ML19312D244
| ML19312D244 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 01/08/1980 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUDOCS 8003240052 | |
| Download: ML19312D244 (4) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMisslON
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'JAN 8 1520
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":.7 DOCKET NO.: 70-33 APPLICANT:
Texas Instruments, Inc.
FACILITY:
Attleboro. Massachusetts
SUBJECT:
REVIEW 0F LICENSE AMENDMENT APPLICATION DA"0 OCTOBER 10, 1979 Si AND SUPPLEMENTS DATED NOVEMBER 27 AND DECEhiR 13, 1979
'.:.~.Z PIVIEWERi N. Ketzlach I.
Background
Texas Instruments, Inc. (TI) by letter dated October 10, 1979, and its
~J supplements dated November 27 and December 13, 1979 requested authorization for the following:
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uranium enriched between 10.0 and 93.5% }3glements made with Fabrication of box type test reactor fue 1.
g, 2.
Revision of surface contamination action levels and related
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survey frequencies (see discussion below).
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Revision of acceptable action level based on routine urinalysis 7:.
results.
235 TI currently is authorized to fabricate only 93%
U enriched fuel elements.
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II.
Discussion A.
Nuclear Criticality Safety 235 h~
Although the licensee is authorized to fabricate highly enriched U
,,..l fuel elggnts with approved MSQs (maximum safe quantities) based on the con-tained U in the fuel, the same MSQs for the fuels of lower enrichment are not necessarily safe. The amendment application included the licensee's justification for the application of the highly enriched criteria to the fuels L. -. ;
2 of lower enrichment.
235 In the absence of moderation, the minimum critical mass of contained 0
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increases as the enrichment decreases (NUPIG/CR-0095, Nuclear Safet: luide, H
T'0-7016 Revfsion 2, dated June 1978). Therefore, it is conservatiw to use E~"h, tia h1ghly enriched MSQs for fuels of lower enrichment in the absence of
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moderation.
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JAN 8 1980
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2 iith.~?%
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[kh Eht; optimum watier moderation.for the minimum critical mass of contained 0
as Da function of 2350 enrichment, the minimum critical mass increases as the
=21 235, safe 9
- 2350 enrichment decreases. Therefor.e, all MSQs- <350 g contained U
for-the; 93% enriched-2350 fuels, are safe for thii fuels of lower enrichment.
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All operations, normally conducted dry. are perfomed in limited geometry
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containers. The geometry of the containers, with the.specified MSQ of con-
- tained 2350 for the' 93% enriched 2350 fuels are.' safe for. the fuels of lower M":
enrichment even if accidentally moderated. This may not be true where larger containers are used.-,For a particular H/U moderation ratio, the minimum critical. mass of contained 2350 may be smaller for the lower enrichments '( ANSI
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N16.5-1975, " Guide for Nuclear Criticality Safety in the Storage of Fissile
' Materials"). ~ However, the volume for the minimum critical mass increases with c==.
Mi a decrease in enrichment.
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The applicant limits both the number of discrete items (e.g., number of compacts, fuel plates) and 235U centent for the fuels of lower enrichment at a work or storage station to those authorized for the 93% 2350 enriched fuels.. The 235U TEi L9Sn:L content / plate of the lower. enriched fuels is the same as that in the plates of
..ip higher enrichment. The controlled volumas, and number of discrete items at a J
work or storage station, based on those authorized for the 93% 235U enriched 3.m fuels, are safe for the fuels of lower enrichment.
Moderation is normally present in the plate pickling, degreasing and ultrasonic testing a, i in the cleaning of elements. In the plat reating operations there is.never more than 24 plates.(<468 g contained g3gU) in the moderator at l4 sc5 one time. This mass is safe for a11235U enrichments < 93% and is independent 17E of container size. The elements in the cleaning tank Tmaximum of five)'are
=h separated by at least six inches of water. They have been shown to be safe -
.d!E (ORNL/CSD/TM-55, " Nuclear Criticality Safety of the Fuel Element Facility at Sri Attleboro, Massachusetts," dated June 1978) for the 93% 2350 enriched assem-zn blies and are safe for assemblies-of lower enrichment (having a maximum 235U RE:
content ~ equal to that in the highly enriched assemblies) with the fixed thick-
"~T ness of water between assemblies.
