ML20054L271

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Requests Deletion of All Ref to Bldg 24D from License SNM-368.All Operations Previously Performed in 24D Relocated to Montville Site.Statement Indicating Condition of Bldg Encl
ML20054L271
Person / Time
Site: 07000371
Issue date: 04/10/1975
From: Clemons P
UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.)
To: Rouse L
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20054L248 List:
References
NUDOCS 8207070328
Download: ML20054L271 (18)
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{{#Wiki_filter:. <UGC UNITED NUCLEAR c o a e o n a : i o u In Reply, Please e7 sa~oy ersr=r nono Refer To: NIS: 75-4-27 uncAsvius co.%cevicur essen vet e4e-isi April 10, 1975 Mr. L.C. Rouse, Chief Fuel Fabrication and Reprocessing Branch No. 1 Division of Materials and Fuel Cycle Facility Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 3 a s.,

Reference:

1. Docket No. 70-171 SN.i-368 2. License No. I

Dear Mr. Rouse:

This is a request to delete all references to the building designated as 24D from our license. All operations previously performed in 24D have been relocated to our Montville site. Enclosed is a summary statement indicating the condition of the building as it exists at this time. Your cooperation in deleting this building from our license is appreciated. Sincerely yours, UNITED NUCLEAR CORPORATION -a-te* f, %W Clemons, Manager Percy Nuclear and Industrial j Safety Services Department PEC:cjm i Attachments ce. 1.P. O'Reilly l Region I King of Frostia l l l F207070328 B20630 PDR ADOCK 07000371 C PDR y--- r-- .-4---,r -F

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SUMMARY

STATEMENT AND CONCLUSION This report is presented to justify United Nuclear Corporation, Naval Products Division's request to remove its facility designated 24D and D Tract from Special Nuclear Material License SNM-368 and to release the premises for unrestricted use. The following sections of this report establish that contamination is within the limits specified by the Nuclear Regulatory Commission. In order to reach these release levels, it was necessary to decontaminate only one 8 foot by 7-1/2 foot by 12 foot room. This ef fort also involved -the removal of a small autoclave (approximately 5 inches diameter by 3. feet long), table associated ducting, blower and plumbing. All other areas of the building were below release levels. The building was used to fabricate clad fuel bearing material, specifiejlly enriched uranium. Our in-house quality control program required that no significant removable alpha contamination be permitted in the general manufacturing area. Therefore, smear surveys for removable alpha radiation were taken routinely when the building was in operation. For quality con-trol purposes, contamination levels for removable alpha were controlled to greater than one-thirtieth the permissible limit for unrestricted use, i.e., t 30 disintegrations per minute per 100 square centimeters. These Health Physics records remain on file at our Montville facility. All areas of this building are below the limits established by the Commission. All radiation surveys for this report and for previous routine inspections during production have been documented and are on file in Health Physics i records. i e h l l

SECTION t.n Facility Identification 2.0 Facility Release Specifications 3.0 Instrumentation 4.0 Scope of Survey 5.0 Area Survey Results s.. e ? I [ T

acility Ident111 cation 1.6 r 1.1 The building is identified as 24D and referred to as "D" Tract in our SNM License. The tract is within an area bounded by Winchester Avenue, Division Street, Mansfield Street and Munson Street (See Figure 1; Mason Street and Sheffield Avenue are private streets and closed). The 24D building design is conventional, consisting of a first floor area of 65,000 square feet, with a partial basement area of 16,000 square feet and a mezzanine area of 5270 square foot. 1.2 Facility Use WLth the one exception of the autoclave room discussed below, only clad fuel bearing material was processed in 24D. Elements were received from the "H" Tract production area and fastened and welded together into larger fuel-bearing uc-fonents. These components were then shipped to the Montville facility for further upgrading. Structurals and other non-fuel bearing core components were also pro-cessed in this tract. Assoc'iated operations such as cleaning, pickling, corrosion testing and vacuum annealing were conducted along with quality control inspection and non-destructive testing. It ic appropriate to note that one of these inspections required a quality control " alpha count" which was performed on every fuel element in the 24D production line. This inspection, utilized gas flow alpha radiation detectors and was sufficient to determine the lack of alpha surface contamination. The mezzanine was restricted to officer, lunch room and locker facilities. The basement area containct element r+nra9., naintenance, and Q.C. inspection areas.

