... .......... ..... . ... .... .. 21-4 21.4.1 Loss of the Main Generator . . ........... .... ... ... 21-4 21.4.2 Loss of Offsite Power . ..... .. ... . .... .. ... 21-4 21.4.3 Loss of 4160-vae and 480-vac Busses . . . .. ..... ........ 21-5 21.5 System Logic Models . . . .... . .. .... ..... ... .. ..... . 21-5 21.5.1 Assumptions and Boundary Conditions . . . .. . . . . . . . . . 21 5
( 21.5.2 Fault Tree Models . . . ... . ....... .... .. ........ 21-8
\ 21.5.3 Human Interactions ... .. .. .......... ... .. ..... . 21-8 21.5.4 Common Cause Failures . . . ...... ..................... 21-9 21.6 References .. ...... . ... .. ... . . . 21-9 CHAPTER 22 CLASS 1E DC AND UNINTERRUPTIBLE POWER SUPPLY SYSTEM 22.1 System Description ......... . . .. .. ....... . . ....... 22-1 22.1.1 Support Systems ........ ... ... .......... . . . . 22-1 22.1.2 Instrumentation and Control ........ . ... .... ... .... 22-1 22.1.3 Test and Maintenance Assumptions . . . ..... .. . .... . 22-2 22.2 System Operation . . . . . . . . . . . . . . ... ............. . .. ... .. 22-2 22.3 Performance during Accident Conditions . .. .. .. . .. . ... 22-2 22.4 Initiating Event Review .. ................ ...... .... .... . 22-3 22.4.1 Initiating Events Impacting the Class IE de and UPS System .. ... 22-3 22.4.2 Initiating Events Due to Loss of the Class 1E de and UPS System . . 22-3 22.5 System Logic Models . . . . . . . . . . . . . . . . . . . . . . ...... ........ . . 22-3 22.5.1 Assumptions and Boundary Conditions . . . . . . . . ....... . 22-3 22.5.2 Fault Tree Models .... ........ ...... .... .. . . . 22-4 22.5.3 Human 1 interactions . . ... ............ . ........ ... 22-5 22.5.4 Common Cause Failures . . . . ... .... . .. . 22-5 22.6 References . . . .......... .... ................ ...... 22-5 i
l fm C ~
Revision: 9 ENE 3 Westinghouse wh. April 11,1997 xvij o:\ap600Nprairev.95ra-toc.wptib
g -- %
l_
TABLE OF CONTENTS (Cont.)
O Section Title Page CHAPTER 23 NON-CLASS lE DC AND UPS SYSTEM 23.1 System Description .... . .......... ............. ...... ... 23-1 23.1.1 Support Systems . . . . . . . . . . . . . . . . . . ...... .......... 23-1 23.1.2 Instrumentation and Control ..................... . . . . . . 23-1 23.1.3 Test and Maintenance Assumptions . . . . ............. . . . . . 23-1 23.2 System Operation . . . . . . . . . . ....... .............. .......... 23-2 23.3 Performance during Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . ... 23-2 23.4 Initiating Event Review ..................... . ............ . 23-2 23.4.1 Initiating Events Impacting the Non-Class IE de and UPS System ..... .. ........ . . ... .. ........... . 23-3 23.4.2 Initiating Events Due to Loss of the Non-Class IE de and UPS System . . ................ . . .... ...... 23-3 23.5 System Logic Models . .. .. .. ..... ... . ... ......... . 23-3 23.5.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . . . ..... 23-3 23.5.2 Fault Tree Models . ....... .. ..... . . . . ... .. 23-5 23.5.3 Human Interactions . ... .. ... . . . ..... ... 23-5 23.5.4 Common Cause Failures . . . . . . . . . ..... . . . . . . . . . . . . . . 23-5 23.6 References . . . ................. ......... ............... 23-5 CHAPTER 24 CONTAINMENT ISOLATION 24.1 System Description . ....... ...... ............... ...... 24-1 24.1.1 Support Systems . . . . . . . . . . . .. .......... ... ... .. 24-1 24.1.2 Instrumentation and Control ......... ..... ... . .... 24-1 24.1.3 Test and Maintenance Assumptions . ......................24-1 24.2 System Operation . . . ............ ....... . .......... ... .. 24-2 24.3 Performance during Accident Conditions . . . ..... ............. .... 24-2 24.4 Initiating Even; Review . ................. ... ..... ......... 24-2 24.4.1 Initiating Events Impacting Containment Isolation ....... ..... 24-2 24.4.2 Initiating Events Due to Loss of Containment Isolation System . . . . . 24-2 24.5 System Logie Models . .............. ......... . .... .... 24-3 24.5.1 Assumptions and Boundary Conditions . . . . . . .... . ...... . 24-4 24.5.2 Fault Tree Models . . . ..... . .......... .... ...... 24-5 24.5.3 Human Interactions . . ... ......... ................. 24-6 24.5.4 Common Cause Failures . . ............. .... .... .... 24-6 24.6 References . ....... . .......... . ... ... . . ....... . 24-6 O
Revision: 9 ENEL April 11,1997 kva h 3 Westiligh00Se o:\ap600\pra\rev.9pra-tocwpf.lb xviii
ilN G
TABLE OF CONTENTS (Cont.)
Section Title Eage CHAPTER 25 COMPRESSED AND INSTRUMENT AIR SYSTEM 25.1 System Description . ........ . .. .... .. . . .. . ... 25-1 25.1.1 Support Systems ..... ... . .... ... . .. . . 25-2 25.1.2 Instrumentation and Control . .. ......... ... . ..... 25-2 25.1.3 Test and Maintenance Assumptions . . . . . . . . . . . . . . . .. . .. 25-3 25.2 System Operation . . . . . . . . . . . . . . . ... .... . ..... .. . 25-3 25.3 Performance during Accident Conditions . . .. . . . .. 25-3 25.4 Initiating Event Review ....... .. ...... .. . ...... . ... . 25-4 25.4.1 Initiating Events Impacting the Instmment Air Subsystem ....... 25-4 25.4.2 Initiating Events Due to Loss of the Instrument Air Subsystem . . . . 25-4 25.5 System Logic Models . . . . . . . . ... . . . ... .... . . . . . 25-5 25.5.1 Assumptions and Boundary Conditions . . . . . .. .... . . 25-5 25.5.2 Fault Tree Models . . .. . ...... ...... . . . 25-6 25.5.3 liuman Interactions ..... . . . ...... ... ... ... . 25-7 25.5.4 Common Cause Failures . . .... ... . . ...... 25-8 25.6 References ...... . . ...... ........... . .. .. .. .... 25-8 t
O d CHAPTER 26 PROTECTION AND SAFETY MONITORING SYSTEM 26.1 System Analysis Description . . . . . . ......... . .... . . 26-1 1 26.1.1 Analysis of Support Systems . . . . . ...... . . . . . . . 26-4 26.1.2 Analysis of Instrumentation . . . . . . . .... . .. . .... . 26-6 26.1.3 Test and Maintenance Assumptions . . . . . . ....... . . ... 26-6 1 26.2 Performance during Accident Conditions . . . . . . . . .. ... .. . 26-7 26.3 Initiating Event Review ......... . . .. . .. . . . . . 26-8 26.3.1 Initiating Event Impacting PMS . . . .. ... . ... . . . . . 26-8 1 26.3.2 Initiating Event due to Loss of PMS . . . . . . . . ...... . . . . . 26-8 26.4 System Logic Model Development . .. ............. .. . . . . . 26-9 l 26.4.1 Assumptions and Boundary Conditions . . . . .. .. . . . . . 26-9 26.4.2 Fault Tree Models . . . . ................ . .. ... . . . . 26-13 l 26.4.3 Description of 1&C Subtree Development ........... . . . . 26- 13 26.4.4 Human Interactions .. ... . .......... . ..... . . . . 26-21 i
1 26.5 Discussion of Methodology . . ....... .................. ... . 26-21 l l l 26.5.1 Fault Tree Analysis ..... .................... .. . . . 26-21 ;
l 26.5.2 Unavailability . . . . . . . . ....... ............. ... . . 26-22 26.5.3 Spurious Failure Rate Per Year ... ...... .. . . . ... 26-22 26.5.4 Common Cause Failures . . ... ..... ..... ..... . . 26-24 ,
i 26.5.5 Data Manipulation . . . . . ... ............... .. . . 26-24 l l 26.6- References . .... .. .. . ... ...... ... . . . . . . 26-26 l
O !
N.]
l ENEL Revision: 10 l [ WSStiflgh0llS8 :ggw- June 30,1997 xix o:\ap60opraWv.t0%pra-toc.wpf Ib
-I>
0 TABLE OF CONTENTS (Cont.)
Section Ili!! ERES CHAPIER 27 DIVERSE ACTUATION SYS'IEM 27.1 System Analysis Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27-1 27.1.1 Support Systems Analysis . . . . . . . . . . . ........... ..... 27-1 27.1.2 Analysis of Instrumentation and Control . . . . . ......... .... . 27-2 27.1.3 Test and Maintenance . . . . . . ....................... . 27-2 27.2 Analysis of System Operation . . . . . . . . . . ...................... . 27-2 27.3 Performance during Accident Conditions ...........,........... ... 27-6 27.4 Initiating .svent Review ..................... ........... . .. 27-7 27.4.1 Initiating Events impacting the Diverse Actuation System . . . . . . . . . 27-7 27.4.2 Initiating Events Due to the Loss of the Diverse Actuation System . . 27-7 27.5 System Logic Model . . . . . . . . . . . . . . . . . . ................ .. . 27-7 27.5.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . .... . 27-7 27.5.2 Fault Tree Model . . . . . . ........ ................ . . 27-8 27.5.3 Human Interactions ................. ............. ... 27-8 27.5.4 Common Cause Failums . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27-8 27.6 References . . . . . . . . . . . . . . . . . . ....... ... ............... . 27 8 CHAPTER 28 PLANT CONTROL SYSTEM 28.1 System Analysis Description . . . . . . . . . . . . . . . . . . . . . . . .......... . 28 1 28.1.1 Analysis of Support Systems . . . . . . . ................... . 28-3 28.1.2 Analysis of Instrumentation . . . . . . . .................. . . . 28-4 28.1.3 Test and Maintenance Assumptions . . .. .................. 28-5 28.2 Performance during Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-6 28.3 Initiating Event Review . ..................................... 28-6 28.3.1 Initiaing Events Impacting the Plant Control System . . . . . . . . . . 28-6 28.3.2 Initiating Event due to Loss of Plant Control System . . . . . . . . . . 28-7 28.4 System Logic Model Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-7 28.4.1 Assumptions and Boundary Conditions . . . . . . . . . . . . . . . . . . . . 28-7 28.4.2 Fault Tree Models . . . . . . . . . . . . . . . . ............... . 28-10 28.4.3 Description of I&C Subtree Development . . . . . . . . ..... .... 28-11 28.4.4 Human Interactions ..... . ......................... . 28-18 28.5 Discussion of Methodology . . . . . . . . . . . . . . . . . . . . ....... . . .. . 28-19 28.5.1 Fault Tree Analysis . . .. .......................... . 28-19 28.5.2 Unavailability ....... .. .... .............. .... 28-19 28.5.3 Common Cause Failures . . . . . ... .. ........ .... . . 28-19 28.5.4 Data Manipulation . . . . . . ..... ........ .... . . 28 20 28.6 References .. .. .. ......... ......... . ....... . . . . 28-21 O
Revision: 9 April 11,1997 _ W85tingh00S8 o$ap6oopr \rn 9spra-soc wpf:Ib n
l
- /'~~N C/'
l TABLE OF CONTENTS (Cont.)
Section Title Page CHAPTER 29 COMMON CAUSE ANALYSIS 29.1 Introduction .... .................. ............... ... . . . 29-1 29.2 Dependent Failures . . . ........ .................... ..... . 29-1 29.3 Common Cause Analysis . . . . . . . . . . . . . . . . . . . ... .. . . . . . . . . . . . 29-4 29.3.1 A ssumptions . . . . . . . . . . . . . . . . . . . . . ... ........ . . 29-4 29.3.2 Analysis of Potential Common Cause Failures within the System . . . . 29-5 29.3.3 Analysis of Potential Common Cause Failures among Several Systems . 29-6 29.4 Calculations for Component Groups . .............................29-6 29.4.1 Class 1E DC Batteries ........ . .......... ........... 29-6 29.4.2 Non-Class IE DC Batteries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29-7 29.4.3 Air-Operated Valves on the Core Makeup Tanks . . . . .......... 29-8 29.4.4 Automatic Depressurization System Motor-Operated Valves . . . . . . . 29-9 29.4.5 Automatic Depressurization System Squib Valves . ......... . 29-11 29.4.6 Common Cause Failure for IRWST Valves . . . . .... .. . . . . . 29-11 29.5 Results . . . . . . . . . . . . . . . . . . . . . . ..... .......... ......... . 29-15 29.6 References ....... ....... ... ... ........... ...... .. 29-15 p CHAPTER 30 HbW RELIABILITY ANALYSIS t i 30.1 Introduction ............ .... ...... .. ....... ... .. . 30-1
'/ 30.2 Summary of Results . . . . . ................. ... .......... . . . 30-1 30.3 Methodology . . . . . . . . . . . . . . . . . ......... ...... . . . . . . . . . . . . 3 0-2 30.4 Major Assumptions ........ ....... ... . .... .. . . . . . . . . . 3 0-4 30.5 Types of Human Interactions . . . . . . . . ...................... . . 30-10 30.5.1 Quantification Model . . . . ..... . .. .. . . . . . . . . . . . . . 30- 1 1 ;
30.6 Quantification . . . . . . . . . . . . . . . . . . . . . . . .......... ....... .. 30-12 30.6.1 ZON-MAN 01 (Start the Onsite Standby Diesel Generator) . ..... 30-12 ,
30.6.2 LPM-MAN 01 (Recognize the Need for Reactor i Coolant System Depressurization) .. ..... .... .... .. . 30-13 30.6.3 LPM-MAN 02 (Recognize the Need for Reactor Coolant System Depressurization . . . . . . . . . . . . . . .. . .. . . 30-16 30.6.4 LPM-MANOS (Recognize the Need for Reactor Coolant System Depressurization . . . ........ ...... .. . 30-16 30.6.5 LPM-REC 01 (Recognize the Need for Reactor Coolant System Depressurization . . . . . ................ . . 30-17 30.6.6 ADN-MAN 01 (Actuate the Automatic Depressurization System) . . . 30-18 30.6.7 ADN-REC 01 (Actuate the Automatic Depressurization System) . . . . 30-19 30.6.8 CCB-MAN 01 (Start the Standby Component Cooling Water Pump) . . . . . . ... .... .. . .... ...... . 30-20 30.6.9 CCN-MAN 02 (Inadvertent Misalignment of Heat Exchanger) . . . . 30-21 i
I I \
G
! Revision: 9
[ W 6S Ullgt10LIS8 April 11,1997 xxi c:\a;f00prairevfpra.coc.wpf.Ib
M TABLE OF CONTENTS (Cont.)
e Section Title Page 30.6.10 CIB-MAN 00 (Diagnose Steam Generator Tube Rupture) . . . . . . . . 30-21 30.6.11 DUMP-MAN 01 (Operate Steam Dump Valves) . ............. 30-22 30.6.12 CIC-MAN 01 (Isolate Containment) ...... ... .... . . . . . . . 30-23 30.6.13 ADS-MANTEST (Recognize the Need and Reclose ADS Stage MOV) . . . . . . . . . . . ......... ... ............. 30-24 30.6.14 CAN-MANOS (Locally Close Manual Valve CAS-V204 to Isolate Containment) . ............ .. ......... .. . 30-26 30.6.15 CIT-MANOS (Isolate Containment) ........... . ....... . 30-27 30.6.16 CNM-MAN 01 (Actuate Core Makeup Tank) . . . . . . . . . . . . . . . . . 30-27 30.6.17 CNM-REC 01 (Actuate the Core Makeup Tanks) . . . . .... . . . . 30-29 30.6.18 CVN-MAN 00 (Align Chemical and Volume Control System) . . . . . 30-29 30.6.19 CVN-MAN 02 (Align Chemical and Volume Control System) . . . . . 30-30 30.6.20 CVN-MANO3 (Start Chemical and Volume Control System Pump B) . . . . . ......... ......... .. .. ......... 30-31 30.6.21 ADF-MAN 01 (Depressurize the RCS to Refill the Pressurizer) . . . . . 30-32 30.6.22 SGHL-MAN 01 (Isolate Feedwater to Failed Steam Generator) . . . . . 30-32 30.6.23 CAN-MAN 01 (Start Standby Compressor) ......... .. . . . . . 30-33 30.6.24 REN-MAN 02 (Initiate Recirculation) ......... ..... ...... 30-34 30.6.25 REN-MANO3 (Initiate Recirculation) .. . .. ... .... . . . 30-35 30.6.26 IWN-MAN 00 (Operate In-Containment Refueling Water Storage Tank Motor-Operated Valves) ....... . ......... . 30-36 30.6.27 RHN-MAN 01 (Align Normal Residual Heat Removal System) . . . . 30-37 30.6.28 RHN-MANDIV (Align Normal Residual Heat Removal System) . . . 30-39 30.6.29 RHN-MAN 02/RHN-MANO3 (Align Normal Residual Heat Removal System) . ....... ......... . ....... . . . . 30-40 30.6.30 PCN-MAN 01 (Actuate Passive Containment Cooling System) . . . . 30-41 30.6.31 HPM-MAN 01 (Diagnose Need for High Pressure Heat Removal) ............ ............... ... . . . . . . . 30-42 30.6.32 PRN-MAN 01 (Align Passive Residual Heat Removal System) . .. 30-43 30.6.33 PRN-MAN 02 (Align Passive Residual Heat Removal System) ... . 30-44 30.6.34 PRN-MANO3 (Align Passive Residual Heat Removal System) . . . . 30-45 30.6T PRI-MAN 01 (Isolate Failed Passive Residual Heat Removal Heat Exchanger) ...... ........ ..... ....... . . . . . . 30-46 30.6.36 REN-MAN 04 (Initiate Recirculation) ..... ... .... .. ... . 30-47 30.6.37 RCN-MAN 01 (Trip Reactor Coolant Pumps) . . . . .... . ... . 30-48 30.6.38 ATW-MAN 01 (Manually Insert Control Rods) ... . ... . . . . . 30-49 30.6.39 ATW-MANO3 (Manually Trip the Reactor through Protection and Safety Monitoring System in One Minute) .............. . 30-50 30.6.40 ATW-MAN 04 (Manually Trip the Reactor through Diverse Actuation System in One Minute) .. .... ..... . . . . . . . 30-51 Revision: 9 O
April 11,1997 EN.~ELa
'" W Westingh011S8 onap600\pra\rev.,95pra-toc.wpf:1b Xxii
1 na sEs j t
e i a
TABLE OF CONTENTS (Cont.)
Section Title PaZe I 30.6.41 ATW-MANOS (Manually Trip the Reactor through Protection k and Safety Monitoring System in Seven Minutes) . . . . . . . . . . . . . 30-52 1 30.6.42 ATW-MAN 06 (Manually Trip the Reactor through Diverse Actuation System in Seven Minutes) ..... ....... .. .... 30-53 30.6.43 RTN-MAN 01 (Perform Controlled Reactor Shutdown) . . . . . . . . . 30-53 l 30.6.44 FWN-MAN 02 (Start the Startup Feedwater Pumps) . . . . . . . . . 30-54 l 30.6.45 FWN-MAN 03 (Start the Startup Feedwater Pumps) . . . . . . . . . . . . 30-55 30.6.46 REG-MAN 00 (Regulate Startup Feedwater) . . .. ........... 30-56 .
30.6.47 CIA-MAN 01 (Isolate Failed Steam Generator) . . . .. . . . . . . . 30-57 30.6.48 CIB-MAN 01 (Close Main Steam Isolation Valve) .. .. . . . . 30-58 l 30.6.49 SGA-MAN 01 (Inadvertent Opening of Steam Generator Power-Operated Relief Valve) . .... .......... .... ... 30-59 30.6.50 SWN-MAN 0lN (Open Air-Operated Valve on Motor Strainer Line) . ...... .. ... .... . . ... . . . . . . 30-60 30.6.51 SWB-MAN 02 (Start Standby Service Water Pump) . . . . . . . . . . . 30-61 ,
30.6.52 SWB-MAN 02N (Start Standby Service Water Pump) .........
30-62 30.6.53 TCB-MAN 01 (Start Standby Turbine Closed Cooling
- Water Pump) . ... ......... ..... .. .......... . . . 30-63 30.6.54 TCB-MAN 02 (Locally Align Standby Turbine Closed Cooling Water Heat Exchanger) . . . . ...... ........... . . . . . . 30-64 {
30.6.55 VLN-MAN 01 (Actuate Hydrogen Control System) . .. . .. . 30-65 l 30.6.56 VWN-MAN 01 (Align Standby Chiller) . . . . . . . . . .. .. .. . 30-66 L 30.6.57 ATW-MAN 11 (Recognize the Need for Manual Boration) . . . . . . . . 30-67 30.6.58 REC-MANDAS (Diagnosis of an Event Through DAS Signals or Perform an Activity by Operating DAS Controls) . . . . . . . . . . 30-68 {
30.6.59 RHN-MAN 04 (Isolate the RNS during Shutdown Conditions) . . . . 30-68 j 30.6.60 RHN-MANOS (Initiate Gravity Injection from IRWST via l RNS Suction Line) . . . . ....... .... ...... . ... 30-70 30.6.61 RHN-MAN 06 (Recognize the Need and 'Ihrottle RNS {
Valve V011) . . . . . . . . .............. . .... .. ... 30-71 30.6.62 RCS-MANODS1 (Close AOVs CVS-V045 or -V047, Given l Failure of HL Level Instruments) ...... . .. .. .. . . 30-72 30.6.63 RCS-MANODS2 (Close AOVs CVS-V045 or -V047, Given Failure of Valves to Close Automatically) . ... . .. ... . . . 30-73 l 30.6.64 SWN-MANO3 (Recognize the Need and Locally Refill i Service Water Basin) ....... . ..... ...... . . 30-74 I 30.7 Conditional Probability Evaluation . . . ......... ........ . . . . . . 30-75 l 30.7.1 Application . . . . . . . . . . ......... . ..... .. .... . 30-76 !
30.7.2 Process Used to Determine Dependencies . . . . . . .. 30-76 !
30.7.3 Calculation of Dependent Human Error Probabilities ..... .... 30-77 l 30.8 References . . . . . . . . ........................... .. .. . .. 30-78 g
V ENEL Revision: 9 i
(
T Westinghouse a
. n%, April 11,1997 l xxiii oV mpr*n8 W N*P:lb f l
TABLE OF CONTENTS (Cont.)
e Section Title Page CHAPTER 31 OTHER EVENT TREE NODE PROBABILITIES 31.1 Introduction .. .. ................................... . . 31-1 31.2 Identification of Cases Requiring Calculations . . ..... ....... ....... 31-1 31.2.1 BL - Main Steam Line Break Occurs Inside Containment . ....... 31-1 31.2.2 CNB -- Containment Isolation Fails Due to Reactor Coolant System Vessel Rupture . . . . .............. .. . . 31-1 31.2.3 MGSET - Control Rods Motor-Generator Set Trip ......... .. 31-1 31.2.4 NSGTR -- Consequential Steam Generator Tube Rupture . . . . .... 31-2 31.2.5 PO - Pre-existing Containment Opening Allowing Bypass . . . . . . . . 31-2 31.2.6 PRES - Reactor Coolant System Pressure Relief via Pressurizer Safety Valves . . . . . . . ..... .. ..... ... .... 31-2 31.2.7 PRSOV -- Pressurizer Safety Valves Reclose .. .... ..... . 31-2 31.2.8 R05 -- Offsite Power Recovered within One-half Hour .... .. . . 31-2 31.2.9 SLSOV -- Main Steam Line Relief Valves Reclose . . ... . 31-2 31.3 Case-Specific Calculations . . .. ........... ....... . . 31 3 31.3.1 BL - Main Steam Line Break Occurs Inside Containment . . . . . . . . 31-3 31.3.2 CNB -- Containment Isolation Fails Due to RCS Vessel Rupture . 31-3 31.3.3 MGSET - Control Rods Motor-Generator Set Trip . . . . . . .. . . 31-4 31.3.4 PO -- Pre-existing Containment Opening Allowing Bypass . . .. . 31-4 31.3.5 PRES - Reactor Coolant System Pressure Relief sia Pressurizer Safety Valves . . . . . . . . . . . . .......... .. 31-4 31.3.6 PRSOV -- Pressurizer Safety Valves Reclose .. .. .. . .... 31-8 31.3.7 R05 -- Offsite Power Recovered within One-Half Hour . . . . ...... 31-8 31.3.8 SGTRI -- Single Consequential Steam Generator Tube Runture . . .. 31-9 31.3.9 SGTR - Multiple Consequential Steam Generator Tube Rupture . . . 31-10 31.3.10 SLSOV -- Main Steam Line Relief and Safety Valves Reclose . . . 31-11 31.3.11 SLSOV1 - Main Steam Line Relief and Safety Valves Reclose ... 31-12 31.3.12 SLSOV2 - Main Steam Line Safety Valves Reclose ........ .. 31-12 31.3.13 SLSOV3 - Main Steamline Relief and Safety Valves Reclose, SGTR. ... .. .... .... .. ............ . 31-13 31.3.14 BSIZE -- Large LOCA Break Size Sufficient for Gravity Injection without ADS if Containment Isolation Fails .. .. 31-13 31.4 References .... . . ...... .. ... .. ....... . .. 31-14 CHAPTER 32 DATA ANALYSIS AND MASTER DATA BANK 32.1 Data Analysis . . . . . . . . . .... ..... .. ................... . .32-1 32.1.1 Random Component Failure Data . . . .... . ... . 32-1 32.1.2 Test and Maintenance Unavailability . . . ..... ... .... 32-2 32.1.3 Common Cause Failure Data . . . . . . . . .. ... .. .. . 32-2 32.1.4 Human Reliability Data . .... ... ... ...... ... .. 32-2 32.1.5 Initiating Event Frequency Data ........ 32-2 e
Revision: 9 April 11,1997 E. NELa
- W WBStingh00S8 c:\ap6(Xhprairev.,9%pra-toc.wpf:Ib XXIV
=
E_j m
{d' TABLE OF CONTENTS (Cont.)
Section Title hge 32.2 Master Data Bank . . . . . . . . .................... ......... . . . 32-3 32.2.1 Initiating Event Frequencies ....... .. ........ ..... ... 32-3 32.2.2 Random Component Failures . ..... .... . . ... . . 32-3 32.2.3 Common Cause Failure Probabilities ... ....... ....... . .32-3 32.2.4 Human Error Probabilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2-3 32.2.5 System-Specific Calculations . . ..... ......... ......., .32-3 32.2.6 Other Event Tree Node Probabilides . . .. ............ ... . 32-4 32.2.7 Master Data Bank . . . ... ... ... . . . . . . . . . . . . . . . . 3 2 -4 32.3 References . . ................................. .. .. . 32-4 CHAPTER 33 FAULT TREE AND CORE DAMAGE QUANTIFICATION 33.1 Introduction . ........ ... .. ... ....... .. .... .... 33-1 33.2 Fault Tree Model Quantification . . .... .......... .. . . . . . . 3 3- 1 33.3 Event Tree Model Calculation . . . ........ . ... ...... ... . 33-2 33.3.1 Core Damage Quantification Method . . . . . . . . .. . . . . . 33-2 33.3.2 Input Files and Data . .............. ......... .... 33-4 33.3.3 Definition of Consequential Event Categories . . ..... . 33-4 g 33.3.4 Plant Core Damage Frequency ............. .......... . . 33-6 i]
\ CHAPTER 34 SEVERE ACCIDENT PHENOMENA TREATMENT 34.1 Introduction . ......... .... .. ... ............. ... .. 34-1 34.2 Treatment of Physical Processes . . .. ................ ... .. . 34-1 34.2.1 In-Vessel Retention of Molten Core Debris . . ................ 34-2 34.2.2 Fuel-Coolant Interaction (Steam Explosions) . . .. . . .. . 34-2 34.2.3 Hydrogen Combustion and Detonation .......... .. .. . 34-3 34.2.4 High-Pressure Melt Ejection . ...... ........... . .. . 34-4 34.2.5 Core Debris Coolability . . . . . . ... .. ... .. .... ... 34-5 34.2.6 Elevated Temperatures (Equipment Survivability) . . . .... .... 34-5 34.2.7 Summary . . . . . . . . . . . . . . ....... ....... ... ..... 34-8 34.3 Analysis Method . . . . . . . . ............... . ................ . 34-9 34.4 Severe Accident Analyses . . . . . . . . . . . . . . . . . . . . . . . ............ . 34-10 34.4.1 Accident Class 3BE - Intact Containment . . .. .. ... . 34 10 34.4.2 Accident Class 3BE - Failed Containment . . . . . . . . ........ 34-12 34.4.3 Accident Class 3BL - Intact Containment ......... ....... 34-15 34.4.4 Accident Class 3BL - Failed Containment . . ..... . . . . . . . . . . 34- 17 34.4.5 Accident Class 3BR - Intact Containment .. .. ............. 34-18 34.4.6 Accident Class 3BR - Failed Containment . . . . .. .. ...... 34-19 34.4.7 Accident Class 3C - Intact Containment . ....... .. ..... 34-19 34.4.8 Accident Class 3C - Failed Containment . ............... . 34-20 34.4.9 Accident Class 3D - Intact Containment .. .. . ..... ... . 34-20 34.4.10 Accident Class 3D - Failed Containment . . . . . . . . ........ .. 34-21
/^T t
- V Revisiom 9 ENEL
- T Westinghouse w- April 11,1997 XXv o:\ap60opraVev.,9\pra- toc.wpf.l b L___.-. -_ __ __ _ . . - . _ . - . . __.i
TABLE OF CONTENTS (Cont.)
e!
