enclosure 3 utlr-0014, rev 0 abwr severe accident evaluations · p13 small line break 5.oe-04 k p14...

TOS-CR-DCA-2011-002

Enclosure 3

UTLR-0014, Rev 0

"ABWR Severe Accident Evaluations"

TOSHIBALeading Innovation >))

Export Control Number: PSN-2010-1254

N I 0n o r a •

UTLR-0014 Rev.0Nov 2010

Technical Report

ABWR Severe Accident Evaluations

Approved by H.Oikawa Nov 8, 2010

Safety & Dynamics Engineering Group

Toshiba Corporation

System Design & Engineering Department

©2010 Toshiba Corporation All Rights Reserved

RSC 10-15

Toshiba America Nuclear Energy ABWRSupplemental DCDRA Chapter 19EDocumentation Toshiba Documew No. Revision I

Revision 0

August 2010

Principal Analyst

Joshua Bartlett

Developed for

ETRANCO/MPR/Toshiba America Nuclear Energy

Reliability & Safety Consulting Engineers, Inc.2220 Award Winning Way, Suite 200Knoxville, TN 37932 USA

RSC

UTLR-O0 14 0

projwct DCA

Contract No. :9R06682

0 1Appoval I a2formto

Action

A 0 Approved No Further Action

C Approved with CommentCRevised and Resbmit

DisapprovedD Revised sad Resuabmit

Accepted for Information Only13 leomnton nluded

urgnUS: •aw a1 uvaav$c Ia~lne~serimauroun•

Approved by Revitw~d by

H. Oikawa Y. KojimaNov. 3, 2010 Nov. 8, 2010

Approval by buyer deno m k rla s"lle= of hisobligation to furnish stl goods sad services in

strict coafatmaence with &H of the terms of theporokose Order.

TOSHIBA CORPORATIONNED

RSC 10-15

Document Revision History

Document RSC RSC RSC Summary of RevisionRevision Principle Internal Approval for

Analyst/ Reviewer/ ClientProject Date Review Release/

Manager Complete Date of(initials/date) Approval

(initials/date)

Original Issue JWB CLE RLS 8/7/20108/6/2010

1

2

3

4

5

Supplemental DCDRA Chapter 19E Documentation

Table of Contents

Section Page

1.0 INTRO DUCTIO N ........................................................................................................... 3

2.0 REFERENCES .......................................................................................................... 3

List of Tables

Table Page

Table 19E.2-20 Failure Probabilities ................................................................................................ 4

Table 19E.2-21 Sum m ary of Bypass Probabilities .......................................................................... 5

Table 19E.3-1 G ESSAR Reactor Release Param eters ................................................................ 20

Table 19E.3-6 Event Release Param eters .................................................................................... 21

List of Figures

Table Page

Figure 19E.2-19a Suppression Pool Bypass Paths and Configurations ....................................... 6

Figure 19E.2-19b Suppression Pool Bypass Paths and Configurations ......................................... 7

Figure 19E.2-19c Suppression Pool Bypass Paths and Configurations ........................................ 8

Figure 19E.2-19d Suppression Pool Bypass Paths and Configurations ......................................... 9

Figure 19E.2-19e Suppression Pool Bypass Paths and Configurations ....................................... 10

Figure 19E.2-19f Suppression Pool Bypass Paths and Configurations ....................................... 11

Figure 19E.2-19g Suppression Pool Bypass Paths and Configurations ....................................... 12

Figure 19E.2-19h Suppression Pool Bypass Paths and Configurations ....................................... 13

Figure 19E.2-19i Suppression Pool Bypass Paths and Configurations ....................................... 14

Figure 19E.2-19j Suppression Pool Bypass Paths and Configurations ....................................... 15

Figure 19E.2-19k Suppression Pool Bypass Paths and Configurations ....................................... 16

Figure 19E.2-20a Small LOCAs Outside Containment ................................................................ 17

RSC 10- 15 Printed: 10/13/2010


Figure 19E.2-20b Intermediate LOCAs Outside Containment ..................................................... 18

Figure 19E.2-20c Large LOCAs Outside Containment ................................................................ 19

Figure 19EA-1 DCH Event Tree for Sequences with Low Containment Pressure ..................... 22

Figure 19EA-2 DCH Event Tree for Sequences with Intermediate Containment Pressure ........ 23

