ML19347F359
| ML19347F359 | |
| Person / Time | |
|---|---|
| Issue date: | 03/27/1981 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML19347F358 | List: |
| References | |
| REF-10CFR9.7 NUREG-0767, NUREG-0767-DRFT, NUREG-767, NUREG-767-DRFT, NUDOCS 8105190063 | |
| Download: ML19347F359 (8) | |
Text
.
i NUREG-0767 CRITERIA FOR SELECTION OF FUEL CYCLE AND MAJOR MATERIALS LICENSES NEEDING RADIOLOGICAL CONTINGENCY PLANS I.
INTRODUCTION i
The NRC believes there is a pressing need for upgrading of radiological 1
contingency planning of tnose licensed fuel cycle and major materials facilities which exhibit the potential for accidents which could result in (1) offsite doses exceeding 1 rem to the whole body, 5 rems to the thyroid or 3 rems to other critical organs, or (2) potentially serious radiation overexposures of workers from a' nuclear criticality incident or from release of radioactive materials, or (3) chemical exposures which could impact radiological safety.
Radiation doses of 1 rem to the whole body and 5 rems to the thyroid are the lowest Protective Action Guides (PAG's) established by the Environmental Protection Agency for triggering a protective action in public areas following a radiation accident.
Radiological contingency planning is that part of emergency response preparedness contributed by plant operators to assure (1) that plants are properly configured to limit releases of radioactive materials and radiation exposures in the event of an accident, (2) that a capability exists for measuring and assessing the significance of accidental releases of radio-active materials, (3) that appropriate emergency equipment and procedures are provided onsite to protect workers against radiation hazards that might be encountered following an accident, (4) that notifications are promptly made to Federal, State and local government agencies, and (5) that necessary recovery actions are taken in a timely fashion to return a plant to a safe condition following an accident.
Limiting possession limits, i.e., quantities and forms of radioactive materials which can be reasonably estimated to be capable of causing, due to accWents, offsite doses equal to or greater than 1 rem total body, 5 rem thyroid or 3. rem other critical organ or potentially serious radiation exposures of workers from a. criticality excursion or from release of radioactive materials, are developed in this report.
II.
SUMMARY
AND CONCLUSIONS-- -
Table I is a listing of those quantities of radioisotopes, as license possession limits and conditions of use, which the NRC has determined to be of potential significant concern in the event of a major accident involving those radioactive materials. -
M yggggpf CF o g g r /)
Enclosure "D"
- 051?o 063
~
S
.' TABLE I Schedule of Limiting Possession Limits Arranged Alphabetically by Elements Radionuclide Limiting Possession Limits Curies Americium-241 0.30 Americium-243 0.30 Antimony-124 1000 Barium-140 2000 Cadmium-113m 1500 Calcium-45 800 Carbon-14 1300 Californium-252 0.30 Cesium-134 350 Cesium-137 600 Chromium-51 150,000 Cobalt-60 4000 Copper-64 50,000 Curium-242 8.0 Curium-244 0.50 Gold-198 100,000 Hydrogen-3 6000 Iodine-125 8.0 Iodine-129 1.0 Iodine-131 3.3 Iridium-192 50,000 Iron-55 30,000 Iron-59 Krypton-85 2400 7000 Manganese-54 1500 Manganese-56 120,000 Molybder4um-99 3000 Neptunium-237 0.20 Nickel-63 5000 Niobium-95 5000 Phosphorous-32
- - ~ - - - -
15 Plutonium-238 0.10 Plutonium-239 0.10 Polonium-210 3.2 Promethium-147 3500 Ruthenium-103 1500 Enclosure "D"
.e
. '. Ruthenium-105 15,000 Scandium-46 2,500 Selenium-75 500 Silver-110m 500 Strontium-90 25 Sulfur-35 400 Tantalum-182 15,000 Technetium-99m 200,000 Thallium-204 30,000 Thulium-170 1,000 Thorium-228 0.30 Tin-ll3 10,000 Tin-123 1,000 Tungsten-187 5,000 Uranium-233 5.0 Xenon-133 10,000 Zinc-65 2,500 Zirconium-93 5,000 Zirconium-95 1,300 CONDITIONS Where a license authorizes possession of a single radionuclide in forms other than as sealed sources or special form,* the licensee shall prepare and submit a Radiological Contingency Plan if the authorized possession limit exceeds that qantity specified for that radionuclide in the Schedule of Limiting Possession Limits.
