ML19345B600

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Viewgraphs Entitled Environ Impact of Postulated Accidents
ML19345B600
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/17/1980
From:
NRC COMMISSION (OCM)
To:
Shared Package
ML19345B596 List:
References
REF-10CFR9.7 NUDOCS 8012020166
Download: ML19345B600 (19)
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Text

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TABLE OF CONTENTS 1

n 6.

ENVIRONMENTAL IMPACT OF POSTULATED ACCIDENTS l-6.1 PLANT ACCIDENTS 6.1.1 6ENERAL CHARACTERISTICS OF ACCID.ENTS j.

'6.1.2 ACCIDENT EXPERIENCE AND OBSERVED IMPACTS 6.1.3 MITIGATION OF ACCIDENT CONSEQUENCES S.1.4 ACCIDENT RISK AND IMPACT ASSESSMENT 6.

1.5 CONCLUSION

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8 012020]$

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6.1.1 GENERAL CHARACTERISTICS OF ACCIDENTS' 6.1.1.1 FISSION PRODUCT CHARACTERISTICS IN-PLANT SOURCE LOCATIONS CORE INVENTORY SPENT FUEL PRIMARY COOLANT WASTE HANDLING SYSTEMS FISSION PRODUCT PROPERTIES RELATIVE VOLATILITIES RADIOACTIVE DECAY 6.1.1.2 EXPOSURE PATHWAYS COMPARISON TO NORMAL OPERATIONAL RELEASES ADDITIONAL LIOu1D PATHWAYS DISPERSION DURING IRANSPORT 1

b

)

6.1.1 GENERAL CHARACTERISTICS OF ACCIDENTS (CONT'D.)

6.1.1.3 HEALTH EFFECTS HIGH DOSES - FATAL INJURIES L0w DOSES - CANCER RISK v

3 6.1.1.4 HEALTH EFFECTS AVOIDANCE ECONOMIC AtlD SOCIETAL IMPACTS

t 6.1.2 ACCIDENT EXPERIENCE AND OBSERVED IMPACTS i

LICENSED POWER REACTOR EXPERIENCE c

CA 500 REACTOR - YEARS

~

i IHREE MILE ISLAND-2 EXPERIENCE RELEASES EXPOSURES PSYCHOLOGICAL IMPACT ACCIDENTS AT OTHER REACTOR FACILITIES CORE MELTING AT FERMI-J.

~

IODINE RELEASE AT WINDSCALE i

1 f

6.1.3 MITIGATION OF ACCIDENT CONSEQUENCES 6.1.3.1 C? SIGN FEATURES CONTAINMEf4T ECCS CONTAINMENT HEAT REMOVAL CONTAINMENT SPRAYS FILTER SYSTEMS TMI-2 LESSONS LEARNED REQUIREMENTS 4

e l

6.1.3 MITIGATION OF ACCIDENT CONSEQUENCES (Cont'D,)

6.1.3.2 SITE FEATURES EXCLUSION AREA L0w POPULATION ZONE POPULATION CENTER DISTANCE EXTERNAL HAZARDS 6.1.3.3 EMERGENCY PREPAREDNESS COMPLIANCE WITH NEW RULES

s.

1 i

6.1.4 ACCIDENT RISK AND IMPACT ASSESSMENT 6.1.4.1 DESIGN BASIS ACCIDENTS t

SAFETY EVALUATION CLASSIFICATION SCHEME a

i REALISTIC DOSE CALCULATIONS TABLE 6.1.4-1, INDIVIDUAL l

POPULATION DOSES l

SAFETY EVALUATION DOSE CALCULATIONS j

NON-DEGRADED CONTAINMENT I

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J 1

e a

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TABLE 6.1.4-1 Approximate Radiation Doses from Design Basis Accidents Dose (rem) at 1 Mile Duration Infrecuent Accidents of Release Whole Body Thyroid Waste Gas Tank Failure

<2hr.

0.04 nil (1)

SmalhBreak LOCA hrs-days 0.02

< 0.001 (2)

Steam Generator Tube Rupture

< 2 hr.

0,03

< 0.001 Fuel Handling Accident

< 2 hr.

0.10

< 0.005 Limiting Faults Main Steam Line Break

< 2 hr.

0.0005

< 0.001 Control Rod Ejection hrs-days 0.06 0.1 Largc-Break LOCA hrs-days 0.60

< l.0 (1)

LOCA-Loss of Coolant Accident; the TMI-2 accident was one kind of a small-break LOCA.,

(2)

See NUREG-0651 (Reference 5) for descriptions of three steam generator tube rupture accidents that have occurred in the United States.

< means "less than" i

, -=m;

. +..

