ML20206A679
| ML20206A679 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 11/02/1988 |
| From: | Della Ratta A, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206A658 | List: |
| References | |
| 70-0820-88-02, 70-820-88-2, NUDOCS 8811150209 | |
| Download: ML20206A679 (3) | |
Text
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U.S. NUCLEAR REGULATORY COMMI$SION REGION I Report No.
70-820/88-02 D(
et No.70-820 License No.
$afeguards Group:
IV Licensee: UNC Incorporated USC'1Recoyery Systems Wood River Junction, Rhode Island 02594 Facility Name:
_UNC Recovery Systm Inspection At: Wood River Junction, Rhode Island Inspection Conducted:
September 15, 1933 Type of Inspection:
Routine _ Unannounced Material Control, Accounting a nd P hy s_i c a,l Security A ()/td uf
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a Inspector:
f4 A.(Oe1Ta Ratta,
/c s f J V x
afeguarcs huditor cate Approved by:
Y ' W*
_/~/- 2 ~ S t RTR. Ae f=477-Chie ' afeguarcs $ection. OR5$
date Inspection Sumea g: b pection on Septe.-ber 15,1933 (Report No. 70-320/88-0D Are a s In spec _t, d :
Nuclear raterial control, accounting and physical security, including:
storage and internal control, inventory, records and reports, and physical protection measures for special nuclear material of low strategic significance.
Results:
The licensee was in compliance with NRC requirements in the areas emanfned during this inspection, 8911150009 801104 PDR C
ADOCK 07000020 PNU
~
A DETAILS 1.0 K_ey Persons Contacted Mr. R. Gregg, Plant Manager
- Mr. K. Helgeson, Manager Nuclear and Industrial Safety Mr. R. Gigliotti, Corporate Security Director Sgt. J. Smith, Plant Security Officer Hr. J. L'Heureux, Nuclear Material Control Specialist
- present at exit interview 2.0 Material Control and Accounting a.
Storage and Internal Control The inspector reviewed the licensee's special nuclear material (SNM) file system, which indicates the quantity and location of all SNM at the facil' i. A comparison of the SNM records was performed by the inspector, as described in paraaraph 2.b.
No discrepancies were identified, b.
Inventory, The inspector reviewed supporting records that showed physical inventories were conducted at least annually as required by 10 CFR 70.51(d).
The licensee's last physical inventory was performed on August 30, 1988.
The inspection included an inventory verification performed by the inspector on September 15, 1388.
The licensee's most re:ent physical inventory listing was used as the basit fo; the verification. All items on the listing were located and identified by the seal number on each tamper-safed container and other identification markings.
The licensee's current inventory consists of 384 grams of U-235 contained in 32, tamper-safed 55 gallon barrels that are used as standards.
c.
Records and Reports The inspector reviewei the licensee's records, reports and source data. All Material Balance Reports (00E/NRC Form-742), submitted by the licensee fnr the period October 1, 1983 to March 31, 1988, wera reviewed for ccopliance with 10 CFR 70.53.
No discrepancies were identified.
During the period of July 6, 1987 to September 22, 1987, the iicensee shipped 3,360 barrels (55 gallon) of contaminated soil to burial.
A calculation made by the licensee during 1982 indicated that 17.4 E-5 grams of U-235 would be contained in each shipment of 60 barrels of the contaminated soil.
That value would La w-
2 not require the completion and submission to the NRC of a DOE /NRC Form-7 D Sy the licensee since it is below 1 gram.
Upon review of the lice >see's calculations, the inspector identified an error in their me wodology.
The inspector performed an independent verification of the licensee's 1982 calculation.
The inspector's calculation indicated the presence of 4.2 grams of uranium per shipment.
Since the ratio of U-234 to U-235 for this facility is approximately 27, the actual U-235 content for each contaminated waste shipment of sixty barrels, based on the inspector's calculation, should have been 0.16 grams.
Based on this value, the completion and submittal of a DOE /NRC Form-741 by the licensee for each contaminated waste shipment of sixty barrels would not be required.
The licensee was directed to re-evaluate its methodology and calculations and to the determine again the actual U-235 cor.nt of each waste shipment.
This will remain an open item until th:
re-evaluation is completed by the licensee.
The results of the re-evaluation will be reported to the NRC.
3.0 General Physical Security Requirements for SNM of ow Strategic Significance
~
The licensee's program for the physicci protection of SNM of low strategic significance was reviewed by the inspector for conformance to 10 CFR 73.67(f) requirements and the licensee's implementing procedures.
Specific components of the program that were inspected included:
records and reports; security organization; access and key control; physical barriers and written security procedures.
Implementation of the licensee's physical security procedures (PSPs) was found to conform to NRC requirements.
The inspector noted that the licensee's practice in one area, while meeting the requirements of 10 CFR 73.67(f), appeared to be inconsistent with the applicable portio,, of a PSP.
The licensee stated that the practice had ' een recently modified but revision of the procedure had a
been overlooked.
The inst. actor informed the licensee that the PSP should l
j be revised to refleet tne current practice. On September 19, 1988 the l
licensee contacted the inspector by telephone and advised him that a i
revised PSP had been issued.
4.0 Exit Interview The inspector met with the licensee representative indicated in paragraph 1 on September 15, 1988 and summarized the scope and findings of the inspection.
l At no time during this inspection was written mater'al provided to the l
licensee by the inspector.
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