ML20010A681

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Safety Evaluation Supporting Teledyne Cast Products Request for Termination of License SNM-1677 & Release of Facility for Unrestricted Use
ML20010A681
Person / Time
Site: 07002317
Issue date: 07/30/1981
From: Crow W, Soong A
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20010A678 List:
References
NUDOCS 8108120024
Download: ML20010A681 (2)


Text

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Distribution:

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NMSS r/f FCUF r/r JUL 3 01981 FCUP r/f ALSoong LTyson WTCrow IE HQ (2)

RErickson DOCKET NO: 70-2317 JRobertson APPLICANT: Teledyne Cast Products (TCP)

JBlaylock HEBook, R:V FACILITY:

Pomona, California

SUBJECT:

RCVIEW 0F TCP'S REQUEST FOR TERiilNATION OF MATERIALS LICENSE N0. S!!M-1677 AND RELEASE OF THE FACILITY FOR UNRESTRICTED USE REVIEWER:

A. L. Soong I.

Background

Teledyne ca.it Products of Pomona, California, is the holder of Materials License No. SNM-1677. The lienses was issued in 197C, anc' is due to axpire on September 30, 1981. The licensee is authorind to possess and use up to 4800 grams of U-235 as contained in aluminum contaminated with :.pecial nuclear material (SNM) enriched to a maximum of 1.5% in the U-235 isotope. The licensee had planned to melt cast aluminum billets that contattled small quantities of Sitt and cast them into com-pressor stator assemblies for use by Union Carbide Corporation (a DOE l

pri'ne contractor) in the gaseous diffusion plants; however, because of technical difficulties, only one aluminum casting was made that contained licensed matirjal and all licensed matetial was returned to Union Carbide Corporation. Paducah, Kentucky. By letter dated January 8,1980, TCP re-quested that itsMaterials License be terninated.

By letter dated September 18, 1980, the Comission indicated to the licensee that they must provide the Comission with results of a radiation survey of the facilities to show that the contamination levels are below those limits specifico in Tho'a 1 of the Comission's " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unre-stricted Use or Temination of I.icense for Byproduct Source or Special Nuclear Material," dated flovember 1976 (Enclosure 1). These guidelines also describe tne procedures to be followed and infomation required prior to termination of the Materials License.

By lecter dated February 24, 1981, TCP submitted a final radiolcgical survey report (Enclosure 2) showing that measured contamination levels in the melting pot and storage area of the faci'ity were below the limits as specified in the above guidelines.

By letter dated March 19,1981 (Enclosure 3), IE concluded, based on the result of IE's confimatory survey of the facility, that the centamination levels in the facility met the Comissior guidelines for releasing the ~

facility for unrestricted _uit_AnLreIEInended temination ef_fhe_Special OFFICE k SlhfONb "I

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, JUL 3 01981 II. Discussion The licensee's radiological survey repcrt shows that the contamination level is at background level, and IE's confimatory survey verifies that the residual contamination level in the facility is insignificant and below the guidelines for releasing the facility for unrestricted use.

On July 7,1981, I discussed this case with Mr. R. Thomas, IE Region V inspector. He indicated that all the equipment for handling the licensed material had been decontaminated by the licensee to the level below the guideline's limits.

The licensee's Nuclear Material Transaction Report, NRC Form 741, shows that TCP had returned the licensed material to Union Carbide Corporation at Paducah, Kentucky on August 29, 1977. This was confinned by a telephone conversation with Mr. Kraemer of Union Carbide Corporation.

on July 9, 1981.

III. Conclusion Based on the findings in the current assessment, the release of the Tcledyne Cast Products facility for unrestricted use represents an insignificant risk to the public health and safety to the environment.

Therefore, it is recommended that TCP's Matetlais License No. SNM-1677 be terminated and the facility released for unrestricted use, Or* gina151gned By:

A. L. Soong A. L. Soong Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Original sis 6ed bii-Material Safety W. 7. crov Approved by:

W. T. Crow, Section Leader l

Enclosures:

As stated l

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ENCLOSURE.1.