P/ ag e M h.t t_o g,1 gv e_ R o o_m_ one corrosion test involved small sectioned pieces of clad fuel-bearing material which had exposed fuel-metal edges. This autoclave operation was confined to an approximately 8 foot by 7-1/2 foot by 12 foot enclosed room located in the basement between Columns 158 and 15C approximately and identified as Autoclave Room. s,. 9 0 h

"ACILITY RELEASE SP5d!IICA~~ONS

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2.1 The maximum amount of fixed alpha radicactivity in disintegrations per minute per 100 square centimeters en buildings or equipment should not exceed 25,000. f 2.2 The average amount of fixed alpha radioactivity in disintegrations per minute per 100 squarc centimeters on buildings or equipment should not exceed 5000. 2.3 The maximum amount of removable (capable of being removed by wiping the surface with dry filter or soft absorbent paper) alpha radio-activity in disintegrations per minute per 100 square centimeters on buildings or equipment should not exceed 1,000. 2.4 The average amount of fixed radiation on surfaces of buildings or equipment should not exceed 0.2 mrad per hour at one centimeter when meadured through not more than 7 milligrams per square centimeters I of total absorber. e 1 2.5 The maximum amount of fixed radiation pn surfaces of buildings or 1 mrad ped hour equipment should not exceed at one centimeter when measured through not more than 7 milligrams per square centimeters of total absorber. 2.6 The average amount of removable (capable of being removed by wiping the surface with dry filter or soft absorbent paper) beta-gamma radioactivity in disintegrations per minute per 100 square centimeters should not exceed 1,000. I The above figures represent Table I and Table II release values as i i detailed in the Nuclear Regulatory Commission's " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Un-e i restricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear Material". t i 1 i l i i e i l e I i

3.,0 Instrumentati Direct alpha radiation surveys were made utilizing an Eberline Gas Flow Proportional Counter Model PAC-4G with Eberline Alpha Probe Model AC-21. The units were calibrated to an Eberline Standard Set containing certified sources with special holders for positioning the alpha detector probe. Direct beta / gamma radiation surveys were =ade utilizing an Eberline Pulse Rate Meter PRM-5 with an Eberline Hand Probe Model HP-210. Removable radioactive material was determined by smears which were counted in the Health Physics Laboratory on appropriate counting instrumentation. l \\ e e 9

0, Scope of Survey 4.1 Fl. s t Floor, Basement and Mezzanine The building is essentially empty with all usable process and p ro-duction equipment having been removed to the Montville facility. A final survey was taken on the floors in all areas as displayed in Figures 2 and 3. This is felt to be sufficiently ccmprehensive based on the following: No exposed fuel was introduced in these areas. 'No airborne radioactivity was ever introduced. Only clad uranium was processed. The re fo re, wall surfaces, ceiling surfaces and structural surfaces are not likely to be contaminated. No beta-gamma emitters (isotopes with decay modes other than alpha emission) were processed in this buiJding. It follows that the decontamination to below release levels for removable alpha activity makes a detailed beta-gamma survey for removable activity unnecessary in this situation. The final survey included smears for removable alpha contamination, and surveys for fixed alpha and fixed beta-gamma radiation at each designated location in Figures 2 and 3. 4.2 Autoclave Room Final surveys were taken on the floors, walls and ceiling of the autoclave room as displayed in Figures 4 through 9. Removable alpha, fixed alpha and fixed beta-gamma radiation were determined. 4.3 Element Storage Vault In addition to the floor survey, each rack of the element fuel storage vault was surveyed for removable and fixed alpha contamination. No radiation exceeding background was observed. i t l I i r j 6 l

5.0 Area Survey Findings 1:o removable alpha contamination was found in any area of the building except the autoclave room. Hot spots (less than 3000 disintegrations per minute per 100 square centimeters were found on one wall in this room. The entire room was decontaminated. Final results are presented below for all areas [ Figures 2 through 9]). I l The grid legend used is as follows: Removable Average S.' Alpha Fixed Alpha i 2 2 dpm/100 cm dpm/100 cm Maximum Maximum i fixed beta-Fixed gamma Alpha mrad /hr de-f l00 cm2 /' Average fixed alpha radiation is not indicated in those areas where the maximum fixed alpha is 4 100 dpm/100 cm2 Figures 4 { 0.5 square meters. through 9 have grid areas In no case does the removable alpha contamination exceed 1000 dpm per 100 square centimeters l i em t ~.

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