ML19256E255
| ML19256E255 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 09/21/1979 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Sutherland J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19256E253 | List: |
| References | |
| NUDOCS 7911020024 | |
| Download: ML19256E255 (3) | |
Text
F
'e GEN ER AL h ELECTRjC NUCLEAR ENERGY PRODUCTS DIVISION
' ~ -
WILMINGTON MANUF ACTURING CASTLE HAYNE ROAD P. O. BOX 780. WILMINGTON', Pf. c, h8401. [9th) 543 DEPARTM ENT Sept mber 21. 1979 Mr. J. T. Sutherland U. S. Nuclear Regulatory Otnmission, RII 101 Marietta Street, NW - Suite 3100 Atlanta, Georgia 30303
Dear Mr. Sutherland:
References:
(1) FRC Inspection Report RII:GLT, 70-1113/79-17, dated 8/3.~/79 (2) NRC License SNM-1097, Docket #70-1113 Thank you for your letter referenced above which reported the results of the inspectica of our fuel fabrication plant by Mr. G. L. Troup of your office va August 13-16, 1979 Pertaining to the itm of apparent ncnccmpliance with NRC requirments in your letter, the mply to this its is given in the attachment to this letter.
We appmciate your inspector's ccrrments and suggestions mlated to our sployee safety and environmental protection progrann. These ccr:ments and suggestions am helpful to us in our constant efforts to inprove these programs, ensum the continued health and safety of plant personnel, and ensure our cocpliance with NRC mgulations and license conditions. We also selecme further discussion with your staff on the its in your letter and in our mlated reply, if necessary, for further clarification of this it m.
Your inspection report referred to above does not contain information which m believe to be proprietary.
Very truly yours, GENERAL ELECTRIC RMPANY Arthur L. Kaplan, Manager Licensing & Ocupliance Audits M/C J26 AIX:bnw NSD-I Attachrent 1Y6186 @
7911020 OFFiggt COPY
i GENERAL $ ELECTRIC s
Mr. J. T. Sutherland Septcmber 21, 1979 1
ATTAOB!ENT The information given below refers to the iten in Appendix A, " Notice of Violation," in the NBC Inspection Report RII:GLT, 70-1113/79-17, dated 8/31/79.
'Ibe corrective actions detailed below have already been implenented or will be implenented by the dates shown.
As regttirea by Condition 14 of License SNM-1097, materials and equipment released from restricted areas shall meet the contaminatan laut. of Annex C.
Annex C specifies
.the limits for the release of material from restricted areas as a maxunum amount of fhed alpha radioactivity of 25,000 disintegrations per minute per 100 square centi-meters and the average amount should not exceed 5,000 dhintegrations per ninute per 100 square centimeters.
Conttary to the above, on or about Augttst 7,1979, ma.teratt tais removed from the site restticted areas which was contaminated to tevels.in excess of the limits of Annex C to SNM-1097. The highest maximum level tats 30,700 dis-integratwns per ninate per 100 square centimeters and the highest average level was 14,800 disintegrations per ninute per 100 square centime.ters of fixed alpha radio-activity.
This is an infraction.
'Ihe following steps were initiated and ccmpleted prarptly after the discovery of the unterial which had been renoved fran the site:
(1) All trash raroval frun the site of uncontaminated trash fran the fuels building was stopped and such trash on hand was sorted to assure that no further nnterial of this type left the plant site.
(2) Contamination surveys of itens which could be found on the ground at the locatics and of the ground surface itself were nnde. No excessive contamination levels were found at that time (1645 on 8/8/79) by the Manager, Licensing &
Otzrpliance Audits.
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I Mr. J. T. Sutherland Septauber 21, 1979 Attachnent - Page 2 (3) The owner of the property upon which the material was found was infonned that all of the material would be mnoved prcmptly.
(4) The contractor providing raroval services was contacted and taken to the offsite location.
(5) The contractor raroved the nnterial from the offsite location and brought it back to our plant site.
(6) Surveys were conducted at the offsite location during and after the renoval process to assure that all of the contaminated itens had been removed and to assure that no residual detectable contamination ranained at the location.
(7) All of the itens in the returned material believed to be potentially contaminated were surveyed as soon as returned to the plant site.
As a result of this review, the following actions have been taken to reduce this opportunity for crossover:
(1) Tuo dimpsters were noved outside +,he fence around the fuel nanufacturing building canplex, one for lunchroan trash and one for canputer roan trash, to minimize the opportunity for crossover with contaminated trash.
(2) All uncontannnated trash fran the fuels building is being sorted and suspect itens retrieved and nonitored prior to rt:2aase of this trash fran the oite.
(3) Although we feel that the two actions described above constitute sufficient corrective actions to prevent recurrence of the noncanpliance situation, we are evaluating and will continue to evabtate long-tenn programs which could lead to longer tenn engineering or ouer types of activities to prevent recurrence of this situation. We plan to continue the present corrective actions described above until or unless we implenent additional actions as a result of our evaluations.
'A. L. Kaplan
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