Section Title P_.jyte 34.4.11 Accident Class 6E - Bypass Containment ....... ... .. .. 34-22 34.4.12 Accident Class 6L - Bypass Containment ...... . . . . . . . . . . . 34 24 34.4.13 Accident Class I AP . . . . . . . . . . . . . . . . . . . . . . . ...... .. 34-25 34.4.14 Accident Class I A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-26 34.5 Summary ........... ................ ..... ... .. .. . 34-28 34.6 Insights and Conclusions . ........... . . . . . . . . . . . . . . . . . . . . . . . 34-2 8 34.7 References ... .... ..................... ......... ... .. 34-28 CHAPTER 35 CONTAINMENT EVENT TREE ANALYSIS 35.1 Introduction ........ . . ............. . . ......... . . 35-1 35.2 Containment Event Tree - General Discussion .. .. .......... .. 35-1 35.3 Event Tree Construction . . . . . . . . . . . .. . .... .... .. .... . 35-2 35.4 Level 1/ Level 2 Interface . . . . . . . . ........... .... . ... .... 35-3 35.5 Containment Event Tree Top Events . .... . ......... .... 35-3 35.5.1 Severe Accident Phenomena Considerations . . . . . . . . .. .... 35-4 35.5.2 Operator Action and Systems Top-Event Considerations . . . . . . . .. 35-5 35.6 Release Category Definitions . . . . . . . . . . .. ..................358 35.6.1 Release Category BP - Containment Bypass . . . . . . ........ .. 35-9 35.6.2 Release Category CI - Containment Isolation Failure . . . .... 35-9 35.6.3 Release Category CFE - Early Containment Failure . . . . . . . . . . . 35-10 35.6.4 Release Category CFI - Intermediate Containment Failure . . . . . . . 35-10 35.6.5 Release Category CFL - Late Containment Failure . . ........ . 35-10 35.6.6 Release Category IC - Intact Containment . . . . . . . . . . . . . . . 35-10 35.7 Top-Event Nodal Questions and Success Criteria . . . . . . . . . . ... .... 35-11 35.7.1 Top Event DP - RCS Depressurization After Core Uncovery . . . . . 35-11 35.7.2 Top Event IS - Containment Isolation . . . . . . . . . . . . . . . . . . . . . 35-13 35.7.3 Top Event IR - Reactor Cavity Flooding .. ........ .. . 35-14 35.7.4 Top Event RFL - Reflooding of a Degrade /. Core ....... .. . 35-15 35.7.5 Top Event VF - Debris Relocation to tb Reactor Cavity . . .. 35-15 35.7.6 Top Event PC - Passive Containmer.1 Cooling . .. .. . ... 35-16 35.7.7 Top Event IG - Hydrogen Control System . . . . . . . . . . . . . . . 3 5- 17 35.7.8 Top Event DF - Diffusion Flame . . .... ......... .... 35-17 35.7.9 Top Event DTE - Early Hydrogen Detonation ...... . . ... 35-18 35.7.10 Top Event DFG - Hydrogen Deflagration .. .. ..... . . . . . . 35-19 35.7.11 Top Event DTI - Intermediate Hydrogen Detonation . . . . . .. . . 35-19 35.8 Summary . . . .. .. ... ............... ............. . . . . 35-20 35.9 References ........ .................. ..... .. ........ . 35-20 Revision: 9 0
ENEl. Westinghouse April 11,1997 cm,,,,
oAar6o&pra\rev 9pra-toc.wpf:lb XXVi
A
=
/
\
/.
W_.
x TABLE OF CONTENTS (Cont.)
Section Title Page CHAFTER 36 REACTOR COOLANT SYSTEM DEPRESSURIZATION 36.1 Introduction ... .. . . .... .. . . .. ... 36-1 36.2 Definition of High Pressure . ..... . ... ........ . .... . . . 36 1 36.3 Node DP .... . .. . ..... .. .... ........ ... .. . . . 36-2 36.4 Success Criterion . . .... .. .. .... .. ..... ... ... . . 36-2 36.4.1 Accident Classes 3BE. 3BL,3BR. 3C . . ....... . ... ... 36-3 36.4.2 Accident Classes 1D and 3D . . ...... ...... .. . . . . 36-3 36.4.3 Accident Classes 1 A and 1 AP ..... ....... ... ...... . 36-3 36.5 Anticipated Transient Without Scram - Accident Class 3A . .. . .. . . . . 3 6-5 36.6 Steam Generator Tube Rupture - Accident Class 6. .. ... .. ...... 36-5 36.7 References .. .. .. ....... ..... . .... . . ... . . . . 36-6 CHAPTER 37 CONTAINMENT ISOLATION 37.1 Introduction . .. .. . .... . . ..... . . . ....... . 37-1 37.2 Definition of Containment Isolation . . . . . . . . . .. . ....... 37-1 37.3 Success Cntena ............... ......................... . 37-1 Accident Classes IA and LAP ..................... .
/]
V 37.3.1 37.3.2 Accident Class 3A . . . . . . . . . .. ...................
37-2 37-2 37.3.3 Accident Class 3BR . . . . . . . . . . .......... .. ........ 37-2 37.3.4 Accident Class 3BE ............ . ... ... ........... 37-2 37.3.5 Accident Class 3BL .. .. ..................... .. ... 37-2 37.3.6 Accident Class 3C . ... .... . ... . ... .. ... . 37-3 1 37.3.7 Accident Class 3D/lD .... ... ... ...... ........ ... 37-3 Accident Class 6 . . . . . . . . . . . . ...... .............
37.3.8 .. 37-3 37.4 Summary ... .. . ............... ............. . . . . . . . . 3 7-4 ;
37.5 References ............ . . .... .. ........ .. ......... 37-4 j t
CHAPTER 38 REACTOR VESSEL REFLOODING 38.1 Introduction ..................... .........................38-1 38.2 Definition of Reflooding Success . . . . . ...... ........ .... . . . . 38-1 38.3 Success Criteria . . . . . . . . . . . . . . . . .... .......... . ... . . . . . 3 8- 1 38.3.1 Accident Classes l A and I AP . . . ... ... . . ............ 38-1 38.3.2 Accident Class 3BR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 8-2 38.3.3 Accident Class 3BE . . . . . . . . . . . ... ..... . . . . . . . . . . . . . 3 8-2 38.3.4 Accident Class 3BL . . . . . .. ................... . . 38-3 1 38.3.5 Accident Class 3D/lD .... ... . ........ . ... . . . . 3 8-4 38.3.6 Accident Class 6 . . . . . . . . . . . . . . ........ ...... . . 38-4 1 38.3.7 Accident Class 3C . . . . . . ..... . ... ............ . 38-4 1 38.3.8 Accident Class 3A . . .. .... .. ... ... ... ... . 38-4 1 38.4 Summary . . . . .. ......... . . 38-4 e)
(
v l Revision: 10 l [ Westingh0llS8 6 June 30,1997 XXVij o Tap 600prairev.,10\pra-toc. wpf: I b j
L_.____._________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ . . _ _ _ . . _. _ _ _ . _ _ _ . _ _ _
1 1
1 l
IRE e
TABLE OF CONTENTS (Cont.)
.SEli.931 T.Ltit Eau CHAPTER 39 IN-VESSEL RETENTION OF MOLTEN CORE DEBRIS 39.1 Introduction .......................... .................. . 39 1 39.2 Summary of In-Vessel Retention ROAAM . . . . . . . . . . . . . . . . . . . . . . . . . . 39-2 39.3 Reactor Coolant System Depressurization . . .. ....... ...... . ... 39-4 39.4 Reactor Cavity Flooding (Node IR) . . . . ..................... . . . 39-4 39.4.1 Success Criteria . . . . . . . ........................... . 39-4
. 39.4.2 Cavity Flooding Scenario Dependencies . . . . . . . . . . . . . . . . . . . . . 39-6
. 39.5 Reactor Vessel Insulation Design Concept . . . . . . . . . . . . . . . . . . . . . . . . . . 39-7 39.5.1 Description of Insulation . . . . . ..................... . . . 39-8 39.5.2 Determination of Forces on Insulation and Support System . . . . . . . 39-9 39.5.3 Conclusion . . . . . . . . . ...... .. .............. . . . . 39-12 39.6 Reactor Vessel Extemal Surface Treatment . . . . . ....... . .... . . . 39-13 39.7 Reactor Vessel Failure (Node VF) ... .. . . ...... ... .. . .. 39-13 39.7.1 Node VF Success Criteria . . ................. . . . . 39-13 39.8 S u mm ary . . . . . . . . . . . . . . . . . . ... .................... . . . . 39-14 39.9 References ........... ... ... . .... . . . . . . . . . . . . . . . . . . . . 3 9- 14 CHAPTER 40 PASSIVE CONTAINMEffr COOLING CHAPTER 41 HYDROGEN MIXING AND COMBUSTION ANALYSIS 41.1 Discussion of the Issue . . . . . . . . . . . . . ............. . . . . . . . . . . . . 41 - 1 ,
41.2 Controlling Phenomena . . . . . . . . . . . . .. ........... ........ .. 41-2 41.3 Major Assumptions and Phenomenological Uncertainties . . . . .......... . 41-3 41.3.1 Hydrogen Generation . . . . . . . . . . ................ ...... 41-3 41.3.2 Containn.ent Pressure . . . . . . . . ..................... .. 41-3 41.3.3 Flammability Limits . . . . . . . . ... . .. .... ........ 41-4 41.3.4 Detonation Limits and Loads . .. ... .. ..... ........ 41-4 41.3.5 Igniter System . . . . . . . . . . . .. ........ ............ 41-5 41.3.6 Other Ignition Sources . . . . . . . ..................... .. 41-6 41.3.7 Severe Accident Management Actions ............. ........ 41-6 41.4 MAAP4 Hydrogen Cases . . . . . . . ......... ..... ......... .. 41-6 41.4.1 Modeling Assumptions and Limitations . .............. ... . 41-6 41.4.2 MAAP4 Hydrogen Generation and Mixing Analyses . ........ 41-9 41.4.3 MAAP4 Hydrogen Burning Analyses . . . . . . . . . . . . . . . . . . . . . . 41-18 41.5 Early Hydrogen Combustion . ... ... ... ........ .... ... . 41-20 41.5.1 Hydrogen Generation Rates . ..... ....... .. ... .. . 41-20 41.5.2 Hydrogen Release Locations ......... .. .. .. .. . 41-22 41.5.3 Early Hydrogen Combustion Ignition Sources .. .. ...... . 41-23 41.6 Diffusion Flame Analysis - CET Node DF . ...... ..... . ...... . 41-24 i 41.6.1 Diffusion Flame Analysis Summary ... ...... .. ..... 41-24 41.6.2 Node DF Containment Failure Probability Assignment ..... . . 41-25 .
Revision: 9 ENEL April 11,1997 t# M - W8Stingt100S8 oiap600ganv.9$ra-toe wpf.lb XxViii
1 r~~s M
( )
v TABLE OF CONTENTS (Cont.)
Section Title Pgte 41.7 Early Hydrogen Detonation - Containment Event Tree Node DTE ........ 41-25 41.7.1 Containment Success Criteria at Node DTE . . . . . . . .......... 41-25 41.7.2 Early Hydrogen Detonation Decomposition Event Tree ........ 41-26 41.8 Sherman-Berman Methodology for Evaluating the Potential for Deflagration-to-Detonation Transition . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -2 7 41.8.1 General Description of the Sherman-Berman Methodology ....... 41-27 41.8.2 Compartment Geometry . . . . . . . . . . . . . . . . . . . . . . . . ..... 41-27 41.8.3 Mixture Reactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -28 41.8.4 Deflagration-to-Detonation Transition Probability . . . . . . . . . . . . . 41 -28 41.8.5 Application of Sher: nan-Berman Methodology to the AP600 for Deflagration-to-Detonation Transition in Time Frame 2 . ........ 41-29 41.9 Deflagration in Time Frame 3 . . . . . . . ........ ... ... . . . . . . . . 41 -30 41.9.1 Containment Success Criterion.at Node DFL . . . . . ........... 41-30 41.9.2 AICC Peak Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41-31 l 41.9.3 Conditional Containment Failure Probability from Deflagration . . . . 41-32 41.10 Detonation in Intermediate Time Frame . .. ............ . . . . . . . . . 41 -3 8 41.10.1 Containment Success Criterion at Node DTI .. . ..... . 41-38 ;
41.10.2 Mixing and Stratification . . .. ........... .. . . ..... 41-38 l 73
. . . . . 41 -3 8 (V ) 41.10.3 Quantification of DTI Failure Probabilities 41.10.4 Hydrogen Stratification Sensitivity . . . . . .
........ 41-39 l l
41.11 Safety Margin Basis Containment Performance Requirement . .......... 41-39 41.12 S u mmary . . . . . . . . . . . . . . . . . . . . ............ . . . . . . . . . . . . 41 -40 41.13 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -41 CHAITER 42 CONDITIONAL CONTAINMENT FAILURE PROBABILITY DISTRIBUTION 42.1 Introduction ... ..... .... .............. ... ...... . . . . 42-1 42.2 Probabilistic Model . . . . . . ................ ..... . . . . . . . . . . . 4 2- 1 42.3 Containment Failure Characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42-2 42.3.1 Median Values for Containment Failure .. .............. . . 42-2 42.3.2 Uncertainties in Containment Failure .... .... . . . . . . . . . . . . 4 2-3 42.4 Containment Failure Predictions . . ..............,................42-5 42.4.1 Containment Cylindrical Shell . . ........ . .. .... .. 42-5 42.4.2 Ellipsoidal Upper Head . . . . . . . . . . . . ...... .. . . . . . . . . 4 2-5 42.4.3 Equipment Hatches ..... ... .. ... .... . . . . . . . . . . . . . 4 2-6 42.4.4 Personnel Airlock . ............... .. ............. . 42-6 l 42.5 Overall Failure Distribution . . . . . . . ........... . ..... ..... .. . 42-7 42.6 Summary and Conclusions . . . . . . ........ ....... .......... .. 42-8 42.7 References . . .........................................42-8 t
[h G Ruistom 9 ENEL T Westinghouse aw- April 11,1997 xxix oAap600\pra\rt v_9\pra-toc.wpf:lb
k TABLE OF CONTENTS (Cont.)
O Section Title Page CHAPTER 43 RFIFASE FREQUENCY QUANTIFICATION 43.1 Containment Event Tree Quantification . . . . . . . . .. ................43-1 43.1.1 Containment Event Tree Base Quantification . . . . . . . . ........ 43-1 43.2 Accident Class 3BE . . ........................ . ............ 43-2 43.3 Accident Class 3BL . . . . . . . .. ......... .................. . . 43-2 43.4 Accident Class 3BR . . . . . . . . . . . . . . ..... ....... ...... . . . . . 43-3 43.5 Accident Class l A . ... . ... . ........ ........... . . . . . . . 43-3 43.6 Accident Class I AP . . . . . ....... .... .. ............. . . . . . 43-4 43.7 Accident Class 3A . . . . ...... .......... ..... . . . .... .. . 43-4 43.8 Accident Class 3C . . . . . . . ....... ... .. .... ......... ..... 43-5 43.9 Accident Class 3D ............ . .. .. . ......... ....... . 43-6 43.10 Accident Class 6 (6E+6L) . . .. ........ .. .. ...... ....... . 43-6 43.11 Accident Class I D . . . . . . . . . . . . . . . . . . . . . . . ... ... . ...... . 43-7 43.12 Large Release Frequency Importance and Sensitivities . .. . . ... ... 43-7 43.13 Containment Event Tree Conclusions and Insights . . ..... ... . . . . 43-7 CHAPTER 44 MAAP4 CODE DESCRIPTION AND AP600 MODELING 44.0 MAAP Background . . . . . . . . .. .. .......... ... ..... . 44-1 44.1 MAAP4 . . . . . .... .................. .................. 44-1 44.2 The AP600 MAAP4 Modeling ... . . .......... ....... ... 44-3 44.3 Benchmarking .............................. .. ........ 44-6 44.4 Summary and Conclusions . . . . .. ... .. ..... ... ....... 44-7 44.5 References ..... ...... .. .. ... .. . . ... ... .... .. 44-7 CHAPTER 45 FISSION-PRODUCT SOURCE TERMS 45.1 Summary of AP600 Release Categories . .. ........ ...... . . 45-1 45.2 Release Category Source Terms . . . . . . . . . . . . . . . . ... . ...... . 45-2 45.2.1 Release Category IC . . . . . . .. . .. . . . ..... .45-2 45.2.2 Release Category BP . ........ . ....... .......... 45-3 45.2.3 Release Category CI . . . .......... ........ .... .. . . 45-3 45.2.4 Release Category CFE . .. ... .............. .. . . . 45-4 45.2.5 Release Category CFI . . ...... . ..... ..... . .. .. 45-4 45.2.6 Release Category CFL . . . . . . ..... ....... ....... . .. 45-5 45.3 Direct-Release Sensitivity Case . ...... . . ............ . .. . 45-5 45.4 MAAP4 Model Parameter Sensitivities . .... ................... . 45-6 45.4.1 FPRAT Sensitivity . ..... .. .. ....... . . . . 45-6 45.4.2 FAERDC Sensitivity . . . . ..... ...... ...... ... . 45-6 45.5 Comparison with NUREG-1150 Results . . . . .. ... ... . .. ... . . 45-6 45.6 Summary . . . . . . . . . . . . . . ............. . ... . . .... ... 45-6 45.7 References .... . .. . . .... ........ .... 45-7 Revision: 9 9
April 11,1997 6 [ W85tl!1gh00S8 o:\ap600\pra\rev.9pra-toc.wpf; 1 b XXX
o TABLE OF CONTENTS (Cont.)
Section Title Page CHAPTERS 46 THROUGH 48 DELETED CHAPTER 49 OFFSITE DOSE EVALUATION 49.1 Introduction ........... ...... ...................... . . . . 49-1 49.2 Conformance with Regulatory Requirements . . . . . . . . . . . . . . . . . . . . .... 49-1 49.3 Assumptions . . . . . . . . . . .................... . .............492 49.4 Methodology . . . . . ................................. ....... 49-2 49.5 Dose Evaluation Results and Discussions . . . . . . . . . . . . . . . . . . . . . . . . . . . 49-6 49.6 Quantification of Site Risk . . ............... . . . . . . . . . . . . . . . . . 4 9-7 49.7 Risk Quantification Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49-7 49.8 References . . .......... .............. . . . . . . . . . . . . . . . . . . . 4 9- 8 CHAPTER 50 IMPORTANCE AND SENSITIVITY ANALYSIS 50.1 Introduction .. . ................ ........ ......... .. . 50-1 50.2 Imponance Analyses for Core Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 0- 1, 50.2.1 Initiating Event Importances (Case 1) . . . . . . . . . . . . . . . . . . . . . . . 50-2 50.2.2 Common Cause Failure Importances (Case 2) . . . ........ . . . . 50 3 O 50.2.3 Human Error Importances (Case 3) . . . . . . . . . . . . . . . . . . . . . . . . . 50-5 50.2.4 Component Importances (Case 4) . . . . . . . . . . . . . . . . . . . . . . . . . 50-6 50.3 System Importances for Core Damage .......................... . . 50-7 50.4 Human Error Sensitivity Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 0-9 50.4.1 Set Human Error Probabilities to 1.0 (Failure) in Core Damage Results (Case 25) . . . ................................. 50-9 50.4.2 Set Human Error Probabilities to 0.0 (Success) in Core Damage Results (Case 26) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 50-10 50.4.3 Assess Importance of Increasing Human Error Probabilities by a Factor of 10 (Case 27) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-10 50.5 Other Sensitivity Analyses for Core Damage . . . . . . . . . . . . . . . . . . . . . . 50-11 50.5.1 Diesel Generator Mission Time (Case 28) . . . . . . . . . . . . . . . . . 50- 1 1 50.5.2 Impact of Passive System Check Valves on Core Damage Frequency (Case 29 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50- 12 50.5.3 Instrumentation and Control Cutoff Probability (Case 30) . . . . . . . . 50-12 50.5.4 Containment Recirculation After Safety Injection Line Break l Event (Case 31) . . . . . . . ............. ......... . 50-12 50.5.5 Quantification Tmncation Probability (Case 32) . . . . . . . . . . . . . . . 50 13 l 50.5.6 Sensitivity to ADS Stage 4 Success Criteria (Case 33) ........ . 50 13 50.5.7 Squib Valve Failure Probability (Case 34) . . . . . . . . . . . . . . . . . . . 5 0- 13 50.5.8 Circuit Breaker Failure Probability (Case 35) . . . . . . . . . . . . . . . . . 50 14 50.5.9 End-State Importances (Case 36) . . . . . . ... .............. 50-14 v ,
1 Revision: 9
[ W85tiflgh0088 % April 11,1997 xxxi ovm4=*v 9*=#1b
TABLE OF CONTENTS (Cont.)
e Section Title Page 50.6 Sensitivity and Importance Analyses For Large Release Frequency . . ... . 50-15 50.6.1 Importance Analyses For Large Release Frequency . . ....... 50-15 50.6.2 Sensitivity Analyses For Large Release Frequency . .. .. . . 50-21 50.7 Sensitivity Analysis for Offsite Dose Risk . . . . . . . . . ... ... . 50-22 50.8 Results Summary . .... ..... . . ....... .. . . . 50-23 Attachment 50A ATWS PRA Sensitivity Case . . . . . .... ................. 50A-1 CHAPTER 51 UNCERTAINTY ANALYSIS 51.1 Introduction .. . ........ . ... ..... . .... . .... 51-1 51.2 Methodology .. . .. .... . . . ...... .... .. ..... 51-1 51.3 Summary of Results . ... . .. . .. .... .. . .. .. . 51-3 51.4 Sensitivity Studies for the Uncertainty Calculations .. .. .. .. ...... . 51-4 51.4.1 Uncertainty in the Cutoff Frequency ........ . . ... 51-4 51.4.2 Uncertainty in the Number of Cutsets Sampled . .. 51-4 51.4.3 Uncertainty in the Mean Failure Probability for Basic Events . . . 51-4 51.4.4 Sensitivity to the Random Number Input for Sampling . . . . . . . . . . . 51-5 51.5 References .. ............. . .. ..... ... . . . .... 51-6 CHAPTER 52 RTNSS - FOCUSED PRA SENSITIVITY STUDY 52.1 Focused PRA Sensitivity Study Analysis Method . . . . . . . .. .... .. 52-1 52.1.1 Core Damage Frequency Calculation .. . . . ........ 52-2 52.1.2 Release Frequency Calculation . . .. .. . . .. ... 52-5 52.2 At-Power Focused PRA Sensitivity Study . . . ...... . . . .. .. 52-5 52.2.1 At-Power Focused PRA Sensitivity Study Core Damage Frequency Quantification . ... . . .. ...... .. .. 52-6 52.2.2 At Power Focused PRA Sensitivity Study Release Frequency Quantification .. .... ........ ..... . ... 52-11 52.3 Shutdown Focused PRA Sensitivity Study . . . . . . . . ...... .. . . . . 52-16 52.3.1 Shutdown Focused PRA Sensitivity Study Core Damage Quantification . . ..... . .. . . . .. 52-16 52.3.2 Shutdown Focused PRA Sensitivity Study Release Frequency Calculation . . . . .. .. .. . . . . . . . . . 52-19 52.4 Focused PRA Sensitivity Fire Analysis . . . . . . ..... . .. .... . 52 21 52.5 Focused PRA Sensitivity Study Flooding Analysis . . ....... .. 52-21 52.5.1 At-Power Focused PRA Sensitivity Study Flooding Scenarios . . . . . 52-21 52.5.2 Shutdown Focused PRA Sensitivity Study Flooding Scenarios . . . . . 52-22 52.5.3 Focused PRA Sensitivity Study Flooding Analysis Results Summary . ... ... ...... ...... .... . . .. 52-23 52.6 Focused PRA Sensitivity Study Results and Conclusions . . . .. . ..... 52-23 52.7 References . ... .. .... . .. - - - 52*14 O
Revision: 11 March 1998 E,NEd W Westinghouse
-~ =
o:\prairev.llpa-toe.wpf;lb XXXii
TABLE OF CONTENTS (Cont.)
Section Title P,_ age CHAPTER 53 DELETED CHAPTER 54 LOW-POWER AND SHUTDOWN RISK ASSESSMENT 54.1 Introduction .... .................. ................... . . 54-1 54.2 Initiating Events .................. ................... ..... 54-1 54.2.1 Identification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. 54-2 54.2.2 Events Modeled . . . . . . . . . . . . ...................... .. 54-2 54.2.3 Shutdown Phases Summary Description . . ..... . ....... . . 54-3 54.2.4 Initiating Events for Operanng Modes . . . . . . . . . . . . . . . . . . . . . . . 54-4 54.2.5 Actuanng Signals and Systems Available ................... 54-15 54.2.6 Scenarios for Detailed Analysis . . . . . . . . . . . . . . . . . . . . . . . . . 54-16 l 54.2.7 Summary of Initiaring Events Analyzed . . . . . . . . . . . . . . . . . . . 54-21 54.3 Data . . . . ................ ........................... 54-22 54.3.1 Shutdown Frequency . . ....................... ... . 54-22 54.3.2 Mission Times . . . . . . . . . . ...... ....... .. ......... 54-25 54.4 Event Tree Development . . ...... ........................... 54-28
- 54.4.1 Event Tree LOSP-ND . . .. ........................ . 54-30 l\ 54.4.2 Event Tree RNS-ND . ........................ . . . 54-33 54.4.3 Event Tree CCW-ND . . . . . . . . . . . . .................. 54-33 54.4.4 Event Tree LOCA-PR-ND ..... .................... 54-33 54.4.5 Event Tree LOCA-V24-ND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-34 54.4.6 Event Tree RCS-OD . . . ....... .................... 54-36 54.4.7 Event Tree LOSP-D . . ............................ . 54-38 54.4.8 Event Tree RNS-D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-40 54.4.9 Event Tree CCW-D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-40 54.4.10 Event Tree LOCA-V24-D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-40 54.4.11 Boron Dilution Events (Reactivity Events) . . . . . . . . . . . . . . . . . . . 54-41 54.4.12 Boron Dilution Events Due to Chemical and Volume Control System Opecation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-45 l 54.4.13 Endstates Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-48 ,
54.5 Fault Tree Models for Shutdown and Low-Power Events . . . . . . . . . . . . . . . 54-48 l
54.5.1 Instrumentation and Control Modeling for Shutdown (Level 1) .... 54-48 l 54.5.2 Instrumentation and Control Modeling for Shutdown (Level 2) .... 54-51 54.6' Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-51 54.6.1 MAAP4 Code Analysis for Shutdown Success Criteria . . . . . . . . . . 54-52 54.6.2 MAAP4 Parameter File . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54-52 54.6.3 MAAP4 Input Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 54-54 54.6.4 Definition of MAAP4 Cases From Event Trees . . . . . . . . . . . . . . . 54-55 54.6.5 Results From MAAP4 Analyses . . . . . . . . . . . . . ........... . 54-57 54.7 Common Cause Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 54-57 A
.m.
Revision: 9 ENE 3 WSSdngh0tist :gxz:1, April 11,1997 xxxiii .wme.w p
. TABLE OF CONTENTS (Cont.)