Figure 19EA-3 DCH Event Tree for Sequences with High Containment Pressure ..................... 24

Figure 19EA-4 DET for Probability of Early Containment Failure-High RV Press and Low ContP ress S eq ue nces ....................................................................................................................... 25

Figure 19EA-5 DET for Probability of Early Containment Failure-High RV Press and Inter ContP re ss S e q ue nce s ........................................................................................................................ 2 6

Figure 19EA-6 DET for Probability of Early Containment Failure-High RV Press and High ContP re ss S e q ue nce s ........................................................................................................................ 2 7

Figure 19EA-14 Cumulative Distribution for Peak Pressure Dueto DCH .................................... 28

Figure 19EC-1 Core Debris Concrete Attack DET ....................................................................... 29

Figure 19EC-2 Containment Event Evaluation DET for Pedestal Failure .................................... 30

Figure 19EE-1 Containment Event Evaluation DET for Suppression Pool Bypass ..................... 31

RSC 10-15 ii Printed: 10/13/2010


1.0 INTRODUCTION

This document provides tables and figures for the Advanced Boiling Water Reactor (ABWR)Design Control Document (DCD) for:1) Appendix 19E, Deterministic Evaluations.2) Appendix 19EA, Direct Containment Heating3) Appendix 19EC, Debris Coolability and Core Concrete Interaction4) Appendix 19EE Suppression Pool BypassThe tables and figures are numbered to correspond the figures in Reference 1.

Revised Level 1 and 2 plant risk models were used to determine the risk associated with

different accident sequences. The Level 2 risk analysis is discussed in detail in Reference 2.

2.0 REFERENCES

1. ABWR Design Control Document, RS-5146900 Rev. 0

2. Bartlett, J., "Toshiba ABWR DCDRA Severe Accident Analysis and Level 2 MORDevelopment", Reliability and Safety Consulting (RSC) Engineers, Inc., RSC 10-17.

RSC 10- 15 3 Printed: 10/13/2010


Table 19E.2-20 Failure Probabilities

Symbol Description Prob/Event BasisP1 Main Steam Isolation Valve Common 1.0E-04 a

Mode FailureP2 MSIV leakage probability 0.71 bP3 Turbine Bypass Isolation 4.0E-03 cP4 Main condenser failure .1.0 cP5 MSL break outside containment 6.8E-06 dP6 Air-operated valve (NO) 1.5E-03 eP7 Motor-operated valve (NO) 3.9E-03 eP8 Motor-operated valve (NO) 3.9E-03 fP9 Check Valve 1.6E-04 g

P10 Motor-operated valves (NC) 0.5 hP11 Motor-operated valves (NC) 0.5P12 Inadvertant opening 1.0E-03P13 Small line break 5.OE-04 kP14 Medium line break 1.OE-04 kP15 Large line break 6.8E-06 kP16 CUW line break 3.7E-04 k

RSC 10-15 4 Printed: 10/13/2010


Table 19E.2-21 Summary of Bypass Probabilities

FiguresFlow Split Bypass Probability Bypass Bypass 19E.2-19a to

Pathway Fraction Equation Probability Fraction 19E.2-19k

Lines from the RPVMain Steam

Main Steam Leakage

Feedwater

Reactor Inst. Lines

HPCF DischargeHPCF Equalizing Line

SLC Injection

RCIC Steam Supply

LPFL Discharge

LPFL Equalizing Line

CUW Suction

CUW Inst. Lines

Post Acc Sampling

LDS Instruments

SRV Discharge

Lines from the Drywell

Cont Atmos MonitorLDS Samples

Drywell Sump Drain

DW PurgeInerting Makeup

ACS Supply

WW-DW Vac Bkrt

6.7E-01

2.2E-055.2E-01

3.1 E-05

1.1E-011.OE-033.OE-03

6.9E-02

1.7E-01

1.OE-03

1.2E-01

3.1E-05

1.OE-033.1 E-05

6.9E-02

8.90E-041.70E-03

3.OOE-02

5.40E-01

1.20E-02

7.50E-01

2.60E-01

4*P1*(P3*P4+P5)4*P2*(P3*P4+P5)

