ML20151R254

Insp Rept 70-0371/88-01 on 880201-05 & 16-19.No Violations Noted.Major Areas Inspected:Measurement Sys for SNM & Soil Sampling of Contaminated Area

ML20151R254
Person / Time
Site:	07000371
Issue date:	03/31/1988
From:	Della Ratta A, Jang J, Pasciak W, Zibulsky H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20151R237	List: ML20151R233 ML20151R254
References
70-0371-88-01, 70-371-88-1, NUDOCS 8804270281
Download: ML20151R254 (3)

Text

-. - -. _.. .- - -- - .

4Y. y, s

Ih t

. if .

U.S. NUCLEAR REGULATORY' COMMISSION REGION I Report No.' 70-371/88-01 Docket No.70-371 License No. SNM-368 Safeguards Group 1 Licensee: UNC Naval Products Division ,

67 Sandy Desert Road 4 Uncasville, Connecticut 06382  :

Facility Name: UNC Naval Products 1

-l l

Inspection At: Uncasville, Connecticut i Inspection Conducted: February 1-5, 1988 and February 16-19, 1988- '

+

i Inspectors: ?O-L TE H. Zi ulsky,4 hemist ) ckte t 0 orv 3 8(f J. ng, Sr. Rad ation pecialist date Av0e ia . tta', Aufitor '

$ 3 30~hY date i Approved by a n ,- v  ?! J' asciak, Chief, Efflilents Radiation / d(te W .fP ection Section, FRSSB, DRSS Inspection Summary: Routine, announced, material control and accounting  !

inspection on February 1-5, 1988 and February 16-19, 1988 l

, (Report No. 70-371/88-01) l l

Areas Inspected: Measurement systems for special nuclear material and soil sampling of a contaminated area. .

I

,Results: The licensee was in compliance with NRC requirements in the areas examined during this inspection.

1

~

8804270281 880404 PDR ADOCK 07000371 C Oc0

!~

. f ':

l w

fl

~

Details t

1. Persons Contacted

• T. Collopy, Manager Nuclear Material Control

• N. Grennon, Supervisor, Nuclear Mater 41 Contro I

• M. Kelly, Statistical Specialist' . - <

• All Present at exit interview.

2. Independent Inspection Effort l Independent inspection effort was conducted by a tour of the plant, during which the inspector observed plant operations and personnel l handling special nuclear material. No problems were noted.  !

3. Measurement Systems ,

A. Elements (February 1-5,1988)

The inspection results were obtained by performing independent l overcheck measurements of the licensee's element inventory to assure '

the inventory was. free of gross defects and that a formula quantity of U-235 was not missing. Elements selected were measured using a ,

Brookhaven Survey Assay Meter (B-SAM III) with a 2" x 2" NaI crystal detector.

The inspectors stratified the element population by nominal uranium-235 loadings. Three substrata that constituted the major portion of the licensee's inventory were chosen for verification by attribute testing using the formula:

n = (1-6 D ) (2N-D+1) 2 where; n = sample size to be measured 0="

w -

M = goal amount = 5000 gms U-235 B = 0.05 (95'4 confidenci level) u- = Average amount = loading N = Vault population

D = number of items that amount to 5000 gms (M )

e

, One element, chosen at random from each substratum, was used as the standard for its respective substratum. The inspectors independently verified the loadings of the "standard"_ elements by a -

_,_ __ . _ . . , _ . _ , _ - _ . . _ . _ . . _ . _ _ . - ,_..s-_e-._.,__-,.._ _ . _ _ _ .

1

-g '

m  !

_1 ... ,

3 / I i l

.i 3

review of: licensee documentation. Of the elements measured, the results indicated that no sample item was found to be gross i defective (>20% difference)'and no formula quantity of U-235 was ,

missing. F '

, ~i B. Feed Material (February 16-19,1988)

The inspection results were obtained by performing independent 1 overcheck measurements of the' U-235 content in feed material ,

containers located in the feed material vault (MBA-1). The containers selected were measured using a Brookhaven Survey Assay Meter (B-SAM III) with a 2" x 2" NaI crystal detector.

The inspectors generated a calibration curve of net counts versus net weight of containers. Containers, with varying net weights of the same fuel type, were chosen at random to be used as calibration standards. The containers were measured while they were rotating. ,  ;

, Types 3 and 5 fuels were measured. Of the fuel containers measured, the results indicated that no fuel container was found.to be gross  !

defective P20*; difference), i

4. Inadvertent 5ptilrifUraniumContaminatedWater ,

On February 17, 1988, a four inch iron pipe, from the final treatment tank inside the plant to a settling tank located outside the southeast corner of Building B, was broken during excavation to obtain fill dirt.

' Approx 1hately,2400 gallons of slightly contaminated shower and process water were released to the restricted area inside the fence line. Gross  :

alpha concentration of the water was 5.4 picocuries per milliliter, .

q assumed to be uranium, which is about 18% of the 10 CFR 20, Appendix B, '

Table II value for uranium contaminated water released to an unrestricted I area. Calculations indicated that about 0.6 grams of uranium-235 was I

released. I Tw inspector observed the licensee as the contaminated area (6 feet long {

I x 3 feet wide) was excavated to a depth of about 3 feet. Soil samples 4 l were obtained at 5 points at the bottom of the excavation pit. The 5 ia samples were composited and split in half. One sample remained with the e

licensee and the duplicate sample was given to the NRC inspector.to be brought back to Region 1. The sample is to be sent to the NRC reference 1

laboratory, Department of Energy, Radiological and Environmental Sciences Laboratory (RESL) for isotopic uranium analysis and gamma scan. On completion of the analyses by the licensee's contractor laboratory and

, (RESL) the results will be compared and evaluated by the NRC inspector.

(0 pen Item 70-371/88-01-01).

l 4

3

~

y 'b t

t

..h,'