ML20214G781
| ML20214G781 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/24/1972 |
| From: | Harold Denton US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0103, CON-WNP-103 NUDOCS 8605220500 | |
| Download: ML20214G781 (12) | |
Text
,
AUG 2 4 572 h
R. S. Boyd, Assictant Director for BWR's, L s
METEOROLOGY SITE AND ACCIDENT SECTIONS FOR REPORT TO ACRS PLANT NA!E: Hanford No. 2 LICENSING STAGE: CP DOCKET NUMBER: 50-397 EESP0;SIELE BPl.NCll: LWR Br. #3 REll'ESTED C01:FLETI0n DATE: August 17, 1972 AFFLICAETS RESPOESS DA~E KECESSARY TO3 IT.XT ACTICU PLA!:ID 03 FF0JECI: Non:
DESCRIPTIOT OT RESP 0 Ir: TA REVIE'J STATUS: Analysis Cc:::plete Attechn 3 are the tieteorolocy ani cit? an1 a^cident anelysit. w eticac for inclusion in th: report to the ACRC on the subject plant.
3 o 1::teer: logy section var prepa*e1 by E. H. Markec, Jr., Ci;c Anal;rsis Branch, L.
The Site ani Accident Analycis coction ver prepared by R. Smith, Effluent Treatment Systems Brcnch, L.
DISTRIBUTICit Dochet File 397 /
Orimnal star.ed by y
g, g,p,go,
L - Edg L:AD/SS-Rdg lic.rcli R. Denten, Assistant Diractor L:SAE - Edg for Eite Enfety Directorate of Iicensir.g Enciccure:
Ac stated ces v/oenclocure A. Giambucce W. Mcdonald een w/eneleeure E. H. Hanauer J. !!endric W. Gaernill, L R. Clerk, L S. !!iner, L J. Ecetner, L E. H. Markee F. Ettith orna >
.......t wa..
2 ma...
..t: AvI)......
L.--..-
mj $1m.. M[N.an.....muka.
.c....,4,,.in k. = M M'. L.
M 2 R..=,....=..
om>
e m om l.,....~,..,_,,..a 8605220500 720024 PDR ADOCK 05000397 F
1W.TORD NO. 2 DOCKET UO. 50-397 ACR3 REPORT INPUT METEOROLOGY The plant will be cituated on the IIanford Reservation in the Columbia River basin which hac the lowest elevation in central Washington. The climate of the area is continental steppe.
Airflow over the cite area is predominantly northwesterly due to channeling by topography.
Accident and annual averace diffusion conditionc expected for the plant site have been evaluated from measurements of wind direction, wind cpeed and vertical temperature difference ( AT) en 4 LlO-foot tower located at the }!anford Meteorological Station (ICC,) approximately 11+ milec northwect of the plant cite. This tower has provided measuremente of wind directicn, wirld cpeed and temperature at ceveral levela since 1955. Based on a comprcmice between data recovery and cuitable meteorological measurement heights, 16 years of data record (1955-1970) were colected and precented by the applicant in joint frequency diutribution form for evaluation of diffucion conditions at the cite. n e meteorological parametere used in the evaluation are wind direction at the 200 foot level, wind cpeed measured at the 200-foot level and reduced to the 33-foct icvel using a power Inw reduction factor of wind epced with height, and vertical temperature difference betwoon the 250- and 50-foot levels.
In evaluation of diffusion of short-term accidental releases from the plant, a ground level release with a building wake factor, cA, of 1435 m wac assumed. The relative concentration (X/Q) which is exceeded 5% of the time was calculated from the joint frequency of wind speed and6T class to be 2.45 x 10*k see/m3 at the exclusion radiuc dictance of 1950 m.
This relative concentration is equivalent to dispercion conditions produced by pacquill type F stability with n wind cpeed of 0.7 meters /second. The applicant has used a value which is less conservative by more than a factor of two due to his assumpticns of an elevated release, stable condition with a wind speed of one meter /second and diffusion rates that are different from pacquill'c.
For longer time period accidental releaces, the relative con-centrations presented in Safety Guide L appear to provide adequately conservative estimates for the outer boundary of the zero population zone (L829 m).
The maximin offsite annual average relative concentraticn estimate is L.9 x 10-7 sec/m3attheHanfordReservation boundary 6h00 m southeact of the plant site. The applicant hac uced a value which is lesc concervative by about a factor of two.
It is known from past studiec at different locations on the Hanford recervation that the distribution of wind direction frequenciec will be different at the plant cite from those at 1
l
ICC due to increased druimge flow probability from the north-eact thuc decreasirg the frequency of northwest vinds. However, only small variaticnc in the frequency of occurrence of sta-bility clacsca are expected. Therefore, we conclude that the meteorological data precented in the PSAR provide an acceptable bacia for the calculation of preliminary atmospheric dilution factora for use in the staff'c accident doce models and provide a basic for the calculation of concervative annual avera6e dilution factors. The applicant plans an chaite meteorolcgical program with inctrumentation in accordance with Cafety Guide 23 recommendations which will begin late in 1972. The data frem this program will be used to verify the preliminary atmocpheric dilution factors and to calculate the effects of operational relcaces of gaceouc effluents.