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--7 C row LTyson OCS HBook, P:5 WCooley, R:5 Teledyne Cast Products IE HQ (2) p9q ATTH: Mr. Emett H. Bossing RGPage Radiation Safety Officer TFCarter 4700 W. Valley Boulevard P.O. Box 2348 RECunningham SH0 Pomona, California 91766 JPartlow Gentlemen:

This is in response to'your request of January 8,1930, to teminate Specic!

Huclear l',aterial License Number SNM-1677.

Encloseu is a copy of HRC's

" Guidelines for Decontamination of Facilities and Equipment Prior to Release For Unrestricted Use or Temination of Licenses For Byproduct, Source or Special Huclear Material." These " Guidelines" describe the procedures to be followed and infomation required prior to temination of a Special Nuclear Material License. After you have provided the Coonission with a radiation survey of youi facilities, as described in these guidelines, NRC's Office of Inspection and Enforcement will visit your facility and perfom a confimetory survey.

If this survey confims that contanination levels are below those specified in Table I of the Commission's Guidelines, SNM-1677 will be teminated and your facilities will be releated for unrestricted use.

Should you have any questions concerning these guidelines or the procedures i

for teminating your license, please feel free to call me at 301/427-4100'.

Sincerely, Original Signed By:

W.T. Crow W. T. Crow, Section Leader Uranium Process Licensing Section Uranir.m Fuel '.icensing Branch Division of Fuel Cycle and Material Safety

Enclosure:

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UNIfED STATERS

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WALNUT CREEX, CALIFORNIA 94596 Ma c h 10, 1981 License No. SNM 1677 Decket No. 70-2317 Teledyne Cast Products 4200 West Valley Boulevard P. O. Box 2348 Pomona, California 91766 i

a Attention:

Edgar W. Dansby s.

President -

Gentleren:

Subject:

NRC Inspection (Confimatory Survey)

This letter refers to the close-out safety inspection conducted by Mr. R. D.

Thomas of this office on Decerber 16, 1980 of activities authorized by NRC License No. SNM-1677 and to the discussion of our findings held by Mr. Thoras with Mr. Stephen Beal, of your staff, at the conclusion of the inspection.

This inspection consisted of a review of the' licensee's survey records and the corducting of a confinatory survey of the areas where sp'ecial nuclear raterials had been used and stored pursuant to those activities conducted under 4"C License No. SNM-1677. The results of the confirratory survey are recorded in the enclosed inspection report.

Based upon the results of the confimatory survey, it has been determined that the contamination levels in the areas examined are below those specified in Table I of the "Comission Guidelir,es." A copy of the " Guidelines' was sent to you as an enclosure to NRC letter dated September 18, 1980.

A copy of the enciosed inspection report will be sent to our headquarters licensing staff for consideraticn in the termination of License No. SNM-1677 and the return of your facilities to unrestricted use.

If you have any questions regardir.g this inspection, we will be glad to discuss them with you.

Sincer ly, C

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v H. E. Book, Chief Raoiological Safety Branch x

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e i-m U.S. IlUCLEAR REGULATORY.COMMISS10t!

0FFICE OF INSPECTIOil Arid EllFORCEMEt1T REGION V Report tio. 80-01 License flo.SfiM-1677 Priority

'IV Category E

Licensee: Teledyne Cast Products 4200 W. Valley Eculevard

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Pomona, California 91766' Facility ?!ame: (Sameasabove)

Inspection at: (Sameasabove)

Irispection Conducted: December 16, 1980 Inspe: tors:

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R. D. Thomas, Inspector 0' ate' Signed 4

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C-Approved by:

e H. E. Book, Chief DAte signed Radiological Safety Branch Sur. mary:

Inspection of December 16, 1980 (Recort No. 70-2317/80-01)

This inspection was conducted as a confirmatory survey cf the r.rcas where special nuclear materials (SNM) had been used by the licensee.

The results of this survey will establish if the facilities can be released for unrestricted use. The areas had previct31y been decontaminated and surveyed by the licensee.

.The.NRC inspection required two hours onsite by one inspector.

Resul ts :

A physical radiation survey and contamination checks were made in the storage area, the handling area, and the melting pot areas. No significant radiat(on levels or areas of contamination were observed.

