ML19221A855
| ML19221A855 | |
| Person / Time | |
|---|---|
| Issue date: | 03/23/1972 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.025, REGGD-1.025, NUDOCS 7907100118 | |
| Download: ML19221A855 (10) | |
Text
'
3/23/7 SAFETY GUIDE 25 ASSUMPTIONS USED FOR EVALUATING THE POTENTIAL RADIOLOGICAL CONSEQUENCES OF A FUEL HANDLING ACCIDENT IN THE FUEL HANDLING AND STORAGE FACILITY FOR BOILING AND PRESSURIZED WATER REACTORS A. Introduction during a fuel handling accident. Although the design of the fuel, the fuel transfer equipment, Section 50.34 of 10 CFR Part 50, thq fuel pool, and the methods used to handle
" Contents of Applications: Technical discharged fuel should all be considered in Information," requires that each applicant for a arriving at the number of fuel assemblies or rods construction permit or operating license provide assumed to be damaged, this guide rather than an analysis and evaluation of the design and being addressed to this determination is per fo rmance of structures, systems, and ad dressed to the determination of the components of the facility with the objective of radiologeal consequences of a handling accident assessing the risk to public health and safety once an asumption as to the number of resulting from operation of the facility. A fuel assemblies or roos damaged has been made.
handling accident in the fuel handling and A conservative approach to determining the storage facility resulting in damage to fuel quantity of radioactive material available for cladding and subsequent release of radioactive release from a fuel assembly is to assume that material is one of the postulated accidents used the assembly with the peak inventory is the one to evaluate the adequacy of these structures, damaged. De inventory for the peak assembly systems, and components with respect to the represents an upper limit value and is not public health and safety. This safety guide gives expected to be exceeded. The inventory should acceptable assumptions that may be used in ha calculated assuming maximum full power evaluating the radiological consepences of this operation at the end of core life immediately accident for boiling and pressurized water preceding shutdown and such calculation should reactors.
include an appropriate radial p' aking factor.
e Only that fraction of the fission products B. Discussion which migrates from the fuel matrix to the gap and plenum regions during normal operation A fuel handling accident during refueling would be available for immediate rease into operations could release a fraction of the fission the water in the event of clad damage.
product inventory in a nuclear power plant to (Migration of fission products is a function of the environment. An illustrative accident s everal variables including operating sequence consists of the dropping of a fuel temperature, burnup, and isotopic half life taken assembly resulting m breachmg of the fuel rod into consideration in eMablishing the release cladding, release of a portion of the volatile fractions listed in this guide.) As compared to fission gases from the damaged fuel rods, the quantity immediately released, the quantity absorption of water soluble gases in and of radioactive material released subsequent to transport of soluble and insoluble gases through the immediate release is consMered for the the water, air filtration (if provided) prior to purposes of this guide to be negligible.
release into the environment, and dispersion of The assumptions set forth in this guide are the released fission products into the based on engineering judgment and results from atmosphere.
safety research programs conducted by the AEC The number and exposure histories of fuel and the nuclear industry and are believed to be assemblies assumed to be damaged determine appropnately conservative. In some cases the total amount of radioactive material unusual site -characteristics, plant design available for immediate release into the water features, or other factors may require different
}h 25.1 79071001/8
assumptions which will be considered on an e.
The values assumed for individual' individual case basis. Major changes in fuel fission product inventories are composition or management may also require calculated assuming full power alterations of these assumptions.
operation at the end of core life immediately preceding shutdown C.
Regulatory Position and such calculation should include an appropriate radial 1.
The assumptions' related to the release peaking factor. The minimum of radioactive material from the fuel acceptable radial peaking factors and fuel storage facility as a result of a are 1.3 for BWR's and 1.65 for fuel handling accident are:
PW R's.
a.
The accident occurs at a time after f.