O Section Title Page 54.8 Human Reliability Analysis ............ .......... . . . 54 57 54.8.1 Operator Actions Calculated . .... .... ......... .. .. 54-58 54.8.2 Conditiona! Human Error Probabilities . . . . . . . .. ...... . 54-64 54.9 Fault Tree Quantification ... ....... ............... .. . . 54-64 54.10 Level 1 Core Damage Frequency Quantification . ........ .... . .... 54-67 54.10.1 Core Damage Quantification Method ................. 54-68 54.10.2 Quantification Inputs ....... .. ................. .... 54-69 54.10.3 Level 1 Shutdown Core Damage Frequency Results . . . . ... .. 54-70 54.11 Shutdown and Low-Power Release Category Quantification . . . . . ... . . . 54-71 54.12 Shutdown Assessment Importance and Sensitivity Analyses . . . . . . . . . . . . . . 54-71 54.12.1 Importance Analyses for Core Damage at Shutdown . . . ... .. . 54-72 54.12.2 Other Sensitivity Analyses for Shutdown Core Damage . . . . . . . 54-77 54.13 Summary of Shutdown Level 1 Results . ... .. .. . ....... . 54-81 54.14 References . . . .-....... . .... .................... 54-87 Attachment 54A Design Change Impact on Low-Power and Shutdown Risk Assessment ... ............... ... . ..... . 54A-1 Attachment 54B Surge Line Flooding Effect on Low-Power and Shutdown Risk Assessment .... .. . .. ..... ... ....... . 54B-1 Attachment 54C Effect of Modifications to Safe / Cold Shutdown PRA .. ..... . 54C-1 CHAPTER 55 SEISMIC MARGIN ANALYSIS . . . .. ... . .... ... . 55-1 55.1 Introduction . ................. .. ... ............. .. . . 55-1 55.2 Calculation of HCLPF Values . .. .. ... . ... . ... .. . 55-2 55.2.1 Seismic Margin HCLPF Methodology .. ..... . . . . 55-2 55.2.2 Calculation of HCLPF Values .. . .... ...... . . 55-2 55.3 Seismic Margin Model . . . . . . . ...... . .. .. ... ....... . . . 55-12 55.3.1 SMA Model .?nd Assumptions . ........ . .... . . . . 55-14 55.3.2 Seismic Initiating Events . . .. .. ......... . . . . . . . 55-16 55.3.3 Initiating Event Category HCLPFs . . . . . . . . . . . . . . ..... . 55-17 55.3.4 Event Tree Models . . ... .... ..... .. ........... 55-20 55.3.5 Fault Tree Modeling and Quantification .. .... ..... . . 55-28 55.3.6 Seismic Event Core Damage Sequence Evaluation . ..... ... . 55-36 55.3.7 Containment Performance Model . .. .. .... .. .... . . 55-37 55.4 Calculation of Sequence and Plant HCLPF . ... ........ . . . . 55-38 55.4.1 HCLPFs for Basic Events . . . . . . . . . ... . ... .. ... . . 55-39 55.4.2 Calculation of Initiating Event HCLPFs .. ...... ... .. . 55-39 55.4.3 Calculation of System Fault Tree HCLPFs ..... . .... . . . . 55-39 55.4.4 Calculation of Sequence HCLPFs . .. ......... . . 55-40 55.4.5 Calculation of Plant HCLPF . ..... ............... . . 55-43 55.4.6 Large Release HCLPF . . . . .. . .... ......... . 55-43 Revision: 11 9
ENEL
' ~ ~-a W Westinghouse March 1998 o:\pra\rev.llptoc.wpf.lb XXXIV
E V
TABLE OF CONTENTS (Cont.) l l
Section Title _P, age
{
1 55.5 Sensitivity Analyses . . . . . . . . . . . . . . . . . . . . . ........ ... .. . 55-46 1 55.5.1 Robust Fuel and Core Assembly ............ ... .. 55-48 I 55.5.2 Credit for Operator Actions . ... . ......... ...... .... 55-49 55.5.3 Less Credit for Operator Actions in LOSP Event at 0.09g . . ..... 55-52 55.5.4 72-Hour Mission Time . . . . . . . . . . . . ......... . . . . 55-53 55.5.5 Containment Isolation - Smaller Size Valves . . . . . . ... . .. . 55-56 55.5.6 Steam Generator Tube Rupture Success Criteria . . . . . . . . . .. . 55-57 55.5.7 Steam Line Break Success Criteria . . . ............. . . 55-58 55.5.8 Seismic Interaction Between Turbine and Auxiliary Buildings .... 55-59 55.6 SMA Results and Insights . . . . .. ....... ........ ..... .. .. 55-63 55.9.6 AP600 SMA Results ........... .. . . ... . . ... 55-63 55.9.6 AP600 SMA Insights . . . . . . . .... .. ... .. . .. 55-68 55.7 References ... . ... . .. .......... . ... ...... .. . 55-70 I Attachment SSA System HCLPF Calculations . . . . . . . . . . .... . 55A-1 Attachment SSB Sequence HCLPF Calculations . . . ... ... ... . .. . 55B-1 l
m Attechment 55C Seismic Margin Analysis HCLPF Sensitivity Study .. ... .. 55C-1 h
CHAPTER 56 PRA INTERNAL FLOODING ANALYSIS 56.1 Introduction .............. .. .... .... ...... .... . . . . 56-1 56.1.1 Definitions . . . . . . . . . . . . . .. .. .. .. .. .. . . . . 56-1 56.2 Methodology . . . . . . . . . . . ...................... ... .. . . . 56-1 56.2.1 Summary of Methodology . . . . . . . . . . . . . . . . . . . . . . . 56-1 56.2.2 Information Collection . . . . . . . . . ........... .. . . . 56-2 56.2.3 Initial Screening Assessment . .. ..... ...... .. .. . . 56-3 56.2.4 Detailed Screening Assessment .... . ...... ...... . . 56-4 56.2.5 Identification of Flood-Induced Initiating Events . . .. . . 56-6 56.2.6 Initiating Event Frequencies ....... ... . . ... . . . . 56-7 56.3 Assumptions . . . . . . . . . . . .......... . ......... . ... . . . . . . 56-7 56.3.1 General Flooding Analysis Assumptions and Engineering Judgments . 56-7 56.3.2 AP600-Specific Assumptions . . .... .... . ....... . . . 56-9 56.4 Information Collection . . . . . . . . . ...... .. ........... .. . .. 56-11 56.4.1 PRA-Modeled Equipment and Locations . . . . . . . . .... . . 56-11 56.4.2 Identification of Areas for Flooding Evaluation . .. . . . . . 56-11 36.5 At-Power Operations . . . . . .................... . . . . . . . . . . . 56- 12 56.5.1 Initial Screening Assessment . . . .... . ..... .. ... . 56-12 56.5.2 Detailed Screening Assessment ............ ..... . . 56-12 56.5.3 Identification of Flood-Induced Initiating Events ...... . . . . 56-28 56.5.4 Calculation of Flood-Induced Initiating Event Fr.quencies . . . . 56-32 56.5.5 Quantification of At-Power Flood-Induced Events . .. .. .... 56-39 i'3 V
ENEl. Revision: 11
! T Westiflgh0USB g m 'a t March 1998 XXXV o:\pra\rev.ll\pra. toc.wpf:lb t
i _. _ . _ . . _ . . _ . _ _ _ _ _ _ . . _ . _ . _ _ _ _ _ _ _ _ _
I O
TABLE OF CONTENTS (Coat.)
Section Title .P_ age 56.6 Shutdown Operations . . . . . . . . . ..... ... .. ... .... .... .. 56-41 56.6.1 Detailed Screening Assessment ............ ........... . 56-41 56.6.2 Identification of Flood-Induced Initiating Events . ...... .. .. 56-42 56.6.3 Calculation of Flood. Induced Initiating Event Frequencies . . . . . . . . 56-43 56.6.4 Shutdown Quantification . . . . . . . ... . .... ...... . . . . 56-48 56.7 Seismically Induced Flooding . .... ..... ..... . . . . . . . . . . . . . . . 5 6-51 56.8 Flooding Hazards During Refueling Outages . . . . . . . . ...... ........ 56-52 56.9 Flooding Sensitivity Study .................... .. . .. . . . . . . . 56-52 56.9.1 Flooding Human Error Probabilities Sensitivity Study . . . . . . . . . . . 56-52 56.10 Summary of Findings . . . . . . . . ............ ................ . 56-53 CHAPTER 57 INTERNAL FIRE ANALYSIS 57.1 Introduction ..... .................... . .. ...... ... . 57-1 57.2 Qualitative Analysis Methodology ...... ... . . ... .. ..... 57-2 57.3 Quantitative Methodology of Fire Area Frequency . . . . ... ...... ..... 57-6 57.3.1 Fire Frequency Calculations .......... . ........... . 57 6 57.3.2 Fire Damage Category Quantification . . . . . . . . . . . . . . . . . . . . . . 57-7 57.4 Core Damage Quantification Methodology ..... .. .. ....... . . . . 57-10 57.5 Fire Analysis Assumptions . . . . . . . . . . . . ............ .......... 57-12 57.5.1 Qualitative Analysis Assumptions and Other Modeling Considerations . . . . . . . .. ...................... . . . . 57-12 57.5.2 Quantification Assumptions And Modeling Considerations .... . . 57-14 57.6 At-Power Qualitative Analysis Results . . . . . . . . . . . . . . . . .. ... .. . 57-17 57.7 At-Power Quantitative Results . ... ........... .. ........... 57-19 57.7.1 Fire Ignition Frequencies for Quantitative Analysis . . . . ... ... . 57-19 57.7.2 Fire Damage Category Quantification . . . . . . .. ....... .. . 57-19 57.7.3 Individual Area PRA Analysis . . . . . . . . . . . . . ....... .... . 57-19 57.8 Control Room Fire Analysis - Power Operation . . . . . . . . . . ...... .. . 57-22 57.8.1 Description of the Control Room and Associated Fire Protection . . . 57-22 57.8.2 Alternate Shutdown Capability . . . . . . . . . . . . . . ............ 57-23 57.8.3 Fire Hazard Review . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . 5 7-2 4 57.8.4 AP600 Control Room Fire Evaluation . . . . . . . .............. 57-25 l 57.8.5 Fire Scenario Identification and Frequency Detennination . . . .. 57-29 57.8.6 Control Room Fire Scenario Quantification and Results ... ... 57-32 57.9' Shutdown Fire Analysis . ..... .............. . ..... . ... 57-33 57.9.1 Fire Ignition Frequencies during Shutdown Modes of Operation . .. 57-33 )
57.9.2 Fire Damage Category Quantification . . .. ... ........... 57-34 57.9.3 Individual Area PRA Analysis . . . . . . .... .. ............ 57-34 l 57.9.4 Fire Analysis for Safe Shutdown . . . . . . . ........... .. 57-34 57.9.5 Fire Analysis for Mid-Loop Operation . . . . . . . . . . . . . . 5 7-41 O
Revision: 9 April 11,1997 chp600\pra\rev 9\pra. toc.wptib xxxyj h_ [ WSStingh00$8
RF 7-s TABLE OF CONTENTS (Cont.)
Section Title P_aage 57.10 Summary and Conclusions . .. . ..... .. ... .. . . .... . 57-42 57.10.1 At-Power Analysis ........ . ... ....... . . 57-42 57.10.2 Shutdown Fire Analysis . . . . . . . . . . . . .. .. ... . . . 57-45 57.10.3 Conclusions . . . . . ........... ............... .... 57-47 57.11 References ........... . .... .......... .... .. .. . .. 57-48 ATTACHMENT 57A DEFINITIONS . . . .......... . ............. .. 57A-1 ATTACHMENT 57B DESIGN CHANGE EFFECT ON INTERNAL FIRE ANALYSIS . 57B-1 CHAPIER 58 WINDS, FLOODS, AND OTHER EXTERNAL EVENTS 58.1 Introduction . . ... .. ...... ...... ..... ........... . 58-1 58.2 External Events Analysis .. ... ....... ....,..... .........58-1 58.2.1 Severe Winds and Tornadoes . . . . ...... .. .. . . . . . 5 8- 1 58.2.2 External Floods . . . ........ ..... ......... . ..... . 58-2 58.2.3 Transportation and Nearby Facility Accidents . ...... .. .. .. 58-2 58.3 Conclusion ... .. ...... ........... .. .. ........... 58-3 58.4 References ... . .. .... ..... .. . .. .. ..... ....... 58-3 o CHAPTEP,59 PRA RESULTS AND INSIGHTS V) 59.1 Introduction ...... ................. ................ .. .59-1 59.2 Use of PRA in the Design Process . . . . . . . . . . . . . . . ..... . . .... 59-3 59.2.1 Stage 1 - Use of PRA During the Early Design Stage . . . . . . . . . . . 59-4 59.2.2 Stage 2 - Preliminary PRA . . . . . . . . . . . .. . ... ....... . 59-5 59.2.3 Stage 3 - AP600 PRA Submittal to NRC (1992) . . . . . . ...... . 59-7 59.2.4 Stage 4 - PRA Revision 1 (1994) . . . . . . . . . ......... .. .. 59-8 59.2.5 Stage 5 - PRA Revisions 2-8 (1995-1996) . . . . . . . . . . .. ..... 59-8 59.3 Core Damage Frequency from Intemal Initiating Events at Power ... .. .. 59-10 59.3.1 Dominant Core Damage Sequences . . . . . . . . . . . ...... . 59-12 59.3.2 Component Importances for At-Power Core Damage Frequency . 59-44 59.3.3 System Importances for At-Power Core Damage . .... . . . . . . . 5 9-44 59.3.4 System Failure Probabilities for At-Power Core Damage . . . ... 59-45 59.3.5 Common Cause Failure Importances for At-Power Core Damage . 59-45 59.3.6 Human Error Importances for At-Power Core Damage . . .. . . . . 59-45 59.3.7 Accident Class Importances . ....................... .. 59-47 59.3.8 Sensitivity Analyses Summary for At-Power Core Damage . ... 59-47 59.3.9 Summary of Important Level 1 At-Power Results . . . ...... .. 59-48 59.4 Large Release Frequency for Intemal Initiating Events at Power . . . .... 59-51 59.4.1 Dominant Large Release Frequency Sequences . ... . . ... . 59-52 59.4.2 Sensitivity Analyses for Containment Response . . . . . . . . . .. . 59-72 i
}
)
t J
ENEL Revision: 11 W Westinghouse muh March 1998 XXXvii c:\pra\rev llipra-toc wpf;1b
z l
! TABLE OF CONTENTS (Cont.)
e l
Section Title Eage i
i 59.4.3 Comparison of Initiating Event Importances for Core Damage Fmquency and Large Release Frequency . . . . . . . . . .... .. . 59-72 59.4.4 Summary of Imponant Level 2 At-Power Results . . . . . . . . . . 5 9-73 59.5 Core Damage and Severe Release Frequency from Events at Shutdown . .. . .... .... .......... ..... . .. . . 59-75 59.5.1 Summary of Shutdown Level 1 Results . . . .. . ....... .. 59-75 59.5.2 Large Release Frequency for Shutdown and Low-Power Events . ......... .. ... ..... .. ... .... . . . 59-81 59.5.3 Shutdown Results Summary . . . . . . . ... . .. . . . . . . . . 5 9-82 59.6 Results from Intemal Flooding, Internal Fire, and Seismic Margin Analyses . . . . . . ...... ..... .. ........ . . . . . . . . . 5 9-82 59.6.1 Results of Internal Flooding Assessment . . . . . . . . .. . . . 59-82 59.6.2 Results ofIntemal Fire Assessment .... ... .. . .. . 59-83 59.6.3 Results of Seismic Margin Analysis . . . . ..... . . . . . . . 5 9-87 59.7 Plant Dose Risk from Release of Fission Products . . .. ..... .. .... 59-87 59.8 Overall Plant Risk Results . . . . ... . ..... ... . .. .. . 59-88 59.9 Plant Features Imponant to Reducing Risk . . . . . . . . . . . .. ... 59-89 59.9.1 Reactor Design ... .. . .. ..... ..... . . . . . . 59-90 59.9.2 Systems Design .. . . . . ..... ... . .. ...... 59-91 59.9.3 Instrumentation and Control Design . . . . . .. .. .. 59-94 59.9.4 Plant Layout . . ....... ... .... ... ... . .. . . . 59-95 59.9 5 Plant Structures . . . .... . ....... . . .. .. . ... 59-96 59.9.6 Containment Design . . . . .. ...... ......... .. 59-96 59.10 PRA Input to the Design Certification Process . . . . . ...... .. . ... .59-101 59.10.1 FRA Input to Reliability Assurance Program . . . . . . . . . . . . . . . 59 102 59.10.2 PRA Input to Certified Design Material .. . .. ...... . . . .59-102 59.10.3 PRA Input to the Technical Specifications . . . . .... . . . . . .59-102 59.10.4 PRA Input to MMI/ Human Factors / Emergency Response Guidelines . . . . .... ... ........... .. . . . . . . .59-102 59.10.5 Summary of PRA-Based Insights . . . . . . . . . . . . .. .59-103 59.10.6 Combined License Information ...... .. .. .. ... ...59-103 APPENDIX A MAAP4 ANALYSIS TO SUPPORT SUCCESS CRITERIA . . . ..... . . A-1 APPENDIX B EX-VESSEL SEVERE ACCIDENT PHENOMENA .. . .. . . . . . . . . . . B- 1 APPENDIX C DESIGN CHANGES THAT OCCURRED AFTER THE PRA ANALYSES WERE COMPLETED . ...... . ....... .. ... .. ..... C-1 APPENDIX D EQUIPMENT SURVIVABILITY ASSESSMENT . . . . ... . .. . . . . . D- 1 9
Revision: 11 ENEL March 1998 'r.'xh.
, W65tiflgh09Se o:WVev thpra. toc.wpf.lb XXXViii
b LIST OF TABLES Table No. Title Eage 2-1 Intemal Initiating Event Grouping - Plant Systems and Equipment Available for Transient / Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . . 2-31 2-2 NUREG/CR-3862 Initiator Categories . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-48 2-3 NUREG/CR-3862 Initiator Categories Not Considered in the AP600 PRA Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-52 2-4 AP600 Intemal Initiating Event Frequencies .........................2-53 2-5 Initiating Event Frequencies Used in Event Tree Quantification . . . . . . . . . . . . 2-56 2A.1-1 Summary of Primary System Piping Data . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-1 2A.1-2 Summary of Primary System Pipe Break Frequency Quantification and Frequency Apportionments . . . . . . . . . . . . . .......... 2A-4 2A.1-3 Attribution of Line Break Frequencies to Specific LOCA Initiating Event Categories . . . . . . . . . . .............. . . . . . . . . . . . . . . . . . 2A- 5 2A.2-1 RCS Leakage Events . . . . . . . . . . . ................. ........... 2A-7 2A.3-1 Summary of Steam Generator Tube Rupture Events . . . . . . . . . . . . . . . . . . . 2A-18 2A.4-1 Identification of the Situations Potentially Leading to LOCA and Interfacing LOCA on RNS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2A-20
,m 2A.4-2 Screening Quantification of LOCA and Interfacing LOCA Frequencies (v ) on Normal RHR System . . . . . . . . . . . . . . .......... ............ 2A-23 2A.4-3 Summary of Screening Quantification of LOCA and Interfacing LOCA Frequencies on RNS . . . . . . . ............... .......... ...... 2A-28 2A.51 Spurious Stuck-open Pressurizer Safety Valve .................. .. 2A-29 2A.5-2 Interface Break on Accumulator Lines . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-30 2A.5-3 Interface Break on IRWST Injection Lines . . . . . . . . . . . . . . . . . . . . . . . . . 2A-32 2A.6-1 Summary of Main Steam Line and Feedwater Line Piping Data for Secondary-side Break Frequency Quantification . . . . . . . . . . . . . . . . ... 2A-35 2A.6-2 Secondary-side Line Break Frequency Quantification . . . . . . . . . . . . . . . . . . 2A-36 2A.6-3 Stuck-open Main Steam Line Safety Valve Frequency Quantification . . . . . . . 2A-37 2A.71 Initiating Events Review Data Summary . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-40 3-1 Loss of CCS/SWS Initiating Event Fault Tree CSWF Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... 3-9 3-2 Spurious Actuation of Automatic Depressur zation Failure Criteria Summary . . . 3-10 3-3 Evaluation of Spurious Automatic Depressurization System Frequencies . . . . . 3-11 4-1 Summary of Systems Associated with Mitigating Functions for AP600 . . . . . . 4-115 4-2 Summary List of Event Tree Top Events ..........................4-116 4-3 Summary of Core Damage Categories . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 19 i i V
Revision: 9 .
3 W8Stingh00S8 % April 11,1997 l XXXIX o Aap600Npra\rev ,9)pra-lot.wpf. l b l
i
" =5 T
, LIST OF TABLES (Cont.)
O Table NL Title P_ age 5-1 AP600 Safety-Related Plant Support Systems with Letter Designators . . . . . . . . . 5-3 5-2 AP600 Nonsafety-Related Plant Support Systems with Letter Designators . . . . . . 5-3 5-3 AP600 Support System Interdependency Matrix . . . . . ..... ........... 5-4 5-4 AP600 Safety-Related Front-Line Plant System Letter Designators . . . . . . . . . . 5-17 5-5 AP600 Nonsafety-Related Front-Line Plant System Letter Designators . . . ... 5-17 5-6 AP600 Front-Line System Dependency Matrix . . . . . . . . . . . . ...........5-18 6-1 Summary of Event Tree Top Events Success Criteria . . . . ........ ... . 6-102 6-2 Summary of Success Criteria for the Mitigating Systems . . . . ... . . . . . . . 6-130 6-3 Summary of Success Criteria for Operator Actions and Mission Times . . . . . 6-144 6-4 Deleted 7-1 Example for Fault Tree XXX Success Criteria Summary . . . . . . .. .. . . 7-16 7-2 Example for System Dependency Matrix . . . ........ .. ... .. . . 7-16 7-3 Example for Component Test Assumptions . . . . ............... .. 7-17 7-4 Example for Component Maintenance Assumptions . . . . . . . . . . ... . . . . . 7-17 7-5 Example for Operator Actions and Disposition Analysis Summary . . ... . . 7-17 7-6 Fault Tree Identification Codes ... ....... ................ . . . . . 7-18 7-7 System Identification Codes for Basic Events ... .... . .. ..... .. 7-21 7-8 Component Identification Codes .. . ... .. ................... . 7-24 7-9 Failure Mode Identification Codes . . . ............... .... ....... 7-31 8-1 List of System Fault Trees ............. .. ......... .... ..... 8-8 8-2a Fault Tree PRT Success Criteria Summary . . . .............. . .... 8-9 8-2b Fault Tree PRL Success Criteria Summary . . .............. . . ... 8-10 8-2c Fault Tree PRP Success Criteria Summary .. .. ..... . . . . . . . . . 8- 1 1 8-2d Fault Tree PRS Success Criteria Summary ........... .. .... . . . . . . 8- 12 8-2e Fault Tree PRW Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . 8 - 13 8-2f Fault Tree PRI Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . . 8- 14 1 8-2g Fault Tree PRTA Success Criteria Summary .. .... ... .. ... . . . 8-15 l 8-3 Notes Related to System Fault Tree Assumptions . . . . . . . . . . . . . . . . . . . 8- 16 l
8-4 System Dependency Matrix . . . . . ....... . .... ..... . . . . . 8-17 '
8-5 Component Test Assumptions . . . . . . . . . . . .......... . ... .. . . 8-18 8-6 Component Maintenance Assumptions . . . . . . . . . ......... . . . . . 8-18 8-7 Operator Actions and Disposition Analysis Summary .. . .. .. 8-19 8-8 Common Cause Failure Analysis Summary . . . ............. . ... . . 8-19 f 8-9 Fault Tree Basic Events for Passive Residual Heat Removal System . . . ..... 8-20 l 1
(
!l l
l Revision: 9 O
ENEL 3 Westiflgh00Se April 11,1997 sh {
o:\ap600prairev.,9%pra-lot.wpf. l b x) l 4
I
O U LIST OF TABLES (Cont.)
Table No. Title P_ age 9-1 List of System Fault Trees .. .. ........ ..................... 9-9 9-2a Fault Tree CM2AB Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 9-10 9-2b Fault Tree CM2SL Success Criteria Summary . ................. . . . 9-11 9-2c Fault Tree CM2L Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 9-12 9-2d Fault Tree CM2P Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 9-13 9-2e Fault Tree CM1 A Success Criteria Summary . . . . . . . ............... . 9-14 l 9-2f Fault Tree CM2LLT Success Criteria Summary . . . . ... ... . . . . . . . . . . 9- 15
{
9-2g Fault Tree CMBOTH Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 9-16 i 9-2h Fault Tree CM2LA Success Criteria Summary . . ............. . ..... 9-17 9-2i Fault Tree CM2NL Success Criteria Summary . . . . . . . . . . ........ .. . 9-18 9-3 Notes Related to System Fault Tree Assumptions . . ............. . .. . 9-19 9-4 System Dependency Matrix . . . . . . . 9-19
)
9-5 Component Test Assumptions . . .......... . . . . . . . . . . . . . . . . . . . . . 9-2 0 l 9-6 Component Maintenance Assumptions . . . . . ...... .... ....... .. 9-20 i 9-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . ...... 9-21 9-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . ...... ... 9-21 9-9 Fault Tree Basic Events for Core Makeup Tank Subsystem ........ ..... 9-22
/m List of System Fault Trees . . 10-6 V) 10-1 10-2a Fault Tree AC2AB Success Criteria Summary
.......................10-7 10-2b Fault Tree ACI A Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 10-8 10-2c Fault Tree ACBOTH Success Criteria Summary ............. .. . . 10-9 10-3 Notes Related to System Fault Tree Assumptions . . . .... ......... . . 10-10 10-4 System Dependency Matrix . . . ...... ......... ......... . . . . 10-10 10-5 Component Test Assumptions . . . . . . . ............. . . . . . . . . . . . . 10- 10 104$ Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . 10-11 10-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . 10- 1 1 10-8 Common Cause Failure Analysis Summary . . . . . . . . . . . .......... . 10-11 10-9 Fault Tree Basic Events for Accumulator Subsystem .. ............ . 10-12 Il-la List of System Fault Trees . . . . . . . . . . . . . . ..... ......... . .. .11-9 11-1b List of System Fault Trees (For Plant Damage States Analysis) . . ... ................ . . . 11-10 11-2a Automatic Depressurization System Success Criteria Versus Accident Conditions Full Depressurization . . . . .... ... .. . . . . I1-11 11-2b Automatic Depressurization System Success Criteria Versus Accident Conditions Partial Depressurization ............................. . 11-12 11-2c Automatic Depressurization System Fault Tree Summary (For Plant Damage States Analysis) . .... .................... .. 11-13 11-2d Fault Tree ADA Success Criteria .... ... ...... ............. . 11-13 11-2e Fault Tree ADT Success Criteria . . . . . .... . .. .. . ....... .. . 11-14 m
Revision: 9
[ Westinghouse ENEL mh% April 11,1997 xlj o$ap600pra\rev_9\pra-lot.wpf.lb E-------_______________________._______-- - - - _ _ _ _ _ _ _
M LIST OF TABLES (Cont.)
e Table No. Title Eage 11-2f Fault Tree ADI A Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . ..... 11-14 Il-2g Fault Tree ADI Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-15 11-2h Fault Tree ADS Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-16 11-2i Fault Tree ADU Success Criteda . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . 11-17 11-2j Fault Tree ADV Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-18 11-2k Fault Tree ADZ Success Criteria . . . . . .................. ... ... 11-18 1 2-21 Fault Tree ADM Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-19 11-2m Fault Tree ADQ Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-19 11-2n Fault Tree ADAL Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-20 11-20 Fault Tree ADL Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-21 11-2p Fault Tree ADRA Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-21 11-2q Fault Tree ADR Success Criteria . . . . . . . . . . ..................... 11-22 11-2r Fault Tree ADAB Success Criteria ...... .......... ......... . 11-23 11-2s Fault Tree ADB Success Criteria . .............................. 11-23 11-2t Fault Tree ADW Success Criteria . . . . . . . . ......... . . . . . . . . . . . . . 1 1 24 11-2u Fault Tree ADUM Success Criteria . . . . . . . . . . ...... ........... Il-24 11-2v Fault Tree ADF Success Criteria . . ................... .......... Il-25 11-2w Fau!r Tree ADMA Success Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1-25 11-2x Fault Tree ADTLT Data Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-26 11-2y Fault Tree ADQLT Success Criteria . . . . . . . . . . . . . . . . . . ........... 11-26 11-3 Notes Related to System Fault Tree Assumptions . . . . . . . . . . . . . . . . . . . . . 11-27 11-4 System Dependency Matrix . . . . . . ................. ...... .... 11-28 11-5 Component Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 11-29 11-6 Component Mainten .nce Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-29 11-7 Operator Actions and Disposition Analysis Summary . . .......... . . . . 11-30 11-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . 11-31 11-9 Fault Tree Basic Events for Automatic Depressurization System . . . . . . . . . . 1 1 -3 2 12-1 List of System Fault Trees . ,, . . . . . .............. . ... . . . . . . 12-11 12-2a Fault Tree IW2AB Success Criteria Summary ......................12-12 12-2b Fault Tree IW2ABM Success Criteria Summary ............. . . . . . . 12-13 12-2c Fault Tree IW2ABA Success Criteria Summary .. .... .. . . . . 12-14 12-2d Fault Tree IW2ABP Success Criteria Summary .....................12-15 12-2e Fault Tree IW2 BPM Success Criteria Summary ......... . . . . . . . . . . . 12- 16 12-2f Fault Tree IW2ABB Success Criteria Summary ............. ... . . . 12-17 12-2g Fault Tree IW2ABBM Success Criteria Summary ........ ...... . . . . 12-18 12-2h Fault Tree IW1 A Success Criteria Summary ............... . . . . . . . 12-19 12-2i Fault Tree IW1AM Success Criteria Summary ............. . . . . . . . . 12-20 12-2j Fault Tree IWF Success Criteria Sumt.tary . . . . . . . . . . . . . . . . . . ...... 12-21 12-2k Fault Tree RECIRC Success Criteria Summary . . . . . . . . . . . . . . . . ..... 12-22 e
Apn ,1997 W85tingh00S8 cAs,400$rairev 9spra-lotwpf:Ib xlji
1
=-
si ~.
l O
V LIST OF TABLES (Cont.) f Table No. Title Page 1 2-21 Fault Tree RECIRP Success Criteria Summary ...................... 12-23 12-2m Fault Tree RECIRB Success Critena Summary .... ................ 12-24 12-2n Fault Tree RECIRA Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 12-25 12-2o Fault Tree RECIRAP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . 12-26 12-3 Notes Related to System Fault Tree Assumptions .................... 12-27 12-4 System Dependency Matnx . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12-27 j 12-5 Component Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12-28 12-6 Component Maintenance Assumptions . . . . . . . . . . . . . . .......... .. 12-29 12-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 12-29 12-8 Common Cause Failure Analysis Summary . . . ................... . 12-30 12-9 Fault Tree Basic Events for IRWST Subsystem . . . . . . . . . . . . . . . ...... 12-31 13-1 List of Sy stem Fault Trees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 13-8 13-2 Fault Tree PCT Success Criteria Summary . . . . . . . ............... .. 13-8 ,
13-3 Notes Related to System Fault Tree Assumptions ..................... 13-8 l 13-4 System Dependency Matrix . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13-9 )
13-5 Component Test Assumptions . . ............................. .. 13-9 f3 13-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13-10 13-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 13-10 13-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . 13-10 13-9 Fault Tree Basic Events for Passive Containment Cooling System . . . . . . . . . 13-11 14-1 List of System Fault Trees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-9 14-2a Fault Tree FWT Success Criteria Summary ................. . . . . . . 14-10 14-2b Fault Tree FWF Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . 14-11 14 2c Fault Trie SFWT Success Criteria Summar; . . . . . . . . . . . . . . . . . . . . . . . . 14-12 14-2d Fault Tree SFW Success Criteria Summary . . . . . .... .. ......... . 14-13 14-2e Fault Tree SFW1 Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 14-14 14-2f Fault Tree SFWP Success Criteria Summary . . . . . ....... . . . . . . . . . . 14- 15 14-2g Fault Tree SFWM Success Criteria Summary .. ...... ..... ... . . . 14-16
, 14-2h Fault Tree SFWA Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . 14-17 14-2i Fault Tree COND Success Criteria Summary . . . . . . . . . . . . ............ 14-18 l 14-2j Fault Tree CONDI Success Criteria Summary . . ............... . . . . 14-19 14-2k Fault Tree CDS Success Criteria Summary . . . . . . . . . . . . . . . . . . . ... . 14-20 1 4-21 Fault Tree TCCW Success Criteria Summary . . . . . . . . . . . . . ... .... . 14-21 14-3 Notes Related to System Fault Tree Assumptions . . ............ . . . . . 14-22 l 14-4 System Dependency Matrix . . . . . . . . . . . . . . . . . . . . . . . . . .... . ... 14-23 l 14-5 Component Test Assumptions . . . . . . . . . . . , . . . . . . . . . ............. 14-31 l 14-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . 14- 3 2 14-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . 14-32 1
Revision: 9 W Westingholise $Eh April 11,1997 xliii OM PM P*ev.9Wlampf:lb I
l
E=5 l O
LIST OF TABLES (Cont.)
