ML20054L265
| ML20054L265 | |
| Person / Time | |
|---|---|
| Site: | 07000371 |
| Issue date: | 05/30/1975 |
| From: | William Allen, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20054L248 | List: |
| References | |
| 70-0371-75-06, 70-371-75-6, NUDOCS 8207070323 | |
| Download: ML20054L265 (4) | |
Text
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7 IE:I Fom 12 (Jan 75) (Rev)
U. S. NUCLEAR REGUIATORY COMMISSION OFFICE OF INT?ECTION AND ENFORCDIENT REGION I IE Inspection Report No:
7n '471/7s-n6 Docket Ko:
70-371 Licensee:
pno,,a v,,clont enrnnrntinn License No:
SNM-368 q
'?m n1 Prnducts_DiriElon Priority:
I Category:
g ri g V'
Safeguards Location:
New 11aven, Connecticut Type of Licensee: gagggg.,
Type of Inspection:
Announced Special (Closecut Survey)
Dates of Inspection:
May 16, 1975 Dates of Previous Inspection:
March 3-6,1975 (Radiation Protection) l
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Reporting Inspector:
DATE W. D. Allen, Radiation Specialist
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Accompanying Inspectors:
xnnn DATE DATE DATE None Other Acco=panying Personnel:
DATE
%Q(qf Ecviewed By:
D_
P. J. Knapp, C f, Facilities Radiological DATQ l
Protection Section l
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SUMMARY
OF FINDINGS r
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Enforcement Action A.
Items of Noncomyliance None B.
Deviat_ ions None 3..
J Other Significant Finding A.
Current Findings The inspection was licited to independent ceasurements in and around Building 24-D in New Haven, Connecticut, and discussions with licensee
]y representatives relative to a licensee report dated April 10, 1975. The report documented the licensee's final survey of the building and re-requested its deletion from the license.
H Id B.
Status of Previously Identified Unresolved Items
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,y a
Not Applicable Licensee Action on Previously Identified Enforcement Action Not Applicable Management Interview The inspector held an exit interview with D. Luster, Specialist P.adio-logical and Environmental Control at the conclusion of the inspection on May 16, 1975.
The inspector stated that, following analyses of the smears taken during the inspection, a report docu=enting the findings would be forwarded to IE:llQ for transmittal to the Fuel Cycle Licensing Branch.
ne inspector stated that a letter and a copy of the Inspection Report vould be sent to UNC.
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DETAILS I
L 1.
Persons Contacted D. Luster, Specialist, Radiological and Environtental Control N. Grenon, licalth Physics Technician 2.
Plant Tour l
A.
General Plant
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The inspector toured the facility identified in licensee's report
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dated April 10, 1975 as Building 24-D.
The floor plan, as presented, was verified.
It was noted that survey locations I
identified in the report were marked on floors and valls, hij B.
Autoclave Room 1.
The inspector visually inspected the only roo= where enriched uranium was handled according to the licensee. The inspector
'j asked if any air ducts or drains that served the room vere to l
remain.
A licensee representative stated that the only duct
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or drain work were on equipment which exhausted or drained l
within the room. lie further stated all this equip =ent had been removed to other licensed facilities for disposal. A visual inspection revealed no apparent drain lines or air exhaust ducts.
2.
The inspector asked what efforts had been made to decontaminate the autoclave room. A licensee representative stated that valls had been completely washed down twice and floors had been scrubbed five times, lie further stated that followin a finding of no additional reduction in removable contamination, the washing was discontinued.
C.
Outside Areas The inspector toured the outside areas of D-Tract and noted no unusual conditions or equipment, t
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3.
Independent Measurements i
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Fixed Alpha r
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The inspector took readings at random locations within the
'S plant with - Eberline PAC-4S alpha meter. The only detectable 3
fixed alpha readings were in the autoclave room.
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~3 fixed alpha readings were verified by the inspector and were with the levels presented in the licensee's report.
j in agreement t;o Icvels greater than those reported were identified.
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General Gamma Levels jN 1.
In Plant Areas
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.P Due to the fact that highly enriched uranium was handled in J
9 Building 24-D, the inspector toured the building with an j,
Eberline PR11-5-3 with a SPA-3 NaI crystal. No gan=a Icvels y
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above operating background were detected. The only exception f
was noted in the autoclave room where a slight increase above operating background was noted.
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Outside Areas c
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A gamma survey with the PRii-5-3 was performed on areas outside k
the building within D-Tract.
No gamma levels above operating M
background were detected.
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Removable Contamination
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A random number of smears were taken throughout the facility with
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I ny The smears were analyzed at IE:I on an Eberline SAC-4.
A summary
' d of results is as follows:
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General Plant Areas:
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1 All smears indicated 5 dpm/100 cm2 removable alpha or less X
Autoclave Room:
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?!aximum Removable Alpha - 40 dpm/100 cm2 X,
, A, Average Removable Alpha (Floor) - 12 dpm/100 cm2 Average Removable Alpha (Total Smears) - 15 dpm/100 cm2 f,.
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