UNID S ATE NULA REUATR C- UM I

Senio Tehia Adviso

Ofic of Advsr Comte on Reco Safeguards (ACR

US~- Nula euaoycmiso

Prsented 6at

10th Internatio nal~~~ Prbblsi Saet Asssmn &-aaeetCneec

6 -- - U10

Seatle Wahngo USA- ~~~~

Jue7-1 21

Bc erecun d

Thi prsnato is bsed on a whiteS pape prpae

readn the feasblt of using a sipife appoc

forupatin reut fro eale See- P. suc SOas

SUE- 150 fo coprio wit aset of SOA

resulSts5 **

U= USNCCýýEUL R)CIBCS

ProeehigP*plbjn tetnviones000~ (D 0* 0 :

To prvd hitria pesecie and0

inigt on prviu 0stateof-te-ar

anayse of th cosqecsfsvr

reato accidents0

SOARCA

aciet wer pulihe in th 195 AE

publi hazad reulig from ceti seerhypothetica aciet

- So us of qunittv tehiqe to esia eth

prbblte of suc aciet.Hwvr hr a

a geea agemn httepoaiiyo

ocurec of seer acidnt in nucea 00owe0

rectr wa xedigylw

Reco Sft Std 000 0-A0

-nlue ganayial mehd foa deemnn bot the

- w peii aaeacto des gns weea alyeu *anPec

a- C alcu atin wer aefre aor a au be of acaident

defianeg a sre ofel as catgore a nn ao g an fiv foa r

B int whc all af the idnife acidn aeune coul

be disrib aed

1ý-DG tTk1-2 Re iOev of source TeryachniHCal Basius

oloigh puliato of WASH10 andth

accdn at T 2 wor intae to reie th rditv

mtods fo cacltn fiso prdc release and

tranpor

" Reie reule insvrlcnlsosta ersne

Sinfcn deatr fro WASHS 1400 asumtin

incudngth suggetio tha cs iu ioid (C wilb

th exece prdo inn ioin chmia for Sne

mos potlae 5R accideStSconditions

S Ths stde fome Sh basi S OSelpmn of a C- -

geei se of railoia reeaes chratrie aCs

Sitin Sorc Tem (dntdST-,ue nSni

Sitig Stdy NURE/CR-239

Brief Descriptions of the Characteristics of theAccident Groups

(NUREG-0771, p. 8)

Group 5

Group 4

Group 3

Limited core damage. No failures of engineered safetyfeatures beyond those postulated by the various design basisaccidents are assumed. The most severe accident in thisgroup includes substantial core melt, but containmentfunctions as designed (siting DBA equivalent).

Limited to modest core damage. Containment systems operatebut in somewhat degraded mode (TMI-2 equivalent)

Severe core damage. Containment fails by basemat melt-through.All other release mitigation systems have functioned asdesigned (analogous to Reactor Safety Study PressurizedWater Reactor, PWR, Categories 6 and 7)

Group 2 - Severe core damage. Containment fails to isolate. Fissionproduct release mitigating systems (e.g., sprays, suppres-sion pool, fan coolers) operate to reduce release (analagousto Reactor Safety Study PWR Categories 4 and 5)

Severe core damage. Essentially involves loss of allinstalled safety features. Severe direct breach of contain-ment (analogous to Reactor Safety Study PWR Categories 1and 3)

Group 1 -

9

USARC

UsdStn Souc Tem (S0)t9

exstn or00 prpoe reato sie to pefr

acidn cosqec analyses

NC sugse th folwn rereenatv

-e SST 1 X 10-5m

- S.T2 2S XJ -5S

-* ST 1~ X 10-

S1

Frequecy of Release for Iodine(Comparison of WASH-1400 PWR Release Categories and SSTs)

(D~

U)

U-

xwj

1.00E-03

1.00E-04 -

1.00E-05 -

1.OOE-06 -

1.OOE-07 -

1.00E-08

SST3- -, .. -

" ,- -SST2

-. •SST1

----------- ------- E-

* PWR Release Categories (WASH-1400)

[ Siting Source Terms (NUREG/CR-2239)

