ML20058Q285
| ML20058Q285 | |
| Person / Time | |
|---|---|
| Issue date: | 08/02/1993 |
| From: | Arredondo S, Kinneman J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20058Q263 | List: |
| References | |
| REF-QA-99990001-930803 99990001-93-05, 99990001-93-5, NUDOCS 9310260129 | |
| Download: ML20058Q285 (8) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION REGION I INSPECTION REPORT Repon No.
99990001/93-005 Docket No.
030-04659 License No. 20-06799-02 (Retired)
Owner:
DBT Comoration Shawmut Bank One Federal Street OF-3303 Boston. Massachusetts 02211 Former:
Cambridge Medical Technology. Inc.
575 Middlesex Turnpike Billeriet Massachusetts Inspection At:
575 hiiddlesex Turnpike Billerica. Massachusetts Inspection Conducted: March 10. April 23. June 4. and June 24.1993 Inspector:
MLLA h.
7/2 93 Sheri A. Arredondo, Health Physicist date I)
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Approved by:
M L
3 ohn Kinneifian, Chief flati:
esea ch, Development and D' onunissioning Section Inspection Summary: Closecut Inspection on March 10. telephone conversations on April
- 23. and June 24. 1993 and review of decommissioning report received on June 4.1993.
Onspection No. 99990001/93-005) 9310260129 930803 REC 1 GA999 EEC*****
99990001 PDR
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Areas Inspected: Announced, closcout inspection limited to a survey of the site of the radioactive materials waste storage shed bcNind the building located at 575 Middlesex Turnpike, Billerica, Massachusetts for residual radioactive contamination and a review of the radiological decommissioning report of that area prepared by a contractor. Two composite soil samples were taken and assayed for gamma emitting isotopes; measurements of radiation levels were perfonned at selected locations.
Results: No violations were identified. Twelve,110-liter (thirty gallon) dntms containing radioactive waste were observed on March 12, 1993 inside a fenced area near the site of the waste storage shed. Thes. drums were picked up on March 25,1993 by U.S. Ecology for licensed disposal. The removal of these drums was confinned during a telephone conversation with Michael Madonia of Roy F. Weston on April 23,1993. This disposal was documented in the radiological decommissioning report received on June 4,1993.
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DETAILS t
1.
Persons Contacted John Myers, Assistant Vice President, DBT Corporation Michael Madonia, Section Manager of Radiological Services, Roy F. Weston, Inc.
(by telephone)
Anne White, Health Physicist, Roy F. Weston, Inc.
===2.
Background===
The main building located at 575 Middlesex Turnpike, Billerica, Massachusetts, was decontaminated and surveyed prior to the tennination of Cambridge Medical' Technology's NRC License (No. 20-06799-02) on October 1,1991. A final survey of this building was perfonned by Chem-Nuclear Systems, Inc. and confinned by i
Region I. In recent years Cambridge Medical Technology had used only iodine-125, but in prior years a variety of isotopes had been used. A shed behind the facility and adjacent to the parking lot where radioactive waste had been stored was inadvertently not included in the facility decontamination or surveys.
Measurements by an independent consultant indicated that radioactive contamination remained in the waste stomge shed. DBT Corpomtion, the new owner of the facility, contracted with Roy F. Weston, Inc., (Weston) to chanteterize the extent of the mdioactive contamination and to develop a remediation plan.
In a letter dated December 8,1992, Weston submitted a report of their characterization survey of the waste storage shed to the NRC on behalf of DBT. That survey identified radiological contamination in excess of the values in the NRC's
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Tennination of Licenses for Byproduct, Source, or Special Nuclear Material (May 1987)." Concentrations of radioactive material in soil exceeding the current NRC criteria for residual radioactivity in soil were also identified. Weston also submitted a remediation plan, entitled, " Radiological Decommissioning Work Plan," to Region I on behalf of DBT. On Febmary 17, i
1993, Region I wrote to Weston stating no objection to the proposed remediation plan, On March 1,1993, Weston submitted a letter to Region I indicating that site remediation was completed and survey results would be sent at a later date. The 2.4 cubic meters (85 cubic feet) of radioactive waste (concrete and soil) genemted dering the remediation was held in twelve,110-liter (30 gallon) drums and was subsequently transpor1ed to the licensed low-level waste site at Barnwell, South Carolina for disposal.
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Instnnnents Used in Survey i
Two composite soil samples wen: taken to evaluate contamination in soil. Samples were counted and analyzed using a PGT intrinsic gennanium dctector and a Nuclear Data gamma spectrometry system at the Region I analytical laboratory.
Exposure rate measurements were perfonned using a Ludlum Model 19 Micro R meter.
4.