6.1.4 ACCIDENT RISK AND IMPACT ASSESSMENT (CONT'D.)

6.1.4.2 PROBABILISTIC AS9ESSMENT OF SEVERE ACCIDENTS REACTOR SAFETY STUDY METHODOLOGY -

ATMOSPHERIC RELEASES RELEASE CATEGORIES AND PROBABILITIES TABLE 6.1.4-2 CONSEQUENCE MODEL SITE-SPECIFIC ENVIRONMENTAL PARAMETERS METEOROLOGY POPULATION HABITABLE LAND FRACTION LAND USE - STATE-WIDE BASIS 6.1.4.3 DOSE AND HEALTH IMPACTS OF ATMOSPHERIC RELEASES NO PROTECTIVE ACTIONS ASSUMED FIGURES 6.1.4-2 THRU -5 TABLE 6.1.4-4 6.1.4.4 ECONOMIC AND SOCIETAL IMPACTS FIGURE 6.1.4-6 4

.c

l ABLE 6.1.4 -2 i

p SONMARY Of A1H051'lilRIC RELEASE CAllG0 RIES REPRESENTIN'i ItYP0illETICAL ACCIDENTS IN A PWR l

(a)

Fraction of fore Inventory Released 4elease Prohah'ility (b)

(c)

I tiateggy

( reac t or-yr -I)

Xe-Kr I

Cs-Rb Te-Sh Ba-Sr Ru La (d)

-8

-3 PWR 1 S.I a 10 0.9 0.7 0.4 0.4 0.05 0.4 3 x 10

/

-6

-3 PWR 2

/ x 10 0.9 0.7 0.5 0.3 0.06 0.02 4 x 10

-6

-3 PWR 3 2.3 x 10 0.8 0.'(

0.2 0.3 0.02 0.03 3 x 10

-11

-3

-3

-4 PWR 4 2.I x 10 0.6 0.09 0'.04 0.03 5 x 10 3 x 10 4 x 10 l

1 :

-8

-3

-3

-3

-4

-5 l'un S S x 10 0.2 0.03 9 x 10 5 x 10 1 x 10 6x10 7 x 10

-7

-3

-4

-3

-S

-S

-S PWR 6 6 x 10 0.3 3 x 10 8 x 10 1 x 10 S s 10 7 x 10 1 x 10

-5

-3

-5

-5

-S

-6

-6

-7 PWR /

4 x 10 6 x 10 4 x 10 I x 10 PA 10 1 x 10 1 i 10 2 x 10 1

-S

-3

-4

-4

-6

-8 PWR 8 4 x 10 2 x 10 I x 10 5 x 10 1 x 10 I x 10 0

0

-4

-6

-7

-7

-9

-11 0

0

?

PWF 9 4 x 10 3 x 10 1 x 10 6 x 10.

1 x 10 1 x 10 (a) Bacl yound on the isotope groups 401 release mechanisms is presented in Appendix Vil, WASil-1400 (Ref.8 ).

(b) includes Ru, Rh, Co, No. Tc.

(c) Includes Y La, Zr, Nb, Ce, Pr, Nd, Np, Pu, Am, Cm.

1 (d) Current understanding of the phenomenon of contairsnent failure by steam explosion enbodied in this release category indicates that this probability should be lower than stated.

NUTE: Please refer to Section 6.1.4.6 for a discussion of uncertainties in risk estimates.

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i s

16. 1. 4 ' ACCIDENT RISK AND IMPACT ASSESSMENT (CONT D.)

6.1.4.5-

-CONSIDERATION OF.POSSIBLE RELEASES To GROUNDWATER l

COMPARISON TO LIQUID. PATHWAY GENERIC STUDY DRINKING WATER 4

IRRIGATION AQUATIC FOOD CONSUMPTION-SWIMMING AND SHORELINE USAGE

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r

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.,---np.m...

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,--r---

y

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. 6.1.4 ACCIDENT RISK AND. IMPACT ASSESSMENT (CONT'D.)

6.1.4.6 RISK CONSIDERATICNS i

RISK AS PROBABILITY TIMES CONSEQUENCES TABLE' 6.1.4-5 ADDITIONAL ECONOMIC RISK i

DECONTAMINATION REPLACEMENT POWER 4

6.1.4.7 UNCEP.~AINTIES Lew1S COMMITTEE FINDINGS flMMISSION POLICY STATEMENT TMI-2 EXPECTATION NRC ACTION PLAN ITEMS NOT REFLECTED I

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E

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i x

--r Al g-3 so i

5

~

10 "

S

~

E5 10-5

- ~ ~ -

-~--

10-'

=

x y

-r g

I hHCLE SCDY DOSE z 25 REM io-7 THYROID DCSE 2 306 REM

/

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{

wm_E BCDY DCSE z 200 REM m.

L 10-s

=

o

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E i

~

m t

i 10 10 10 10 10 10' 2

8 4

5 X = IUEER T k'TECTED PERSCMS FIGURE 6,1A - 2 FRCEABILITY DISTRIBUTIONS CF INDIVIDUAL COSE IffACTS NOTE: Please see Section 6.1.4.6 for discussion of uncertainties in risk estimates.

w +-m as= %

E 10-1.