Table No, Title Pag _e 14-8 Common Cause Failure Analysis Summary . . . . . . . . . . .... ......... 14-33 14-9 Fault Tree Basic Events for Main and Startup Feedwater System . . . . . . . . . . 14-34 15-1 List of System Fault Trees . . . . . . . . . . . . . . . . . . . ... . ........ .. 15-9 15-2a Fault Tree CSBORI Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . 15-10 15-2b Fault Tree CVS1 Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . 15-11 15-2c Fault Tree CSAX Success Criteria Summary . . . . . . . . . . . . . .... . . . . . 15-12 15-2d Fault Tree SGHL Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 15- 13 15-2e Fault Tree CSP Success Criteria Summary ......... . . . . . . . . . . . . . . . 15- 14 15-3 Notes Related to System Fault Tree Assumptions . . ...... ....... ... 15-15 15-4 System Dependency Matrix . . . ............. ......... . . . . . . -. 15-16 15-5 Component Test Assumptions .......... .. ....... . . . . . . . . 15-17 15-6 Component Maintenance Assumptions . .........................15-18 15-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 15-19 15-8 Common Cause Failure Analysis Summary . . . . . . . . .............. . 15-20 15-9 Fault Tree Basic Events for Chemict.1 and Volume Control System . . . . . . . 15 21 16-1 List of System Fault Trees . . . ....... ........... .... . . . . . . . 16-5 16-2 Fault Tree VLH Success Criteria Summary . . . . . . ............. . . . . . 16-5 16-3 Notes Related to System Fault Tree Assumptions . . . .................. 16-5 16-4 System Dependency Matrix . . . . . . .................... . . . . . . . . . 16-6 16-5 Component Test Assumptions . . . . . . . ........... . . . . . . . . . 16-6 16-6 Componem Maintenance Assumptions ...... . . . . . . . . . . . . . . . . . . . . . 1 6-6 16-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 16-7 16-8 Common Cause Failure Analysis Summny . . . . . . . . . . . . . .. . . . . ... . 16-7 16-9 Fault Tree Basic Events for Containment Hydrogen Control System . . . . . . . . . 16-8 17-1 List of System Fault Trees . ...... .......... .. ............ . 17-8 17-2a Fault Tree RNR Success Criterin Summary . . . . . . . . ........... ..... 17-9 17-2b Fault Tree RNP Success Criteria Summary . . . . . . . . .......... . ..... 17-9 17-3 Notes Related to System Fault Tree Assumptions . . . ....... . . . . . . . 17-10 17-4 System Dependencies Matrix . . . . . ....... ........... . . . . . . . 17-11 17-5 Component Test Assumptions . . . . ......... ..... .. . . . . . . 17-12 17-6 Component Maintenance Assumptions . ......... ... . . . . . . . . 17-12 17-7 Operator Actions and Disposition Analysis Summary . .. ....... ... . 17-13 17-8 Common Cause Failure Summary ... .. ........... ... . . .. . 17-13 17-9 Fault Tree Basic Events for Normal Residual Heat Removal System . . . . .. . 17-14 !
Revision: 9 O
April 11,1997 _ WeStiligh00Se o:\ap600Nprairev,,9\pra-lot.wpf.lb xliv l.
__--. __ __-- , . _ _ _ . _ _ _ m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
(n V)
LIST OF TABLES (Cont.)
Table No. Title Page 18-1 List of System Fault Trees ........... . .................... .. 18-6 18-2a Fault Tree CCN Success Criterie Summary . . . . . . . . . . . . . . . . . . . . . . . . . . 18-6 18-2b Fault Tree CCT Success Criteria Summary ........ ................. I8-7 18 2c Fault Tree CCP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . I8-7 j 18-3 Notes Related to System Fault Tree Assumptions . . . . . . . . . . ....... .. .18-8 18-4 System Dependency Matrix . . . . . . . . . . . . . ........................I8-8 18-5 Component Test Assumptions . . . . . . . . . . . . . . . ...............I8-9 )
18-6 Component Maintenance Assumptions . . . . . . . . . . ...... ......... ..I8-9 i 18-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . . I8-10 18-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . I 8- 10 18-9 Fault Tree Basic Events for Component Cooling Water System . . . . . . . . . . . 18-11 19-1 List of System Fault Trees ..................................... 19-6 19-2a Fault Tree SWN Success Criteria Summary . . .. ....... .......... 19-6 1 19-2b Fault Tree SWT Success Criteria Summary . . . ......................19-7 l 19-2c Fault Tree SWP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . ... 19-7 I 19-3 Notes Related to System Fault Tree Assumptions .. .......... .... .19-8 19-4 System Dependency Matrix . . . . . . . . . . . . . . . . . . . . . .......... ... 19-9 19-5 Component Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. 19-10 (S'} 19-6 Component Maintenance Assumptions . . . . . . . , , . . . . . . . . . . . . . . . . . . . 19-10 19-7 Operator Actions and Disposition Analysis Summary ................. 19-11 19-8 Common Cause Failure Analysis Summary . . ...................... 19-11 19-9 Fault Tree Basic Events for Service Water System . . . . . . . . . . . . . . . . . . . 19-12 20-1 List of System Fault Trees ...... .............. ............... 20-6 20-2 Fault Tree VWH Success Criteria Summary .... ........ ..... . . 20-6 20-3 Notes Rels.ted to System Fault Tree Assumptions ....... ... ....... .20-6 20-4 System Dependency Matrix . .. ........................... . . 20-7 20-5 Component Test Assumptions . . . . . . . . . . . ........ .. .. ....... . 20-8 20-6 Component Maintenance Assumptions .. .......... .......... .. . 20-8 20-7 Operator Actions and Disposition Analysis Summary . . . . . . . . ........ . 20-9 20-8 Common Cause Failure Anslysis Summary ......... ...... ........ 20-9 20-9 Fault Tree Basic Events for Central Chilled Water System ....... . . . . 20-10 21-1 List of System Fault Trees . . . ........ .... ...... ...... . 21-10 21-2 Fault Tree Success Criteria Summary . . . . ................... . .. 21-13 l
21-3 Nou:s Related to System Fault Tree Assumptions ................ . . . 21-29 l 21-4 System Dependency Matrix . . . . . . . . . . . . . . . . ................... 21-32 21-5 Component Test Assumptions . ......... ............... ... . 21-32 o\
(d Revision: 9 l T Westinghouse fh_ xlv c:\ap600\pra\rev.9\pra-ktwpf.lb April 11,1997
=
C EE 1
LIST OF TABLES (Cont.)
O Title Ea.ge Table No.
Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . ......
. 21-33 21-6 21-7 Operator Actions and Disposition Analysis Summary . . . .............. 21-33 Common Cause Failure Analysis Summary ....... ..... . ........ 21-33 21-8 Fault Tree Basic Events for AC Power System ..... .... ........... 21-34 21-9 List of System Fault Trees ...... .... ............ ............ 22-6 22-1 22-2 Fault Tree Success Criteria Summary . ........ ...... ...... . . . . 22-10 22-3 Notes Related to System Fault Tree Assumptions . . . . . . .............. 22-26 22-4 Systems Dependercy Matrix . . . . . . . . . . . . . . . . . . ..... ....... .. 22-26 22-5 Component Test Assumptions . . . ................ .... ....... 22-27 Component Maintenance Assumptions . . . . . . . . ..... ....... ..... 22-27 22-6 Operator Actions and Disposition Analysis Summary . . . ... ... ..... 22-27 22-7 Common Cause Faibre Analysis Summary ... ............. . ... 22-28 22-8 22-9 Fault Tree Basic Events for Class IE de and Uninterruptible Power Supply System .............. ................ ............ 22-29 22-10 System Power Requirements / Dependencies . ............ . . . . . . . . . 22-41 23-1 List of System Fault Trees . . . . . ... .. ...... . ............... 23-6 _
23-2 Fault Tree Success Criteria Summary . . . . . . . . . . . . . . . . . ... .. .... . 23-9 23-3 Notes Related to System Fault Tree Assumptions . . . . . . . . . . . . . . . . . . . . 23-20 23-4 System Dependency Matrix . . . . ....... . ................ .... 23-20 23-5 Component Test Assumptions . . . . . . .................... ...... 23-21 23-6 Component Maintenance Assumptions . . . . . . . . ... .............. 23-21 23-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 23-21 23-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . .. .... 23-22 23-9 Fault Tree Basic Events for Non-Class 1E de and UPS System . . .... ... 23-23 24-1 AP600 Containment Penetration List ......... .. ....... .. ..... 24-7 24-2 Screening Analysis Evaluation . . . . . . . . . . . . .... .... .... . .. . 24-16 24-3 Containment Penetrations Not Screened Out for Normal Operation at Power Analysis . . . . . . . . . . . . . . . . . . .......... ........... 24-22 24-4 List of System Fault Trees ...... .... ..... . .. ..... ...... . 24-22 24-5a Fanit Tree CIC Success Criteria Summay ...... . ........... .. . 24-23 24-5b Fault Tree CIA Success Criteria Summary . . . .... ........... ..... 24-23 24-Sc Fault Tree CIB Success Criteria Summary . . . . .......... .......... 24-24 24-6 Notes Related to System Fault Trees Assumptions . . . . ..... ....... 24-24 24-7 System Dependency Matrix . . . . . . ................. ..... .. . 24-25 {
.... 24-28 j 24-8 Component Test Assumptions . . . . . . .. ...... ...... .. ..
24-9 Component Maintenance Assumptions . . . .. ... ............. .. 24-28 Revision: 9 O.l April 11,1997 c:\ap600pu\rev.9\pra-lot.wpf.lb xlvi h_ T Westinghouse l
(
)
t
'O LIST OF TABLES (Cont.)
Table No. Title P. age 24-10 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . . . . . . . . 24 29 24-11 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . 24-29 24-12 Fault Tree Basic Events for Containment Isolation System . . . . . . . . . . . . . . 24-30 25-1 List of System Fault Trees ................. ................... 25-9 25-2a Fault Tree CAIAIR Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 25 - 10 25-2b Fault Tree CAIR Success Criteria Summary .......... . . . . . . . . . . . . . 25- 10 25-2c Fault Tree CAIAIRP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 25-11 25-2d Fault Tree ENDCAIAI Success Criteria Summary . . . . . . . . . . . . . . . . . . . . 25-11 25-2e Fault Tree ENDCAIAP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . 2512 25-2f Fault Tree CASF Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . 25-13 25-3 Notes Related to System Fault Tree Assumptions . . . . . . . . . . . . . . . . . . . . . 25-13 25-4 System Dependency Matrix . . . . . . . . . . . ........ . . . . . . . . . . . . . . . 25 - 14 25-5 Component Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25-14 25-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25-15 25-7 Operator Actions and Disposition Analysis Summary . . . . . . . . . . . .. .. 25-15 25-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . 25-15 l
25-9 Fault Tree Basic Events for Instrument Air Subsystem . . . . . . . . . . . . . . . . . 25-16 26-1 List of System Fault Trees . . . . . . ..............................26-28 26-2a Fault Tree RTPMS and RTPMS1 Success Criteria Summary . . . . . . . . . . . . . 26-29 l 26-2b Fault Tree RTSTP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 26-29 26-2c Fault Tree RCL Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . 26-30 26-2d.1 Fault Tree RCT Success Criteria Summary . . . . . . . . . . . ... . . . . . . . . . 26-30 26-2d.2 Fault Tree RCN Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . 26-31 26-2e I&C Subtree Success Criteria Summary .......... . .............. 26-32 26-3a PMS I&C Subtree Constmetions . . . . . . . . . . . . . . . . . . . . . . . . . . . ...26-130 26-3b Representative PMS I&C Subtree Plot Listing . . . . . . . . . . . . . . . . . . . . .26-149 26-4 PMS Dependency Matrix . . ................... ........ . . . .26-163 26-5 PMS Components Test Assumptions ....................... ... 26 166 26-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . .26-166 26-7 Failure Probabilities Calculated in this Section . . . ........ ..... ...26-167 26-8 Operator Actions and System Disposition Analysis Summary . . . . . . . ...26-172 l 26-9 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . .....26-175
!26-10a Fault Tree Basic Events for Reactor Trip System . . . . . . . . ....... ..26-177 26-10b Fault Tree Basic Events for the I&C Subsystem . . . . . . . . . . . . . . . . . . . . .26-181 26-11 Assumed List of I&C Instrumentation . . . . . . . . . . . . . . . . . . . . . . . ... .26-230 l
27 1 List of System Fault Trees . . . . . . . . . . . . ..... . . . . . . . . . . . . . . . . . . 2 7-9 27-2a Fault Tree DAS Success Criteria Summary . . . . . . . . . . . . . . . . ......... 27-9 27-2b Fault Tree DASI Success Criteria Summary . . . . ... ........... .... 27-9 C
Revision: 9 ENEL T Westinghouse cah. April 11,1997 xlvii oVW*n_%I1*P :Ib f
=
M.
LIST OF TABLES (Cont.)
O 1 Table No. Title Page 27-3 Notes Related to System Fault Tree Assumptions .............. . . . . . 27-10 27-4 System Dependency Matrix . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27-10 27-5 Component Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 27-10 27-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . 27-10 27-7 Operator Actions and System Disposition Analysis Summary . . . . . . . . . . . 27-10 27-8 Common Cause Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . 27-11 27-9 Fault Tree Basic Events for Diverse Actuation System . . . . . . . . . . . . . . . . . 27-12 28-1 List of System Fault Trees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-23 28-2 Fault Tree Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-24 28-3a PLS 1&C Subtree Constructions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-46 28-3b Representative PLS 1&C Subtree Plot Listing . . . . . . . . . . . . . . . . . . . . . . . 28-55 28-4 PLS Dependency Matrix . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-66 28-5 PLS Components Test Assumptions . . . . . . . . . . . . . . . . . . . . . . . ...... 28-68 28-6 Component Maintenance Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . 28-69 28-7 Failure Probabilities Calculated in this Section . . . . . . . . . . . . . . . . . . . . . . 28-70 28-8 Operator Actions and System Disposition Analysis Summary . . . . . . . . . . . . 28-73 28-9 Common Cau:e Failure Analysis Summary . . . . . . . . . . . . . . . . . . . . . . . . . 28-75 28-10 Fault Tree Basic Events for 1&C Subsystem . . . . . . . . . . . . . . . . . . . . . . . 2 8 -77 28-11 Assumed List of 1&C Instrumentation . ..........................28-136 28-12 Assignments of Plant Systems to Control Logic Cabinets ............ .28-139 28-13 Assignments of Plant Systems to the Control Gruup Cabinets . . . . . . . . . . .28-140 29-1 Electrical Components with Low Common Cause Failure Rate . . . . . . . . . . . 29-16 25 '. Common Cause Failure Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29- 17 30-1 AP600 Human Error Probability Summary Results . . . . . . . . . . . . . . . . . . . 30-79 30-2 Manual DAS Actuation .................................... . 30-95 30-3 Dependency Level Evaluation Summary . . ... .... .. ........ . . . 30-97 30-4 Dependency Level Evaluation .. ......... ............. . ...30-111 30-5 List of Acronyms . . . . . . . . . . . . . . . . . . . ........ ... . . . . . . . .30-114 31-1 Summary of Event Tree Scalar Probabilities . . . . . . . . .... .......... 31-15 31-2 UET Versus Cumulative Fraction of Transients in the UET Period (Transient Time) ..... ........... ... .......... .. ..... . 31-17 32-1 Generic Data B ase . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32-5 32-2 Test and Maintenance Outal,e Generic Data . ......... .. . . . . . . . . . 32-21 32-3 Test and Maintenance Unavailabilities Used in AP600 Core Damage Quantification . . . . . . . . . . . . .................... 32-22 Revision: 9 April 11,1997 % [ Westiligh0USB o$ap600hpra\rev 9\pra-lotspf;1b xlyjij
1 l
l LIST OF TABLES (Cont.)
i Table No. Title Eage 32-4 Common Cause Factors . . . . . . . . . . . . . . . . ........ ........ . . 32-23 32 5 Master Data Bank (SIMON.OUT File) . . . . . .. . ... ...... . 32-29 33 1 Summary of AP600 System Fault Tree Failure Probabilities . . . . . . . ... .. 33 7 33-2 Example Accident Sequence Definitions for Large LOCA . . . . . . . . . . . . . . 3 3 19 33-3 List of Dominant Cutsets (At Power) . . . . . . ......... ....... . . . . 33-20 33 4 List of Dominant Sequences (At Power) . . . . . . . . .... ....... . . 33-29 33-5 Importance Calculations for Initiating Events . . . ..... .......... . . . 33-42 l
334) AP600 PRA List of Basic Event Descriptions . . . . . . . . . . . . ...... .. 33-43 34-1 Post-Accident Monitoring Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-30 ,
34-2 Level 1 Accident Class . . .................. ... . ...... ... 34 31 34 3 AP600 Level 1 Dominant Core Damage Sequences . . . . . . . . . . . . . . . . . 34-3 2 34-4 Summary of Release Categories .................................%38 34-5 3BE-1 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-3 9 34-6 3 BE-2 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 40 j
!\f 34-7 3BE 3 Event Summary . . . . . . . . . . . . . . . . . . ........... . . ....... 34-41 l l
34-8 3BE-4 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 42 34-9 Summary of Releasc Categories Considered for Accident Class 3BE . . . . . . . 34-43 34-10 Summary of Release Category Disposition for Accident Class 3BE . . . . . . . . 34 43
% 11 3 B E-5 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-44
% 12 3 B E-7 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-45 j
% 13 3 B E-8 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-46 W14 3BE-9 Event Summary . . . . . . ...............................34-47
% 15 3BE- 10 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-48 34-16 3 B L-1 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-49
%I7 3 B L-2 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . % 50 l 34-18 Summary of Release Categories C'onsidered for Accident Class 3BL ....... 34-51 Summary of Release Category Disposition for Accident Class 3BL ........ 34-51 34-19 34-20 3 BL-3 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-52 l 34-21 3BR-1 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . %53 l 34-22 Summary of Release Category Disposition for Accident Class 3BR . . . . . . . . 34-54 i
% 23 3C-1 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-55
% 24 Summary of Release Category Disposition for Accident Class 3C ......... 34-56 l 34-25 3 D-1 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-57
'* 34 26 Summary of Release Categories Considered for Accident Class 3D . . . . . . . . 34 5 8
% 27 Summary of Release Category Disposition for Accident Class 3D ..........%58 34-28 3 D-2 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . %59 6E- 1 Event S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-60
) 34-29 6E 2 Event Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-61 j
/ % 30 I
34-31 6E 3 Event Summary .......................................34-62 Revision: 9 W W8Silligh0088 E..S-April 11,1997
l l
, e i l
LIST OF TABLES (Cont.)
Table No. Title Page !
l 34-32 6L-1 Event Summary . ........ ........ ...... .. . . . . . . . 34 63 34-33 Summary of Release Categories Considered for Accident Class I AP . . ... 34-64 34-34 Summary of Release Category Disposition for Accident Class I AP . .. . 34-64 34-35 1 AP-1 Event Summary . . ........ ... ..................... 34-65 34-36 Summary of Release Categories Considered for Accident Class IA .... ... 34-66 4
34-37 Summary of Release Category Disposition for Accident Class 1 A ........ 34-66 34-38 1 A-1 Event Summary . . ................................ .. 34-67 35-1 Functional Definitions of Level 1 Accident Classes ........... ....... 35-22 35-2 CET Initial Conditions for Level 1 Accident Classes ............. . . . . 35-23 35-3 Containment Event Tree Nodal Questions . . . ........ .. . . . . . . . . . . 3 5-24 35-4 Summary of Release Category Definitions . . . . . ........ . . . . . . . . . . . 35-25 35-5 Summary of Containment Event Tree Success Criteria . . . ........... 35-26 35-6 Summary of Operator Actions Credited on Containment Event Tree . . .... 35-29 36-1 Summary Table for RCS Depressurization (CET Node DP) . . . . . . . . . . . . . . 36-7 j 37-1 Summary Table for Containment Isolation (CET Node IS) .......... .... 37-5 l 38-1 Summary Table for Reflooding (CET Node RFL) .............. ...... 38-6 39-1 Pressure Loading on Insulation .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9- 1 5 39-2 Summary Table for Reactor Cavity Flooding (CET NODE IR) . . . . . . . . . . . 39- 16 39-3 Summary Table for Debris Relocation to Cavity (CET NODE VF) . . . ..... 39-16 41-1 Containment Event Tree Nodal Failure Probabilities . . . . . . . . . . . . . . . . . . 41 -4 3 41-2 Summary of System Assumptions for MAAP4 Hydrogen Mixing Analyses . . . 41-44 41-3 Summary of Hydrogen Gene;ation Results MAAP4 Hydrogen Mixing Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................... 41-51 41-4 Summary of Early Compartment Gas Composition Results for MAAP4 Hydrogen Mixing Analyses . . . . . . ..... ... ........ . . . . . . . . . . 41 -57 41-5 Summary of System Assumptions for MAAP4 Hydrogen Burning Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ . . . . 41 -67 41-6 Summary of Hydrogen Generation Results for MAAP4 Hydrogen Buming Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -68 41-7 Summary of Early Compartment Gas Composition Results for MAAP4 Hydrogen Buming Analyses . . . . . . . ................... . . . . . . 41 -69 41-8 Geometric Classes for Flame Acceleration . ............. . . . . . . . . . . 41 -71 41-9 fammary of DDT Potential Evaluation from NUREG/CR-4803 . . . . . . . . . . 41-72 41-10a Dependence of Result Class on Mixture and Geometric Class . . . . . . . . . . . 41 -73 41-10b Classification of the Probability of Deflagration to-Detonation Transition . . . 41-73 l Revision: 10 ENEL l June 30,1997 :ng_ T Westirigholise obp600$rn\rev.10$ra-lot wpf.lb 1
i
/m I i
{
wJ l LIST OF TABLES (Cont) j I
Table No. Title P,_ age 41-11 AP600 Compartment Geometry Class Assignment for Sherman-Berman i Methodology for the Estimation of the Likelihood of Detonation . . . . . . . . . . 41-74 l 41-12 AP600 Scenario Dependencies for Early Detonation Analysis . . . . . . . . . . . . 41-75 1 41-13 Early Detonation Probability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -7 6 )
41-14 Intermediate Time Frame Detonation Probability . . . . . . . . ............ 41-87 l 41-15 Safety Margin Basis Containment Performance Requirement . . . . ........ 41-90 l 1
4 42-1 Parameters Used in the Construction of the AP600 Containment i l
Failure Probability Distribution for Containment Temperature = 400*F . . . . . . . 42-9 !
40 " Parameters Used in the Construction of the AP600 Conditional Containment l Failure Probability Distribution for Containment Temperature = 331'F . . . . . . 42-10 42-3 Cumulative Containment Failure Probability, Temperature = 400'F . . . . . . . . 42-11 i 42-4 Cumulative Contair. ment Failure Probability, Temperature = 331*F . . .... . 42-12 43-1 AP600 Containment Event Tree Nodes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43-9 43-2 Release Category Descriptions . . . . . . . . . . . .......... . . . . . . . 43-10 43-3 Large Release Frequency, CCFP, and C, by Accident Class . . . . . . . . . . . . . 43-11 ]
, 43-4 Dominant Containment Event Tree Sequences for Large Release
('s j Ivequency .... .................... .....................43-12 43-5 Accident Class 3BE Core Damage Sequences . . . . . . . . . . . . . . . . . . . . . . 43-15 43-6 Accident Class 3BL Core Damage Sequences . . . . . . . . . . . . . . . . . . . . . . 4 3 - 17 l 43-7 Accident Class 3BR Core Damage Sequences . . . . . . . . . . . ........... 43-20 )
43-8 Accident Class 1 A Core Damage Sequences . . . . . . . . . . . . . . . . . . . . . . 43-21 43-9 Accident Class I AP Core Damage Sequences . . . . . . . . . . . . . . . . . . . . . . . 43-23 43-10 Accident Class 3A Core Damage Sequences . . . . . . . . . . . . . . . . . . . . . . . . 43-24 43-11 Accident Class 3C Core Damage Sequences . . . . . . . . . . . . . ... ..,... 43-25 43-12 Accident Class ::D Core Damage Sequences . . . . . . . . . . . . . . . . . . . .... 43-26 43-13 Accident Class 6 Core Damage Sequences .................... . . . . 43-27 ;
43-14 Dominant Cutsets for Large Release Frequency . . . . . . . . . . . . . . . . . . . 43-29 !
43-15 17CFE 3BE Large Release Frequency Sequence Cutsets . . . . . . ........ . 43-33 43-16 19BP6 Large Release Frequency Sequence Cutsets . . . ....... . ...... 43-42 43-17 19BP 3A Large Release Frequency Sequence Cutsets . . . . . . . . . ...... . 43-52 !
43-18 19P1 A Large Release Frequency Sequence Cutsets . . . . . . . . . . . . . . . . . . . . 43-60 !
43-19 19BPI AP Large Release Frequency Sequence Cutsets ........ .. . . . . . 43-69 43-20 8CFE 3C Release Frequency Sequence Cutsets . . . . . . . . . . . . . . . . . . . 43-79 43-21 17CFE 3D Large Release Frequency Sequence Cutsets . ..... ........ 43-80 43-22 1 SCI 3BE Large Release Frequency Sequence Cutsets ............. . . . 43-88 :
43-23 18CI 3D Large Release Frequency Sequence Cutsets . . . . . . ......... . 43-97 (
! 43-24 18CI 3BL Large Release Frequency Sequence Cutsets ...... . . . . . . . . .43-106 43-25 18CI 3C Large Release Frequency Sequence Cutsets ................ .43-115 43-26 6 CFE 3BE Large Release Frequency Sequence Cutsets . . . . . . . . . . . .43-118 Revision: 9 ENEL l [ W85tingh0Use m =: % April 11,1997 l [j o:\ap600\pravev_9%pra-latwpf;1b I
L
& -~
LIST OF TABLES (Cont.)