2*P9*P9*P15

30*P13*P9

2*P9*P1O*P14

2*P1O*P11*P131*P9*P13

1*P8*P14

2*P9*P10*P15

2*P1O*P11*P13

1*P8*P144*P13*P9

4*P8*P119*P13*P9

8*P14

6*P8*P132*P8*P11

2*P8*P13

1*P6*P11

1*P62*P12*P6

8*P9

1.6E-06

1.1 E-02

3.6E-132.4E-06

1.1 E-092.5E-04

4.1 E-07

4.1 E-07

1.1 E-09

2.5E-04

4.1 E-07

3.3E-07

7.8E-03

7.3E-07

8.3E-04

1.17E-053.90E-03

3.90E-06

7.50E-04

1.50E-03

3.OOE-06

1.30E-03

1.07E-06

2.50E-07

1.87E-13

7.56E-11

1.21E-102.50E-07

1.22E-09

2.80E-08

1.87E-10

2.50E-07

4.87E-08

1.01 E-11

7.80E-06

2.27E-11

5.74E-05

1.04E-086.63E-06

1.17E-07

4.05E-04

1.80E-05

2.25E-06

3.38E-04

4.99E-048.40E-04

Total excluding vaccum breakerGoal

* These lines may be excluded for station blackout events.t Addressed on Containment Event Trees.

RSC 10-15 5 Printed: 10/13/2010


Figure 19E.2-19a Suppression Pool Bypass Paths and Configurations

RSC 10-15 6 Printed: 10/13/2010


Figure 19E.2-19b Suppression Pool Bypass Paths and Configurations

RSC 10-15 7 Printed: 10/13/2010


C. ECCS LinesNo Checkvalve

Failure (P9)or

OperatorCloses Valve

OK

OK

OK

Bypass

RPV Reactor Building

Figure 19E.2-19c Suppression Pool Bypass Paths and Configurations

RSC 10-15 8 Printed: 10/13/2010


D. Insltmwon UnesNo Lkmie*

(P13, P14, P15)No Check Faiure

(P9)OK

OK

Bypan

RPV

Figure 19E.2-19d Suppression Pool Bypass Paths and Configurations

RSC 10-15 9 Printed: 10/13/2010


E. Station Blackout Affected LinesIlsolation

(P8)No Linebreak

(P13, P14, P15)OK

OK

Bypass

Figure 19E.2-19e Suppression Pool Bypass Paths and Configurations

RSC 10-15 10 Printed: 10/13/2010


F. Containment Amospheric Monitor

No CheckvalveFailure

(P9)

OperaorCoses Valve

(P10)No kinmbbuA

(P13)OK

OK

OK

Bypass

Drywell

Figure 19E.2-19f Suppression Pool Bypass Paths and Configurations

RSC 10-15 11 Printed: 10/13/2010


G. Drywell-Wetwell Vac. BkrsCheckvalveFailure (P9)

OK

Bypass

Drywell WetwellContainment Vent

I Assumed

Figure 19E.2-19g Suppression Pool Bypass Paths and Configurations

RSC 10-15 12 Printed: 10/13/2010


H. Atmosph..ic Control System Supply

No InadveetwitOpening (P12)

No AO Valve CommonMode Fadure (P6)

OK

OK

Bypass

Drywell--0 •->- Wetwel

Figure 19E.2-19h Suppression Pool Bypass Paths and Configurations

RSC 10-15 13 Printed: 10/13/2010


Drywell PurgeNo Ai'r ValveFailure (P6)

Valve Open(P11)

OK

OK

Bypass,

Drywell ><1 • Stack

Drywell/Wetwell Makeup

No Air ValveFailure (P6)

OK

Bypass

Drywelt • -<3 - Wetwell

Figure 19E.2-19i Suppression Pool Bypass Paths and Configurations

RSC 10-15 14 Printed: 10/13/2010


J. Sample Unes or Sumps

No StatioBlackout (PS)

Normlly Closed (P 1)or No Uine Break (P13)

No CheckValve Failure(Sumps Only)

(PS)OK

OK

Bypas

Bypass

RPV Sample,/IPV<I Station

D/ w [ReactorOrywll • I • / • Building Sump

Figure 19E.2-19j Suppression Pool Bypass Paths and Configurations

RSC 10-15 15 Printed: 10/13/2010


K. SRV DischargeADS/SRV

Open

No. SRV DLlBreak(P14)