Where possession of two or more radionuclides, in forms other than as sealed sources or special form,* is authorized by the license, the licensee shall prepare and submit a Radiological Contingency Plan if the sum of the quotients of the auth'orized possession limits for individual radionuclides divided by the quantities of those radionuclides specified in the Schedule of Limiting Possession Limits exceeds unity.
Where the license authorizes possession of a broad range of radionu-clides, e.g., any byproduct material of atomic numbers 3.through 83, inclusive, in excess of those quantities specified in Schedule A of 33.100, i.e.
Type A specific Licenses of Broad Scope, and in forms other than as sealed sources or-special form,* the licensee shall prepare and submit a Radiological Contingency Plan if the quantity of any radionuclide authorized, either explicitly or i
l implicitly, exceeds that quantity specified in the Schedule of Possession Limits or if the sums of the quotients of those quantities explicitly or implicitly authorized divided by the quantities of those radionuclides speci-fied in the Schedule of Limiting Possession Limits exceeds unity.
l l
Licensees possessing U-235, U-233, or plutonium in any form in such quan-tities as to require criticality monitors and alarms in accordance with 10 CFR "See.10 CFR 30.4(r) and 10 CFR 71.4(o) for definitions of " sealed source" and "special form."
Enclosure "D"
.s
..- 70.24 are also required to prepare and submit for review Radiological Contin-gency Plans.
Possession of large quantities of UFs, even where no criticality hazards exist, shall also require preparation and submittal for review of Radiological Contingency Plans.
III.
DISCUSSION Estimates of quantities of materials, wnich could lead to significant offsite doses and to overexposures of workers from accidents, that require protective actions have been based upon the relationship:
Q=
Dn DCF RI n
Where Q = Limiting possession limit, i.e. the quantity of radionuclide authorized to be possessed and assumed subject to an accidental release D
=
D ses requiring protective actions, rem n
DCF" The inhalation dose conversion factor and the
=
limiting body organ R
Release fraction likely to be dispersed in a
=
severe real accident i
I Intercept fraction that could be inhaled by an
=
individual For the purposes of selecting licensees to prepare and submit Radiolo-gical Contingency Plans it is necessary to base the selection criteria upon the authorized possession limits since we have no other information available upon which to base a conclusion that lesser quantities of radionuclides would be subject to the same severe accident condition.
Doses requiring protective actions are 1 rem to the whole body, 5 rems to the thyroid and 3 rems to any other critical organ in the case of individuals offsite.
One rem to the whole body and 5 rems to the thyroid are the minimum _
doses requiring protective actions by the Environmental Protection Agency in their Protective Action Guides (PAG.'s), EPA-520/1-75-001. Three rems to other vital organs is an equivalent criterion.
Doses constituting significant overexposures of workers are at least 5 times greater than those, i.e., about 5 rems whole body, about 25 rems thyroid and about 15 rems to other critical organs.
Selection criteria are based upon inhalation limiting doses except for Xe-133 and Kr-85 where submersion is the acute exposure pathway for which preplanned protective actions are needed.
Ingestion pathways are not likely to cause prompt acute exposures to individuals and are believed not to be limiting in this analysis.
Enclosure "D"
n Rigoreds estimates of release fractions, i.e., those portions of inven-tories of radioactive materials that could be made airborne in an accident, require plant-specific analyses to discover and characterize possible accident scenarios and to estimate possible releases.
Insufficient data are presently available to support such analyses.
In the absence of such data, release fractions have been estimated based upon experience and the generic physical and chemical forms of the radionuclides normally involved.
Encapsulated materials and materials in "special form" have been assumed to be non-dispersible and to have zero release fractions.
Stable solid monolithic materials known to be accompanied by finely divided materials in industrial manufacturing operations, viz. Ir-192 and Co-60 have been assigned release fractions of 0.001.
Other solids and liquids have been assigned release fractions of 0.01.
Semi-volatiles have been assigned release fractions of 0.03 and volatile and/or combus'tible radionuclides have been assigned release fractions of unity.
Only a fraction of the materials released, the " intercept fraction," will likely be inhaled and contribute to radiation dose.
An intercept fraction 10 6.for offsite exposures has been mentioned repeatedly in the literature (9$(2) 3 and corresponds to a breathing rate _of 20 m / day and an atmospheric relative 3
concentration value, X/Q, of 4 x 10 3 sec/m, where the receptor is present throughout the gntire release event.
An atmospheric relative concentration value of 4 x 10 3 is believed to be an appropriately typical value for fuel cycle and materials licensee installations.
This corresponds to the ground level relative concentrations experienced 150 meters from a ground level release under stable conditions. Workers could be subjected to higher concen-trations but only for short periods since they leave the scene of the accident or don protective equipment soon after any large releases occur.
The details of the estimation of Limiting Possession Limits are presented in Table II.
1.
Allen Brodsky, "Resuspension Factors and Probabilities of Intake of Material in Process (or "Is 10 S a Magic Number in Health ~ Physics?"),
Health Physics, Volume 39, No. 6 December 1980, pp. 992-1000 l
2.
Allen Brodsky, " Determining Industrial Hygiene Requirements for Installa-tions Using Radioactive Materials," American Industrial Hygiene Associa-tion Journal, Volume 26, May-June, 1965, pp. 294-310.
e l
Enclosure "D"
- I g.I. uI som 7'..
03__.1I.I.S I I I.I.I.I.I.I.I.I.I.I.I I.C I.I.I.I.I.I.I.I I.I.I.I.
I.III.I.I.
1 N
m -.n m
-m
~o--
o Nm..
e=e w~
NS.22NweSN 1
.J i
3 M
m M
ocoaucoa m m et.pt sul E N m a m N N s*9 set M N u
est est N N m 8 m 8 E m s 9 m E 889 N oco o coo co cocco ococo 3
oo m m N e N E =. = * *m * * * * * *. ***M**5****.*E*
- 5*
=W*
- W w~4~N.
3-w om3~
wN.
m
~-
JasAsnauaAa4J4ad naa4Aaaasaias saaAs 3
a 5
I e.n ~
o.
.n mm 3
ooo o
ao W M k
- M
- a~woA Em 4
mm 3
=
w" Ja a
adassa y
g an a
5
.f M
N.
m m N N E m a.n e 8 3 8 w o w N N w w e ~ S.n3s.ne w.nE N N.n E w NN occo o co oooo ocooo o omo
== o o o g
M*
- mx===*==sMa
=s**mam===xts
- 8 **z**
mme-NN5Nmaawmm~~
mmw8-Nommoeow g
w eN--o w8 JaaaaAsaenaaaaad aaaaaa44anAad aA AJAAa U
8
- 6..x i.
-u L-.O.
---. ooo ooooooooooooo cooco
~
.demmm mm ooooooo n
a-u
}
m22
~~--ddddddddddde adidddddddddd~~- ddddd 1
.u v.
x
. u u
-e
.= ! !". ! ! ? [1 F [ T 3 f ?4 E E F ff ? F.- F F ! F T
_ _d
- F3 3 23 2
aC e a P*e d.m.eadQ =*-.5 S C.s.W
-maoa5 0 o o-m o-ooa --
s s.m o o I
-e n. 6 M S ad w Q Q.J Q -s ad o ad ad
=.<8 ouo dae
{
1 8.
-a n
.a.u?
-8 00 s
e e
e n
=. 3 5. u ;u 3 3 3 3 3. 3 3 3 3 3 3 3 8 3 3 3 3..3883833.3333 E. 8 3 8 3..
m N e w s o"'= o.n m -e N.o a N @.nd LeJ ha.d W W W w neJ w hJ n.J Las nad W tad w a had.e4 bed n.e.d W.ad naJ w.ad w w w and W aaJ Led w w
.n
==. 0.=s Ca
.A C.A 8 89 w N==*
oo-Ne@
Co
.O @ e P N
==.
d G~moNew-om NNNM-Nmo ~o-e-o~mmN eu-
~42b anaaaaaaasaaddad AJadaa54AAAaA aaasA
~
s
.3
.f. U w
u C C==
A e. p e e.
i
- o. o. o.
P=
mm n
- p. m.
et
,x
- o. o.
o.
_ _ _. c. o. o,w o. o.
1 o
- s..c
@ r**.P kJ.w @t a@
w o@w@ Aw c 8.
en N w
~32 ad a
adidda 1
i
- s.
.3 44
'a N
8 8
88-en e
e e
- s. i..
3 3 3 3 3 8 3 3. :. 3 3 3 3. :. 3 3. :3 3 3 3 8. :. 3. :. 3 3 3 3 3 3 3. : $. $. 3 3 3 6
MadMWWMEM*WMOMMWIMEM3WWWWWWWWM $*2WMMWW jeu mNNeo-NaNememeewgemeNeeNewemem eMg-mN-c 82 asiaaaaaaaaaaaaamaaaaaadAasasa Jamaaaas o
oo.
oo eomweme8.e.emeloo-Amme 9"? 9 *AS
- &~a 7
mw t
E m
-NNee-mmm w~
w N.n w, n..n. 3. e.n me.
w w u z u ~ m u m ~ ~ E E ~u s s 2 = m= e d..
....... 0 - s e. L i. e. L. e. e.......
N N m - - - - - -
z u m m u m u f E w.n..... ~..
en e
- m.. m. m.
o e
.....as v i.
== u
--muums-t.
Enclosure "0"
}o Table II (Continued)
Inhalation Inhalation dose Inhalation dose dose conversion Other Dispers-Lietting conversion factor 8 conversion factor 8 f actor' for other critical lbility 1
5 3
possession Isttope for total teody for thyroid critical organ organ factor, DF 6Cf ul000 M DCF 8
yg thyrold*I other"I Ta-182 2.19E-053 1.7CE-043 Liver 0.001 4.57E04 1.76E04 15,b00 W-107 3.10E-10 1.91E-0$
GI-tll 0.03
- 1. 08E 08 5.15E03 5,000 tr-192 5.46E-068 5.13E-053 Kidneys 0.001 1.83E05 5.85E04 50,000 Au-198 4.74E-078 2.43E-063 Kloneys 0.01 2.11E05 1.23E05 100,000 Il-204 6.28E-072 1.03E-053 Kidneys 0.01 1.59E05 2.91E04 30,000 Pa-210 9.58E-05 3.14E-02 tung 0.03 3.48E02 3.18 3.2 lh-2286D E,.77E-03 1.01 tung 0.01 1.48E01 2.97E-01 0.30 U-233*D 6.60E-04 5.32E-02 tung 0.01 1.52E02-5.64 5.0 Np-237+D 6.87E-02 1.69 Sone 0.01 1.46 1.78E-01 0.20 Pu-238 6.90E-02 2.74 Bone 0.01 1.45 1.09E-01 0.10 Pu-239 7.75E-02 3.19 Bone 0.01 1.29 9.40E-02 0.10 An-241 6.71E-02 1.01 Bone 0.001 1.49 2.97E-01 0.30 An-243 6.57E-02 1.01 Bone 0.01 1.52
- 2. 97E-01 0.30 C;:r 242 9.84E-04 3.92E-02 tung 0.01 1.02E02 7.65 8.0 Ca-244 3.51E-02 5.90E-01 Bone 0.01 2.85 5.08E-01 0.50 Cf-252 2.33E-02 9.78E-01 Bone 0.01 4.29 3.07E-01 0.30 t
t inhalation dose conversion f actors for adults, ores /pCl, from NUREG-0172, Age-specific Radiation Oose Commitment Factors for a one-Year Chronic Intake.
v Table 8. (DACRIN).
8 Inhalation dose conversion factors for adults, ares /pCl, where *J solubility class and AHAD = 1 gas are assumed. DACRIN.,
3 Inhalation dose conversion f actors for adults, mree/pCI, from ORNL-4992. A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, Table 4.2, (INREN).
- laiculated for submersion in a seal-infinite cloud taking X/Q = 10 m and with dose factors free. Regulatory Guide 1.109. Calculation of Annual Doses to Man free Routine Releases of Reactor Ef fluents for the Purpose of Evaluattna Compilance with 10 CFR 50. Appendix 1. Table B-1.
Nuclide Dfp erad 0Fy ares 0
y, aree
,g g, yr air
- pCl.yr pCl.yr k
Kr-85 1.34E-03 1.72E-05 1.61E-05 Xe-133 3.06E-04 3.53E-04 2.94E-04 Skindose=31.7QX/Q(Dfhg,*1.11DFh)
Body dose = 31.7Q X/Q DF8Y For skin dose, Q =
31.7 X/q (Dihg,+1.11DF{lrI r
m 3
g Kr-85, skin dose = 31. 7 x 0.0TT1.34E-03 + 1.11 x 1.72E-05) 3 6.96E03 Cl
=
c Me-133, skin dose =
31.7 x 0.01 (3.06E-4 + 1.11 x 3.53E-04) g 1.36E04
=
?
s
- a -,
Tabl2 II (Continesed) 7 I
for body dese, G =
31.7 m M/Q OfoY I
- ** " 31.7 x 0.01 x 1.61E-05
= 1.96E05
- ~
- 31.7 x 0.01 x 2. NE-04
= 1.01E04 for Kr-85, skin dose is lletting and q = 7,000 Cl for Me-133, body dose is lletting and 4 = 10,000
~
9 l-t l
t 1
4 M
3 O
i 1
O un C
7O j.
=
0
=
1
. _, ~..,
W-9
?s ENCLOSURE E O
em
DRAFT CONGRESSIONAL LETTER
Dear Mr. Chairman:
Attached for your information is a copy of an Advance Notice of Pro' posed Rulemaking on upgrading the emergency preparedness of certain fuel cycle and materials licensees.
Also, enclosed is a copy of a letter sent to the State of New Jersey indicating that the part of the petition filed by the State on this issue is being incorporated into this rulemaking.
4 Sincerely, Director Office of Standards Development
Enclosures:
1.
Advance Notice of Proposed Rulemaking 2.
Letter to Petitioners 1
Enclosure "E" l
r
'S d
e 9
ENCLOSURE F G
m m
1 I
)
JAN 16 bbl g
=
Qi}:';
,.) * *;
\\
Dr. Marshall Parrott, Chatrihan Conference of Radiation Control Progran Directors g
Radiation Control Service Department of Human Resources
.1400 Southwest Fifth Avenue Portland, Oregon 97201
Dear liarshall:
As.you know, the ilRC staff is developing regulatory requirements for emerDency preparedness applicable to certain fuel cycle and ritcrials licensces (10 CFR Parts 30, 40, and 70 licensees).
This subject was dis-cussed during the recent All Agreement States !!ceting in Atlanta.
Present actions by HRC include issuing ordcrs to the rore significant-risk NP.C licensecs to upgrade the onsite portions of their emergency preparedness programs and preparing an Advance Notice of Proposed Pulemaking. The attached documents, Enclosures 1 and 2, were developed during the process of selecting those licensees needing upgraded onsite '
t
^-
" emergency preparedness programs.
t!e also expect to publish during the first half of 1981 a IWREG document that describes the nethod for selection of. fuel cycle and material facilities which will be subject to the cmergency preparedness requirements.
l
- *lince we are very much interested in getting State input into the development
'of these regulatory requirements, we v.uuld like the Conference to appoint no.
I rore than two State personnel to represent Agreenent and non-Agreement *$tates as resource persons to provide State input to this effort.
lie propose a meet-Sing prior to March 1,1981 to give the State representatives an opportunity to present their views and to discuss the issues with the llRC staff. The representative's travel and per diem costs should be considered to be part of the continuing support of the Conference by l'RC.
R. J. Doda of.my staff will be coordinating this effort.
Please feel free to contact him for l
additional infonnation.
J 0
~
40
~
5 y pl2.
93I
$.k g q 2 00 T
l i
Enclosure "F" L
m
r.
o-l
.t
- Pr. Marshall Peirott 2
- r
.. ~
(
Flease let us know as soon as possible the nanes of the individuals the Conference croints for this, task so that we nay provide then with infomation for their review.
' 7ss Sincerely, 4
C. Payne Kerr, Director Office of State Prograns.
Enclosures:
1.
Standard format
?.
Liccnsed Possession 1.inits for Which Licensee Padiological Contingency Plans are Required i
~
- s. ;-
l l
l Enclosure "F"
_.