The iodine ga p inventory is shutdown ide ntified in the composed of inorganic species technical specifications as the
( 99.757c) and organic species earliest time fuel handling
(.25% ).
operations may begin. Radioactive g.
The pool decontamination factors decay of the fission product for the inorganic and organic inve ntory during the interval species are 133 and I, respectively, between shutdown and giving an overall effective commencement of fuel handling decontamination factor of 100 operations is taken into (i.e.,
99?c of the total iodine consideration.
released from the damaged rods is b.
The maximum fue1 rod retained by the pool water). This pressurization is 1200 psig.
difference in decontamination 2
c.
The minimum water depth factors for inorganic and organic 2
between the top of the damaged iodine species results in the iodine fuel rods and the fuel pool surface above the fuel pool being is 23 feet.
composed of 757e inorganic and d.
All of the gap activity in the 257c organic species.
damaged rods is released and h.
The retention of noble gases in the consists of 10% of the total noble pooI is negiigibie (i.e.,
gases other than Kr-85,30% of the decontamination factor of 1).
K'-8 5, and 107c of the total i.
The radioactive material that radioactive iodine in the rods at escapes from the pool to the the time of the accident. For the build e.g is released from the 3
purpose of sizing filtcis for the fuel building over a two hour time handling accider't addressed in this period.
guiie, 30?c of the 1-127 and 1-129 j.
Ifit can be shown that the building inventory is assumed to be released atmosphere is ex6usted through from the damaged rods.
a dsorbers designed to remove iodine, the removal efficiency is 1he assumptions given are valid only for oxide 907c for inorganic species and 707c 8
fu 1s of the types currently in use andin cases where the for organic species.*
fcnlowing conditions are not exceeded:
k.
The effluent frc a the filter system Peak hnear power density of 20.5 kW/ft for the passes directly to the emergency a.
highest power assembly discharged.
exhaust system without mixing in 5
b.
Maximum cen,ter-Une operating fuel temperature The effectiveness of features provided to reduce 3
less than 4500 F for this assembly.
the amount of radioactive material available for release c.
Average bumup for the peak assembly of 25,000 to the environment will be evaluated on an indivHu:J MWD / ton or les3 (this corresponds to a peak local case basis.
bumup of about 45,000 MWD / ton).
- These efficier.cies are based upon a 2. inch charcoa!
For release pressures greater than 1200 psig and bed depth with % second residence time. Efficiencies 2
water depths less than 23 feet. the iodme may be different for other systems and must be decontamination factors will be less than those assumed c iculated on an individual case basis m this guide and must be calculated on an individual Credit for miune will be allowed m some cases.
5 case basis using assumptions comparable in conservatism the amount of credit will be evaluated on an indnidual to those of tius guide.
case basis
'S '
f\\
the c u rr o u n ding building (2) For ground level release,
O, atmmphere and is then released (as atmospheric diffusion factors' an elevated plume for those used in evaluating the iacilities with stacks ).
radiological consequences of 6
2.
The assumptions for atmospheric the accident addressed in this ditTusion are:
guide are based on the a.
Ground Level Releases following assumptions:
(1) The basic eq uation for (a) windspeed of I meter /sec; atmospheric diffusion from a (b) uniform wind direction; ground level point source is:
(c) P asq uiiI diffusion category F.
X/Q =
(3) Figure 1
is a plot of rua o YZ atmospheric diffusion factors Where:
(X/Q) versus distance derived by use of the equation for a X = the short term average ground level release given in centerline value of the re g ulatory position 2.a.( 1 )
ground Ieve1 above under the concentration (curies /m )
meteorological conditions 3
given in reguhtory position Q= amount of material 2.a.(2) above.
released (curies /sec)
(4) Atmospheric diffusion factors for ground level releases may u = windspeed (metersisec) be reduced by a factor ranging from one to a maximum of o = the horizontal standard three (see Figure 2) for y deviation of the plume additional dispersion produced (meters) [See Figure V-1, by the turbulent wake of the Page 48, Nuclear Safety, reactor b u ilding. The June 1961, Volume 2,
volumetric building wake Number 4,
"Use of correction as defined in Routine Meteorological S u b d ivision 3-3.5.2 of Observations for Me teorology and Atomic Estimating Atmospheric Energy-1968, is used with a D is p ersio n,"
F.
