ML19343D264
| ML19343D264 | |
| Person / Time | |
|---|---|
| Site: | 07002317 |
| Issue date: | 03/10/1981 |
| From: | Book H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Higginbotham L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19343D263 | List: |
| References | |
| NUDOCS 8105040070 | |
| Download: ML19343D264 (1) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION s
REGION V k i
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1990 N. CALIFORNIA BOULEVARD I
SUITE 202, WALNUT CREEK PLAZA 4
WALNUT CREEK, CALIFORNIA 94596 O
,,,a March 10, 1981 MEMORANCUM FOR: Leo Higginbotham, Chief Radiological Safety Branch, IE:HQ FROM:
H. E. Book, Chief Radiological Safety Branch, IE:HQ
SUBJECT:
Teledyne Cast Products, Pomona, California License No. SNM-1677, Close-out Survey Enclosed are 2 copies of the report of the close-out survey conducted at the subject facility.
No residual contamination or radiation was detected, and the facility ray be returned to uncontrolled status.
We request that you send one copy of this report to W. T. Crow, NMSS so he can proceed with termination of the license, as requested by Teledyne Cast Products.
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err H. E. Book, Chief Radiological Safety Branch
Enclosure:
Inspection Report No. 70-2317/80-01 81050.40070 I
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o UNITED STATES NUCLEAR REGULATORY COMMISSION g
REGION V t K 'N j
1990 N. CALIFORNIA BOULEVARD o-g V
O SulTE 202. WALNUT CREEK PLAZA o
- ,,,a WALNUT CREEK, CALIFORNIA 94596 March 10, 1981 License No. SNM-1677 Docket No. 70-2317 Teledyne Cast Produc+s 4200 West Valley Boulevard P. O. Box 2348 Pomona, California 91765 Attention: Edgar W. Dansby President Gentlemen:
Subject:
NRC Inspection (Confirmatory Survey)
This letter refers to the close-out safety inspection conducted by Mr. R. D.
Thomas of this office on December 16, 1980 of activities authorized by NRC License No. SNM-1677 and to the discussion of our findings held by Mr. Thomas 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 conducting of a confinratory survey of the areas where special nuclear materials had been used and stored pursuant to those activities conducted under NRC License No. SNM-1677. The results of the confirmatory survey are recorded in the enclosed inspection report.
it has been determined Based upon the results of the confimatory survey,d are below those specified that the contamination levels in the areas examine in Table I of the "Comission Guidelines." A copy of the " Guidelines" was sent to you as an enclosure to NRC letter dated September 18, 1980.
A copy of the enclosed inspection report will be sent to our headquarters licensing staff for consideration in the termination of License No. SNM-1677 and the return of your facilities to unrestricted use.
If you have any questions regarding this inspection, we will be glad to discuss them with you.
Sincer ly,
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H. E. Book, Chief Radiological Safety Branch
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U.S. IlUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EHFORCEMENT REGION V Report no. 80-01 License No.SNM-1677 Priority
~IV Category E
Licensee: Teledyne Cast Products 4200 W. Valley Boulevard Pomona, California 91766 Facility Name: (Same as above)
Inspection at: (Same as above)
Inspection Conducted: Decerrber 16, 1980
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Inspectors:
0' ate' S igneo R. D. Thomas, Inspector
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Approved by:
Ofte Signed H. E. Book, Chief Radiological Safety Branch 3
y, Insoection of Decerter 16, 1980 (Report No. 70-2317/80-01)
This inspection was conducted as a confirmatory survey of the areas 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 The treas had previously been decontaminated and surveyed by the licensee.
use.
The NRC inspection required two hours onsite by one inspector.
Results:
A physical radiation survey and contamination checks were made in the storage area, the handling area, and the melting pot areas. Nosignificantradiat(on levels or areas of contamination were observed.
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OETAILS A.
Person Contacted Stephen Beal, Resea ch & Development Engineer NOTE:
Messrs. E. W. Dansby, President, and E. N. Bossing, Radiation Safety Officer, were not available during this inspection.
B.