OK

OK

1.0

Bypass

RPVContainment Vent

Assumed

Figure 19E.2-19k Suppression Pool Bypass Paths and Configurations

RSC 10-15 16 Printed: 10/13/2010


Figure 19E.2-20a Small LOCAs Outside Containment

RSC 10- 15 17 Printed: 10/13/2010


LINE BREAK LINE

OUTSIDE ISOLATION

OPER.ACTION

SECOND DIV. COOLANT

NOT AFFECTED MAKEUP

(Vi) (Xl)

HPCF DISCHARGE (2)

(P1) (Q1) (QO)

I11.52E-4 3.16E-08

2.08E-04

[2"P14]

8.1E-05

[P9*P10] 1.52E-4 1.28E-120.5

4.08E_2 3.451E-13

RCIC STEAM SUPPLY (1)

CUW SCUTION (1)

1.52E-4 7.20E-08

4.74E-04

P14+P16]

2.OE-04 1.52E-4 1.43E-11

[COMMON MODE

I

OK

NON-BYPASS

OK

BYPASS

OK

BYPASS

OK

NON-BYPASS

OK

NON-BYPASS

OK

OK

BYPASS

NON-BYPASS

NON-BYPASS

OK

BYPASS

FAILURE) 1.00E-02 14.08E-2

3.868E-11

SRV DISCHARGE (8)

8.3E-04

[8*P14] 1

0

0

1.28E-5 1.065E-08

TOTALS

NON-BYPASS 1.04E-0

BYPASS 1.069E-087

Figure 19E.2-20b Intermediate LOCAs Outside Containment

RSC 10-15 18 Printed: 10/13/2010


Figure 19E.2-20c Large LOCAs Outside Containment

RSC 10-15 19 Printed: 10/13/2010


Table 19E.3-1 GESSAR Reactor Release ParametersIsotopic Release Fractions by Group

Category POj) TLn, DR) TLLw) FPRU) RHu)

Group = 1 3 4 5 6 7 8

C1-TR-E2 2.09C-07 1.66 0.1 0.7 4.0[+07 10.0 1.0["+0 1.31-03 1.01-03 1.0E-03 1.11-03 2.GE-04 1.5E-07

C1-TR-E3 1.316E-06 1.7 4.3 0.7 1.5E+00 10.0 1.OE+0 1.3E-03 1.OE-03 1.OE-03 2.2E-04 3.1E-04 4.9E-05

C1-TR-L3 6.92E-07 11.9 10.0 10.9 5.OE+05 49.0 1.OE+O 4.8E-04 1.8E-04 1.8E-04 3.9E-05 5.7E-05 9.OE-06

C1-TR-12 7.59E-07 3.0 0.1 2.0 4.4E+07 10.0 1.OE+0 1.3E-03 9.9E-04 9.9E-04 1.0E-03 2.5E-04 1.5E-07

C1- IH-13 1.65E-06 3.0 3.6 Z.0 2.IE+0 .1.0 1.0E+t 1.3E-03 1.OE-03 1.0E-U3 Z.ZE-04 3.1 E-04 4.8E-05

Note:See Subsection 19E.3.2.2 for definition of parameters in this table.

RSC 10-15 20 Printed: 10/13/2010


Table 19E.3-6 Event Release ParametersRelease Fractions*

Accident P(i) TL DR TLL FPR RH NG Iodine Cesium

NCL

CASE 1LCHPFSRN

LCHPPSRN

LBLCFSRN

SBRCPFRN

LCLPPFRN

LCLPFSRN

CASE 2

LCLPPFCR

LCLPFSCR

CASE 3LCHPFSD90

CASE 4

DF100FSR

DF10OPFR

CASE 5LBLCPFRN

CASE 6

LCHPPSD90

LBLCPFD90

LBLCFSD90

CASE 7

LCLPFSD90LCHPPFPM

LCLPPFD90

CASE 8LCHPPFEH

LCHPPFBR

LCHPPFBD

CASE 9SBRCPFD90

8.50E-08 2.71.13E-08 20

10

1

1.7 3.30E+05 37

19.2 3.30E+05 37

0.044 2.3E-05 2.3E-05

1 3.9E-04 2.9E-04

<" E-10 19 1 18.2 3.30E+05 37 1 5.OE-06 5.OE-06

< 1E-10 50 10 49.2 3.30E+05 37 1 2.8E-04 2.2E-03

<" E-10 20 1 19.2 3.30E+05 37 1 1.6E-03 1.6E-03

< 1E-10 19 1 19.2 3.30E+05 37 1 6.OE-03 5.3E-04

< 1E-10 19 10 18.2 3.30E+05 37 1 3.1E-02 7.7E-02

<" E-10 20 10 19.2 3.30E+05 37 1 8.9E-02 9.9E-02

< 1E-10 2 10 1.2 1.OOE+06 37 1 1.9E-01 2.5E-01

< 1E-10 23.6 10 12.2 3.30E+05 37 1 3.7E-01 3.6E-01

* Group 5-8 negligible release

Note:See Subsection 19E.3.2.2 for definition of parameters in this table.