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- No request is. included for authorization to reduce the spacing between storage units and/or work stations' The.spd.-- approved for the 93% 2350 enriched
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processing and/or. storage units are safe for those of the lower enrichment:
.~E (1) the 2350 densities are the same, (2) the'same size containers are used and Q
(3) the minimum spacing between units is retained.
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!Efi B.
Radiation Safety
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- 1. ' Surface Contantination Control
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.is The existing surface contamination control program conducted by
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~ TI includes the routine survey of the areas where a potential for uranium' contamiution exists for both-alpha 'and beta counting modes. Since the most A
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3 JAN 8 1980 abundant radionuclides in the uranium are alpha emitters, alpha surveys are related more.directly to _ potential personnel hazards than are beta surveys.
Regulatory Guide 8.24 also calls for alpha surveys alone in determining the level of removable uranium contamination. Therefore, the request for uranium
- contamination control by alpha surveys is justifiable.
The: applicant requests increases in contamination control action levels in several areas of his facility. The following is a table.of current action levels, actica levels. requested after discussions with the FCUF staff, and the survey frequencies:
Current Requested Fixed Removable Fixed Removable Fuel Mfo. Area (FMA) dpm dpm/100cm2 Frecuency dpm/100cm2 dom /100cm2 Frequency 1.
General 200 Monthly 5000 Weekly 2.
Equipment and work surfaces 200 Monthly 5000 Weekly 3.
Equipment for release from FMA 500 1
2000 200 Clean Areas 1.
Smidgen clean 50 1
Weekly 2000 200 Monthly 2.
Health clean 500 50 Weekly 2000 200 Weekly Shipments of.
Trans ferals 1.
For Smidgen cleanliness 50 1
2000 200
- 2. -Other 500 1
2000 200
, Clothing 1.
Protective clothing.in restricted area 5000 500 1000 2.
Clean 5000 50 200 3.
Personnel clothing 50 1
200 4.
Personnel shoes 50 1
200 l
5.
Skin 50 Bkgd.
- Measurements made upon leavi,ng the FMA.
The requested action levels for removable alpha contamination control in the l
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.FMA and in the clean areas and their survey frequencies are consistent with those in Regulatory Guide 8.24, " Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication," dated November 1978.
f;.,, X JAN 8 1980 7
4
' The'. requested action levels -for. fixed. alpha contamination in: the clean areas Land;on elothing in1 the clean areas are less-than those in the"Guidelbes for t Decontamination of Facilities and Equi,xnent Prior to Relea,se for Unre tricted -
Use.or Tcrmination of License for Byproduct, Source or Special Nucle'ar Material,"
. dated Nover..ber 1976.'
21 Bioassay Program' 1The: existing ~ action level' based.on' routine urinalysis results
-is 75' dpm/1500 m1, equivalent to 22 pCi/ liter. The requested action level is
'15 pCi/ liter. The new level is consistent with the ALARA concept and is'com-parable to ;thatLauthorized at other licensed facilities.
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Environmental Effects
~ No significant environmental effe t should result from the authorization c
to fabricate box type test reactor fuel elements with <93% enriched uranium,.
4
- the requested changesL.in action levels for surface contamination control and survey frequencies and the change in the action level based on routine urinalysis
.results.
D.
General
.The amendment application was discussed with W. W. Kinney, Region I
.(IE) inspector, TI facility, = and with P. E. Clemons, Region I (IE) radiation specialist, TI facility, on November 19, 1979. Neither foresaw a safety.or environmental related problem with the requested authorization.
E.
Conclusion The nuclear criticality safety for fabrication of bor type ' test reactor fuel elements having <93% 2350 enrichment has been confimed. The changes in the-action levels Tor surface contamination control and related frequency of surveys,.and change to the action ~1evel based on urinalysis are s
L consistent with good radiation safety practices. Therefore, the requested i
_ changes are adequate to protect the health and safety of the operating l.
personnel. the/public and the environment.
Issuance-of the license amendment is recommended.
hU l.
d Norman Ketzlach
' f
. Uranium Fuel Licensing-Branch -
Division of Fuel Cycle and
((M./.
Material ~ Safety
'. Approved by:-
Y' AM W.-nT. Crow, Section Leader p.
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