Background
Pursuant to a letter dated January 8, IE80, a request was made by the licensee to have License Number SNM-1677 tertainated since all materials had been transferred to Union Carbide Corporation Paducah, Kentucky which is a COE contractor. Subsequently, 9n NRC letter dated September 18, 1980 stated that the licensee must perform a radiation survey of the facilities and submit the results to the Coanission. A confinnatory 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 % Table I of the NRC " Guidelines for Decentamination of Facilities t.nd Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct Source or Special Nuclear Materi al."
1 C.
Licensee'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 contambation 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 Ludlum Alpha Meter, Model 12, with an Air Proportional Alpha Probe, Model 43-4.
In the areas examined, there were no significant contamination levels observed.
A beta-gama survey was also conducted using a Dosimeter;. Corporation, r
Mini CON-RAD Mcdel No. 3032 with a thin end-windcw 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 j A check for loose radioactive contamination was also conducted by the inspector in the areas mentioned above. Particular attention was placed on the floor areas, melting pots, and objects in the stcrage 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 appears that all NRC licensed materials have been transferred to a DOE contractor.
It also appears that the licensee has properly decont'aminated the 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 avaflable at the time of the inspection, only a brief discussion was held with Mr.
Stephen Beal. The results of the confirmatory survey were discussed.
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- } -e 4 c iEDYNE CAST PRODUCTS 4200 W. V ALLE Y 500 LEV AR D' P.O. SOX 2348 [d4 # rouona.cau roRuia mim I heh dh $ E m4: ses 22s2 5 YN[' ip, rwx e aio-sai-seoo February 24, 1981 g U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 1990 North California Blvd. Suite 202 Walnut Creek, California 94$96 Attention: Robert D. Thomas Chief Materials Radiological Protection Section
Reference:
SNM-1677 License
Dear Mr. Thomas:
In Accordance with your request and the " Guidelines for Decontamination of Facilities and Equipment, etc." of November 1976, enclosed please find the survey conducted at Teledyne Cast Products by myself. The survey was performed using an EON Corporation, Portable Survej Meter, PSM-700 that had just been calibrated by an outside laboratory. No readings above background level were found in any area where the licensed material was stored, transported, handled, melted, or repackaged for return to it's original source, UNION CARBIDE. Wipe samples taken on floor, corners, etc., also showed no meter readings above background. I hope this information is satisfactory. If more infor-mation is required, please contact me. Sincerely, TELEDYNE CAST PRODUCTS Emmett N. Bcssing g Radiation Safety Officer ENB:ep i CC: W.T. Crow, U.S. NRC, Washington, D.C. Division of Fuel Cycle 1 and Material Safety Vandy Miller, U.S. NRC, Washington, D.C., Office of Nuclear Material Safety and Safeguards E. W. Dansby - TCP H. Cripe - TCP
Enclosure:
Monitor g Survey Report, 12-13-79 h//N]0/X k
~ e 'b .. f, NM i 77 MONITORING SURVEY REPORT Date: /2 l).3 79 f //d /ST / ro/a ch, fo,1tesis (>si,y I Time Period Location l^ to' MelTIA4 /frer / Sroxir&g gi,a f,, 2.19 l Description of job: - ConTitMsM4Te*ci 4'?/k I//dd alisi m l N C4bem>De }' 2 l> a ed beVe O. l} A pe. So TC.P (~,p.J c/bre co r J / JJ
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i i Measurements Made { Contamination Level . Radiation Level No. Ite m mrad /hr mr/hr cpq dpm (WO) (WC) p,cret nvo k-sv'r~ survey wim He rer 1 ft (t,D,) f pf y e a. - 0 0 0 O + fsL7er fo r Web >
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STodd kd //rta (by bfiltrN V/**W)) 0 O O O v3 4 5 6 7 l i '8 '9 10 Ins'tr. Used: [$#1 700 Scrial If Instr. Used: [SM 760 Serial # Comments: /JC y~pal,gns ohTaisp l hroa )) r?.r farveats or $rog is*j pr S. J J / o' NrMis!# Y~ted O $ YI bl[t'A'St'
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