RSC 10-15 21 Printed: 10/13/2010


CONTAINMENT DRYWELL HEAD FAILSPRESSURE PRIOR TO REACTOR VESSEL FOLLOWING VESSELREACTOR VESSEL PRESSURE AT FAILURE FIUE REF STC PO

FAILURE # #

DET CNTPRESL RVPRESS EARLYCFEVENT CONTPRESS RVPRESS EARLYCFL

NO FAILURE 0 I0.g948781 0 1 0994878

0.994878

HIGH1

2 0 1 0.005122LOW (0.1-0.21 MPa)11

5.12E-03

LOW 33~I

0

4t I* I*

5PDS 1 INT (0.21-0.31 MPa

D

6i i i

7

8+ -

IHIGH (>0.31 MPa)0

9

FIgure 191A-1 UGH Event I ree Tor Sequences with LOW ;ontainmert Pressure

RSC 10-15 22 Printed: 10/13/2010


CONTAINMENT JDRYWELL HEAD FAILSPRESSURE PRIOR TO REACTOR VESSEL FOLLOWING VESSEL

REACTOR VESSEL PRESSURE AT FAILURE FAILURE REF STC PROBFAILURE # #


1

7-2

LOW (0.1-0.2 MPa)I0

3

NO FAILURE 4 04-1.-I.

0.986182

HIGH

FAILURE

0.986182

5 0PDS 1 INT (0.21-0.3 MPa) 1.38E-02 0.013818

1

LOW 66.--- 1

0

7

88.

IHIGH (>0.31 MPa)0

9

Figure 19EA-2 DCH Event Tree for Sequences with Intermediate Containment Pressure

RSC 10-15 23 Printed: 10/13/2010


CONTAINMENT JDRYWELL HEAD FAILSPRESSURE PRIOR TO REACTOR VESSEL FOLLOWING VESSEL

REACTOR VESSEL PRESSURE AT FAILURE FIUE REF STC POFAILURE FAILURE # PROB


1

I-f 1--f

2+ - 4-4-

LOW (0.1-0.2 MPa)10

3

4

5I - + 4

PDS 1 INT (0.21-0.3 MPa)0

6

NO FAILURE 7 100.957958

HIGH

FAILURE

0.957958

8 0[HIGH (>0.31 MPa)1

4.20E-02 0.042042

LOW 90

Figure 19EA-3 DCH Event Tree for Sequences with High Containment Pressure

RSC 10-15 24 Printed: 10/13/2010


HIGH RV FRACTION OFPRESSURE AND MODE OF RV FRACTION OF ENTRAINED PEAK

OPERATOR HIGH PRESSURE DEBRIS CONTAINMENT CONTAINMENTLOW FAILURE-TIME CORE DEBRISLOW FAILRM COREN IS DEPRESSURIZE MELT EJECTION FRAGMENTED PRESSURE INTACT AT RPV

CONTAINMENT FOR RV MOLTEN IN S REACTOR OCCURS AND FOLLOWING RPV FAILURE REF#PRESSURE BLOWDOWN LOWER RV TRANSPORTED FAILURE