A.
shape factor of % and the Gifford,.Ir.]
minimum cross-sectional area of the reactor building only.
the vertical standard b.
Elevated Releases
=
oz deviation of the plume (1) The basic eq uation for (meters) [See Figure V-2, atmospheric diffusion from an Page 48, Nuclear Safety, elevated release is:
June 1961, Volume 2'
-h2 j2,2:
Number 4,
"Use of x/Q = e Rou tine Metcorological zua o, y
Obseryations for Where:
Estimating Atmospheric D i s p ersio n,"
F.
A.
the short term average
=
X Gifford, Jr. ]
centerline value of the ground 1evel 3
'Credrt for an ekvated relea e a be given only if concentration (curies /m )
the pomt of release is (a) more than twe and ce,e-half times the beght of any uructure dme enoup to affect
'These diffusion factors should be used until the 4-w of the pume or (b) located far t. nugh adequate site meteorological data are obtamed. In some from any structure wtuch could affect the dnpemon of cases, available information on such site conditions as the pkmw. For thme pants without stacks the meteorology, topography and geographical location may atmospaenc diffuson factors assummg ground level dictate the use of more restnctive parameters to msure a release grwen m regulatory pontion ' b shouJd be used.
conservauve estimate of potential offsite exposures.
125 123 25.3
amount of material (3) Figure 3 is a plot of Q
=
released (curies /sec) atmospheric diffusion factors versus distance for an elevated u = windspeed (meters /sec) re1 esse assuming no rumiaation, and Figure 4 is for o = the horizontal standard an elevated release with Y
deviation of the plume fumigation.
(meters [See Figure V-1, t'4) E l e v a i e d re1 eases are Page 48, Nuclear Safety, considered to be at a height June 1961, Volume 2,
equal to no more than the Number 4,
"Use of actual stack height. Certain Routine Meteorological site conditions may exist, such Obseryations for as surrounding elevated E stimating Atmospheric t o po g ra phy or nearby D i s p e rsion,"
F.
A.
structures, which will have the Gifford, J r. ]
effect of reducing the effective stack height. The degree of the vertical standard stack height reduction will be O
=
z deviation of the p:ume evaluated on an individual case (meters) [See Figure V-2, basis.
Page 48, Nuclear Safety, 3.
The following assumptions and June 1961, Volume 2, equations may be used to obtain Number 4,
"Use of conservative approximations of thyroid Rou tine Meteorological dose trom the inhalation of radioiedine Observations for and external whole body does from Estimating Atmospheric radioactive clouds:
Dis p ersion."
F.
A.
a.
The a ss u m p tions relative to Gifford, J r.]
inhalation thyroid d ose approximations are:
h = effective height of release (i) The receptor is located at a (meteL) point on or beyond the site boundary where the maximum (2) For eieyated
- releases, ground level concentration is atmospheric diffusion factors' expected to occur.
used in evaluating the (2) No correction is made for radiological consequences of d e pletion of the effluent the accident addressed in this plume of radiciodine due to guide are based on the deposition on the ground, or following assumptions:
for the radiological decay of (a) windspeed of 1 meter /sec; radioiodine in transit.
(b) uniform wind direction; (3) Inhalation thyroid doses may (c) envelope of Pasquill be approximated by use of the diffusion categones for following equation:
various release heights; F IFPBR(X/Q)
(d) a fumigation condition p' = g exists at the time of the (DF )(DF )
p r
accident."
