ML20197J441

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Discusses Addl Sampling at Former Gulf-United Nuclear Corp Site.Cleanup Efforts of Small Area of Cs-137 Contamination in Waste Disposal Bldg Continuing.Cleanup to Background Levels Not Complete Due to Lack of Time & Info
ML20197J441
Person / Time
Site: 07000903
Issue date: 03/11/1986
From: Boerner A
OAK RIDGE ASSOCIATED UNIVERSITIES
To: Roth J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20197J402 List:
References
NUDOCS 8605200040
Download: ML20197J441 (3)


Text

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Oak Ridge Manpower Ecucation.

Associated Post Office Box 117 Research. and Training Universities Oak Ridge, Tennessee 37831-0117 Divis.cn March 11, 1986 Mr. Jerry Roth Region I Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Subject:

ADDITIONAL SAMPLING AT THE FORMER GULF-UNITED NUCLEAR CORPORATION SITE, PAWLING, N.Y.

Dear-Mr. Roth:

On February 28, 1986, personnel of Oak Ridge Associated Universities Radiological Site Assessment Program (0RAU/RSAP) continued cleagup efforts (initiated on February 26, 1985) of a small general area (16 ft ) of Cs-137

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contamination located in the northeast portion of the Waste Disposal Building at the former Gulf-United Nuclear Corporation site near Pawling, New York (Figure 1).

Canana scanning, using NaI(TI) scintillation detectors, indicated surface contact levels, prior to cleanup, ranging from 45 to 240 pR/h. Elevated beta-gamma readings were also obtained. Exposure rates of 16 pR/h were recorded at 1 m above the surface.

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Coring operations removed an additional 3 f t of concrete and 6 ft of soil. Contact exposure rates were significantly reduced; however, elevated activity still remains, especially on a small concrete strip located under a metal support (contact levels of 120 pR/h were recorded). This area could not be accessed for cleanup purposes. Exposure rates at 1 m above the surface were reduced to 13 UR/h. Elevated contact exposure rates (45 pR/h) were also noted on the western portion of the contaminated concrete slab. This area covers approximately 0.5 ft x 2 ft.

Exposure rates in this area may be due, however, to the isolated location of elevated activity noted above.

One additional location of elevated radiation levels (230 pR/h) was identified in the extreme northeast corner of the building. Concrete chip fragments were removed, reducing contact exposure rates to 16 pR/h.

8605200040 860502 PDR ADOCK 07000903 C

PDR Enc 1(2)

Mr. Jerry Roth March 11, 1986 4

All concrete debris and removed soil was returned to Oak Ridge, Tennessee for analysis.

It should be noted that because of limited site information and lack of proper equipment and time to finish the survey, ORAU was unable to complete cleanup to background levels.

Comments concerning these findings may be addressed to me or Mr. James Berger at FTS 626-3305.

Sincerely, W

Alex J. Boerner Team Leader Radiological Site Assessment Program AJB: cit

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