SEQUENCES TO UPPER DW

EVENT MODRVFAIL RVCORMASS OP HPME FRAG CONTPRESS CI

RX DEPRESS CONT INTACT 1

HI LIQ (40%)0.1

CONT INTACT 2

HIGH (75%) 1.01 MPa 0.540.01 CO!NT FAILURE 3

0.46HPME CONT INTACT 4

0.8 INTER (50%) 0.90 MPa 0.830.19 CONT FAILUýRE 5

NOT DEPRESS 0.17

LOW (25%) <0.77 MPa CONT INTACT 6

NO HPME <0.77 MPa CONT INTACT 7

SMALL0.9

LARGE0.1

0.2CONT INTACT I 8RX 0FPREFS

DEPRESS

HIGH (75% <0.77 MPaLOWLIQ (10%) 0.010.9 HPME INTER (50%) <0.77 MPa

10.8 0.19NOT DEPRESS LOW (25%) <0.77 MPa

<- 0.8NO HPME <0.77 MPa

CONT INTACT 1 9

CONT INTACT 10

CONT INTACT 11

CONT INTACT 120.2

CONT INTACT 13RX DEPRESS

HI LIQ (40%)0.1

CONT INTACT 14

HIGH (75%) 1.39 MPa 0.020.01 ]CONT FAILURE 15

0.98CONT INTACT 16

HPME INTER (50%) 1.19MPa 0.160.8 0.19 ]CONT FAILURE 17

0.84

NOT DEPRESS CONT INTACT 18LOW (25%) 0.90 MPa 0.830.8 CONT FAILURE 19

0.17NO HPME <0.77 MPa CONT INTACT 200.2

RX DEPRESS CONT INTACT 21

CONT INTACT 22LOWLI (10% HIGH (75%) 0.970.9 0.01 CONT FAILURE 23

HPME 0.030.8 INTER (50%) <0.77 MPa CONT INTACT 24

NOT DEPRESS 0.19LOW (25%) <0.77 MPa CONT INTACT 250.8

NO HPME <0.77 MPa CONT INTACT 260.2

Figure 19EA-4 DET for Probability of Early Containment Failure-High RV Press and Low ContPress Sequences

RSC 10- 15 25 Printed: 10/13/2010


HIGH RV FRACTION OF

PRESSURE AND MODE OF RV FRACTION OF ENTRAINED PEAK DRYWELL HEADINTER FAILURE-TIME CORE DEBRIS DEBRIS CONTAINMENT FAILS

CONTAINMENT FOR RV MOLTEN IN MELT EJECTION FRAGMENTED PRESSURE FOLLOWING REF #PRESSURE BLOWDOWN LOWER RV OCCURS AND FOLLOWING RPV VESSEL FAILURE

SEQUENCES TRANSPORTED FAILURETO UPPER DW

EVENT MODRVFAIL RVCORMASS HPME FRAG CONTPRESS EARLYCF

NO FAILURE 110.1HIGH (75%) 1.24 MPa

0.01

HPME INTER (50%)0.8

HI LIQ N40%0.1

NO HPME

0.19

FAILURE0.9NO FAILURE

1.03 MPa 0.48FAILURE0.52NO FAILURE

0.79 MPa 0.97FAILURE0.03

<0.77 MPa NO FAILURE

2

3

4

5

6

7

LOW (25%)0.8

SMALL10.9 0.2

HIGH (75%) <0.77 MPa NO FAILURE 80.01

HPME LINTER (50%) <0.77 MPa NO FAILURE 9!0.8

LOW LIQ (10% 0

0.9NO HPME

0.19LOW (25%) <0.77 MPa NO FAILURE 100.8

<0.77 MPa NO FAILURE 110.2

HIGH (75%• 1.58 MPa -~l 1 1 D -: ý Ir•ILU•E IL

HIG H. (7 % 1... t . ... .. ... ..0.01

INTER (50%)HPME0.8

HI LIQ (40%0.1

NO HPME

0.19

LOW (25%)0.8

NO FAILURE1.32 MPa 4.OOE-02




13

14

15

16

17LARGE0.1

0.2

HIGH (75%)NO FAILURE



18

19

20

0.01HPME0.8 INTER (50%)

LOW LIQ (10%) 0.190.9 LOW (25%)

0.8NO HPME

<0.77 MPa NO FAILURE 21

<0.77 MPa NO FAILURE 22I.-

0.2

Figure 19EA-5 DET for Probability of Early Containment Failure-High RV Press and Inter ContPress Sequences

RSC 10-15 26 Printed: 10/13/2010


HIGH RV FRACTION OF

PRESSURE AND MODE OF RV FRACTION OF ENTRAINED PEAK DRYWELL HEADHIGH FAILURE-TIME CORE DEBRIS HIGH PRESSURE DEBRIS CONTAINMENT FAILS

CONTAINMENT FOR RV MOLTEN IN MELT EJECTION FRAGMENTED PRESSURE FOLLOWING REF #PRESSURE BLOWDOWN LOWER RV OCCURS AND FOLLOWING RPV VESSEL FAILURE

SEQUENCES TRANSPORTED FAILURETO UPPER DW

EVENT MODRVFAIL RVCORMASS HPME FRAG CONTPRESS EARLYCF

HIGH (75%) 1.52 MPa NO FAILURE I. . . . . " . . . f . . . . . .. . . . .. . . . .