O Table No. Title Page 43-27 18CI 3A Large Release Frequency Sequence Cutsets . . . . . . . . . . . . . . . 4 3- 129 43-28 18CI 3BR Large Release Frequency Sequence cutsets . . . . . . . . . . . . . . . 4 3- 143 44-3 MAAP Model Benchmarks . . . . . . . ......... ........... . . . . . . 44-8 45-1 Environmental Release Fmetions at 24 Hours After Core Damage Per Release Category . .. ..... ........ . .. . ........ . . . 45-8 45-2 Environmental Release Fractions at 72 Hours After Core Damage Per Release Category . . . ............... . .. . ... ..... .45-9 45-3 Release Category IC Cases for Comparison . . ........ ........... . 45-10 f 45-4 Release Category BP Cases for Comparison .. ...... . . . . . . . . . . . 45-11 45-5 Release Category CFE Cases for Cotaparison ... .... ........... .. 45-12 45-6 Release Category CFI Cases for Comparison . . . . . . . ...... ..... . . 45-13 45-7 Summary of Source Term Sensitivity Studies ..... . . . . . . . . . . . . . . 45- 14 45-8 Volatile Aerosols (Represented by Iodine) . . . . . . .. ... .. .. 45-15 1 45-9 Non-Volatile Aerosols (Represented by Strontium) . .. . . . . . . . . . . . . . 45- 16 49-1 AP600 Source Terms From Level 2 Analysis . ... . .. . ...... . 49-9 49-2 AP600 Source Tcrms for Dose Evaluation (MACCS) ..... ........ . 49-10 l
49-3 Site Boundary Whole-Body Dose (Effective Dose Equivalent) . . . . . . . . ... 49-11 49-4 Site Boundary Thyroid Dose . . . . ...... .........,........... 49-12 l 49-5 Po,nulation Whole-Body Dose (0 to 80.5 km Radius) . . . . . . .... . . . . 49-13
! 49-6 Site Boundary Red Marrow Dose .. .... . ....... ..... . . 49-14 49 7 Dose Summary . . . . . . . . . . . . . . . . . . . ........................49-15 49-8 Site Boundary Dose Risk - 24 Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9- 16 49-9 Site Boundary Dose Risk - 72 Hours . . . . . . . ... ......... . . . . . . 49-17 49-10 Population Dose Risk - 24 Hours . . . . . . . . . . . . ............ ... . 49-18 49-11 Population Boundary Dose Risk - 72 Hours ... .. .. ........... . 49-19 50-1 AP600 PRA Core Damage From Intemal Initiating Events At-Power Risk Decrease Ranking of Initiating Events . . . . . . . . . . . . . . . . . . . 5 0-26 50-2 AP6'00 PRA Core Damage From Intemal Initiating Events At-Power Conditional Core Damage Ranking of Initiating Events . . ....... .. . 50-28 50-3 AP600 Common Cause Importances - Risk Decrease .. .. . . . ... 50-30 50-4 AP600 Common Cause Importances Risk Increase . .............. . 50 31 50-5 Human Error Risk Importances - Risk Decrease ....... . . . . . . . . . 50-33 50-6 Human Error Risk Importances - Risk Increase . . . . . ........ . 50-34 50-7 AP600 Component Importances - Risk Decrease . . . . . . . . . ...... . . 50-35 50-8 AP600 Component Importances - Risk Increase . . ... . . . . . . . . . . . . 50-36 50-9 System Importance Calculation Results ..... ... .... ..... . . . 50-37 50-10 AP600 Systems Grouped by PRA System Importance . ........... . 50-39 Revision: 9 9
April 11,1997 o:\ap600\praWv 9\pra-lot.wpf:lb lii h_ [ Westingh0!!Se
w s
LIST OF TABLES (Cont.)
Table No. TJat Esse 50-11 Operator Actions in the hcMine PRA . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-40 50-12 Contribution orInitiating Events to Core Damage Frequency for Sensitivity Case with Failure of all Operator Actions . . . . . . . . . . . . . . . . . 50-4 2 50 13 Operator Actions in Sensitivity Case 27 . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-43 50-14 Component Importances - For Risk Decrease Measure (At Power) . . . . . . . . . 50-45 50-15 Component Importances - For Risk-Increase Measure (At Power) . . . . . . . . . . 50-55 50-16 Containment Event Tree Node Irpportances . . . . . . . . . . . . . . . . . . . . . . . . . 50-65 50-17 Contribution of Initiating Events to Large Release Frequency . . . . . . . . . . . . 50-66 50-18 Initiating Event vs Containment Effectiveness (C,) . . . . . . . . . . . . . . . . . . . 50-67 50-19 End-State Importances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-68 50-20 Summary of Large Release Frequency Component Importances Sorted ,
l .
by Risk Increase . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-69
- l. 50-21 Summary of Large Release Frequency Component Importances Sorted by Risk Decrease . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50-75 51-1 Uncertainty Analysis Cases . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 51-7 ,
51-2 Basic Event Uncertainties . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51-9 51-3 Summary of Results of PRA Uncertainty Analysis for Internal Events at Power . . . . . . . . ...................................51-17 52-1 Nonsafety-Related Systems Removed from Baseline PRA Analysis . . . . . . . . 52-25 52-2 Safety-Related Systems credhed in the Focused PRA Sensitivity Study . . . . . 52-26 52-3 At-Power Front-Line System Fault Trees . . . . . . . . . . . . . . . . . . . . . . . . . . 52-27 52-4 At-Power Focused PRA Sensitivity Study PMS Fault Trees . . . . . . . . . . . . . . 52-29 52-5 At-Power Focused PRA Sensitivity Study Core Damage Contribution by Initiating Event . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 52-31 l 52 6 At-Power Focused PRA Core Damage Quantification Cutsets . . . . . . . . . . . . 52-33
~ 52-7 At-Power Focused PRA Core Damage Quantification Accident Sequences . . . . 52-50 52-8 At-Power Focused PRA Sensitivity Study Core Damage Contribution by B asic Events . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . 5 2-56 52-9 Results of the Accident Class Quantification . . . . . . . . . . . . . . . . . . . . . . . . 52-66 52-10 Summary of Release Frequency Calculations . . . . . . . . . . . . . . . . . . . . . . . . 52-67 52-11 Dominant Containment Event Tree Sequences . . . . . . . . . . . . . . . . . . . . . . . 52-68 52-12 AbPower Initiating Event Contributions to Large Release Frequency . . . . . . . 52-70 52-13 Shudown Frontline System Fault Trees . . . . . . . . . . . . . . . . . . . . . . . . . . . 52-72 52-14 Shutdown Focused PRA SensiCvity Study PMS Fault Trees . . . . . . . . . . . . . 52-73 52-15 Shutdown Focused PRA Sensitivity Study Core Damage Contribution by Initiating Event . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52-74 52-16 Shutdown Focused PRA Sensitivity Study Top 200 Cutsets . . . . . . . . . . . . . . 52-75 52-17 Shutdown Focused PRA Sensitivity Study Accident Sequences . . . . . . . . . . . 52-93 (O_-) Revisi a: 9 g
RMg 6 April 11,1997 jjjj cAap600%prairev.9\pra-lot.wpf.lb
Bs n
LIST OF TABLES (Cont.)
O.l l
1 T
_ able No. Title P_ age l 52-18 Shutdown Focused PRA Sensitivity Study Core Damage Contribution by Basic Event ........ ..... ..... ..... ... ..... .... . 52-97 52-19 Shutdown Focused PRA Sensitivity Study Release Frequency Results Summary by Release Category ... ...... . ..... .........52-103 52-20 Shutdown Release Category IC Reaults Summary .. ....... ...... .52-104 52-21 Shutdown Release Category ICP Results Summary . . . . . . . . . . . . . . . . . . .52-105 52-22 Shutdown Release Category XL Results Summary ................ .52-106 52-23 Shutdown Release Category BP Results Summary . . .......... . . . .52-107 52-24 Shutdown Release Category CI Results Summary .. ............ ...52-107 52-25 Shutdown Release Category CI-C Results Summary . . . . . . . . . . . . . . . .52-108 52-26 Shutdown Release Category CFE Results Summary . . . . . . . . . . . . . . . .52-108 52-27 Shutdown Release Category CFE-C Results Summary ................52-109 52-28 Shutdown Release Category CFI Results Summary . . . . . . . . . . . . . . . . . . 5 2- 1 10 52-29 Shutdown Release Category CFL Results Summary . . . . . . . . . .. ...52-110 52-30 Shutdown Release Category CFV Results Summary . . . . . . . . .... .52-111 52-31 At-Power Focused PRA Sensitivity Study Flooding-Induced Core Damage Frequency Quantification Results Summary . . . . . . . . . . . . . . . ..52-112 52-32 Shutdown Focused PRA Sensitivity Study Flooding-Induced Core Damage Frequency Quantification Results Summary . . . . . . . . . . . . . . .52-114 52-33 Summary of Focused PRA Sensitivity Study Results ... ........... .52-116 54-1 Matrix: Shutdown Phase / Outage Type / Operating Mode . . . . . . . . . . . . . . . . 54-89 54-2 Systems Availability and Actuating Signals Type . . . . . . . . . . . . . . . . .. 54-90 54-3 Initiating Event Frequencies Used in Event Tree Quantification . . . . . . . . . . 54-92 54-4 AP600 Shutdown Mission Times and Frequencies . ........... .... . 54-93 54-5 Mission Times for Normally Operating Systems for AP600 Shutdown Fault Trees & Event Tree Quantification . . ....... ..... ... . ... 54-94 54-6 Initiating Event Frequencies Used in AP600 Shutdown Event Tree Quantification . . . . ............. . ... ............. ... 54-95 54 7 List of System Fault Trees (Shutdown Case) . . . . . . . . . ...... .. 54-96 54-8 System Unavailability Status . . . . . . . . . . ..... . ..... . .. ..54-101 54-9 PMS/DAS I&C Subtrees for Modeling Shutdown PRA . ....... .. ...54-106 54-10 PMS/DAS I&C Fault Tree Equivalents: Shutdown and At-Power Cases . . . . . . . . ........... ............... ..54-109 54-11 PMS/DAS Subtree Success Criteria Summary . . . . ......... . ...54-111 54-12 Data Developed for the PMS/DAS Shutdown I&C Models . . ... ... .54-129 54-13 Operator Actions Assignments for the PMS/DAS I&C Analysis . . . . . . . . . .54-131 54-14 PLS I&C Subtrees for Modeling Shutdown PRA . . . ...... ..... .54-138 54-15 PLS I&C Fault Tree Equivalents: Shutdown and At-Power Cases . . ..54-139 54-16 PLS Subtree Success Criteria Summary .. ............. . . . . . . . .54-140 54-17 Data Developed for PLS I&C Analysis . . . . ............. ..54-142 Revision: 9 O
ENEL April 11,1997 my=6 [ Westi!1gt100S8 c:hp600\pra\rev.9\pra-lot.wpf: I b liv
151 pJ LIST OF TABLES (Cont.)
Table No. Title P_REe 54-18 Operator Actions Assignments for the PLS I&C Analysis . . . . . . . . . . . . . .54-143 54-19 PMS/DAS I&C Subtrees Used in Modeling Shutdown Assessment Plant Damage State Trees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54- 144 54-20 PMS/DAS I&C Fault Tree Equivalents: Shutdown and At-Power Level 2 Cases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 144 54-21 Operator Action Assignments for the PMS/DAS Level 2 I&C Analysis . . . . .54-145 54-22a ADS Success Criteria Versus Accident Conditions Fell Depressurization Shutdown Condition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4- 14 6 54-22b ADS Fault Tree Summary (For Plant Damage States for Events Initiated During Shutdown) . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4- 1 46 54-23 Fault Tree ADAS Success Crite-ia Summary . . . . . . . . . . . . . . . . . . . . . . .54-147 54-24 Fault Tree ADTS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-148 54-25 Fault Tree ADALS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-149 54-26 Fault Tree ADLS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-150 54-27 Fault Tree CIST Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . 54- 151 54-28 Fault Tree CM2AM Success Criteria Summary . . . . . . . . . . . . . . . . . . . . 54- 15 2 54-29 Fault Tree CM2 AMP Success Criteria Summary . . . . . . . . . . . . . . . . .. .54-153
' (g 54-30 54-31 Fault Tree IW2AB Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-154 Fault Tree IW2A Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-155 54-32 Fault Tree IW2AO Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-156 54-33 Fault Tree IW2AP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-157 54-34 Fault Tree IWFS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . 54- 15 8 54-35 Fault Tree IWRNS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-159 54-36 Fault Tree PCTS Success Criteria Summary ................ . . . . . .54-160 54-37 Fault Tree PRM Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-161 54-38 Fault Tree PRMP Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-162 54-39 Fault Tree PRW Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . 54- 163 !
54-40 Fault Tree RNC2 Success Criteria Surmnary . . . . . . . . . . . . . . . . . . . . . . .54-164 54-41 Fault Tree RNT2 Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-165 54-42 Fault Tree RNP2 Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-166 54-43 Loss of CCS/SWS During Shutdown Initiating Event Fault Tree CSWF2 Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .54-167 l l 54-44 Fault Tree CCTS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . 54- 16 8 1 54-45 Fault Tree CCPS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-169 54-46 Fault Tree SWTS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . . .54-170 54-47 Fault Tree SWPS Success Criteria Summary . . . . . . . . . . . . . . . .......54-171 i
54-48 Fault Tree VLHS Success Criteria Summary . . . . . . . . . . . . . . . . . . . . . .54-172 I I
l 54-49 AC & DC Fault Trees Success Criteria Summary . . . . . . . . . . . . . . . . . . . .54-173 l 54-50 Fault Tree ADQLTS Data Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . .54-187
'54-51 Fault Tree ADTLTS Data Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . .54-188 1 54-52 AP600 Shutdown Modes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4- 1 8 9 f
iw ENE Revision: 9 3 W8Shl @ 0tlS8 m:5.,:. April 11,1997 ly oMp600\pra\rev_9%pra lot wpf.lb L________________ __ . _ _ _ _ _ _
u.w=
' i l
LIST OF TABLES (Cont.)
O l
Table No. Title _P,aage 54-53 ADS Success Criteria for Shutdown Conditions . . . . . . .. . . . . . . . . . . . 54- 190 54-54a Sequence of Events for MAAP4 Cases Supporting ADS Success Criteria ADTS, ADLS . . . . . . . . . . . . . . . . . ...................... .. .54-192 54-54b Sequence of Events for MAAP4 Cases Supporting ADS Success Criteria ADSS .. ................ . .............. . . . . . . . . . .54-193 54-54c Sequence of Events for MAAP4 Cases Supporting ADS Success Criteria ADTS ............................................ ....54-194 54-54d Sequence of Events for MAAP4 Cases Supporting ADS Success Criteria ADLS and ADTS . . . . . . . . . . .. . ...... ....... .... .. .54-195 54-54e Sequence of Events for MAAP Cases Supporting ADS Success Criteria ADNS ..... .............. ............ . ...........54-196 54-55 Common Cause Failure Evaluated for Shutdown . . . . . . . ..........54-197 54-56 AP600 Shutdown Assessment HEP Summary Results . . . ........ ...54-198 54-57 Dependency Level Evaluation Summary for Shutdown Assessment ......54-207 .
54-58 Shutdown Master Data Bank . . . . . . . . . . . . . . . . . . . ...... .. ... .54-211 54-59 List of Basic Events and their Descriptions (Shutdown Model) . . . . . . . . .54-227 54-60 AP600 Shutdown Assessment Level 1 Accident Sequences Quantification Results . . . . . ............... ........ ........54-235 54-61 List of Dominant Sequences (At Shutdown) ................ . . . . . .54-236 54-62 List of Dotninant Cutsets (At Shutdown) . . . . . . . . . . . . . . . . . . . . . . . . .54-240 54-63 Shutdown initiating Event Importances . . . . . . . . . . . . . . . . . . . . . . . . . . .54-251 54-64 Basic Event Importances Using Risk-Decrease Measure (At Shutdown) . . . . .54-252 54-65 Basic Event Importances Using Risk-Increase Measure (At Shutdown) . . . . .54-258 54-66 AP600 Containment Event Tree Nodal Questions . .. ..... . ... ...54-264 54-67 AP600 Release Category Summary ..... ................ ...54-265 54-68 Summary of Shutdown and Low-Power Accident Classes . . . . . . . . . . . .54-266 54-69 AP600 Shutdown and Low-Power Plant Damage Substate Frequencies . .54-267 54-70 AP600 Shutdown and Low-Power Plant Damage Substate Conditional Probabilities . . . . ................ . ...... ....... .54-268 54-71 AP600 Shutdown and Low-Power Containment Event Tree Quantification Results - Release Category Frequencies (Per Reactor-Year) . . . . . . . . . . . . .54-269 54-72 Release Category IC Dominant Sequences . . . . . . . ........... .. .54-270 54-73 Release Category ICP Dominant Sequences . . . . . . . . . . . . . . ......54-271 54-74 Release Category XL Dominant Sequences . . . . . ... ... ..... ...54-272 54-75 Release Category BP Dominant Sequences . . . . .. .. .. ... . . . .54-273 54-76 Release Category CI Dominant Sequences . . . .............. .. .54-274 54-77 Release Category CI-C Dominant Sequences . . . . . . . ....... ...54-275 54-78 Release Category CFE Dominant Sequences . . . . . . . . . . . . . . . . . . ....54-276 54-79 Release Category CFE-C Dominant Sequences .....................54-277 54-80 Release Category CFI Dominant Sequences . . . . . ... .. .. ... ...54-278 54-81 . Release Category CFL Dominant Sequences ......... ... ... ...54-279 Revision: 9 O
ENE [ Westiligh0USB April 11,1997 wrah onap600praWv.9pra-lot.wpf;1b lvi
1 LIST OF TABLES (Cont.)
Table No. .Thlt East 54-82 Release Category CFV Dominant Sequences . . . . . . . . . . . . . . . . . . . . . . .54-280 54-83 Core Damage for Intemal Initiating Events at Shutdown - Risk Decrease . . .54-281 54-84 Core Damage for Internal Initiating Events at Shutdown - Risk Increase . . . .54-282 54-85 Shutdown Common Cause Importance - Risk Decrease . . . . . . . . . . . . . . . .54-283 54-86 Shutdown Common Cause Importance - Risk Increase . . . . . . . . . . . . . . . .54-284 54-87 Shutdown Human Error Risk Importance - Risk Decrease . . . . . . . . . . . . . .54-285 54-88 Shutdown Human Errcr Risk Imponance - Risk Increase ..............54-285 54-89 Shutdown Component Importance - Risk Decrease . . . . . . . . . . . . . . . . . . .54-286 54-90 Shutdown Component Imponance - Risk Increase . . . . . . . . . . . . . . . . . . .54-286 54-91 Operator Actions for Sensitivity Cases 7 and 8 . . . . . . . . . . . . . . . . . . . . .54-287 54-92 Matrix of Shutdown Initiating Events Screening Process . . . . . . . . . . . . . . .54-288 q 54-93 Technical Specification Requirements for Safety-Related Components . . . . . .54-298 1 t
55-1 Seismic Margin HCLPF Values . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . . 55-72 55-2 SMA Event Tree Success Paths . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-77
~ 55 3 - Basic Event HCLPF Values ................................... 55-80 i 55-4 EQ-IEV-STRUC HCLPF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-84 l 55-5 EQ-IEV-RVFA HCLPF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-85
[ 55-6 EQ-IEV-LLOCA HCLPF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-86 55-7 EQ-IEV-SLOCA HCLPF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-87 a 55-8 EQ-IEV-A*IWS HCLPF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-88 {
55 9 System HCLPFs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-89 )
55-10 Sequence HCLPFs ........................................55-90 55-11 SM. . Mixed Cutsets . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-92 55-12 LarFe Release HCLPFS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-93 55-13 med Cutsets for LOSP Operator Action Sensitivity . . . . . . . . . . . . . . . . . . 55-95 55-14 Mixed Cutsets for LOSP 72-hour Mission Time Sensitivity . . . . . . . . . . . . . 55-102 56-1 AC and Non-class IE DC Equipment Locations . . . . . . . . . . . . . . . . . . . . . . 56-55 56-2 AP600 Building Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-57 56-3 Flooding Analysis Initial Screening Results . . . . . . . . . . . . . . . . . . . . . . . . . 56-59
, 56-4 At. Power Detailed Screening Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-63 l 56-5 At-Power Flooding-Induced Core Damage Frequency Quantification Summary Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-68
! 56-6 Shutdown Flooding-Induced Core Damage Frequency Quantification Summary Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-72 56-7 At Power Flooding Dominant Cutsets . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-77 56-8 Shutdown Flooding Dominant Cutsets . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 6- 87 l
l Revision: 9 l YN w Ivii April 11,1997 oVmPa*v W"P *f
l I LIST OF TABLES (Cont.)
O Table No. Title _P_ age 57-la AP600 Systems Credited for Power Operation . . . . . . . . . . . . . . . . . . . . . . 57-50 57-lb AP600 Systems Credited During Safe Shutdown and Mid-Loop Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7-51 57-2a Automatic Suppression System Reliability . . . . . . . . . . . . . . . . . . . . . . . . . . 57-52 57-2b Fire Areas with Automatic Fire Suppression . ...................... 57-52 57-3 Fire Barrier Failure Probabilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57-53 57-4 Summary of Qualitative Evaluation Results - Power Operation . . . . . . . . . . . . . . . ................ . . . . . . . . . . . . . . . 5 7-54 57-5 Summary of Qualitative Evaluation Results for Containment for Power Operation . . . . . . . . . . . . . . . . . . . . . . . 5 7 -67 57-6 Fire Ignition Frequencies for AP600 Fire Areas . . . . . . ......... . . . . . 57-69 57-7 Fire Ignition Frequencies for AP600 Containment Fire Area . . . . . . . . . . . . 57-72 57-8 Summary of Fire Damage State Binning Process -
Power Operation . . . . . . . . . .................... ........ . . . 57-73 57-9 Summary of Fire Damage State Binning Process for Containment - Power Operation . . . . . . . . . . . . . . . . . ............ . . 57-81 57-10 Contribution of Fire-Induced Initiating Event to Plant Core Damage Frequency - Power Operation ....... .. ....... 57-83 57-11 AP600 Fire Scenario Initiating Frequency Binning -
Power Operation . . . . . . .................................... 57-84 57-12 List of Top 200 Dominant Cutsets - Power Operation . . . . . . . . . . . . . . . . . . 57-86 57-13 Summary of Quantitative Analysis Results . . . . . . . . . . . . . . . . . . . . . . . . 57- 100 57-14 Summary of QuantitatNe Analysis Results for Containment . . . . . ......................... . . . . . . . . . . . . .57-109 57-15 Quantification of Core Damage Frequency for Control Room Fire Scenarios - Power Operation . . . . . . . . . . ............ .57-111 57-16 Summary of AP600 Plant Operational State (POS)
Times for Shutdown . . . . . . . . ..,... ..... ......... . . . .57-112 57-17 Shutdown Fire Ignition Frequencies for AP600 Fire Areas ..... . . . . . . .57-113 57-18 Fire Ignition Frequencies for AP600 Containment Fire Area . . . . ...................... .. ............. ..57-116 57-19 Summary of Fire Areas in which a Fire Can Initiate Spurious ADS Actuation (LOCA) .................... ... ...57-117 57-20 Shutdown Fire Damage State Definitions ........... .......... .57-118 57-21 Shutdown Containment Fire Damage State Definitions ..... ......57-119 57-22 Summary of Qualitative Evaluation Results - Safe Shutdown . . . . . . . . ..... ...... .. .... .... ........ .57-120 57-23 Summary of Qualitative Evaluation Results for Containment Shutdown Operation (After Screening) . . . . . . . . . . . . . . . . .57-128 57-24 Summary of Quantitative Analysis Results - Safe Shutdown . . . . . . ..... .... ................... .... .57-129 Revision: 9 9
ENEL WeStiflgt10USB April 11,1997 mut:6 ow600pwev_9,maatwpr.ib Iviii
g b
LIST OF TABLES (Cont.)
Table No. Title bage 57-25 Quantitative Summary - Control Room Fires During ,
Safe Shutdown .......................................57-138 l 57-26 Summary of Qualitative Evaluation Results -
Mid-Loop Operation . . . . . . . . . . ..... ................... ...57-139
]
l 57-27 Summary of Quantitative Results - Mid-Loop Operation . . . . . . . . . .57-146 .
57-28 Quantitative Summary - Control Room Fires During Mid-Loop Operation ............ .......... ..............57-154 j 57-29 Safe Shutdown Containment Single-Hot-Short LOCA Sensitivity . . ......57-155 1
59-1 Contribution of Initiating Events to Core Damage .. .. ........ ...59-104 59-2 Conditional Core Damage Probability of Initiating Events . . . . . . . . . .59-105 59-3 Intemal Initiating Events at Power Dominant Core Damage Sequences . . . .59-106 !
59-4 Sequonce 1 - Safety Injection Line Break Dominant Cutsets (SI-LB-02) . . . .59-108 i 59-5 Sequence 2 - Intermediate LOCA Dominant Cutsets (NLOCA-03) . . . . . . . .59-113 59-6 Sequence 3 - Large LOCA Dominant Cutsets (LLOCA-06) . . . . ......59-118 I 59-7 Sequence 4 - Large LOCA Dominant Cutsets (LLOCA-03) . . .. . . . . . .59-124 I 59-8 Sequence 5 - Reactor Vessel Rupture Cutset (RV-RP-02) . . . . . . . . . . . .. 59 130
,- 59-9 Sequence 6 - Large LOCA Dominant Cutsets (LLOCA-11) ..... . ....59-131
(~qj 59-10 Sequence 7 - ATWS Dominant Cutsets (ATWS-28) . . . . ........., ..59-133 59-11 Sequence 8 - Medium LOCA Dominant Cutsets (MLOCA-03) ..........59-141 59-12 Sequence 9 - ATWS Dominant Cutsets (ATWS-13) . . . . . . . . . . . . . . . .59-146 ,
59-13 Sequence 10 - Intermediate LOCA Dominant Cutsets (NLOCA-04) . . . . . . .59-151 59-14 Sequence 11 - Safety Injection Line Break Dominant Cutsets (SI-LB-03) .. 59 156 59-15 Sequence 12 - Small LOCA Dominant Cutsets (SLOCA-03) . . . . . . . . . ..59-160 59-16 Sequence 13 - Lore Makeup Tank Line Break Dominant Cutsets (CMTLB-03)59-165 59-17 Sequence 14 - Steam Generator Tube Rupture Dominant Cutsers (SGTR-07) .59-170 59-18 Sequence 15 - Steam Generator Tube Rupture Dominant Cutsets (SGTR-23) .59-171 j 59-19 Sequence 16 - Large LOCA Dominant Cutsets (LLOCA-02) . .... ...59-177
{
59-20 Sequence 17 - Large LOCA Dominant Cutsets (LLOCA-05) . . ...... .59-183 59-21 Sequence 18 - Consequential SGTR Dominant Cutsets (SGTRC-03) . . . .59-189 59-22 Sequence 19 - Intermediate LOCA Dominant Cutsets (NLOCA-16) . . . ...59-195 l 59-23 Typical System Failure Probabilities. Showing Higher Reliabilities l for Safety Systems . . . . . . . . . . . .. ......... . ............ .59-201 l
59-24 Dominant CET Sequences . .... .. ........... .... . ... 5M02 J 59-25 Comparison of Initiating Event Contribution to Core Damage and Large Release Frequencies ...... ............ .... . . . . . . . .59-203 3 59-26 Summary of AP600 PRA Results . . . . . . . . . . . . . . . . . . . . . . .......59-204 l l 59-27 Comparison of AP600 PRA Results to Risk Goals . . . . . . . . . . . . . . . . . . .59-205 59-28 Site Boundary Dose Risk at 24 Hours .......... ... . . . . . . . . . 5 9-206 1 59-29 AP600 PRA-Based Insights . . . . . . . . .. .. .. .......... . . .59-207 O
'V1 l Revision: 11 l j
[ W85tiligh00S8 hh_ }jx March 1998 o:\ap600\ prs \rev_l l\pra-lot.wpf:I b
! l i ___________a
)
LIST OF FIGURES e
Firure No. Title P_ age 2-1 Core Damage Logic Diagram for Internal Initiators . ...... .. . .. . 2-58 2-2 Core Damage Logic Diagram for Internal Initiators . ....... .. . . . 2-59 2-3 Core Damage Logic Diagram for Intemal Initiators .. ........ .. . . . 2-60 2-4 Core Damage Logic Diagram for Internal Initiators ............... .... 2-61 4-1 Large Loss-of-Coolant-Accident Event Tree ... ... ..... ......... 4-120 4-2 Medium Loss-of-Coolant Accident Event Tree . .. . . . . . . . . . . . . . . . ... . 4-121 4-3 Core Makeup Tank Line Break Event Tree . . . . ................ . . . 4-122 4-4 Direct Vessel Injection Line Break Event Tree . ... .......... . . . . . 4-123 4-5 Intermediate Loss-of-Coolant Accident Event Tree . ......... . .. 4-124 4-6 Small Loss-of-Coolant Accident Event Tree .. . ... ... . . . 4-125 4-7 Reactor Coolant System Leak Event Tree . . .... . ...... . . . . . . . . 4-126 4-8 Pa.;sive Residual Heat Removal Tube Rupture Event Tree . . . . . . .. . . . 4-127 4-9 Steam Generator Tube Rupture Event Tree . . . . . . . . ........ .. . . . . 4-128 4-10 Reactor Vessel Rupture Event Tree ....................... .... . 4-130 4-11 Interfacing Systems Loss-of-Coolant Accident Event Tree . . . . . . . . . .. .. 4-131 4-12 Transients with Main Feedwater Event Tree ... ........... . . . . 4-132 4-13 Transients with Loss of Reactor Coolant Sstem Event Tree . . . . . . . . . . . . . 4-133 4-14 Transients with Loss of Main Feedwater Event Tree . . . . . . . . . . . . . . . . . . 4- 134 _
4-15 Transients with Core Power Excursion Event Tree .......... ... . . . . 4- 13 5 4-16 Loss of Component Cooling Water System / Service Water System Event Tree ...... . . .... ..... .... .. ... ...... . . 4-136 4-17 Loss of Main Feedwater Event Tree . . . -. . . . . .. ..... . ... . . . . . 4-137 4-18 Loss of Condenser Event Tree . . . . . . . . ... .. ............. . . 4-138 4-19 Loss of Compressed Air Event Tree . . . . . . .. ............... . . 4-139 4-20 Loss of Offsite Power Event Tree .. ....... ................. . 4-140 4-21 Main Steam Line Break Downstream of Main Steam Isolation Valves Event Tree . . . . . . . . . . . . . . . . . ....... .......... .. . 4-141 4-22 Main Steam Line Break Upstream of Main Steam Isolation Valves Event Tree . . ............ ........ . .. . . 4-142 4-23 Stuck-Open Secondary. Side Safety Valve Event Tree . . . . . . . . . .. . . . . 4-143 4-24 Anticipated Transient Without Scram Precursor without Main Feedwater Event Tree . . .... ... .. . . . .. ... . . . . 4-144 4-25 Anticipated Transient Without Scram Precursor with Injection Event Tree ....... .. .. . ...... . ... .... ... .. . 4-146 4-26 Anticipated Transient Without Scram Precursor Transients with Main Feedwater Event Tree . . ...... ... ......... ... . 4-147 O
Revision: 9 April 11,1997 _ 3 WBStiflgh0USB oWGprairev.9%pra-lof wpf.lb lx
IO l v)
'\
LIST OF FIGURES (Cont.)
