ML20127N737
| ML20127N737 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 01/22/1993 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20127N498 | List: |
| References | |
| NUDOCS 9302010052 | |
| Download: ML20127N737 (3) | |
Text
w, oc ;7
, 3
- , 7590-01 U.S. NUCLEAR REGULATORY COMMIS1[0S u '
FINDING 0F NO SIGNIFLQANT IMPACT AND ,
NOTICE OF OPPORTUNITY FOR A HEARit@ l AMENDMENT OF SPECI AL NUCLEAR MATERI@a LICENSE N0;-SNM-33 COMBUSTION ENGINEERING. INC.
HEMATITE. MISSOURI DOCKET NO. 70-36 CORRECTION In FR Doc. 92-31706, appearing on pages 62392-62394- in the issue of Wednesday, December 30, 1992, three corrections are required: ,
- 1. Page 62392, the right column, the third line of the third paragraph reads, "8,000 kilograms of uranium enriched to..." and should read "8,000 kilograms of U-235 contained in uranium enriched up to..."
- 2. Page 62393, right column, third paragraph,.the location-of the nearest-resident reads " east-southeast" and should read " west-northwest."
- 3. Page 62394, left column, second line under heading Opportunity for _a i Hearing, the word " renewal" should be " amendment."
y 81 -
4 Dated at Rockville, Maryland, this M day of January 1993.
_l FOR THE NUCLEAR REGULATORY COMMISSION
%wseuer John Hickey,. Chief Fuel Cycle Safety Branch Division of Industrial 'and Medical Nuclear Safety, NMSS _
n 0FC IMUF: 6x K_. :IMUF6 IMUF/fd4j IMSF l NAME EKeegan: VTh5ph: Oi 'MT6(Yrf JHkkey:-
~
DATE 01/ M 93: 01Ql/93: 01/Sh93: 01/6Q/93:
OFFICIAL RECORD COPY C DCK 07000036 PDR :
n
- .q o-i Combustion Engineering, Inc. 2 jlW 2 2 $$ -
The licensee is authorized to receive, use,' possess,Lstore'fand; ,
transfer up to 8,000 kilograms of U-235' contained in uranium thatL is enriched to a maximum of 5.0 weight. percent in:U-235Lin accordance with 10 CFR Part 70, and up to 50,000 kilograms of?
source material in accordance with 10.CFR Part: 40.:. The-
~
possession limits for low-enriched uranium and source materials will not change with consolidation. ^
Need for the Proposed Action The proposed action is based on CE's expressed need-to improve:
commercial competitiveness in_the marketplace. Consolidation ~of-the fuel fabrication activities at the Hematite = facility.Will; ,
eliminate the need to transport radioactive materials between Connecticut and Missouri.- Consolidating: activities 1at Hematite, will eliminate the need for the Windsor-license.- The licensee -
will, therefore, no longer be required to pay;the annual fees;and-associated costs for two special nuclear. material licenses.-
The-licensee is the largest employer, and approval ofJthe proposed action would add ~ new ' jobs to this area.- Denial of-the- a proposed. action may cause CE to shutdown which would create 1a negative socioeconomic impact on the; area.
Alternatives-Including the Proposed. Action 1 i
The alternative to the proposed action is to deny the license amendment. -Denial of the proposed action would mean-theflicensee -i would have to continue manufacturing the nuclear fuel rods and. d
- assemblies at the Windsor facility,11f_theytwere-to remainlin a C business. This alternative = would only s be cconsidered if. there were public health'and safety issues that could_not'be resolved' to'the-satisfaction of the NRC.
The environmental impacts of.the alternative of the proposed-action will~be discussed in-this document..
L Background The facility ~1s located approximately 35 miles'(56 km) southiof St. Louis, Missouri, 3/4 of a' mile (1.2 km) northeast.of theitown
.of Hematite' in Jefferson County- (Figure 1) . The site is located-on approximately 155 acres with licensed activities:being 1 conducted in a 6-acre fenced work area.
L t
r
4 ,
a Combustion Engineering, Inc. 9 gg gg gg Airborne Effluents Prior to release to the environment, airborne effluents from process areas and process equipment are air filtered. While the processes are in operation, particulate filters continuously collect stack samples. The filters are changed weekly and are analyzed for gross alpha levels after suitable delay for the-decay of the naturally occurring radon daughter products. The licensee's existing control limits will not change for gross alpha activity in the exhaust air effluents of 4x10"2 pCi/cc, when averaged over a 2-week period, and 150 pCi per calendar quarter.
Prior to consolidation there were 17 exhaust stacks, and after-consolidation, there will be 16 stacks (Figure 4). Six of the existing stacks will be eliminated and replaced with three new stacks. New stacks will be added in the new pellet drying area and in Building 230. All new stacks will be HEPA-filtered to remove the particulate material in the air stream prior to discharge to the atmosphere.
The ventilation system for the fuel process areas in Building 230 is designed to move air from uncontaminated to contaminated areas. The specific operations in Building 230 that will be ventilated using a centralized HEPA-filtered ventilation system are the pellet alignment tables, the pellet / tube loading blocks, the short stack hood, and the scrap packaging hood. Other operations in the building may also be ventilated through HEPA filters. The air passing through this system will move through two tandem banks of absolute HEPA filters, which should remove essentially all of the particulate matter. The exhaust air will be continuously sampled and analyzed for uranium content. The air exiting the filter banks can either be recycled back into the work place or exhausted to the outside atmosphere.
A dose assessment was pe ned to evaluate if the proposed action would significant. crease the dose to the nearest residence from activitie. . Sucted at the site. The nearest private residence'is loc' 190 meters west-northwest of the plant site. The calcula Jfective dose equivalent to the. _
nearest adult resident is .024 mrem. For uranium exposure, the critical organ is the bone surface. The calculatea dose to the bone surface is 0.36 mrem.
The calculated doses are well below the annual whole' body dose limits set in 40 CFR 190.10 of 25 mrem and 10 CFR 20.105 of 500 mrem. The addition of the fuel rod and assembly work to the