0.01

INTER (50%)HPME0.8

HINLIO 40%0.1

NO HPME

0.19

LOW (25%)0.8

NO FAILURE1.27 MPa 0.07




2

3

4

5

6SMALL0.9 i0.2

HIGH (75%)HPME 0.010.8

LOW LIQ (10%) INTER (50%)0.9 0.19

LOW (25%)0.8

NO HPME


FAILURE0.1


7

8

9

<0.77 MPa NO FAILURE 10

<0.77 MPa NO FAILURE 110.2

HIGH (75%) 1.81 MPa FAILURE 120.01

HPME IINTER (50%) 1.52 MPa NO FAILURE 130.8

HI LIQ (40%)0.1

NO HPME

0.19

LOW (25%)0.8


FAILURE0.73


14

15

160.2

HIGH (75%)0.01

LARGE0.1

HPME INTER (50%)0.8

LOW LIQ (10%)

0.9

NO HPME

0.19



0.90 MPa 0.83FAILURE0.17NO FAILURE



17

18

19

20

21

22

23

LOW (25%)0.8

0.2

Figure 19EA-6 DET for Probability of Early Containment Failure-High RV Press and High ContPress Sequences

RSC 10-15 27 Printed: 10/13/2010


Peak Drywell Pressure (MPa)

1.360.7 1.03 1.69 2.02

=• tT If

8

C

0z

C

E

0.95 I

I

II II I

Median DrywellFailure Pressure

1.36 1.69 2.02--•

0.85

Initial Drywell Pressure

- Intermediate

High

Low

0.8

100 150 200 250 300

Peak Drywell Pressure (psia)

Figure 19EA-14 Cumulative Distribution for Peak Pressure Due to DCH

RSC 10-15 28 Printed: 10/13/2010


FRACTION OF DEBRIS WATER ENTERS TIMEREMAINING HEATTANSFER DEBRISFRACTIN OF INITIAL DEBRIS QUENCHED CAVITY LATE (1-3 FALL IN OVERTOLYINGRATTDEBRIS IN LOWER CAV LLSINTO OVERLYING CONCRETE REF#