P m.-_
I SITE DESCRIPTION Hanford No. 2 is located on the U. S. Atomic Energy Cc= mission's Hanford Reservation, in Benton County, Washington. The closest reservation boundary to the site is approximately three milec.
There are no areas of dence population within 10 miles of the site; i.e., 150 people from 1970 census and h50 pecple projected in 2015 live within 10 milec of the site. The Fast Flux Test Facility (FFIF) is being constructed two and three-quarters miles frcm the cite.
The applicant has specified a minimum exclucien area radius of 1950 meterc (1.2 miles) and a low population zone (LPZ) of 4620 meterc (3 milec). Both of these areas are completely within the Hanford Reservation, and therefore, have zero permanent population.
The FFTF, which will be the only facility within the LPZ, will have about ninety persons en a normal day shift and fifteen perconc cn evening and night shifts. The nearest population center in Richland, Wachington, which is twelve miles from the-site.
Land use within Benton County is primarily farming, with the principal crop being grain, vegetables, and livestock feed.
Come land is used for pasture for cattle, pigs, cheep, poultry, and horsec. The larrect industrial facility off the Hanford Recervation in ten milco from the site and will have no significant effect on the site.
F Based on our evaluation of the population data and land use, we conclude that the distances established for the exclusion zone, the low population zone and the nearest population center neet the criteria given in 10 CFR Part 100.
t e
S
f PIJJ;T SAFETY K;AI,YSIS We have calculated the doces for the period 0-2 hours at the exclusion radius and the course of the accident at the low population zone which would result fraa the loss-of-coolant accident, the refueling accident, the control rod drop i
accident and the steam line break' accident. The calculated doses for each of these accidents are presented in Table 14.1.
'ihey all nect the criteria presented in 10 CFR Part 100, be.ced on the respective accumptions present6d in Tables 14.2, 1L.3, 14.4 and 1L.5.
We alro considered the gas decay tank failure accident, and concluded that Technical Specification limits can be placed en the maxis:um radioisotopic content in the decay tanks such that calculated doses will be ',cc11 within the criteria of 10 CFR Part 100.
I e
D 4
I s
t
I Table 11,. 1 Calculated Offsite Doses 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Dose at Course of Accident Site Boundary (Rem)
Accident Thyroid Whole Body Thyroid Whole Body LOCA 110 15 160 10 Refueling 1
<1
<1
<1 Control Rod Drop 3
<1
<1
<1
<1
<1 Steam Line Break 3
<1
Table 14.2 Loss of Coolant Accident (LOCA) Assumptions 1.
Power level of 3458 MWt 2.
100% release of noble gases, 50% release of iodines to coolant; 50%
of iodines plate out in reactor vessel 3.
8% of iodines available for leakage is in an organic fom; 5% in a particulate fom 4
Design containment leak rate of.5% per day for duration of accident 5.
Meteorology (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period)
Pasquill T Stability and windspeed of 0.7 m/see with credit for building 2
wake (2900 m, cross-sectional area) 6.
Exclusion radius = 1950 meters 7.
Low populatien zone = 4830 meters 8.
Charcoal filter efficiency Organic 90%
Elemental 95%
I Table 14.3 Refueling Accident Assumption
-1.
Power level 3458 MWt 2
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay period 3.
Peaking f actor of 1.5 4.
49 fuel rods are damaged.
5.
10% of the noble gases and 10% of the iodines are released to fuel pool water.
6.
Fuel pool water retains 99% of the released iodines; none of the noble gases 7.
Composition of the iodines above the pool is.25% organic and 99.75% elemental 8.
Charcoal filter iodine removal efficiency is 90% or organic and 95%
for elemntals,
i 9.
Meteorology same as for LOCA 10.
Doses is delivered within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 11.
Exclusion radius and low population zone same as for LOCA i
i
l Table 1k;h Control Rod Drop Assumptions 1.
Power level 3458 MWT 2.
30 minute decay period 3.
Peaking factor of 1.5 t
4 330 fuel rods are damaged 5.
100% release of noble gases 50% release of iodines 'from danaged rods to coolant; 50% of iodines plate out in the reactor vessel.
6.
Meteorology same as LOCA 7.
Exclusion radius and low population zone are same as for LOCA 8.
Leak rate from turbine and condenser is.5% for one day
Table 14.5 Steam Line Break Assumptions 1.
Power level 3L 8 MWt 5
2.
Steam line isolation values close in 10.5 seconds 3.
Radioactivity in the coolant is k times the design objective concentrations h.
Iodine carry-over during the accident is 10 tfines worse than normal 5.
All the iodine and noble gases from the released coolant are released to atmocphere within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at a height of 30 meters 6.
Metecrolog same as LOCA
.