4. ---

i $ iI iI

Ivn3

'4%

4;P4%

x

Release Fraction

11

HU '.EG-115ISOS iuiy

int syte beavo an phnmnooia aspecs of 0

seer accidents, 5 *a

-nlso of the ucra ite in th caclain of cor da ag

frqec and riktaaxs eas ficm lt

unertndn o rato ysem ndsvee cidn

-Surry a 3-o Wetngos P R wihasuamspei

-Pec Botm a B R4raco wit a Mar aotimn

- Gran Guf a 5 BW eco0ihaMr I otimn

a a2

Frequecy of Release for Iodine Group(Comparison of WASH-1400 PWR Release Categories, SSTs, and NUREG-1150)

L.U-(D

Uj

1.00E-03

1.OOE-04 .

1.OOE-05 -

1.00E-06

1.00E-07 -

1.OOE-08

1.

SST3..... ... . . [

SST2

SST1. . .. . . .. . . . . . . . . . ---•-. ..- ---

- PWR Release Categories (WASH-1400)

0] Siting Source Terms (NUREG/CR-2239)

-NUREG-1150 Study (Surry) Mean

m m I I A m m mm A m m A I m m A mm A mI I! | ! |

'VAV*

Iv

4 ; ý 'C

Release Fraction

13

ReRssessmen t of Se~cte Facor@s Aftecto'n SWon of

NUCfea Po'wer INan ts

"A seie of prbblsi conequnc assssen

"~~ Inigt frmNR 110 0n h aal

ineedn ris asssmn stde wer use to0

0- AO smal se of sorc tem 4t-o acln)bsdo

doinn plan daag stts acietprgesongop

" Exmie 0osqune in a risbsed frat

cosstn wit th quatiatv healt 00jetive

0Q~)o th NRm Saft Goa Polc

14

Frequency of Release for IodineBased on Representative Source Terms (RSTs) for Surry

Internal Events

60.U.

0*

1.00E-03

1.OOE-04 -

1.OOE-05 -

1.OOE-06

1.OOE-07

1.00E-08

I.

0 RSTs

NUREG-1150

U -

• = = • • • • = • • • l , • • • •••• a

'.4. N e FrcNt, N.Release Fraction

N,.

15

Frequency of Population Dose toEntire Region at Surry

Cu

soILL

I.OOE-03

I.OOE-04

1.OOE-05

1.OOE-06

1.00E-07

I.OOE-08

5P & #V'

Poulation Dose (person-rem)'V

16

Recent Ad.vainces iHn Understando'ng of syeverAfcIlbden P'henanienaI@ *y aind Can ainment

Fai~ure 'Iechainiosrn

e Sic th copeto of SUE 5

Stdy mor anltia an experimental

stuie hav bee pefre toddes

man seer acidn isue including:

Dirc Cotimn Hetn (DH Issue

- M r ie Atak Isu

-~~ Invse0ta xlso apamd

failure) S.

01

[Reaula sof a hefr LsveI-3 PRAs

way to bechar th SC mehoolAy

reut n nihsfo tAe NE-1 5

Std an Inerae R isk Asssmn fo

Laale toete wit mor Seen advancesin

of suc earlier rrv - P sfrcm aio

wit asetso SOAC results 5.

* - * - - *A8

:305'_

LOSPA- ~ .4~ ~

ALOSP

LOSP

r 1.00E-03

c. 1.00E-04 z •

2 NUREG-1 150. 1.OOE-0O

I.OOE-06

CU RSTs based on NUREG-1150 Study

" 1.00E-07 m RSTs based on results of SPAR Model and no ECF

I. O ,0 E-08 ' . . .. : . . .. . . .. ; • "

x

Release Fraction

0Px

Summnary aznd Cend leHn

An ovrve of mao cotiuin tocneqec

asesmn wa prsne to proid histrica

NUE 5 Std an Inerae Risk Assssen

fo Laale toete with mor reen adane in

unestadn of th seer acidn isue and--0 -

cotimn falr mehnss an deeo a - 5

sipiid yet sytmai an deesbe approac to.55

becmrkmn aset of SARnA