Fieure No. Title Page 4A-1 Example Event Tree for Illustration of Terminology . . . . . . . . . . . . . . . . . . . 4A-7 4A-2 Functional Event Tree .....................................
. 4A-8 4A-3 Illustration of Consequential Event End States . . . . . . . . . . . . . . . . . . . . . . 4 A-9 7-1 Power / Control Model for Large Loads (4160-vac/480-vac Pumps, Fans, and Motors) .. ......................................... .. 7-34 7-2 Power / Control Model for Motor-Operated Valves . . . .................. 7-36 7-3 Power / Control Model for Air-Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . 7-38 7-4 Power / Control Model for Variable Speed Motor (Main Feedwater Pump) . . . . . 7-40 7-5 An Illustration of Fault Tree Basic Events for a Pump following the Model Given in Figure 7-1 . . . . . . . . . ................................7-42 8-1 Passive Residual Heat Removal System Sketch . . . . . . . . . . . . . . . . . . . .. 8-23 8-2 Passive Core Cooling System - Passive Residual Heat Removal Piping and Instrumentation Diagram . . . . . . .............. ........ 8-25 9-1 Core Makeup Tank Subsystem Sketch . . . . . . . . . . . ....... ......... 9-25 9-2 Passive Core Cooling System Piping and Instrumentation Diagram . . . . . . . .. 9-27 i
i \
C) 10-1 Passive Core Cooling System - Accumulator Subsystem . . . . . . . . . . . . . . . 10-13 11-1 Automatic Depressurization System Sketch . . . . . . . . . . . . . . . . . . . . . . .. 11-44 12-1 IRWST Subsystem Sketch . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . 12-38 13-1 Passive Containment Cooling System Sketch . . . . . . . . . . . . . . . . . . . . . .. 13-12 14-1 Feedwater System Piping and Instrumentation Diagram .. ............ 14-45 14-2 Condensate System Piping and Instrumentation Diagram . . .............. 14-51 14-3 Main Steam System Piping and Instrumentation Diagram . , . . . . . . . . . . . . . 14-53 >
14-4 Turbine Building Closed Cooling Water System Piping and i Instrumentation Diagram . . . . . . . . . . . . . . . . . . . .... .. ... . . . . 14-55 !
14-5 Circulating Water System Piping and Instrumentation Diagram . . . . . . . . . 14-61 l l 15-1 Chemical and Volume Control System Sketch . . . . . . . . . . . . . . . . . . . . . 15-25 l
15-2 Chemical and Volume Control System Piping and Instmmentation Diagram . . . . . . . . . . . . ... ......... ........... 15-27 l
l 17-1 Normal Residual Heat Removal System Sketch . .............. . . . . . 17-19
! 17-2 Normal Residual Heat Removal System Piping and Instmmentation Diagram . . 17-21 18-1 Component Cooling Water System Piping and Instrumentation Diagram . . . . 18-13 A
l i
( /
ENEl. Revision: 9
[ WBStinghotise en h April 11,1997
[xi oAap60opa\rev.,9%pra4ofwpf.lb O____________-_____________
. LIST OF FIGURES (Cont.)
e Figure No. Title P_aage 19-1 Service Water System Piping and Instrumentation Diagram . . ...... ... . 19-17 20-1 Central Chilled Water Low-Capacity Subsystem Piping and Instmmentation Diagram . . . . . . ... ....... ...... ........ . . . 20-13 21-1 AC Power System One-Line Diagram . . . . . . . . . . . . . . . . . . . . . . . . . ... 21-61 22-1 Class IE de System One-Line Diagram ........... .. ....... ... 22 53 22-2 Class IE UPS One-Line Diagram ....... ... ....... ..... . .. 22-57 23-1 Non-Class IE de and UPS System One-Line Drawing . . ......... . 23-43 23-2 Non-Class IE de and UPS System Sketch . .... .. ... . . . . . . . . . 23-47 25-1 Instmment Air Subsystem Sketch . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25- 19 27-1 Diverse Actuation System Block and Interface Diagram . . . . . . . . . . . . . . . 27- 13 e
29-1 IRWST Valve Configuration . . . .. . .. .. . ................. 29-23 30-1 Human Reliability Analysis Quantificatio Model ... ... . ........30-115 34-1 Case 3BE-1: RCS Pressure and SG Pressure ........ .............. 34-68 34-2 Case 3BE-1: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . ............. 34-69 34-3 Case 3BE-1: Accumulator Water Mass and CMT Water Mass . . . . . . . . . . . 34-70 34-4 Case 3BE-1: IRWST Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-71 34-5 Case 3BE-1: Break Flows . . .. ......... ... ..... . ...... . 34-72 34-6 Case 3BE-1: Reactor Vessel Levels . . . . . . . . . ........... . ..... 34-73 34-7 Case 3BE-1: Core Temperatures . . . ................... . . . . . . . . 34-74 34-8 Case 3BE-1: Reactor Cavity Water Level and IRWST Water Level . . . . . . . 34-75 34-9 Case 3BE-1: Loop Compartment and Valve Vault Water Levels . ... .. 34-76 34 10 Case 3BE-1: Containment Pressure . . . . . . . . . . . . . . . . ... ..... ... 34-77 34-11 Case 3BE-1: Containment Temperatures . . .. .... .. . . .. . . . 34-78 34-12 Case 3BE-1: Debris Mass . .. ... ........ ...... ... . 34-79 34-13 Case 3BE-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . .. 34-80 34-14 Case 3BE-1: Hydrogen Generation . .. ... ..... ....... ... . 34-81 34-15 Case 3BE-1: Mass of Csl Released to Containment . . .... ....... ... 34-82 34-16 Case 3BE-1: Noble Gases Released . . . . . . . . . . . . . .. . ..... .... 34-83 34-17 Case 3BE-1: Releases to Environment . . . . . . . . . . . ............ ... 34 84 34-18 Case 3BE-1: Non-Volatile Release . ........... ............. 34-85 34-19 Case 3BE-2: RCS Pressure and SG Pressure .... . .......... ..... 34-86 Revision: 9 ENEL e
April 11,1997 e
' x0:::6 W85tingt10US8 oAap600$raWv.9)pra-lof.wnf:Ib lxii j
l
g
- J V
LIST OF FIGURES (Cont.)
Fleure No. Title _P_ age 34-20 Case 3BE-2: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . ... . . 34-87 34-21 Case 3BE-2: Accumulator Water Mass and CMT Water Mass . . . . .... . 34-88 34-22 Case 3BE-2: IRWST Flows . . . . . . . . . . . . . . . .................. . 34-89 34-23 Case 3BE-2: B reak Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-90 34-24 Case 3BE-2: Reactor Vessel Levels . .. ............... . ... ... 34-91 34-25 Case 3BE-2: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-92 34-26 Case 3BE-2: Reactor Cavity Water Level and IRWST Water Level . . . . . . . . 34-93 34-27 Case 3BE-2: Loop Compartment and Valve Vault Water Levels . . . . . . . . . 34-94 34-28 Case 3BE-2: Contain nent Pressure . . . . . . ... ... . . . . ...... 34-95 34-29 Case 3BE-2: Containment Temperatures .. ..... ........ ... .. . 34-96 34-30 Case 3BE-2: Debris Mass ....,............. ...... . . . . . . . . 34-97 34-31 Case 3BE-2: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . ... . 34-98 34-32 Case 3BE-2: Hydrogen Generation . . . . ........ ............... 34-99 34-33 Case 3BE-2: Mass of Csl Released to Containment . . ............ ..34-100 34-34 Case 3BE-2: Noble Gases Released . . . . . . . . . . . . . . . .............34-101 34-35 Case 3BE-2: Releases to Environment . . . . . . . . . . . . . . .. .. . .. .34-102 34-36 Case 3BE-2: Non-Volatile Release ..... .... ........... .... .34-103 m 34-37 Case 3BE-3: RCS Pressure and SG Pressure .... .... ... ...... .34-104 34-38 Case 3BE-3: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . . . . . . . .34-105 34-39 Case 3BE-3: Accumulator Water Mass and CMT Water Mass . . . .. . .34-106 34-40 Case 3BE-3: IRWST Flows . . . . . . . . . . . . . . ... ........... ...34-107 34-41 Case 3BE-3: B reak Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34- 108 34-42 Case 3BE-3: Reactor Vessel Levels . . . . . . . ......... ..... . ..34-109 34-43 Case 3BE-3: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-110 34-44 Case 3BE-3: Reactor Cavity Water Level and IRWST Water Level . .....34-111 34-45 Case 3BE-3: Loop Compartment and Valve Vault Water Levels ....... .34-112 l 34-46 Cast 3BE-3: Containment Pressure . . . . . . . ....................34-113 34-47 Case 3BE-3: Containment Temperatures ...................... .34-114 34-48 Case 3BE-3: Debris Mass . .............................. . .34-115 34-49 Case 3BE-3: Reactor Vessel-to-Cavity Water Heat Transfer . .... .34-116 34-50 Case 3BE-3: Hydrogen Generation ... ..... . ..... ........ .34-117 34-51 Case 3BE-3: Mass of Csl Released to Containment . . . . . . . . . . . . . . . . .34-118 34-52 Case 3BE-3: Noble Gases Released . ......... .... .... . ..34-119 34-53 Case 3BE-3: Releases to Environment . . . . . .......... . . . . . .34-120 l
34-54 Case 3BE-3: Non-Volatile Release . . . . . ...... ............. .34-121 ;
34-55 Case 3BE-4: RCS Pressure and SG Pressure .. .......... . .....34-122 )
34-56 Case 3BE-4: Loop i ADS Stage 4 Flows . . . . ................ ...34-123 34-57 Case 3BE-4: Accumulator Water Mass and CMT Water Mass . . . . . . . . . . 34- 124 )
34-58 Case 3BE-4: IRWST Flows . . . . ... ................ . .. .. .34-125 34-59 Case 3BE-4: Break Flows . . . .... . . . ............. .... .34-126 m 1 V
3 Westinghouse b }xijj Ap 111, o:\ap600\pra\rev_9\pra-lofvpf:1b l
I E______________________________.
l 1
I M 1 0; l LIST OF FIGURES (Cont.)
Figure No. Title Page 34-60 Case 3BE-4: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-127 34-61 Case 3BE-4: Core Temperatures . . . . . . . . . . ....................34-128 34-62 Case 3BE-4: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-129 34-63 Case 3BE-4: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-130 34-64 Case 3BE-4: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-131 34-65 Case 3BE-4: Containment Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . 34- 13 2 34-66 Case 3BE-4: Debris Mass . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . .34-133 34-67 Case 3BE-4: Reactor Vessel-to-Cavity Water Heat Transfer . . ... ... .34-134 34-68 Case 3BE-4: Hydrogen Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-135 34-69 Case 3BE-4: Mass of Csl Released to Containment . . . . . . ... . .. .34-136 34-70 Case 3BE-4: Noble Gases Released . . . . . ...... . ... . . . . . . . . .34-137 34-71 Case 3BE-4: Releases to Environment . . . . . . . . . .................34-138 34-72 Case 3BE-4: Non-Volatile Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-139 34-73 Accident Class 3BE: Comparison of Mass Fraction Csl Released to Ctmt ..34-140 34-74 Case 3BE-5: RCS Pressure and SG Pressure ....... .......... .. .34-141 34-75 Case 3BE-5: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . . . . . . .34-142 34-76 Case 3BE-5: Accumulator Water Mass and CMT Water Mass . . . . . . . .34-143 34-77 Case 3BE-5: IRWST Flows . . . . . ......... .......... .......34-144 34-78 Case 3BE-5: Break Flows ............................. . . . .34-145 34-79 Case 3BE-5: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-146 34-80 Case 3BE-5: Core Temperatures . . . . ... ........... ...... ...34-147 34-81 Case 3BE 5: Containment Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . 34- 14 8 34-82 Case 3BE-5: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-149 34-83 Case 3BE-5: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-150 34-84 Case 3BE-5: Containment Temperatures . . . . . . . . . . . . . . . ...... .34-151 34-85 Case 3BE-5: Debris Mass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34- 15 2 34-86 Case 3BE-5: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-153 34-87 Case 3BE-5: Hydrogen Generation . . . . . . . . . . . . . . . . . . . . . . . . . . ..34-154 34-88 Case 3BE-5: Mass of Csl Released to Containment . . . . . . . . . . ... ...34-155 34-89 Case 3BE-5: Noble Gases Released . . . ... .. . ... ..... . . . .34-156 34-90 Case 3BE-5: Releases to Environment . . . . . . . . . . . . . . . . ..........34-157 34-91 Case 3BE-5: Non-Volatile Release . . . . . . . . . . . . . . . . . . ...... ...34-158 34-92 Case 3BE-7: RCS Pressure and SG Pressure .... ... .. . . . . . . . . . .34-159 34-93 Case 3BE-7: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . ........ .34-160 34-94 Case 3BE-7: Accumulator Water Mass and CMT Water Mass . ..... ..34-161 34-95 Case 3BE-7: IRWST Flows . . . . . . . ............. . ... . . . . . .34-162 34-96 Case 3BE-7: Break Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-163 34-97 Case 3BE-7: Reactor Vessel Levels . . . . . ............. . . . . . . .34-164 34-98 Case 3BE-7: Core Temperatures . . ..... ..... .......... ...34-165 34-99 Case 3BE-7: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-166 O
Revision: 9 April 11,1997 3 W85tingh0USB cAap600;prairev.9pra-lof.wpf;1b lxiv
<m i
LIST OF FIGURES (Cont.)
Fleure No. Title Pege 34-100 Case 3BE-7: Loop Compartment and Valve Vault Water Levels . . . . . . . .34-167 34-101 Case 3BE-7: Containment Pressure . . . . . . . . . .... ......... . . . .34-168 34-102 Case 3BE-7: Gas Flow Rate Through Containment Failure Location . . . . . .34-169 34 103 Case 3BE-7: Containment Temperatures ........................ .34-170 34-104 Case 3BE-7: Debris Mass . .. ...................... .. ....34-171 34-105 Case 3BE-7: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-172 34-1 M Case 3BE-7: Hydrogen Generation . . . ..... .............. . . . .34-173 34-107 Case 3BE-7: Mass of Csl Released to Containment . .... ..........34-174 34-108 Case 3BE-7: Noble Gases Released . . . . . . . . . . ..................34-175 34-109 Case 3BE-7: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . . .34-176 34-110 Case 3BE-7: Non-Volatile Release . . ........ . . . . . . . . . . . . . . . . . 34- 177 34-111 Case 3BE-8: RCS Pressure and SG Pressure ................ . . . . .34-178 34-112 Case 3BE-8: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . . . . . . . .34-179 ,34-113 Case 3BE-8: Accumulator Water Mass and CMT Water Mass . . . . . . . . . 34 180 34-114 Case 3BE-3: IRWST Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-181 ;34-115 Case 3BE-8: Break Flows . . . . . . . . .............. ....... ...34-182 34-116 Case 3BE-8: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-183 g 34-117 Case 3BE-8: Core Temperatures . . . . . . . .. .. . . . . . . . . . . . . . . . . . 34- 184 l
("} Case 3BE-8: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-185 34-118 34-119 Case 3BE-8: Loop Compartment and Valve Vault Water Levels . . . . . . . .34-186 34-120 Case 3BE-8: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-187 34-121 Case 3BE-8: Gas Flow Rate Through Containment Failure Location . . . . . .34-188 l 34-122 Case 3BE 8: Containment Temperatures ................... . . . . .34-189 I 34-123 Case 3BE-8: Debris Mass ....................... . . . . . . . . . . . 34- 190 34-124 Case 3BE-8: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-191 34-125 Case 3BE-8: Hydrogen Generation . . . . .. . . . . . . . . . . . . . . . . . . . . . 34- 192 34-126 Case 3BE-8: Mole Fraction Hydrogen in Valve Vault ........... . . . .34-193 34 127 Case 3BE-8: Mass of Cs1 Released to Containment . . . . . .. . . . . . . . . .34-194 34-128 Case 3BE-8: Noble Gases Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34- 195 34-129 Case 3BE-8: Releases to Environment . . . . . . . . . . . . . . . . . . . . ......34-196 34-130 Case 3BE-8: Non-Volatile Release . . . . . . . . . . . .. .. . .. . . . . .34-197 34-131 Case 3BE-9: RCS Pressure and SG Pressure ..... . . . . . . . . . . . . . . . 34- 19 8 34-132 Case 3BE-9: Loop 1 ADS Stage 4 Flows . . . . . . . ........ . . . . . .34-199 34-133 Case 3BE-9: Accumulator Water Mass and CMT Water Mass . . . . . . . . . .34-200 34-134 Case 3BE-9: IRWST Flows .... ......... ... ... . .......34-201 34-135 Case 3BE-9: Break Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .....34-202 34-136 Case 3BE-9: Reactor Vessel Levels . . . . . ........... ...... ....34-203 34-137 Case 3BE-9: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-204 l
34-138 Case 3BE-9: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-205 34-139 Case 3BE-9: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-206 34-140 Case 3BE-9: Containment Pressure . . . . . . . . ........... ....... .34-207 A
i $
't)
Revision: 9 ENEL y Westinghotise Gh=- April 11,1997 g,wyp.ior wpu t>
l l
I l 1
LIST OF FIGURES (Cont.)
8 1
Firure No. Title _P_ age 34-141 Case 3BE-9: Gas Flow Rate Through Containment Failure Location . . . ..34-208 34-142 Case 3BE-9: Containment Temperatures .. ........ .............34-209 34-143 Case 3BE-9: Debris Mass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-210 34-144 Case 3BE-9: Reac ar Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-211 34-145 Case 3BE-9: Hydrogen Generation . . . . . . .................. ...34-212 34-146 Case 3BE-9: Mole Fraction Hydrogen in Valve Vault . . . . . . . . . . . ....34-213 34-147 Case 3BE-9: Mass of Csl Released ot Containment . . ...............34-214 34-148 Case 3BE-9: Noble Gases Release .......... ..................34-215 34-149 Case 3BE-9: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . .34-216 34-150 Case 3BE-9: Non-Volatile Release . . . . . . . . ...... ....... ....34-217 34-151 Case 3BE-10: RCS Pressure and SG Pressure . . . . . . . . . ...... . . . . .34-218 34-152 Case 3BE-10: Loop 1 ADS Stage 4 Flows . . . . . . . . . .... .........34-219 34-153 Case 3BE-10: Accumulator Water Mass and CMT Water Mass ....... .34-220 34-154 Case 3BE-10: IRWST Flows . . . .......... ..................34-221 34-155 Case 3BE-10: Break Flows . . . . . . . . . . . ... .............. ...34-222 34-156 Case 3BE-10: Reactor Vessel Levels . . . . .... .. .. ........ ...34-223 34-157 Case 3BE-10: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-224 34-158 Case 3BE-10: Reactor Cavity Water Level and IRWST Water Level . . . . .34-225 34-159 Case 3BE-10: Loop Compartment and Valve Vault Water Levels . . . . . . .34-226 34-160 Case 3BE-10: Containment Pressure . . . . . .. ... ... ....... .. .34-227 34-161 Case 3BE-10: Containment Temperatures . . . . . . . . . ... ..........34-228 34-162 Case 3BE-10: Debris Mass . . . . . . . . . . . . . . . . . . ..............34-229 34-163 Case 3BE-10: Reactor Vessel-to-Cavity Water Heat Transfer . , . . . . . . . . .34-230 34-164 Case 3BE-10,: Hydrogen Generation .............. ........ ....34-231 34-165 Case 3BE-10: Mole Fraction Hydrogen in Valve Vault ...............34-232 34-166 Case 3BE-10: Mass of Csl Released to Containment . .......... .34-233 34-167 Case 3BE-10: Noble Gases Released . . . . . . . . . . . . . . ....... ....34-234 34-168 Case 3BE-10: Releases to Environment . . . . . .. . . . ...........34-235 34-169 Case 3BE-10: Non-Volatile Release ....... .... .......... ....34-236 34-170 Case 3BE-10: Gas Flow Rate Through Containment Failure Location ...34-237 34-171 Case 3BL-1: RCS Pressure and SG Pressure ... . . . . . . . . . . . . . . . . . 34-23 8 34-172 Case 3BL-1: Loop 1 ADS Stage 4 Flows . . . .....................34-239 34-173 Case 3BL-1: Accumulator Water Mass and CMT Water Mass ... ......34-240 34-174 Case 3BL-1: IRWST Flows . . . . ............. ... .... .. ...34-241 34-175 Case 3BL-1: Break Flows . ...... .. ..... ... ..... ...34-242 34-176 Case 3BL-1: Reactor Vessel Levels . . . . . ... . .. . . .........34-243 34-177 Case 3BL-1: Core Temperatures . . ........... . .. ..... ....34-244 34-178 Case 3BL-1: Reactor Cavity Water Level and IRWST Water Level . ....34-245 34-179 Case 3BL-1: Loop Compartment and Valve Vault Water Levels . . . .. ..34-246 4 34-180 Case 3BL-1: Containment Pressure . . . . ......... . ...........34-247 O
Ap i ,1997 [ Westingh00S8 oMp600\ prs \rev 9\pra-lof.wpfab lXvi j
____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ __u
i l
l t
,.~
Wi
( )
U LIST OF FIGURES (Cont.)
Fiore No. Title Page 34-181 Case 3BL-1: Containment Temperatures ..... ....................34-248 34-182 Case 3BL-1: Debris Mass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-24 9 34-183 Case 3BL-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-250 34-184 Case 3BL-1: Hydrogen Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-251 34-185 Case 3BL-1: Mass of Csl Released to Containment . . . . . . . . . . . ......34-252 34-186 Case 3BL-1: Noble Gases Released . . . . . . . . . . . . . . . ....... .....34-253 34-187 Case 3BL-1: Releases to Environment . . . . . . . . . . . . . . . ..........34-254 34-188 Case 3BL-1: Non-Volatile Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 255 34-189 Case 3BL-1: RCS Pressure and SG Pressure ............. ........34-256 34-190 Case 3BL-2: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . ..........34-257 34-191 Case 3BL-2: Accumulator Water Mass and CMT Water Mass . . . . . . . . . .34-258 34-192 Case 3BL-2: IRWST Flows . . . . . . . . . .........................34-259 34-193 Case 3BL-2: Break Flows . . . . . . . .......................... .34-260 34-194 Case 3BL-2: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-261 34-195 Case 3BL-2: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-262 34-196 Case 3BL-2: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-263 34-197 Case 3BL-2: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-264 34-198 Case 3BL-2: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-265 t
b] 3A199 34-200 Case 3BL-2: Containment Temperatures . . . . . . . . . . . . . . . . . .......34-266 Case 3BL-2: Debris Mass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 267 34-201 Case 3BL-2: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-268 34-202 Case 3BL-2: Hydrogen Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-269 34-203 Case 3BL-2: Mass of Csl Released to Containment . . . . . . . . . . . . . . . . .34-270 34 204 Case 3BL-2: Noble Gases Released . . . . . . . . . . . . . . . . . . ..........34-271 34-205 Case 3BL-2: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . . .34-272 34 206 Case 3BL-2: Non-Volatile Release . . . . . . . . . . . . . . . . . . ..........34-273 34-207 Case 3BL-3: RCS Pressure and SG Pressure .... ..................34-274 34-208 Case 3BL-3: Loop 1 ADS Stage 4 Flows . . . . . . . ........ ........34-275 34-209 Case 3BL-3: Accumulator Water Mass and CMT Water Mass . . .......34-276 34-210 Case 3BL-3: IRWST Flows . . . . . . . ...................... ...34-277 34-211 Case 3BL-3: Break Flows . . .................... ...........34-278 34-212 Case 3BL-3: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-279 ,34-213 Case 3BL-3: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-280 l 34-214 Case 3BL-3: Reactor Cavity, Water Level and IRWST Water Level . . . . . . .34-281 )34-215 Case 3BL-3: Loop Compartment and Valve Vault Water levels . . . . . . . . .34-282 34 216 Case 3BL-3: Containment Pressure .............................34-283 34-217 Case 3BL-3: Gas Flow Rate Through Containment Failure Location . . . . . .34-284 !
L 34-218 Case 3BL-3: Containment Temperatures .............. ........ .34-285 l l 34-219 Case 3BL-3: Debris Mass ...................................34-286 34-220 Case 3BL-3: Reactor Vessel-to-Cavity Water Heat Transfer . . . . .......34-287 34-221 Case 3BL-3: Hydrogen Generation . . . . . ........................34-288 m
(v I ENE Revision: 9 3 Westinghouse r&= 6 April 11,1997 b;yij c:\np600$rairev.9%pra-lof.wpf:lb
m .-
$ l LIST OF FIGURES (Cont.)
0 Firure No. Title Page 34-222 Case 3BL-3: Mole Fraction Hydrogen in Valve Vavit . . . . . . . . . . . . . . . .34-289 34-223 Case 3BL-3: Mass of CsI Released to Containment . . . . . . . . . . . . . . ...34-290 34-224 Case 3BL-3: Noble Gases Released . . . . . . . . . . . . . . . . . . . . . . . . . . ..34-291 34-225 Case 3BL-3: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . .34-292 34-226 Case 3BL-3: Non-Volatile Release ..... .......................34-293 34-227 Case 3BR-1: RCS Pressure and SG Pressure ......................34-294 34-228 Case 3BR-1: Loop 1 ADS Stage 4 Flows ................... ....34-295 34-229 Case 3BR-1: Accumulator Water Mass and CMT Water Mass . . . . . . . . . .34-296 34-230 Case 3BR-1: IRWST Flows . . . . . . . . . . . . . . . . . . ..............34-297 34-231 Case 3BR-1: B reak Flows . . . . . . . . . . . . . . . . . . . . ..............34-298 34-232 Case 3BR-1: Reactor Vessel Levels . . . . . . . . . . . . . . .......... ...34-299 34-233 Case 3BR-1: Core Temperatures . . . . . . . . . . . . . . . . ............. .34-300 34-234 Case 3BR-1: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-301 34-235 Case 3BR-1: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-302 34-236 Case 3BR-1: Containment Pressure . . . .........................34-303 34-237 Case 3BR-1: Containment Temperatures ................. .. .34-304 34-238 Case 3BR-1: Debris Mass . . . . . . . . . . ... .. . . . . . . . . . . . . . . . . . 34-3 05 34-239 Case 3BR-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-306 34-240 Case 3BR-1: Hydrogen Generation . . . . . . . . . . . . . . . . . . . . . . . . . ...34-307 34-241 Case 3BR-1: Mass of Csl Released to Containment . . . . . . . . . . . . . . . . . .34-308 34-242 Case 3BR-1: Noble Gases Released . . . . . . . . . . . . . .. . . . . . . . . . . .34-309 34-243 Case 3BR-1: Releases to Environment . . . . . ... . . . . . . . . . . . . . . . . .34-310 34-244 Case 3BR-1: Non-Volatile Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-311 34-245 Case 3C-1: RCS Pressure and SG Pressure . . . . . . . . . . . . . . . . . . . . . . . .34-312 34-246 Case 3C-1: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . . . ......34-313 34-247 Case 3C-1: Accumulator Water Mass and CMT Water Mass ....... . .34-314 34-248 Case 3C-1: IRWST Flows . . . . . . . . ................... ......34-315 34-249 Case 3C-1: Break Flows . . . . . .......... .... ........ . . . . .34-316 34-250 Case 3C-1: Reactor Vessel Levels . . . . . ................ .......34-317 34-251 Case 3C-1: Core Temperatures ...... ......... .... . . . . . . . . .34-318 34-252 Case 3C-1: Reactor Cavity Water Level and IRWST Water Level . . . . ...34-319 34-253 Case 3C-1: Loop Compartment and Valve Vault Water Levels . . . . ..34-320 34-254 Case 3C-1: Containment Pressure . .... .. . . ......... . .34-321 34-255 Case 3C-1: Containment Temperatures ......... . . . . . . . . . . . . .34-322 34-256 Case 3C 1: Debris Mass . ................... ....... ...34-323 34-257 Case 3C-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-324 34-258 Case 3C-1: Hydrogen Generation . .... ...... .. ...... ......34-325 34-259 Case 3C-1: Mass of CsI Released to Containment . . ......... ......34-326 34-260 Case 3C-1: Noble Gases Released . . . . . . . .... . .... .........34-327 34-261 Case 3C-1: Releases to Environment . . . . . . . . . . .. ..... ..... .34-328 Revision: 9 9
ENEl. T Westinghouse April 11,1997 mih owaccawv>praaof3rub lxviii
O M
U LIST OF FIGURES (Cont.)