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-e y-e DETAILS A.

Person Contacted Stephen Beal, Research & Development Engineer MOTE:

Messrs. E. W. Dansby, President, and E. H. Bossing, Radiation Safety Officer, were not available during this inspection.

B.

Ba:karound Pursuant to a letter dated January 8,1980, a request vas made by.the licensee to have License Number SNM-1677 terminated since all materials had been transferred to Union Carbide Corporation, Paducah, Kentucky which is a 00E contractor. Subsequently, an NRC letter dated September 18, 1980 stated that the licensee must perform a radiation survey of the facilities and submit the results to the Commission. A confirmatory survey would be conducted by NRC prior to termination ~of the license.

The facilities would be released for unrestricted use if the contamination levels are below those specified in Table I of the NRC " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct Source or Special Nuclear Material. "

C.

Licensea's Survey Results Enclosed as Appendix A is the Monitoring Survey Report, dated 12/13/79, which indicates the results of the survey conducted by the licensee.

The licensee's survey data do not show any radiation or contamination levels present in the melting pot or storage areas.

D.

Confirmatory Survey Results On December 16, 1980, the inspector conducted a confirmatory survey in the storage area, handling areas, and melting pot areas where the SNM had been used or stored.

. An alpha survey was conducted using a Ludium Alpha Meter, Model 12, with an Air Proportional Alpha Probe, Mcdel 43-4.

In the areas examined, there were no significant contamination levels observed.

A beta-gamma survey was also conducted using a DesimetertCorporation; Mini CON-RAD Model No. 3032 with a thin end-window GM detector.

In the areas examined, there were no significant radiation levels observed.

Both of the above instruments were in current calibration.

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A ' check for loose radioactive contamination was also conducted by the inspector in the areas centioned above.

Particular attention was placed on the floor areas, celting pots, and objects in the storage area.

Twelve swipes were taken during the inspection. The swipes'were counted in the NRC -laboratory NMC Model PC-55 Gas Proportional Counter which has an alpha efficiency of 49.0%.

The counting results indicated no significant contamination levels.

E.

Conclusions Based upon the results of this inspection it appear's that all HRC licensed materials have been transferred to a DOE contractor.

It also appears that the licensee has properly decontaminated Lthe facilities and there are no significant radiation or contamination levels present.

It would appear.that the areas surveyed could be released for unrestricted use.

F.

Exit Interview Since the President and Radiation Safety Officer were not available at the tire of the inspection, only a brief discussior, was held with Mr.

Stephen Beal. The results of the confirmatory survey were discussed.

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4 CAST-PRODUCTS 4200 W. VALLE Y BOULEVA RD V

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February 24, 1981 c1, #

U.- S. Nuclear Regulatory Com:nission Office of. Inspection and Enforcement 1990 North ~ California Blvd.

Suite 202 Walnut Creek, California 94596

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Attention:

Robert D. Thomas Chief Materials Radiological Protection Section

Reference:

SNM-1677 License

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Dear Mr. Thomas:

In-Accordance with your request and the " Guidelines for Decontamination of Facilities and Equipment, etc." of November-1976, enclosed please find the survey. conducted at Teledyne-Cast Products by myself.

The survey was performed using an EON Corporation, Portable Survey Meter, PSM-700 that had just been calibrated by. an outside laboratory.

No readings above background level were found in any area where the licensed material was stored, transported, handled, melted, or repackaged for return to it's original source, UNION CARBIDE.

Wipe samples taken on floor, corners, etc.,

also showed no meter readings above background.

I hope this information is satisfactory.

If more infor-cation is required, please contact me.

Sincerely, TELEDYNE CAST PRODUCTS E

Emmett N.

Bessing g

Radiation Safety Officer ENB:ep CC:

W.T. Crow, U.S. NRC, Washing, ton, D.C. Division of Fuel Cycle and Material Safety Vandy Miller, U.S. NRC, Washington, D. C., Office of Nuclear Material Safety and Safeguards E. W. Dansby - TCP H. Cripe - TCP

Enclosure:

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