ML19340D740

Slide Presentation Entitled Encl Bldg Presentation

ML19340D740
Person / Time
Site:	Vogtle
Issue date:	12/22/1980
From:	GEORGIA POWER CO.
To:
Shared Package
ML19340D738	List: ML19340D737 ML19340D740
References
NUDOCS 8101050257
Download: ML19340D740 (8)

Text

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i ENCLOSURE 3-1 ENCLOSURE BUILDING PRESENTATI0fl I

INTRODUCTION AND STATUS II INCREASE EMPHASIS ON LEAKAGE REDUCTION WHILE MAINTAINING LEAKAGE MITIGATION i

111 COMPARIS0tl 0F DOSES TO SER-APPROVED BASES i

A.

ASSUMPTIONS AND METHODOLOGY j

B.

RESULTS IV

SUMMARY

AtlD CONCLUSIONS t

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J ENCLOSURE 3-2 INCREASE EMPHASIS ON:

i LEAKAGE REDUCTION WHILE MAINTAINING THE LEAKAGE MITIGATION CAPABILITY OF FILTERED PENETRATION AREAS i

RESULTING IN AN OVERALL INCREASE IN CONSERVATISM I

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ENCLOSURE 3-3 FSAR CALCULAT10li ASSUMPTIONS USED TO EVALUATE RADI0 ACTIVITY RELEASES FOR A LOSS OF COOLANT ACCIDENT (REGULATORY GUIDE 1.4, REVISION 2 BASIS) 100% OF CORE NOBLE GASES AND 25% OF CORE IODINE AVAILABLE FOR RELEASE FROM CONTAINMENT CONTAINMENT LEAK RATE 0-24 HRS, 100% OF DESIGN 24-720 HRS, 50% 0F DESIGN DISTRIUTION OF 10 DINE 91% ELEMENTAL 4% ORGANIC 5% PARTICULATE C0flTAINMENT MIXING (MINIMUM SAFEGUARDS FAN COOLERS) -- 85,000 CFM SPRAYED CONTAINMENT VOLUME -- 78%

ELEMENTAL 10 DINE LAMEDA -- 10.0 HR-1 ELEMENTAI. 10 DINE DF -- 100 FOR ENTIRE VOLUMNE PARTICULATE LAMBDA -- 0.4 HR-1 PARTICULATE DF -- 100 FOR SPRAYED VOLUME GROUND LEVEL RELEASE - REG. GUIDE - 1.4 BREATHillG RATES PER REG. GUIDE - 1.4 DOSE CONVERSION FACTORS PER REG. GUIDE - 1.109 3

X/0 (SEC/M ) REG. GUIDE - 1.145 BASIS (BASED ON 3-YEA'l SITE DATA) 0-2 HR 0-8 8-24 24-96 92-720 SITE BOUNDARY 1.8(-4)

LPZ 3.3(-5) 2.2(-5) 9.2(-6) 2.7(-6)

FSAR DOSE COMPARIS0N FSAR CALCULATION SER CALCULATION (N0 LEAKAGE 10 CFR 100 (0RIGINAL EB, FILTRATION CREDIT LIMITS 0.3%/ DAY) 0.2%/ DAY)

EXCLUSION AREA BOUNDARY THYROID (REM) 300 122 111 m

3 WHOLE BODY (REM) 25 7

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5 LOW POPULATION ZONE THYROID (REM) 300 70 73 4

WHOLE BODY (REM) 25 8

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FSAR DOSE COMPARISON m,_

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FSAR CALCULATION FSAR CALCULATION SER CALCULATION (N0 LEAKAGE (N0 LEAKAGE 10 CFR 100 (0RIGINAL EB, FILTRATION CREDIT FILTRATION CREDIT LIMITS (0,3%/ DAY) 0.3%/ DAY) 0.2%/ DAY) l 1

EXCLUSION AREA BOUNDARY l

j THYROID (REM) 300 122 167 111 h:

8 WHOLE BODY (REM) 25 7

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Y LOW POPULATION ZONE THYROID (REM) 300 70 110 73 WHOLE BODY (REM) 25 8

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i ENCLOSURE 3-6

SUMMARY

AND CONCLUSIONS e

CONSTRUCTION PERMIT STAGE UNCERTAINTIES RESOLVED, o

INCREASED EMPHASIS ON LEAKAGE REDUCTION WHILE MAINTAINING LEAKAGE MITIGATION CAPABILITY INCREASES RELIABILITY OF CALCULATED DOSES, e

REDUCTION IN CONTAINMENT LEAK RATE INCREASE CONSERVATISM 0F DESIGN, e

PRESTRESSED CONCRETE CONTAINMENT WITH WELDED STEEL i

LINER CAN READILY ACHIEVE LOWER LEAK RATES, e

CURRENT VNP DESIGN IS COMPARABLE TO OTHER LICENSED Ft.CILITIES, il o

PLANT DESIGN INCORPORATES ADDITIONAL CONSERVATISM, l

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ENCLOSURE 4

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Docket flos. 50-424 g; 1 G 1200.

and 50-425 l

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Lester Rubenstein, Chief Light Water Reactors Branch !10. 4, DPM FROM:

L. G. Hulman, Chief

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Hydrology-fieteorology Branch, DSE

SUBJECT:

METEOROLOGICAL REVIEW CONCERNING ENCLOSURE BUILDING MODIFICATIONS FOR ALVIN W. V0GTLE NUCLEAR UNITS 4

We have reviewed the X/Q values presented in Table 158-2 of Supplement 6 of the Vogtle PSAR. Based on meteorological information provided on December 7,1979 i

l by Georgia Power Company, we conclude that X/Q estimates made using the three year period, December 4, 1972 through December 4, 1973 and April 3, 1977 through April 4, 1979, better represents atmospheric dispersion conditions at the Vogtle site thEn estimates based on the April 3, 1977 through April 3, 1978 period alone which was used by the applicant in making the dispersion estimates which appear in Supplement 6.

We have independently evaluated the atmospheric l

dispersion estimates provided in Attachment 4 of the December 7,1979 submittal and conclude that these X/Q values are appropriate for use in determining the acceptability of enclosure building modifications for the Vogtle Nuclear Power l

Plant.

Our estimates are as follows, The highest exclusion area boundary 0.5 percent direction dependent X/Q estimate which occurred in the south direction was L

1.8 x 10-4 sec/m3 at a distance of 1060m, based on the technique discussed in Regulatory Guide 1.145, " Atmospheric Dispersion Models for Potential Accident Consequence Assessnents at Nuclear Power Plants," and the cumulative frequency distribution of hourly X/Q' values. The X/Q values calculated for the low population zone distance of 3218m in the south direction for various time periods up'to 30 days which are listed below are based on the Regulatory Guide 1.145 technique. These values are the applicant's estimates which we have indepen-dently verified.

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X/Q (sec/m3) 3.3 x 10-5 1

0-8 hours 2.2 x 10-5 1

8-24 hours 6

1-4 days 9.2 x 10 6 2.7 x 10-4-30 days 4

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At L. G. Hulman, Chief

.v Hydrology-Meteorology Branch Division of Site Safety and Environmental Analysis I

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