Fleure No. Title Page 34-262 Case 3C-1: Non-Volatile Release .......... . . . ... .... . .34-329 34-263 Case 3D-1: RCS Pressure and SG Pressure ............... ... ...34-330 34-264 Case 3D-1: Loop 1 ADS Stage 4 Flows .. .......................34-331 34-265 Case 3D-1: Accumulator Water Mass and CMT Water Mass . ... ...34-332 34-266 Case 3D-1: IRWST Flows . ................ .. ... ....... .34-333 34-267 Case 3D-1: Break Flows .. ............. . .......... . . . .34-334 34-268 Case 3D-1: Reactor Vessel Levels . . . . . . ... ............. ...34-335 34-269 Case 3D-1: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . ....34-336 34-270 Case 3D-1: Reactor Cavity Water T.evel and IRWST Water Levels ......34-337 34-271 Case 3D-1: Loop Compartment and Valve Vault Water Levels . . . . . . . . . .34-338 34-272 Case 3D-1: Containment Pressure . . . . .......... . . . . .34-339 34-273 Case 3D-1: Co itainment Temperatures ......... ... .. . .... ..34-340 34-274 Case 3D-1: Debris Mass . . . . .... ........ ... ... ....34-341 34-275 Case 3D-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . ..... .34-342 34-276 Case 3D-1: Hydrogen Generation . . . . . . . . .. .. ... . ........34-343 34-277 Case 3D-1: Mass of Csl Released to Containment .. ...... ....34-344 34-278 Case 3D-1: Noble Gases Released . . . . . . ... .. . . .. ...... .34-345 34 279 Case 3D-1: Releases to Environment . . . . . ....... .. . . . . . . . . .34-346 g) i 34-280 Case 3D-1: Non-Volatile Release . . . . . . . . . . . . .... ........ .34-347 V 34-281 Case 3D-2: RCS Pressure and SG Pressure ...... .. ... . . . . . . . . . 34-34 8 34-282 Case 3D-2: Loop 1 ADS Stage 4 Flows .. ..... ........ .......34-349 34 283 Case 3D-2: Accumulator Water Mass and CMT Water Mass . . . . . . . . . . .34-350 34-284 Case 3D-2: IRWST Flows . . . . . . . . . . ... .... ....... ... . .34-351 34-285 Case 3D-2: Break Flows . . . ............... . . . . . . . . . . . . . . 34-3 5 2 !34-286 Case 3D-2: Reactor Vessel Levels . . . . . . . ................. ....34-353 l 34-287 Case 3D-2: Core Temperatures . . ... .. .. .... . . ... .. .34-354 I 34-288 Case 3D-2: Reactor Cavity Water Level and IRWST Water Level ......34-355 34-289 Case 3D-2: Loop Compartment and Valve Vault Water Levels . . . . .. ..34-356 34-290 Case 3D-2: Containment Pressure . . . . . ... ..... . .. . ...34-357 34-291 Case 3D-2: Gas Flow Rate 'Ihrough Containment Failure Location . . . .34-358 34-292 Case 3D-2: Containment Temperatures .... ... ..... ......... .34-359 34-293 Case 3D-2: Debris Mass .............. . .... .. . .. .. .34-360 l 34-294 Case 3D-2: Reactor Vessel-to-Cavity Water Heat Transfer . ........ .34-361 !34-295 Case 3D-2: Hydrogen Generation . . . . . . . . . . . . . . . ........... .34-362 l 34-296 Case 3D-2: Mole Fraction Hydrogen in Valve Vault . . . . . . . . .. .34-363 34-297 Case 3D-2: Mass of Csl Released to Containment .... . . .. . .34-364 34-298 Case 3D-2: Noble Gases Released . . . . . . . . . . . . ........ ..34-365 34-299 Case 3D-2: Releases to Environment . ........ . . .... .... ..34-366
!34-300 Case 3D-2: Non-Volatile Release . .... . ... ..... ...... .34-367 34-301 Case 6E 1: RCS Pressure and SG Pressure . . . . . . . . .. . . . .34-368 34-302 Case 6E-1: Passive RHR Heat Removal .. . .. .... .. ..... .34-369 O)
(
ENEL Revision: 9 Y W85tingh0USS ';;,it0llL=.
, April 11,1997 IXiX o Aap600\pra\rev_9'pra-lof.wpf:I b l
L
Es i
LIST OF FIGURES (Cont.)
O Firure No. Title Pa_ge 34-303 Case 3D-1: Break Flows . . . . . . . . . . . . . . . . . . . . . ........ . ...34-370 34-304 Case 3D-1: Liquid and Steam Flows through Failed-Open SG Safety Valve .34-371 34-305 Case 3D-1: Loop 1 ADS Stage 4 Flows ....................... .34-372 34-306 Case 3D-1: Accumulator Water Mass and CMT Water Mass . . . . . . . . . . .34-373 34-307 Case 3D-1: IRWST Flows . . . . . . . . . . . . . . . . . . . . .. ...........34-374 34-308 Case 3D-1: Reactor Vessel Levels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-375 34-309 Case 3D-1: Core Temperatures . . . . . . . . . . . ....................34-376 34-310 Case 3D-1: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-377 34-311 Case 3D-1: Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-378 34-312 Case 3D-1: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-379 34-313 Case 3D-1: Containment Temperatures ... ........... .. . . . . . . .34-380 34-314 Case 6E-1: Debris Mass ............ ...... ... . . . . . . . . . . . 34-3 81 34-315 Case 6E-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . 34-3 82 34-316 Case 6E-1. Hydrogen Generation . . . . ....................... .34-383 34-317 Case 6E-1: Mass of Csl Released to Containment . .. . .. . . . . . . . . . 34-3 84 34-318 Case 6E-1: Noble Gases Released . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-385 34-319 Case 6E-1: Releases to Environment . . . ................... . . . .34-386 34-320 Case 6E-1: Non-Volatile Release .... ................... . . . . .34-387 34-321 Case 6E-2: RCS Pressure and SG Pressure . . . . . . . . . . . . . . . . . . . . . . . 34 388 34-322 Case 6E-2: Passive RHR Heat Removal . . . . . . . . . . . ..... . . . . . . . .34-389 34-323 Case 6E-2: Break Flows . .............. .............. ....34-390 34-324 Case 6E-2: Liquid and Steam Flows through Failed-Open SG Safety Valve .34-391 34-325 Case 6E-2: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . ............ .34-392 34-326 Case 6E-2: Accumulator Water Mass and CMT Water Mass . . . . . . . . . . .34-393 34 327 Case 6E-2: IRWST Flows . . . . . . . . . . .................. .....34-394 34-328 Case 6E-2: Reactor Vessel I.evels . . . . . . . . . . . .. .... . . . . . . . . .34-395 34 329 Case 6E-2: Core Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-396 34-330 Case 6E-2: Reactor Cavity Water Level and IRWST Water Level . . . . . . . 34 397 34-331 Case 6E-2 Loop Compartment and Valve Vault Water Levels . . . . . . . . .34-398 34-332 Case 6E-2: Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .34-399 34-333 Case 6E-2: Containment Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . .34-400 34-334 Case 6E-2: Debris Mass ......... ...... . . . . . . . . . . . . . . . . . . .34-401 34-335 Case 6E-2: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . . .34-402 34-336 Case 6E-2: Hydrogen Generation ................... .... . . . . .34-403 34-337 Case 6E-2: Mass of Csl Released to Containment . . . . . . . . . . . . . . . . . .34-404 34-338 Case 6E-2: Noble Gases Released . . . . .................. .. ...34-405 34-339 Case 6E-2: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . . .34-406 34-340 Case 6E-2: Non-Volatile Release ............. . . . . . . . . . . . . . . . . 34 407 34-341 Case 6E-3: RCS Pressure and SG Pressure . . . . . . . . . . . . . . . . . . . . . . .34-408 34-342 Case 6E-3: Passive RHR Heat Removal . . . . . . . . . . . ...... . . ..34-409 Revision: 9 ENEL April 11,1997 gu.g:n 3 W8Stinghouse o:\ap60opaVev.9Wlof.wpf.lb lxx
E l
O n
v LIST OF FIGURES (Cont.)
Figure No. Title Page 34-343 Case 6E-3: B reak Flows . . . . . . . . . . . . . . . . . . . . . ...............34-410 34-344 Case 6E-3: Liquid and Steam Flows through Failed-Open SG Safety Valve .24-411 34-345 Case 6E-3: Loop 1 ADS Stage 4 Flows . . . . . . ........... .......34-412 34-346 Case 6E-3: Accumulator Water Mass and CMT Water Mass .. . . . . . . .34-413 34-347 Case 6E-3: IRWST Flows . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .34-414 34-348 Case 6E-3: Reactor Vessel Levels .......... ...................34-415 34-349 Case 6E-3: Cote Temperatures . . . . . . . . . . ............ ........34-416 34 350 Case 6E-3: Reactor Cavity Water Level and IRWST Water Level . . . ...34-417 34-351 Case 6E-3: Loop Companment and Valve Vault Water Levels . . . . . . ...34-418 34-352 Case 6E-3: Containment Pressure . . . . . . . . ........... .........34-419 34-353 Case 6E-3: Containment Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . .34-420 34-354 Case 6E-3: Debris Mass ...... ................... .. . . . .34-421 34-355 Case 6E-3: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . .34-422 34-356 Case 6E-3: Hydrogen Generation . ................ . .. .34-423 34-357 Case 6E-3: Mass of Csl Released to Containment . . ................34-424 34-358 Case 6E-3: Noble Gases Released . . ................. . ... ..34-425 34-359 Case 6E-3: Releases to Environment . . . . . .......................34-426 34-360 Case 6E-3: Non-Volatile Release ...... ......... . .. . . . . . . 34 427 34-361 Case 6L-1: RCS Pressure and SG Pressure . . . . . . . . . . . . . . .34-428
[V_T 1
34-362 Case 6L-1: Loop 1 ADS Stage 4 Fjows . . . . . .............. . . . . .34-429 34-363 Case 6L-1: Break Flows . . . ....... .... ....................34-430 34-364 Case 6L-1: Liquid and Steam Flows through Failed-Open SG Safety Valve .34-431 34 365 Case 6L-1: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . . . . . . . . . . .34-432 34-366 Case 6L-1: Accumulator Water Mass and CMT Water Mass ....... ...34-433 34-367 Case 6L-1: IRWST Flows . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . 34-4 34 34-368 Case 6L-1: Reactor Vessel Levels . . . . . ................. .... .34-435 34-369 Case 6L-1: Core Temperatures . . .... .. ............ . . . . . . .34-436 34-370 Case 6L-1: Reactor Cavity Water Level and IRWST Water Level . . . . . . .34-437 34-371 Case 6L-1: Loop Companment and Valve Vault Water Levels . . . . . . . . .34-438 34-372 Case 6L-1: Containment Pressure . . . . . . . . . . ......... .. . . . .34-439 34-373 Case 6L-1: Containment Temperatures . . . . . . . . . . . . . . . . . . . . . . . . . . .34-440 34-374 Case 6L-1: Debris Mass ............................. .... .34-441 34-375 Case 6L-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . ... ...34-442 34-376 Case 6L-1: Hydrogen Generation . . . . . . . . . . .... ......... ...34-443 34-377 Case 6L-1: Mass of Csl Released to Containment . . . . . . . . . . . . . . . . . . .34-444 34-378 Case 6L-1: Ncble Gases Released . . .... . ............ ........34-445 34-379 Case 6L-1: Releases to Environment . . . ............... ........34-446 34-380 Case 6L-1: Non-Volatile Release . ..... ........... ...........34-447 34-381 Case 1 AP-1: RCS Pressure and SG Pressure .. ............... ..34-448 l 34-382 Case 1AP-1: Passive RHR Heat Removal ... .... .... . ..34-449
!34-383 Case I AP-1: Break Flows . . . . . ...................... . . . . . .34-450 i
C ..
ENEl. Revision: 9 T Westinghouse cath. April 11,1997 IXXi o:\ap600\pra\rev_9\pra-lof.wpf:1b L - - _ -_ _
.-ga,,.o l LIST OF FIGURES (Cont.)
0 Firure No. Title Page 34-384 Case 1 AP-1: Liquid and Steam Flows through Failed-Open SG Safety Valve .34-451 34-385 Case 1 AP-1: Loop 1 ADS Stage 4 Flows . . . . . . . . . . . . . .......... .34-452 34-386 Case 1 AP-1: Accumulator Water Mass and CMT Water Mass . . . . . . . ..34-453 34-387 Case 1 AP-1: IRWST Flows . ............ . . . . . . . . . . . . . . . . . . 34-4 54 34-388 Case 1 AP-1: Reactor Vessel Levels . . . . . . . ...... . . . . . . . . . . . . . 34-4 55 34 389 Case 1 AP-1: Core Temperatures . . . . . . . . . . . . ................ .34-456 34-390 Case 1 AP-1: Reactor Cavity Water Level and IRWST Water Level . . . . . .34-457 34-391 Case I AP-1: Loop Compartment and Valve Vault Water Levels . . . ...34-458 34-392 Case 1 AP-1: Containment Pressure . . . . . . . . . . . . .. .. .. .... ..34-459 34-393 Case 1AP-1: Containment Temperatures ........ . .. . . . .. .34-460 34-394 Case 1 AP-1: Debris Mass ...... . ......... . ..... . . . . .34-461 34-395 Case 1AP-1: Reactor Vessel-to-Cavity Water Heat Transfer . ... ... ..34-462 34-396 Case 1 AP-1: Hydrogen Generation . . . . . . ... ... . ... ....34-463 34-397 Case 1 AP-1: Mass of Csl Released to Containment . . . . . . . . . . . . .... .34-464 34-398 Case 1 AP-1: Noble Gases Released . .. ........... .... ... .34-465 34-399 Case 1 AP-1: Releases to Environment . . . . . .... . . . ... ... .34-466 34-400 Case 1 AP-1: Non-Volatile Release . ... . . .. .. . . ...34-467 34-401 Case I A-1: RCS Pressure and SG Pressure ..... ... . .... . . . . .34-468 34-402 Case 1 A-1: Passive RHR Heat Removal . . . . . . ..... . ....... ...34-469 34-403 Case IA-1: Break Flows . ... .............. ... ...... ...34-470 34-404 Case I A-1: Liquid and Steam Flows through Failed-Open SG Safety Valve .34-471 34-405 Case 1 A-1: Loop 1 ADS Stage 4 Flows . . .. .... .... . .. .34-472 34-406 Case 1 A-1: Accumulator Water Mass and CMT Water Mass .... . .. .34-473 34-407 Case 1 A-1: IRWST Flows . . . .. ............ .......... ..34-474 34-408 Case I A-1: Reactor Vessel Levels . . . ....... ... ......... .34-475 34-409 Case I A.1: Core Temperatures . . . . ........ .. .. ......... . .34-476 34-410 Case I A-1: Reactor Cavity Water Level and IRWST Water Level . . . . ...34-477 34-411 Case I A-1: Loop Companment and Valve Vault Water Levels . . . . . . . ..34-478 34-412 Case I A-1: Containment Pressum . . . . . . . . . . . . .... . . . . . . . . . . .34-479 34-413 Case I A-1: Containment Temperatures .... ... . ..... . ..34-480 34-414 Case I A-1: Debris Mass . . ..... ........... . .. ..... .. .34-481 34-415 Case I A-1: Reactor Vessel-to-Cavity Water Heat Transfer . . . . . . . . . . . .34-482 34-416 Case 1 A-1: Hydrogen Generation . ...... ......... .... ... .34-483 34-417 Case I A-1: Mass of Csl Released to Containment . ..... ...... . .34-484 34-418 Case IA-1: Noble Gases Released . . . . . . . . .... .. . ......... .34-485 34-419 Case I A-1: Releases to Environment . . . . . . . . . . . . . . . . . . . . . . . . . .34-486 34-420 Case 1 A-1: Non-Volatile Release ......... .... . ... .. . .34-487 35-1 Containment Event Tree . . ..... ............ .. .. ..... . . . 35-30 Revision: 9 0
ENEL April 11,1997 mm- W85tiligh00S8 c:\ap600pr:Wv 9\pra-lof2pf:lb IXXii
1 l
(
s l
LIST OF FIGURES (Cont.)
Figure No. Title Page 36-1 AP600 Accident Class I A Base Case for Node DP Success -- RCS Pressure . . . 36-8 36-2 AP600 Accident Class I A Base Case for Node DP Success -- Core.
Exit Gas Temperature . . . ... ..... .. ... . ... . . ....... 36-9 36-3 AP600 Accident Class I A Base Case for Node DP Success -- Steam Generator Tube Creep Damage ......... ... ................ . 36-10 38-1 AP600 DVI Break with Valve Vault Flooding Containment
. I Compartment Water Levels . ..... .. .................... . . . 38-7 39-1 Mini ACOPO Bowl for Testing . . . . . ....... ...... ... .... . 39-17 39-2 ACOPO Testing Arrangement . . . . . . . . ....... ........ .... 39-18 39-3 ULPU Testing Arrangement ............................. . .. 39-19 39-4 AP600 Passive Core Cooling System . . . . ................ .. . .. 39-20 39-5 Containment Floodable Region . . . . . . . . . . . . . . . . . . . . . . ..... . . 39-21 39-6 Containment Floodable Region - Exploded View . ........... ... .. 39-22 39-7 AP600 Cavity Flooding Rate ........... .. .. ...... ... . .. 39-23 39-8 Schematic of Reactor Vessel and Insulation . . . . . . . ....... ......... 39-24 O
Q 39-9 ULPU Test Configuration . . . . . . . . . . . ............. ......... 39-25 40-1 AP600 Containment Schematic . . . ..............................40-3 40-2 AP600 Passive Containment Cooling ........... ....... . . . . . . . . 40-4 '
40-3 Containment Pressure Prediction .................................40-5 41-1 Combustion Cornpleteness for Nevada Test Site Premixed Combustion Tests (Reproduced from Ref. 41-3) . . . . . . . . . . .... . . 41-91 l 41-2 The Flammability Floor Domain for Upward Flame Propagation for H2-Air-H O2 (Vapor) Mixtures. The Flammability Limit ,
Curve is Superimposed on the Isobaric Controus of Calculated !
Adiabatic Explosion Pressure (from Ref. 41 1$) . .......... ......... 41-92 j 41-3 ' Theoretical Adiabatic, Constant-Volume Combustion Pressures l of Hydrogen-air Mixtures (Reproduced from Ref. 41-5) ...... . . . . . . . . . 41 -93 ;
41-4 Typical Calculated Versus Measured Axial Power Distribution . . . . . . . . . . . . 41-94 j 41-5 Normalized Power Density Distribution Near Middle of Life, j Unrodded Core Hot Full Power, Equilibrium Xenon . . . . . . . . . . . ...... 41-95 !
41-6 Reactor Vessel Wa.er Level in AP600 Hydrogen Cases ........... . . 41 -% 1 41-7 Fraction of Cladding Reacted in AP600 Hydrogen Generation Cases ..... . 41-97 41-8 Containment Pressure for AP600 Hydrogen Cases . . . . . . . . . . . . . . . . . . . 41-98 41-9 AP600 Containment Water Level - DVI Line Break with No Valve Vault Flooding . . . . . . . . . .................... .. ... . 41-99 41-10 AP600 Containment Water Level - DVI Line Break with Valve Vault Flooding . ...... ......... . . . . . . . . . . . . . . . . . . . . . . . . 41 - 100 q Accident Class 3BE Early Detonation Decomposition Event Tree . ....41-101 41-11 .
I Revision: 10 l [ W65tif)ghouSE h_ ixxiii June 30,1997 04*Na*v iopr .iorwpr.:b
1 N O .
LIST OF FIGURES (Cont.)
fjgpre No. This Page 41-12 Accident Class 3BL Early Detonation Decomposition Event Tree . . . . . . . . . 41 102 41-13 Accident Class 3BR/3C Early Detonation Decomposition Event Tree . ....41-103 41-14 Accident Class 3D/lD Early Detonation Decomposition Event Tree . . . . . . .41-104 41-15 Accident Class LAP Early Detonation Decomposition Event Tree . . . . . . . . .41-105 41-16 Detonation Cell Width versus Equivalence Ratio for Test Series #1 ,
(H 2-Air at P=1 atm. T=20*C) (Reproduced from Reference 41-4) . . . . . . . . .41-106 41-17 Detonation Cell Width versus Equivalence Ratio for Test Series #3. 4 (H 2-Air-H2 O at p,=41.6 moles /m', T=100*C) (Ref. 41-4) . . . . . . . . . . . . . .41-107 l 41-18 Detonation Cell Width versus Temperature Ratio for Test Series #6. 7 {
(H 2-Air at X,e=0.17) (Ref. 41-4) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-108 1 41-19 AP600 Adiabatic Shell Temperature for Hydrogen Burn . . . . . . . . . . . . . . .41-109 41-20 AP600 Hydrogen Deflagmtion Analysis - Non-Reflood Case Hydrogen Generation Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 -110 41-21 AP600 Hydrogen Deflagration Analysis - Non-Reflooded Case Pre-Burn Pressure Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 - 1 1 1 41-22 AP600 Hydrogen Deflagration Analysis - Non-Reflooded Case Probability Distribution of AICC Peak Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-112 41-23 AP600 Hydrogen Deflagration Analysis - Early-Reflood Case Hydrogen Generation Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-113 41 24 AP600 Hydrogen Deflagration Analysis - Early-Reflood Case Pre-Bum Pressure Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-114 41-25 AP600 Hydrogen Deflagration Analysis - Early Reflood Case Probability .
Distnbution of AICC Peak Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-115 41 26 AP600 Hydrogen Deflagration Analysis - Late-Reflood Case Hydrogen Generation Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-116 41-27 AP600 Hydrogen Deflagration Analysis - Late-Reflood Case Pre Bum Pressure Probability Distribution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-117 41-28 AP600 Hydrogen Deflagration Analysis - Late-Reflood Case Proability Distribution of AICC Peak Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . .41-118 41-29 Reflooded 3BE Case - Lower Flammability Limit Sensitivity . . . . . . . . . .41-119 41-30 Reflooded 3BE Case - Steam Inerting Limit Sensitivity . . . . . . . . . . . . . .41-120 41-31 Accident Class 3BE Intermediate Detonation Decomposition Event Tree . . . .41-121 41-32 Accident Class 3BL Interrraxiiate Detonation Decomposition Event Tree . . . .41-122 41-33 Accident Class 3BR 3C, 3D LAP Intermediate Detonation Decomposition Event Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 - 123 42-1 AP600 Containment Fragility at Contamment Temperature of 400*F . . . . . . . 4213 42-2 AP600 Containment Fragility at Containment Temperature of 331*F . . . . . . . 42-14 43-1 Contribution of Accident Class to Large Release Frequency . . . . . . . . . . . . 43-15 2 43-2 Contribution of Cominant Containment Event Tree Sequences to Large Release Frequency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3- 1 5 3 Apri *
,1997
., D U88
~c l V
LIST OF FIGURES (Cont.)
Figure No. Title Eage 43-3 Containment Event Tree for 3BE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .43-154 43-4 Containment Event Tree for 3BL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .43-155 43-5 Containment Event Tree for 3BR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .43-156 43-6 Containment Event Tree for 1 A . . . . ......................... .43-157 43-7 Containment Event Tree for I AP . . . . . . . . . . . . ...................43-158 43-8 Containment Event Tree for 3A . . . . . . . ............ ... . . . . . . .43-159 43-9 Containment Event Tree for 3C . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .43-160 43-10 Containment Event Tree for 3D ...... ... . .... . . . . . . . . . . .43-161 43-11 Containment Event Tree for 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . .43-162 44-1 AP600 MAAP4 Containment Model Nodalization . . . . . . . . . . . . . . .... 44-12 45-1 Release Category IC Release Fraction Comparison Noble Gases . . ....... . 45-17 45-2 Release Category IC Release Fraction Comparison Csl . . . . . . . . . . . . . . . . 45-18 i 45-3 Release Category IC Release Fraction Comparison Non-Volatiles . . . . . . . . . 45-19 45-4 Case 3BE-4: IC 72-Hour Release Fraction Noble Gases (Xe, Kr) ..... ... 45-20 45-5 Case 3BE-4: IC 72-Hour P/ case Fraction Csl . . . .. ....... . . . . . . 45-21 l 45-6 Case 3BE-4: IC 72-Hour ;elea:e Fraction TeO 2 ........... ... . . 45-22
/ g)
, 45-7 Case 3BE-4: IC 72-Hour Release Fraction Non-Volatiles (SrO) .. . . . . . . . 4 5-23 i
V 45-8 Case 3BE-4: IC 72-Hour Release Fraction moo2 . . . . . . . . . . . . . . . . . . . 4 5-24 l 45-9 Case 3BE-4: IC 72-Hour Release Fraction CsOH . . . . ...... . . . . . . . 45-25 ;
45-10 Case 3BE-4: IC 72-Hour Release Fraction BaO . . .. ............... 45-26 45-11 Case 3BE-4: IC 72-Hour Release Fraction La,,0 3 .............. ... . 45-27 45-12 Case 3BE-4: IC 72-Hour Release Fraction CeO2 ........ .. ....... . 45-28 ;
45-13 Case 3BE-4: IC 72-Hour Release Fraction Sb . . . . . . . . . . . . . . . . . . . . . . 45-29 l 45-14 Case 3BE-4: 1C 72-Hour Release Fraction Te2 . . ................... 45-30 45-15 Case 3BE-4: IC 72-Hour Release Fraction UO 2 . . . . . . . . . . . . . . . . . . . 4 5-31 45-16 Release Category BP Release Fraction Comparison Noble Gases . . . . . . . . . 45-32 45-17 Release Category BP Release Fraction Comparison Csl . . . . . . . . . . ..... 45-33 45-18 Release Category BP Release Fraction Comparison Non-Volatiles ......... 45-34 45-19 Case I A-1: BP 72-Hour Release Fraction Noble Gases (Xe, Kr) . . . . . . . . . . 45-35 l
45-20 Case I A-1: BP 72-Hour Release Fraction Csl . . . . . . . . . . . . . . . . . . . . . . 45-36 45-21 Case 1 A-1: BP 72 Hour Release Fraction TeO 2 . . . . . . . . . . . . . . ...... 45-37 45-22 Case I A-1: BP 72-Hour Release Fraction Non-Volatiles (SrO) . . . . . . . . . . . 45-38 l 45-23 Case IA-1: BP 72-Hour Release Fraction moo 2 ... . . . . . . . . . . . . . . . . 4 5-3 9 45-24 Case 1 A-1: BP 72-Hour Release Fraction CsOH . . . . . . . . . . . . . . . . . . . . 45-40 45-25 Case I A-1: BP 72-Hour Release Fraction Ba0 ...... ......... .. 45-41 45-26 Case I A-1: BP 72-Hour Release Fraction La2 03 ....... . . . . . . . . . . . . 4 5-42 45 27 Case I A-1: BP 72-Hour Release Fraction CeO 2 . . . . . . . . . . . . . . . . . . . . . 45-43 45-28 Case 1 A-1: BP 72-Hour Release Fraction Sb . . . . . . ..... ......... . 45-44 45-29 Case 1 A-1: BP 72-Hour Release Fraction Te2 ......... ...... ... . 45-45 T Westinghouse $k,,. Ap il 11, IXXv c:\ap60Wra\rev_9\pra-lof.wpf.lb i
EN
! LIST OF FIGURES (Cont.)