Where:
' For sites located more than miles from large D = thyroid dose (rads) bodies of water such as oceans or one of the Great F
fraction of feel rod
=
Lakes, a tumigation condition is assumed to exist at the g
time of the accident snd contmue for one half hour. For iodine inventory in fuel sites located less than 2 miles from large bodies of water rod void space (0.1) a turrugation condition is assumed to exist at the time of the accident and continJe tot the duration of the release 1 = core iodme inventory at 4 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />si time of accident (curies)
\\25 \\24 25.4
F = fraction of core damaged b.
The assumptions relative to so as to r.' ease void space external whole body d ose iodine approximations are:
P - fuel peaking factor (1) The receptor is located at a point on or beyond the site B = breathing rate = 3.47 x boundary whers the maximum 10-*
cubic meters per ground level concentration is second (i.e.,
10 cubic expected to occur.
meters per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> work (2) External whole body doses are day as recommended by calculated using " Infinite the ICRP)
Cloud" assumptions, i.e., the dimensions of ti.e cloud are effective iodine DF
=
d e c ontamination factor assumed to be large compared tu the distances thst tne for pool water gamma rays and beta particles DFr= effective iodine travel. The dose at any decontamination factor distance from the reactor is for filters (if present) calculated based on the m a ximum ground level X/Q = atmospheric diffusion concentration at that distance.
factor at receptor location 2
(sec/m )
For an infinite uniform cloud containing x curies of beta adult thyroid dose R
=
radioactivity per cubic meter, conversion factor for the the beta dose rate in air at the iodine isotope of interest cloud center is ' '
(rads per curie). Dose 0 '~ = 0.45 7 E x con version factors for D
0 lodine 131-135 are listed 6
in Table I.' These values Where:
were d e rived from
- 's t a n d a r d m an" D', = beta dose rate from an infinite cloud (rad /sec) parameters recommended in ICRP Publication 2.'
Es = average beta energy per disintegration (Mev/ dis)
TABLEI x = concentration of beta or Adult inhalation Thyroid gamma emitting isotope 3
Dose Conversion Factors in the cloud (curie /m )
Because of the limited range Conversic,n Factor (R) of beta particles in tissue, the lod.me isotope (Rads /cun,e mhaled) surface body dose rate from beta emitters in the infinite i n, i n6 ct u c n be approximated as IjI b5 g I
- "8 135 4[0 x 105 g ', = 0.23 E x D
134 2.5 x 10*
g 135 1.24 x 105 For gamma emitting material the dose rate in tissue at the
' Dose conversion factors taken from " Calculation cloud center is:
of Distance Factors for Power and Test Reactor Sites."
TID-14844. J. J. DiNunno. R. E. Baker F. D. Anderson.
D ' = 0.507 E x 7
7 and R. L Waterfield (i962).
Where:
' ' Reco m me n d a tion s of the I n ternational 9
Commission on Radiotopcal Protection. " Report of D~
= gamma e ate f 7
Committee 11 on Permissible Dose for Internal Radiation an mfimte cloud t radisec)
(1959)." ICRP Publication 2. (New York Permagon Press.1960).
Meteoroic,gy and Atomic Energy - 1968. Chapter '
25.5
pD., = 0.23 Eg$ or E7 = average gamma energy per disintegration D=0.25E $
7 7
(Mev/ dis)
Where $ is the concentration time integral for the cloud H o wever, because of the 3
(curie sec/m ).
presence of the ground, the receptor is assumed to be (3) Tht, beta and gamma energies exposed to only one-half of emitted per disintegration, as the cloud (semi-infinite) and given in Table of Isotopes,i 2 the equation becomes:
are averaged and used D '= 0.25 (x according to the methods y
described in ICRP Publication 2'
Thus, the total beta or gamma dose to an individual located 82 C. M. lederer, J. M. Hollander,.and I. Perlman, at the center of the cloud path TsNe of isotopes. Sixth Edition (New York: John Wiley may be approximated as:
and Sons, Inc.1%7).
O 125 126 25.6
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