DW EARLY SUPERHEAT EARLY HR) CAVITY WATER ATTACK

EVENT COR-DW-E SUP HEAT QUENCHE CAVMAT-L COREDROP HT-UPWARD CCI

CHF LIMIT NO CCI 1AFT LATE INJ (FILM BOIL 0.9 NO CCI 2

QUENCH0.99

LOW0.9

NO QUENCH0.01

0.9WATER

BEF LATE INJ0.1

NO WATER

0.09 [WET CCI 0.75 3CONDUCT LIM WET CCI 0.25 40.01 NO CCI 510.1 NO CCI 60.6 WET CCI 0.75 7

WET CCI 0.25 80.3 DRY CCI

<--NO CCl 10AFT LATE INJ 05NO CCl 11

0.9 0.4 IWET CCI 0.75 12WATER WET CCI 0.25 13

0.1 NO CCI 14

BEF LATE INJ 0.1 NO CCI 150.1 0.6 lWET CCI 0.75 16

WET CCI 0.25 17NO WATER 0.3 DRY CCI 18

<--NO CCl 19

AFT LATE INJ 09NO CCl 20

0.9 0.09 LWET CCl 0.75 21

WATER WET CCI 0.25 22

<-0.01 NO CCl 23

IBEF LATE INJ 10.1 NO CCI 24

0.1 0.6 IWET CCl 0,75 251WET CCI 0.25 26

NO WATER 0.3 DRY CCI 27

QUENCH0.95

HIGH0.1 AFT LATE INJ

0.9WATER

NO QUENCH IBEF LATE [NJ0.05 0.1

NO WATER

NO CCI 28

10.5 NO CCI 290.4 LWET CCI 0.75 30

WET CCI 0.25 310.10.10.6 WET CCI 0.75 34

WET CCl 0.25 35

AFT LATE INJ

0.3 DRY CCI 36NO CCI 37

0.95 NO CCI 380.045 IWET CCI 0.75 39

WET CCI 0.25 400.005 NO CCI 41

0.5WATERI

QUENCH IBEF LATE INJ

0).75 0.5

NO WATER

LOW<-0.5 AFT LATE INJ

0.5WATER

O10QUENCH IBEF LATE I NJ

.25 INO WATER 0

0.1 NO CCI 42

r.60.3

0.-5

r.4

0.1

IWET CC 0.75 43WET CCI 0.25 44

WET CCI 0.75 48WET CCI 0.25 49

IWT CCI 0.75 52

AFT LATE INJ0.5

WATER

QUENCH BEF LATE INJ0.5 0.5

NO WATER'HIGH<-0.5 AFT LATE INJ

0.5WATER

L10 QUENCH IBEF LATE INJ0.5 0.5

NO WATER

0.045 -WET CCI 0.75 57WET CCI 0.25 58

0.005 NO CCI 590.1 NO CCI s0.0.6 -WET CCI 0.75 61WP'TCC 021 (3

.- - . 620.3 DRY CCI

NO CCI 640.5 NO CCI 650.4 IWET CCI 0.75 66

WET CCI 0.25 670.1 NO CCI 680.1 NO CCI 69

.1b IWET CCI 0.75 70WET CCI 0 29 71

0.3 C

Figure 19EC-1 Core Debris Concrete Attack DET

RSC 10-15 29 Printed: 10/13/2010


SUPP POOL DEBRIS FLOWS

CORE DEBRIS WATER FLOODS FROM LOWER DW

CONCRETE LOWER DW AFTER TO SUPP POOL EXTENT OF PEDESTALAFTER RADIAL EROSION FAILURE REF #ATTACK DOWNCOMER DWCOE

PEN DOWNCOMERPENPEN

EVENT CCI SPINGRES WW DEB RAD EROS PED

NO PED FAILNO CCI+

VWV DEBRIS

WET CCI

0.7

NO WW DEBRIS0.3

WW DEBRIS0.7

NO WW DEBRIS

SP INGRESSION0.95

NO PED FAIL11PED FAILURE0NO PED FAIL

1/5 110.45 1PED FAILURE

0NO PED FAIL

40181 [1

0.45 PED FAILURE0NO PED FAIL

,40179 0.50.1 PED FAILURE

0.5NO PED FAIL11IPED FAILURE0NO PED FAIL

1/5 10.45 IPED FAILURE

0NO PED FAIL

40181 0.-990.45 PED FAILURE

0.01NO PED FAIL

40179 F0.50.1 IPED FAILURE

0.5NO PED FAIL

1/5 110.45 IPED FAILURE

0NO PED FAIL

40181 0.990.45PEFALR

0.01NO PED FAIL

,40179 100.1 IPED FAILURE

1

0.3

DRY CCI

NO SP INGRESS0.05

Figure 19EC-2 Containment Event Evaluation DET for Pedestal Failure

RSC 10-15 30 Printed: 10/13/2010


EVENT VB VB LEAK LEAK PLUG POOL BP

VACUUM BREAKER VACUUM BREAKER AEROSOLS PLUS SUPPRESSION POOLSTUCK OPEN LEAKS LEAKAGE PATH BYPASS

0.82NO LEAK NO POOL BP

0.9961INOT STUCKOPEN

0.18VB LEAK

0.9PLUG NO POOL BP

0.1NO FW SPRAY SMALL LEAK

0.0039VB STUCK OPEN LARGE LEAK

Figure 19EE-1 Containment Event Evaluation DET for Suppression Pool Bypass

RSC 10-15 31 Printed: 10/13/2010

RSC 10-15

Review and Quality Page

Reviewer Directions:

Provide detailed technical or global editorial comments here. Individual editorial or illustrative commentsmay be electronically provided (tracking) or attached to this review sheet.

Resolution Process:

Originator must provide resolutions for all comments.

Reviewer is to approve all proposed resolutions prior to completing the review process. No review iscomplete until this step is accomplished.

Reviewer Comment Originator Resolution of Comment ReviewerApproval

File Name: RSC-1 0-15 1 Printed: 10/13/2010

enclosure 3 utlr-0014, rev 0 abwr severe accident evaluations · p13 small line break 5.oe-04 k p14...

Documents