O l
l Firure No. Title Page 45-30 Case I A-1: BP 72-Hour Release Fraction UO2 ............... . . . . . 45-46 45-31 Case 3BE-5: Clair 72-Hour Release Fraction Noble Gases (Xe, Kr) . . . . . .. 45-47 45-32 Case 3BE-5: Clair 72-Hour Release Fraction Csl . . . . . . . . .. ..... . 45-48 45-33 Case 3BE-5: Clair 72-Hour Release Fraction TeO 2 . . . . . . . . . . . . . . . . . . 4 5 -4 9 45-34 Case 3BE-5: Clair 72-Hour Release Fraction Non-Volatiles (SrO) . . . . .. 45-50 45-35 Case 3BE-5: Clair 72-Hour Release Fraction moo 2 . . . . . . . . . . . . . . . . . . 4 5-51 45-36 Case 3BE-5: Clair 72 Hour Release Fraction CsOH . ......... . . . . . 45-52 45-37 Case 3BE-5: Clair 72 Hour Release Fraction Ba0 . . . . . . ..... . . . . 45-53 45-38 Case 3BE-5: Clair 72-Hour Release Fraction La 2O3 ............. ... . 45-54 45-39 Case 3BE-5: Clair 72-Hour Release Fraction CeO2 . ..... ... .. . 45-55 45-40 Case 3BE-5: Clair 72-Hour Release Fraction Sb . .. .... .. . . . . 45-56 45-41 Case 3BE-5: Clair 72-Hour Release Fraction Te2 .............. .. . 45-57 45-42 Case 3BE-5: Clair 72-Hour Release Fraction UO 2 . .... . . .. . . . . 45-58 45-43 Release Category CFE Release Fraction Comparison Noble Gases . . . . . . . . 45-59 45-44 Release Category CFE Release Fraction Comparison CsI . . . . .... ... . 45-60 45-45 Release Category CFE Release Fraction Comparison Non-Volatiles ... . . . 45-61 45-46 Case 3BE-8: CFE 72-Hour Release Fraction Noble Gases (Xe, Kr) . . . . . . . 45-62 45-47 Case 3BE-8: CFE 72-Hour Release Fraction UO2 ......... . ..... . 45-63 45-48 Case 3BE-8: CFE 72-Hour Release Fraction TeO 2 ........ ... .. .. . 45-64 45-49 Case 3BE-8: CFE 72. Hour Release Fraction Non Volatiles (SrO) . . .. 45-65 45-50 Case 3BE-8: CFE 72-Hour Release Fraction moo2 ...... .... .. . . . 45-66 45-51 Case 3BE-8: CFE 72-Hour Release Fraction CsOH . . . . . . . . . . . . . . . . . . 45-67 45-52 Case 3BE-8: CFE 72-Hour Release Fraction BaO .......... .. ... . 45-68 45-53 Case 3BE-8: CFE 72-Hour Release Fraction La,,0 3 ....... .. . . . . . 45-69 45-54 Case 3BE-8: CFE 72-Hour Release Fraction CeO2 ........ . . . . . . . 45-70 45-55 Case 3BE-8: CFE 72-Hour Release Fraction Sb . . . . . . . . . . . . . . . . . . 45-71 45-56 Case 3BE-8: CFE 72-Hour Release Fraction Te2 .. ................ 45-72 45-57 Case 3BE-8: CFE 72-Hour Release Fraction UO2 ............... . . . 45-73 45-58 Release Category CFI Release Fraction Comparison Noble Gases . . . . . . .. 45-74 45-59 Release Category CFI Release Fraction Comparison Csl ... ....... . 45-75 45-60 Release Category CFI Release Fraction Comparison Non-Volatiles . . . . . . . . 45-76 45-61 Case 3BE-9: CFI 72-Hour Release Fraction Noble Gases (Xe, Kr) . ... . 45-77 45-62 Case 3BE-9: CFI 72-Hour Release Fraction Csl . .. ........ . . . . . . . 45-7 8 45-63 Case 3BE-9: CFI 72-Hour Release Fraction TeO2 ......... . . . . . . . . 45-79 45-64 Case 3BE-9: CFI 72-Hour Release Fraction Non-Volatiles (SrO) . . . . . . . . . 45-80 45-65 Case 3BE-9: CFI 72-Hour Release Fraction moo 2 . ... . . . . . . . 45-81 45-66 Case 3BE-9: CFI 72-Hour Release Fraction CsOH . . ...... . .. ... 45-82 45-67 Case 3BE-9: CFI 72-Hour Release Fraction BaO . . . . . . . . . ... . . . 45-83 45-68 Case 3BE-9: CFI 72-Hour Release Fraction2 La 3 0 . . . . . . . . . . . . . . . . . . 45-84 45-69 Case 3BE-9: CFI 72-Hour Release Fraction CeO2 .. ............. .. 45-85 45-70 Case 3BE-9: CFI 72-Hour Release Fraction Sb ........... . . .. 45-86 Revision: 9 9
ENEl.
April 11,1997 lrAuts,., 3 We51righ0Use o:\ap600\prairev.9%pra-lof.wpf:1b I n vi
I q
i V
LIST OF FIGURES (Cont.)
Firure No. Title _P_ age 45-71 Case 3BE-9: CFI 72-Hour Release Fraction Te2 . . . . . . ... .......... 45-87 45-72 Case 3BE-9: CFI 72-Hour Release Fraction UO2 ....................45-88 45-73 Case 3BE-10: CFL 72-Hour Release Fraction Noble Gases (Xe, Kr) . . . . . 45-89 45-74 Case 3BE-10: CFL 72-Hour Release Fraction Csl . . . . . . . . . . . . . . .... 45-90 45-75 Case 3BE-10: CFL 72-Hour Release Fraction TeO 2 ............. . . . . 45-91 J 45-76 Case 3BE-10: CFL 72-Hour Release Fraction Non-Volatiles (SrO) . . . . . . . . 45-92
{
45-77 Case 3BE-10: CFL 72 Hour Release Fraction moo 2 ....... ....... . 45-93 45-78 Case 3BE-10: CFL 72-Hour Release Fraction CsOH . . . . . . . . ....... . 45-94 -
45-79 Case 3BE-10: CFL 72-Hour Release Fraction BaO . . . . .. ........ 45-95 45-80 Case 3BE-10: CFL 72-Hour Release Fraction 2 3 La 0 . . . . . . . . . ........ 45-96 45-81 Case 3BE-10: CFL 72.-Hour Release Fraction CeO2 ..... . . . . . . . . . . 4 5-97 45-82 Case 3BE-10: CFL 72-Hour Release Fraction Sb . . . . . . . . . . . . . . . . . . . 4 5-9 8 45-83 Case 3BE-10: CFL 72-Hour Release Fraction Te2 ............ ... .. 45-99 45-84 Case 3BE-10: CFL 72-Hour Release Fraction UO 2 . . . . . . . ... . . . .45-100 '
45-85 IC 72-Hour Direct Release Sensitivity Noble Gases (Xe, Kr) . . . . . . . . . . .45-101 45-86 IC 72-Hour Direct Release Sensitivity Csl . . . . . . . . ................45-102 ,
45-87 IC 72-Hour Direct Release Sensitivity TeO 2 . . . . . . . . . . . . . . . . . . . . . . 4 5 - 103 l
,, 45-88 IC 72-Hour Direct Release Sensitivity Non-Volatiles (SrO) .. . . . . . . . .45-104 j ) 45-89 IC 72-Hour Direct Release Sensitivity moo 2 ........ ..... . . . . .45-105 i l# ' -- 45 90 IC 72-Hour Direct Release Sensitivity CsOH . . . . ..................45-106 45-91 IC 72-Hour Direct Release Sensitivity BaO . . . . ... ....... . . . .45-107 45-92 IC 72-Hour Direct Release Sensitivity La,,03 . ....... .............45-108 45-93 IC 72-Hour Direct Release Sensitivity CeO 2 . . . . ...................45-109 45-94 IC 72-Hour Direct Release Sensitivity Sb . . . . . . . . . . . . . . . . . . . . . 4 5- 1 10 45-95 IC 72-Hour Direct Release Sensitivity Te2 ..... .......... . . . . . . . 45 111 45-96 IC 72-Hour Direct Release Sensitivity 'UO2 ........ ..... . . . . . . . .45-112 45-97 Case 3BE-4: FRPAT Sensitivity on Release Fraction Noble Gases . . . ...45-113 45-98 Case 3BE-4: FPRAT Sensitivity on Release Fraction CsI .............45-114 45-99 Case 3BE-4: FPRAT Sensitivity on Release Fraction TeO 2 ... . . . . . . .45-115 45-100 Case 3BE-4: FPRAT Sensitivity on Release Fraction SrO . . . . . . . . . . . .45-116 j 45-101 Case 3BE-4: FPRAT Sensitivity on Release Fraction moo2 .. ...... .45-117 45-102 Case 3BE-4: FPRAT Sensitivity on Release Fraction CsOH . . . . . . . . . . .45-118 45-103 Case 3BE-4: FPRAT Sensitivity on Release Fraction Ba0 . . . . . . . . . . . .45-119 45-104 Case 3BE-4: FPRAT Sensitivity on Release Fraction La 2O3 ... . .....45-120 ,45-105 Case 3BE-4: FPRAT Sensitivity or. Release Fraction CeO 2 . . . . . . . . . . . .45-121 45-106 Case 3BE-4: FPRAT Sensitivity en Release Fraction Sb . . . . . . . . . . . . . .45-122 l 45-107 Case 3BE-4: FPRAT Sensitivity on Release Fraction Te2 ..... . .....45-123 45-108 Case 3BE-4: FPRAT Sensitivity on Release Fraction UO2 . . ...........45-124 45-109 Case 3BE-4: FAERDC Sensitivity on Release Fraction Noble Gases .... .45-125 45-110 Case 3BE-4: FAERDC Sensitivity on Release Fraction Csl . . . . . ......45-126 45-111 Case 3BE-4: FAERDC Sensitivity on Release Fraction TeO 2 . . . . . . . . . . .45-127
)
(A)
%d Revision: 9 ENE T Westinghouse W- April 11,1997 1xxvii osp60@mwv.9m-ior.wpt:ib
F"$
LIST OF FIGURES (Cont.)
9 Figure No. Title hge 45-112 Case 3BE-4: FAERDC Sensitivity on Release Fraction SrO ............45-128 45-113 Case 3BE-4: FAERDC Sensitivity on Release Fraction moo 2 ..... . .45-129 45-114 Case 3BE-4: FAERDC Sensitivity on Release Fraction CsOH . . . . . . .45-130 45-115 Case 3BE-4: FAERDC Sensitivity on Release Fraction Ba0 . . . .......45-131 45-116 Case 3BE-4: FAERDC Sensitivity on Release Fraction La 2O3 ... . .45-132 45-117 Case 3BE-4: FAERDC Sensitivity on Release Fraction CcO2 .... ... .45-133 45-118 Case 3BE-4: FAERDC Sensitivity on Release Fraction Sb . . . . . . . ... .45-134
)
J 45-119 Case 3BE-4: FAERDC Sensitivity on Release Fraction Te2 . . . . . . . .. .45-135 45-120 Case 3BE-4: FAERDC Sensitivity on Release Fraction UO 2 ....... ...45-136 49-1 Population Whole Body Dose BP Source Term,24 Hours . ... . . . . . . . . 49-20 49-2 Population Whole Body Dose BP Source Term,72 Hours . . . . ........ . 49-20 49-3 Site Boundary Whole Body Dose BP Source Term,24 Hours .......... 49-21 49-4 Site Boundary Whole Body Dose BP Source Term,72 Hours .. .. . . . . 49-21 49-5 Site Boundary Red Bone Marrow Dose BP Source Term,24 Hours .. ... . 49 22 49-6 Site Boundary Red Bone Marrow Dose BP Source Term,72 Hours . . . . 49-22 49-7 Site Boundary Thyroid Dose BP Source Term,24 Hours . . . . . . . .. . . 49-23 49-8 Site Boundary Thyroid Dose BP Source Term,72 Hours . . . . . . . . . . . .. 49-23 49-9 Population Whole Body Dose CFE Source Term,24 Hours . . . . ....... . 49-24 49-10 Population Whole Body Dose CFE Source Term,72 Hours . . . . . . . . .... 49-24 49-11 Site Boundary Whole Body Dose CFE Source Term,24 Hours .... .. . 49-25 49-12 Site Boundary Whole Body Dose CFE Source Term,72 Hours . .. . . . 49-2S 49-13 Site Boundary Red Bone Marrow Dose CFE Source Term,24 Hours . .. . 49-26 49-14 Site Boundary Red Bone Marrow Dose CFE Source Term,72 Hours .... 49-26 49-15 Site Boundary Dyroid Dose CFE Source Tenu,24 Hours . . . . . . . . . . . . . . 49-27 49-16 Site Boundary Thyroid Dose CFE Source Term,72 Hours ...... . . . 49-27 49-17 Population Whole Body Dose CFI Source Term,24 Hours ... ....... . 49-28 49-18 Population Whole Body Dose CFI Source Term,72 Hours ...... .. . 49-28 49-19 Site Boundary Whole Body Dose CFI Source Term,24 Hours . . . . . . . . . . 49-29 49-20 Site Boundary Whole Body Dose CFI Source Term,72 Hours . ... ... 49-29 49-21 Site Boundary Red Bone Marrow Dose CFI Source Term,24 Hours . . . . . . 49-30 49-22 Site Boundary Red Bone Marrow Dose CFI Source Term,72 Hours . . .. 49-30 49-23 Site Boundary Byroid Dose CFI Source Term,24 Hours . . . . . . . . . . . 49-31 49-24 Site Boundary Byroid Dose CFI Source Tenn,72 Hours . . ..... .. 49 31 49-25 Population Whole Body Dose CFL Source Tenn,24 Hours . . . . . . . . . 49-32 49-26 Population Whole Body Dose CFL Source Term,72 Hours . . . . . ... . 49-32 49-27 Site Boundary Whole Body Dose CFL Source Term,24 Hours ....... .. 49-33 49-28 Site Boundary Whole Body Dose CFL Source Term,72 Hours ...... . 49-33 49-29 Site Boundary Red Bone Marrow Dose CFL Source Term,24 Hours . . . . 49-34 49-30 Site Boundary Red Bone Marrow Dose CFL Source Term,72 Hours .. . 49-34 49-31 Site Boundary Dyroid Dose CFL Source Term,24 Hours . . . . ..... . . 49-35 O
Revision: 9 ENEL mh Westinghouse April 11,1997 owanpovevym or.wprJb a lxxviii
1 I
D (V
LIST OF FIGURES (Cont.)
1 Figure No. Title _P_ age 49-32 Site Boundary Thyroid Dose CFL Source Term,72 Hours . . . . . .. . . . . . 49-35 1 49-33 Population Whole Body Dose CI Source Term,24 Hours ...... . . . . . . . 49-36 l 49-34 Population Whole Body Dose CI Source Term,72 Houn ... ...... . . 49-36 49-35 Site Boundary Whole Body Dose CI Source Term. 24 Hours . . . . . . . . . . . . 49-37 49-36 Site Boundary Whole Body Dose CI Source Term,72 Hours . . .. . . . . . . 49-37 49-37 Site Boundary Red Bone Marrow Dose Ci Source Term,24 Hours . . . . . . . 4 9-3 8 j 49-38 Site Boundary Red Bone Marrow Dose CI Source Term,72 Hours . . . . . . . 49-38 i 49-39 Site Boundary Thyroid Dose CI Source Term,24 Hours .... . . . . . . . 49-39 49-40 Site Boundary Thyroid Dose CI Source Term,72 Hours . . . . . .........
l 49-39 49-41 Population Whole Body Dose DIRECT Source Term 24 Hours . . . . . . . . . 49-40 49-42 Population Whole Body Dose DIRECT Source Term,72 Hours . ... . . . 49-40 l 49-43 Site Boundary Whole Body Dose DIRECT Source Term 24 Hours . . . . . . . 49-41 49-44 Site Boundary Whole Body Dose DIRECT Source Term,72 Hours ..... 49-41 49-45 Site Boundary Red Bone Marrow Dose DIRECT Source Term,24 Hours . . . 49-42 49-46 Site Boundary Red Bone Marrow Dose DIRECT Source Term,72 Hours ... 49-42 49-47 Site Boundary Thyroid Dose DIRECT Source Term. 24 Hours . . . . . . . . . 4 9-4 3 49-48 Site Boundary Thyroid Dose DIRECT Source Term,72 Hours . . . . . . . . . . . 49-43 49-49 Population Whcle Body Dose IC Source Term,24 Hours . ... .... .. 49-44
- i 49-50 Population Whole Body Dose IC Source Term,72 Hours ..... ... . . . 49-44 V 49-51 Site Boundary Whole Body Dose IC Source Term, 24 Hours . . . . . . .... . 49-45 49-52 Site Boundary Whole Body Dose IC Source Term,72 Hours . . .. . .. . 49-45 49-53 Site Boundary Red Bone Marrow Dose IC Source Term,24 Hours . . . . . . . 49-46 49-54 Site Boundary Red Bone Marrow Dose IC Source Term,72 Hours . . . . . . . . 49-46 49-55 Site Boundary Thyroid Dose IC Source Term,24 Hours . . . . . . . . . . . . . . 49-47 49-56 Site Boundary Thyroid Dose IC Source Term,72 Hours .. .. ..... . 49-47 49-57 Overall Dose Risk Site Boundary Whole Body, EDE,24 Hour Dose . . . . . . 49-48 49-58 Overall Dose Risk Site Boundary Acute Red Bone Marrow Dose 24 Hour . 49-48 51-1 AP600 Core Damage Frequency Uncenainty Histogram . . . . . . . . . . . . . . . . 51-19 51-2 AP600 PRA Uncenainty Analysis Results by Dominant Sequences .. ..... 51-20 51-3 AP600 PRA Uncenainty Analysis Results by Initiating Event .... ...... 51-21 52-1 Example Event Tree
- Baseline Configuration . . . ......... ....... .52-117 52-2 Example Event Tree: Nonsafety-Related Systems Removed . . . . . . . . . . . .52-118 52-3 Example Event Tree: Nonsafety-Related Systems Removed and Core Damage States Simplified . . . ....... ........ ...... . . . . . .52-119 52-4 Example Event Tree: Final Focused PRA Sensitivity Study Configuration . .52-120 i
l 52-5 ATWS Event Tree . . . . . . . . . . . . . ............... .. ..... .52-121 52-6 ATWSC Event Tree . ...... . .. ..... .. . . ... .. .. .52-122 52-7 CMTLB CMT Line Break Event Tree . . . . . . . - . .... . . . . . . .52-123 52-8 ISLOC: Interfacing Systems LOCA Event Tree ........ ... . . . . . .52-124 V
ENEL Revision: 9 T Westirighouse mam April 11,1997 lxxix o:\ap600sprairev_9'pra-lof.wpf: I b l
l u_____ _ _ _ _ _ _ _
l l
l LIST OF FIGURES (Cont.)
e Figure No. Title Rage a
52-9 LCAS: Loss of Compressed Air Event Tree . . . . . . ... .... . . . . . . .52-125 52-10 LCCW: Loss of CCW/SWS Event Tree . . . . . ..... . . . . . . . . . . . . . . 5 2 126 52-11 LCOND: Loss of Condenser Event Tree ...... .. ............52-127 52-12 LLOCA: Large LOCA Event Tree .......... .. ... . . . . . . . . . 5 2-128 l
52-13 LMFW. Loss of Main Feedwater to both SGs Event Tree ..... .. . .52-129 52-14 LMFW1: Loss of Main Feedwater to One SG Event Tree . . . . . . . .52-130 52-15 LOSP: Loss of Offsite Power Event Tree . . . . . ... . ... . . . . . . . . .52-131 52-16 LRCS: Loss of Reactor Coolant Flow Event Tree ...... .. .. . .52-132 '
52-17 MLOCA: Medium LOCA Event Tree . . . . . . . . . ... .... ....52-133 52-18 NLOCA/CNLOCA: Intermediate LOCA/ Consequential Intermediate LOCA Event Tree .. ........... . .. ... . . ... . .52-134 52-19 POWEX Power Excursion Event Tree .... .... .. . . . . ..52-135 52-20 PRSTR: Passive RHR Tube Rupture Event Tree . . . . . . ... ...52-136 52-21 RV-RP: Reactor Vessel Rupture Event Tree . . ... .. .. .... ... .52-137 52-22 SGTR/CSGTR: SG Tube Rupture / Consequential SG Tube Rupture Event Tree ... .. . .... ......... . . ..... . ...52-138 52-23 SGTRC: SG Tube Rupture Initial Event Tree . . . . . . . .. .... . . . . .52-139 52-24 SI-LB: SI Line Break Event Tree .... ........ . . . . . . . . . .52-140 52-25 SLB-D: Steam Line Break Downstream of MSIVs Event Tree . . . . . . .52-141 52-26 SLB-U: Steam Line Break Upstream of MSIVs Event Tree . . . . . . ...52-142 52-27 SLB-V/CSLB-V: Stuck-Open Secondary Side Safety Valve / Consequential Stuck-Open Secondary Side Safety Valve Event Tree . .... ...... .52-143 52-28 SLOCA: Small LOCA Event Tree ... . . ..... . ..52-144 52-29 TRANS: Transients with Main Feedwater Event Tree . ..............52-145 52-30 Containment Event Tree for Accident Class 3BE . . . . . . . . . . . . . . .52-146 52-31 Containment Event Tree for Accident Class 3BL . . . . . . . . . . . . . . . 5 2- 147 52-32 Containment Event Tree for Accident Class 3BR . . ..... ...... ...52-148 52-33 Containment Event Tree for Accident Class IA .. .. .. . .. . . . .52-149 52-34 Containment Event Tree for Accident Class I AP . . . .. . .. . ... .52-150 52-35 Containment Event Tree for Accident Class 3A . . . . . . ... ........ .52-151 52-36 Containment Event Tree for Accident Class 3C . . . ... ... ..52-152 52-37 Containment Event Tree for Accident Class 3D . . . . . . . . . . . . . . . .52-153 52-38 Containment Event Tree for Accident Class 6 . . . .... .... ... . . . .52-154 52-39 Loss of Offsite Power (RCS Drained) Event Tree ... .... . .... .. .52-155 52-40 LOSP Dudng Hot / Cold Shutdown (RCS Filled) Event Tree ....... . . . .52-156 54-1 LOSP During Hot / Cold Shutdown (RCS Filled) Event Tree . . . . ..... .54-299 54-2 Loss of RNS Initiator During Hot / Cold Shutdown (RCS Filled) Event Tree . .54-300 54-3 Loss of CCW/SW Initiator During Hot / Cold Shutdown (RCS Filled)
Event Tree .... . ........ ... ....... .. .....54-301 9
p ,1997 1 W Westinghouse oTap600\pra\rev.,9pra-lof.wpf:1b IXT.X
LIST OF FIGURES (Cont.)
Finnre No. T. itis P.nas
$4-4 LOCA/RNS Pipe Rupave Dunng Hot / Cold Shutdown (RCS Filled)
Event Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .54-302 54-5 LOCA/RNS-V024 Opens Dunng Hot / Cold Shutdown (RCS Filled) .
Event Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .54-303 {
54-6 Overdrmmng of Reactor Coolant System Dunng Drundown to Mid. Loop . . .54-304 l 54-7 Loss of Offsite Power (RCS Dramed) Event Tree . . . . . . . . . . . . . . . . . . .54-305 54-8 Loss of RNS Initiator (RCS Dramed) Event Tree . . . . . . . . . . . . . . . . . . . .54-306 54 9 Loss of CCW/SW Initiator (RCS Dramed) Event Tree . . . . . . . . . . . . . . . .54-307 54-10 LOCA/RNS-V024 Opens (RCS Dramed) Event Tree . . . . . . . . . . . . . . . . .54-308 54-11 Accumulator Injection (Dilution Scenario) Event Tree . . . . . . . . . . . . . . . . .54-309 54-12 Shutdown Transient Case SDIB2 RCS Pressure vs. Tune . . . . . . . . . . . . . .54-310 54-13 Shutdown Transient Case SD1B2 Mass Flow Rare vs. Tune . . . . . . . . . . . .54-311 54-14 Shutdown RNS Break Case SD3A (3500 gym) . . . . . . . . . . . . . . . . . . . . .54-312 54-15 Shutdown RNS Break Case SD3A2 (2000 gpm) . . . . . . . . . . . . . . . . . . . .54-313 54-16 Shutdown RNS Break Case SD3A3 (1000 gym) . . . . . . . . . . . . . . . . . . . .54-314 54-17 Shutdown Plant Damage State Substate Event Tree for LP-ADS . . . . . . . . .54-315 54-18 Shutdown Plant Damage State Substate Event Tree for LP-1 A . . . . . . . . . . .54-316 54-19 Shutdown Plant Damage State Substate Event Tme for LP-3D . . . . . . . . . . .54-317 54-20 Shutdown Plant Damage State Substate Event Tree for LP-3BR . . . . . . . . . .54-318 54-21 Shutdown Plant Damage State Substate Event Tree for LP-3BE . . . . . . . . . .54-319 55-1 Seismic Initiating Event merarchy Tree . . . . . . . . . . . . . . . . . . . . . . . . . . 55-105 55-2 EQSTRUC Initiating Event Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-106 55-3 EQRVFA Initiating Event Fanit Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-108 55-4 EQLLOCA Imt anns Event Fanit Tres . . . . . . . . . . . . . . . . . . . . . . . . . . 55-109 55-5 EQSLOCA Initiating Event Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-110 55-6 EQN1WS Initiating Event Fault Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-111 55 EQSTRUC Event Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-112 55-8 EQRVFA Event Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-113 55-9 EQLLOCA Event Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-114 '
55-10 EQSLOCA Event Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-115 55-11 EQA'IWS Event Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-116 55-12 EQ.LOSP Event Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-117 )
55-13 EQLOSP Event Tree (for 0.5g level cantgaake) . . . . . . . . . . . . . . . . . . . . 55-118 55-14 EQAC2AB Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-119 55-15 EQXCIC Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-120 )
55-16 EQXADMA Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-121 l 55-17 EQXIW2A Fault Tres . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-122 1 55-18 EQRECIR Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-123 j 55-19 EQCM2SL Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55-124 55-20 EQADA Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-125 l 55-21 EQIW2AB Fault Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5-126 l Revisient 9 l Y@ ixxx .wsoop._,,wwm Apeil 11,1997
_w f
\
l LIST OF FIGURES (Cont.)
O Figure No. Title Dage 55-22 EQ-PRHR Fault Tree . . . . . .... .. ............ . . . . . . . . . . . 55-127 55-23 EQ-PRESU Fault Tree . . . . . ... ....... .............. .. 55-128 55-24 EQ-PMS Fault Tree . . . . . . . . . . . . . .. ......... . ... ... ... 55-129 55-25 EQ-DC Fault Tree . . . . . . . . . ... ... .................... . 55-130 55-26 Class 1E de Power Block Diagram . . . ... ..... . . . . . . . . . . . . . . . 5 5- 131 55-27 Containment Evaluation Model . . . . . . ............... . . . . . . . . 55-132 55-28 EQ-STRUC Event Sequences . . . . . .. . .. .. ............. . 55-133 55-29 EQ-RVFA Event Sequences . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5 - 1 34 55-30 EQ-LLOCA Event Sequences . . . .. .. ............. ....... . 55-135 55-31 EQ-SLOCA Event Sequences . . .. ........................ .. 55-136 55-32 EQ-SGTR Event Sequences ...... .......... ..... . . . . . . . . . 55-137 55-33 EQ-SLB Event Sequences . ... . ............ . . . . . . . . . . . . 5 5- 138 55-34 EQ-ATWS Event Sequences . . . . . . . . . . . . . . . . . ............... 55-139 55-35 EQ-LOSP Event Sequences (for 0.5g level earthquakes) . .. .. .... . 55-140 56-1 Flood Zones and Barriers Plan at 66'-6" . .. ...... . ....... . . 56-93 56-2 Flood Zones and Barriers Plan at 82'-6" . . . . . . . . . . . . . . . . . . . . . . . . . . 5 6-95 56-3 Flood Zones and Barriers Plan at 96'-6" . . . . . . . . . .. ..... .. .... 56-97 56-4 Flood Zones and Barriers Plan at 100'-0" & 107'-2" . .. . . . . . . . . . . . 5 6-99 56-5 Flood Zones and Barriers Plan at 117'-6" . . . . . . . . . . . . . . .. . .56-101 56-6 Flood Zories and Barriers Plan at 135'-3" .......... ... . . . . . . . . .56-103 56-7 Flood Zones and Barriers Plan at 160'-6" & 153'-0" . . ...... .. ...56-105 56-8 Flood Zones and Barriers Plan at 160'-6" & 180*-0" . . . . . . . . . ..... .56-107 56-9 8-in. Fire Main Rupture at-Power Event Tree ...... ... .... ..56-109 56-10 8-in. Fire Main Rupture during Hot / Cold Shutdown Event Tree . . . . . . . ..56-110 56-11 8-in. Fire Main Rupture during RCS Drained Conditions Event Tree . . . . . .56-111 57-1 Fire Progmssion Event Tree for 1200 AF 01 Fire Area . . . . ... .... ..57-156 59-1 Contribution of Initiating Events to Core Damage ................. .59-233 59-2 Contribution ofInitiating Events to Large Release Frequency and Core Damage Frequency . . . . . . . . . . . . . . . . . . .. ..... .59-234 59-3 Total Plant CDF/LRF . . . . . . ....... ...... .. ............ .59-235 59-4 24-Hour Site Boundary Dose Cumulative Frequency Distribution . . . . . . . . .59-236 Revision: 11 9
March 1998 3 Westlfighouse owemean_nwepra lxxxii
_----_____-_________- _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _