ML20033F463
| ML20033F463 | |
| Person / Time | |
|---|---|
| Issue date: | 10/12/1984 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Lloyd M HOUSE OF REP., SCIENCE, SPACE & TECHNOLOGY (FORMERLY |
| Shared Package | |
| ML20033D963 | List:
|
| References | |
| FOIA-90-29 NUDOCS 9003210149 | |
| Download: ML20033F463 (18) | |
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- ndaj The Nemorable Marflyn Lloyd
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Chairman. Subconsittee en Energy Research
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Committee en Science and Tecluiology
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United States Neuse of Repressistatives F.
Mashington. DC 20515 J
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a bear Madam Chatrunas n;
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- j In response to your letter of September 20.1984 I as pleased d
to supplement the record of.the July 25. 1984 heerlag en the Status of y
the Technical !afrastructure daquired As support Domestic Food h'
Irradiation. % response to th' e isst of questions subettted with your 9;,.
letter is attached.
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9003210149 900312
- Richard E. Cunningham, Director
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f RESPONSES TO ADDITIONAL QUESTIONS 1
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1.
QUESTION:
n 4-Does the chemical form of the Cesium in DOE's current capsules --
T Cesium Chloride (CsC1), which is a liquid and is also very soluble K
in water -- present any safety problems? How do the main safety concerns in licensing use of a Cs-137 radiation source compare to the y
concerns in licensing a Cobalt-60 source?
l P:
ANSWER:
?
4 y
Thecesiumchloride(CsC1)containedintheDOE'scapsulesisasolid.
The main safety issues related to these capsules are potential attack Q
by the cesium salt on capsule containment and solubility if released, s
The DOE has conducted corrosion examinations to confim the adequacy Q
of the capsule to maintain its integrity and is conducting further J
N tests to determine the effects of themal cyclings, as would be 4;
encountered in use of the capsules in a wet-storage, dry irradiation j
0-operation, on the capsule.
If the test data demonstrate containment i
^
Q integrity, we believe that the capsules will. be adequate,for use in i
g irradiators.
?q i
The Cobalt-60 contained in currently used capsules is in the fom of solid R
metal seeds which are only slightly soluble in water. The Cobalt-60 3
capsules have been used several years in irradiators and have a j
good record of integrity, m
a Regardless of capsule integrity, backup' systems are required to y'
detect leakage. Due to the very high solubility of CsC1 comparsd to metallic Cobalt-60, special procedures are contemplated to manage i
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1eakage in the unlikely event that it occurrs.
i
~a y
The safety considerations for operation of an irradiator containing either Cesium-137 or Cobalt-60 are the same.
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2.
QUESTION:
t.;
y Would it not be prudent from a safety concern to require the same standards i
for maintaining an operating license for a cobalt wet storage irradiator?
q h
ANSWER:
- 9..
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Once the integrity and adequacy of the capsules used in an irradiator have i
y been demonstrated, the safety considerations are essentially the same for irradiators containing either cesium chloride or cobalt metal in a
the capsules. As noted above, the management of CsC1 leakage in the event that it occurs requires some additional precautionary procedures
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due to its solubility.
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QUESTION:
What manner of waste disposal is currently required for large radiation
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sources? Do you have an idea of what the cost of disposal is (or might W-be) on a cost per curie of radiation basis? What process does the NRC J
use to assure that radiation sources will be disposed of properly?
l.'$ '
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ANSWER:
2, 1
Most of the large irradiators in the United States use Cobalt-60 R
sources purchased from Atomic Energy Canada Limited (AECL). Under i
present arrangements, most of these sources are replaced and the j
spent sources are reclaimed by AECL. Cesium chloride sources in 1
the for of WESF capsules are supplied by DOE. DOE has stated that 4
it wilt take back spent capsules for storage. Requirements for disposal K
of waste by an individual licensee are set forth in the Comission's i
regulation 10 CFR Part 20. "$tandards for Protection Against Radiation."
i for sources of the type used in irradiators. The regulation permits
);
transfer only to persons specifically licensed to possess the sources 1
such as operators of commercial land burial facilities. The operations V
of a commercial waste burial ground are governed by the Comission's t ir Regulation 10 CFR Part 61. " Licensing Requirements for Land Disposal -
i of Radioactive Waste." or equivalent regulations by an Agreement y
State.
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S Charges by commercial land burial facilities for disposal of wastes j
are based on package volume and the extent of special handling.
j For waste of low activity current charges at burial grounds range 3
from $17.00 to $30.00 per cubic foot of package volume. Based on
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our discussions with a burial ground operator, the cost of disposal j
of very large sources (about 30.000 Ci) could be as high as $3000 q-per cubic foot of package volume, a
K 4.
QUESTION:
d i
Does the NRC know the current location and condition of all radiation 4
sources that are in the United States? What about sources fabricated 1
in the United States and exported to other countries? Are you confident i
that the situation that recently occurred in Mexico -- where a cobalt y
radiation source' was relegated to a -junkyard and wound up exposing j
numerous individuals to excessive radiation levels -- was a fluke and 4
is not likely to ha) pen again? Has the NRC taken any actions that could l
prevent another suc1 occurrence?
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ANSWER:
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The specific licenses issued by the NRC specify the radiation sources J
which may be possessed by licensees and specify the location at which j
the sources nay be used. Specific licensees who distribute radiation A
sources to general licensees are required to report the name and location of persons to whom the sources are sent. Although the NRC does not know the condition of radiation sources at any given time, licenses which
?i provide for possession and use of the sources require periodic leak Q
testing of them. If there is any leakage of radioactive material from a y
source, the licensee is required to report the leakage to the NRC and h
take innediate steps to correct the problem. The NRC conducts periodic Sj -
inspections of persons licensed to possess radiation sources to determine -
M if the licensee's program is in compliance,with NRC regulations and the
- ]
terms and conditions of the licenses.
4 Q.
With respect to radiation sources fabricated in the United States and s.
exported to the other countries, the NRC does not have knowledge of the 1
location and condition of the sources. The NRC staff is analyzing the issues related to notification of foreign governments of the export of 1
4 radioactive sources to persons in foreign countries.
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%y Although we believe the incident which occurred in Mexico to be a unique situation, the following actions are being taken to minimize other
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occurrence or the effects of such an occurrence.
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A study.under contract with Aerospace Corporation has been initiated 7;
to assess the feasibility of detecting unauthorized radioactive material accidentally contained in items that enter the United W
States through connercial import channels.
?1 2.
Radiation detection instruments have been provided to each of the 22 U.S. Customs port of entry locations along the U.S./ Mexico
@) _
border and Customs agents have been instructed in the use of the instruments.
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The NRC is developing plans to provide prompt response to incidents V
such as the Mexican incident. The response plan will incorporate d
interections with other Federal agencies and State governments..
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,7 RCSPONSES TO MINORITY QUESTIONS 7y i,4 1
1.
QUESTION:
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What amount of effort is necessary to reach an agreement with a g
state relative to material irradiation? How soon do you think g
the remaining 23 states will reach such agreement with NRC?
- q ANSWER:
P Section 274 of the Atomic Energy Act, as amended, provides a mechanism b
which permits states to assert regulatory authority over certain 4
categories of radioactive materials - byproduct materials (radio-4 isotopes), source materials (the raw materials of Atomic Energy)
A
.and small quantities of special nuclear material.
Irradiators W.
typically use byproduct materials. The criteria that states wishing d
to enter.into such agreements must meet are provided in a Comission
@h Policy Statement published in the Federal Register (46 FR 7540, January 23,1981; 46 FR 36969, July 16,1981; and 48 FR 33376, July 21, i
1983). After an agreement is signed..the Act requires periodic reviews k
by NRC of Agreement States programs. Guidelines for this purpose have
)]
been issued by the Commission as a Policy Statement (see 46 FR 59341, W
December 4,1981).
..]
The amount of effort needed to enter into an agreement is a function W
of several variables including the scope of the proposed agreement, the number of NRC licenses that will be transferred to the state and the amount of preparatory work that is needed. Preparatory work d
Includes draf ting and enactment of enabling. legislation, recruitment d
and training of staff to carry out the program, drafting and promulgation d
of regulations, and development of administrative and technical q.
procedures. Supporting documentation for-the Governor's request Q
for the agreement showing that the program will meet the criteria 1
must also be prepared. Typically, once a decision is made to seek
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status as an Agreement State, preparations for an agreement take one to j
two years.
M a
Whether or not a state seeks an agreement is a matter of choice for P
the state. At the Iowa and Illinois. present time NRC is negotiating agreements with f
Pennsylvania is actively working toward an k
agreement. While timeframes have not been fimly set, we believe
['i that agreements with Iowa and Illinois are possible by late 1985 or
- i. i carly 1986. Other states are presently examining the possibility of G
entering into an agreement; these include Virginia, Massachusetts
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and Wisconsin.