POP IATICU WipilN WE '

i C0fJIGUOUS U.u m

10'#

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I

,g to-6

8 n

h 4

10 5

E g

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U 10-8 I

s 25 o

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10-'

~

g

~

10 10 10' 10' 10

!Os go9 7

3 4

X = TOTAL Ml-REM (hELE BODY)

  • FIGm E 6,1.4 - 3 PROP.ABIUW DISBIBUTIONS T PCPULATION EXFOSURES NOTE: Please see Section 6.1.4.6 tor aiscussion of uncertainties in risk estimates.

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10-4 x

n c.nW t-10'f y

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u.

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M 10-'

W i

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10-7 3

E E

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10-a

=

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to ' :-

=

m, 2

3 4

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10 10 10 10 10 10' X = A0JTE FATALITIES FIGLE 6.1.4 - 4 PRCBABILITY DISTRIBUTICfi T MUTE FATALITIES

.;0TE : Please see Section 6.1.4.6 tar discussion of ancertainties in risk esti. atas.

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10 10-5 wlm!N TH CCtRIGUCL ; U. S.

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x

$,_0 30-6 wlmlN 50 MILES d

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10-l E

165 i

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c.

A B

6 3

4 105 10 1

10 102 10 ~

10 X = LArtNT CNER FATfLITIES Ff_R Ft/R FIGEE 6.1.4-5 FROBABILITY DISTRIBUTION OF LATENT CAfiCER FATM.ITIE PER YEAR FCa 30 YEAaS NOTE: Please see Section 6.1.4.6 tor discussion of uncertainties in risk estimates.

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TABLE 6.1.4-!

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t-SUIEARY OF ENVIRONMENTAL IMPACTS AND PR0bABILITIES j

D Probability Persons Persons Acute Population Latent *

  • s i t of impact Exposed Exposed Fatalities Exposure Cancers Cost of Offsite Per Year over 200 rem over 25 rem Millions of man-rem 50 mij Mitigating Actions 60/mi/ Total Totai Millions nf on11are 10

<1

<1

<l 4 0.001

<30

<.001

-4 2

10

<g

<g

<l 0.3

<30 80 5.

-5 T

1

-6 5 x 10 750 8,000 20 70/100 7,500/1b,000 200 r

n 10 5,000 60,000 700 150/200 15,000/22,500 1,000

-6 k

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-7 10 20,000 150,000 8,000 200/300 27,000/33,000 2,000 a

9

-8 3,000 200,000 60,000 J,

10

.l Related

(.)

Figure 6.1.4-2 6.1.4-2 6.1.4-4 6.1.4-3 6.1.4-5 6.1.4-6 exposuresandacutefatalitiestosmallfractkonsofthenumbonablerss000rotectiveacti No protective actions are assumed.except for co t imp cts. Hea n.

.

  • Genel.ic effects would be approximately twice the number of latent cancers. Thirty times the values shown in the g

l Figure 6.1.4-b are shown in this column retlecting tne tnirty year period over which they might occur.

Please, refer to Section 6.1.4.6 for a discussion of uncertainties in risk estiniates.

NOTE:

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-3 LO

-4 10 N

n

-t; Lo t

=

w8 i

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_7 5

LO i

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=d

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2 8

-8 Lo

=

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-9 10 10 10f 1 O '~

40'

.l.O 10*

109 X = TOTAL COST t.8 ECu#S GEdO)

FIGLFE 6,1.4 - 6 PRCEABILIT/ DISTRIBUTION CF COST CF CFFSITE MITIGATION PEASURES t'UTE : Please see Section 6.1.4.6 tor discussion of uncertainties in risk estimates.

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1.5 CONCLUSION

S 1

IMPACTS ARE POTENTIALLY SEVERE BUT HAVE SMALL LIT.ELIHOOD OF OCCURRENCE (A)

HISTORICAL EXPERIENCE (B)

COMPLIANCE WITH REGULATIONS (C)

PROBABILISTIC RISK ASSESSMENT RISKS COMPARABLE TO NORMAL OPERATIONS WHEN PROTECTIVE ACTIONS IAKEN NO UNIQUE CIRCUMSTANCES AT SuMecR l

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I NUREG-0534 Supplement Draft Environmental Statement related to the operation of Virgil C. Summer Nuclear Station Unit No.1 Docket No. 50-395 South Carolina Electric and Gas Company U.S. Nuclear Regulatory l

Commission i

Office of Nuclear Reactor Regulation November 1980 p%

o (bd.)

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I DUPLICATE DOCUMENT l

i Entire document previously entered into system under:

ANO 2Q h\\ME%6 i

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of pages:

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