Criteria Current NRC criteria for residual radioactivity in soil released for unrestricted use are given in the NRC's " Action Plan to Ensure Timely Cleanup of Site Decommissioning Management Plan Sites" (57 FR 13389-92) and in Attachment 3 to " Order
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Establishing Criteria and Schedule for Decommissioning the Bloomsburg Site" (issued to Safety Light Corporation, et.al, Docket Nos. 030-05980 and 030-05982, 57 FR 6136-4). This attachment provides release limits for unrestricted use of 15 pCi/g for cesium-137 and 8 pCi/g for cobalt-60. A limit is not given for cesium-134', however, since the primary exposure pathway for cesium-134 in soil is external radiation, a ratio of the specific gamma ray constants for cesium-134 and cesium-137 was used to derive a release limit for cesium-134 of 6 pCi/g.
Current NRC criteria for external gamma radiation exposure rates released for unrestricted use are given in " Radiation Levels for Release of Reactor Facility to Unrestricted Access" attached to the letter to Stanford University from James R. Miller, Chief, Standardization and Special Projects Branch, Division of Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, April 23, 1982, Docket No. 50-141 which was approved for use in the i
above referenced " Action Plan". This document states that facilities should not be released for unrestricted use unless the exposure rate is 5 microroentgens per hour t
(pR/hr) above background or less at one meter.
5.
Inspector Observation and Residual Materials The inspector observed that the contractor had removed the waste storage shed, the concrete pad beneath the storage shed and a volume of contaminated soil. Material contaminated with radioactive material was packaged in twelve 110-liter (30 gallon) drums. These drums were observed in a fenced area at the facility during the inspection on March 10, 1993. U.S. Ecology picked up these dnims on March 25, 1993 for transport and eventual disposal at the Barnwell, South Carolina low-level radioactive waste site. The removal of these drums was confinned during a telephone conversation between Michael Madonia of Roy F. Weston and the inspector on April 23,1993. The disposal was also in the radiological decommissioning repon received on June 4,1993.
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Soil Samples i
Soil samples were taken at four locations at the fonner location of the shed and composited into two samples. A diagram showing the locations of these samples is included as Attachment A to this report. The results are included in Attachment B, Table 1. The samples did not contain concentrations of radioactive materials in excess of the NRC criteria for soil. Since more than one isotope is present, Attachment B, Table 2 lists the calculated value for the sum of the concentmtion of each radionuclide divided by its appropriate limit. As shown in this table, the sum for each sample does not exceed unity.
7.
Exposure Rate Measurements i
The background exposure rate near the site was measured by the inspector to be 5 pR/hr. The dnuns containing radioactive waste stored in the vicinity of the fonner shed increased the measured exposure rate in the remediated area. To determine the actual exposure rate in the area of the fonner shed due to residual materials in that area, the inspector measured the exposure rate on the side of the radioactive waste dntms directly opposite the former shed, but at the same distance from the dnims as the fonner shed. This measurement yielded an exposure rate of approximately 10 R/hr,5 R/hr above the measured background, due to the influence of the stored waste. The inspector then assumed that this measured exposure rate was approximately the same' as the exposure rate in the area of the fonner shed. The inspector performed a survey by holding a Micro R meter at one meter above the soil and observing the exposure rates while walking throughout the area of the removed waste shed. The highest exposure rate measured in the area of the fonner shed was 15 R/hr at one meter above the soil, which calculates to 5 R/hr above the exposure rate in the area. The inspector did not find any exposure rates above the NRC release level of 5 R/hr at one meter.
8.
Radiological Decommissioning Report Review of the mdiological decommissioning report revealed that removal of contaminated material was continued until exposure mtes were below 5 R/hr at one meter and soil concentrations were below 15 pCi/g for cesium-137,8 pCi/g for cobalt-60, and 6 pCi/g for cesium-134. One paved area outside of the building footprint was found to be contaminated and was removed However, the survey data for this paved area (including both the area under the removed asphalt and the areas where asphalt still exists) was not included in the repon. The inspector asked for this additional infonnation in a telephone conversation with Michael Madonia of Roy F.
Weston on June 24,1993. Ile agreed to provide the data.
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Exit IntervigE l
The msults of the initial survey were discussed with Anne White, at the conclusion of the inspection.
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ATTACHMENT A Diagram of Locations of Soil Samples Inspection Repon No. 99990001/93-005 3
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4 ATTACHMENT B Results of Soil Samples Inspection Report No. 99990001/93-005 Table I Location Cesium-137 Cesium-134 Cobalt-60 pCi/g pCi/g pCi/g 1.
Composite 2.7 0.13 0.14 of front-left corner and middle of removed shed 2.
Composite 1.6 0.065 0.19 of back-right corner and front-right corner of removed shed Appropriate limit 15.0 6.0 8.0 1
l Table 2 Concentration of Cesium-137 Cesium-134 Cobalt-60 Sum of j
each nuclide concentration divided by its of each nuclide appropriate limit divided by limit Sampie 1
- 0. I 8 0.022 0.018 0.22 l
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Sample 2 0.I1 0.011 0.024 0.15 h
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