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QUESTION:
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f In your experience, what is the public perception of food irradiation?
h ANSWER:
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We have not dealt with the general public on the matter of food-d irradiation. The Public Health Service, Department of Health and 4
Human Services, published a proposal in the Federal Register on
' February 14, 1984, on the use of radiation sources for the treating
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of food and is analyzing public response on this issue.
A' d
3.-
QUESTION:
5y
.If the individual states are the irradiation regulators, what role fj; do you anticipate for NRC relative to that technology in the
- i future?
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ANSWER:
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4' Irradiators are licensed by both the NRC and the Agreement States. The 1
NRC has offered to provide technical assistance to Agreement States in the review of applications for large irradiators. The NRC has dealt
?;
directly with the Department of Energy on the matter of the use of the h
DOE Cesium-137 capsules in irradiators. The regulatory position developed y
by the NRC, on the basis of, DOE experience and our licensing practices, is d
provided to the Agreement States for their adoption.
d' For future technology, which might be licensed by an Agreement State, l
Wi' we anticipate analyzing the technology for safety considerations and Q
providing guidance as might be appropriate.
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1 Department of Energy Washington, D.C. 20545 JUL 2 515B4
)p Mr. Richard E. Cunningham, Director N
Division of Fuel Cycle and Material Safety
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U.S. Nuclear Regulatory Corsnission g
Dear Mr. Cunningham:
A4 As agreed in our July 10, 1984, meeting regarding the Wo;?9ar Regulatory 3;
Consission's (NRC) licensing of the cesium 137 Waste W 71ation and 4
Storage Facility (WESF) capsule in irradiators, please Gna enclosed the h
June 1984 report PNL-5170, "A Review of Sa'fety Issues That Pertain to the Use of WESF Cesium Chloride Capsules in an Irradiator," which this office is 4
submitting in support of our licensing request.
a lQ h)
As discussed, the Denartmen<: of Enerav (DOE) believes that the test data.
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collected to date. especia19y that from the 6 years operatino experience I d
with the Sandia Irradiator for Dry Sewaoe Solids. should furnish ammle i
Q evidence that an NRC license for similar irradiators ut111rina wet inad_ dry g
storace and dry operation denian concent is warranted, a.
1 With respect to wet load and storage and dry operation irradiators, we
?-
believe that considerable technical inforination. exists from 10 years operation of WESF that are applicable to the licensing process.
In
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addition, we have begun an accelerated therinal cycling tests of two WESF capsules. This evaluation should be completed in 6 months. DOE reconmends j'
that NRC license the first wet / dry facil'ty on the basis that:
4 d
(1) a capsule would be removed annually from one of each type of irradf tor i
A j
and subjected to destructive evaluation to confirm that operation of these i
facilities does not result in conditions beyond those that have previou11y.
!i demonstrated a h1ch decree of intearf tv of the thick-walled,
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douhlv-encaosulated WESF cesium capsules:
E (2) irradiator operating limits be established well within demonstrated j>
integrity limits, e.g.,
m wet load. dry storace.
operatino/storaae temperature i$
dry operation irradiator limit: 23000C A[
- wet load, wet storage, operating surface temperature p
dry operation irradiator limit: 23000C a!
therinal cycle limit:
0 12,000 cycles air to water 2000C maximum delta T a
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I appreciate the opportunity that we had on' July 10,1984, to discuss with J
you and your staff the safety issues and related data.
If you have any questions, please contact me accordingly.
e Sincerel,
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John. Jicha, Jr., Director i
R&D nd, Byproducts Division J;
Of ice of Defense Waste j-and Byproducts Management ilv9 i
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[j AYERAGE TEMPERATURE PROFILES FOR A WESF CAPSULE WITH A 1.5-INCH WALL AND 3. INCH TOP AND BOTTOM 4
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OUTER CAPSULE TCP Y
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Calculated Temperature Versus Time for a 75 kCi niESF Cesium Chloride Capsule Initially r
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Calculated Temperature Versus Time for a 75 kCi idESF Capsule Initially in Equilibrium in
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25'C Air, Then Suddenly Plunged into 25*C Water an4gelg for 150 Sec, Then Held in Air Again
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T O-capsule in 25*C air; O-capsule in 25'c water. The inner h,
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