IR 07100123/2012015
| ML20153D179 | |
| Person / Time | |
|---|---|
| Site: | 04000341, 07100123 |
| Issue date: | 04/28/1988 |
| From: | Kinneman J, Taylor M, Elizabeth Ullrich NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20153D169 | List: |
| References | |
| 40-0341-87-02, 40-341-87-2, NUDOCS 8805090078 | |
| Download: ML20153D179 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
040-00341/87-002 ,, , Docket No.
040-00341 License No.
STC-133 Priority
Category E Licensee: GSA 18th and F Streets, N.W.
Washington, D.C.
20405 Facility Name: GSA/FRPS Curtis Bay Depot Inspection At: Curtis Bay, Maryland Inspection Conducted: November 23, 1987 and December 15, 1987 NRC Personnel: JMy[mN b h[/i[Ph ' Elifabet i U1~ rich, Health Phys'1cist ' / d 'te ~ % =e " Y W i riene M. Ta lor, Health Physicist '/ dafe Approved y.
_ _f 28/pf-A Kinnemah, Chief, d a'te ' u lear Materials Safety Section A Inspection Summary: Clodeout Safety Inspection on November 23 'nd December 15, ' a 1987 (Inspection Report No. 040-00341/87-002) Areas Inspected: Announced, closeout safety inspection limited to a survey of Building 731-F for residual contamination prior to release of the facility for unrestricted use.
Fifteen wipes were taken and assayed for removable alpha and gamma activity.
Four soil samples were taken and assayed for gamma activity.
Specified areas of the facility were surveyed to identify fixed radioactive - contamination.
Results: No violations were identified.
No detectable removable radioactive contamination was found.inside the facility.
No detectable activity was found in the soil samples.
No radiation levels exceeding the NRC guidelines for decontamination were found.
The licensee's survey report dated March, 1987 accurately reflects the condition of the portions of the facility surveyed.
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, = -- . , _. , f DETAILS 1.
Persons Contacted
- Kevin Reilly, Industrial Hygienist
. t Mel Lee, Assistant Chief, Quality Assurance Branch Bill Fritz, Acting Depot Manager
- Dewey Mullenax, Supervisor of Quality-Assurance
- present at exit interview 2.
Background The GSA/FRPS Curtis Bay Depot at Curtis Bay, Maryland is used for storage of a variety of material, including thorium nitrate and monazite sand which contains naturally occurring uranium and thorium.
The storage buildings measure 220. feet by 50 feet each.
Thorium nitrate is stacked in drums in Buildings 911-B, 912-B, and 913-8. Building 731-F is currently empty but was used in the past to store thorium nitrate-contaminated material and equipment used during the re packaging of deteriorating thorium nitrate drums. The positions of these buildings can be seen in Attachment A.
The re packaging project in Building 731-F was completed in August,1985.
Decontamination of Building 731-F by the licensee was completed in January, 1987 and the licensee's closeout survey was completed in March. The licensee has requested the release of the Building 731-F for unrestricted use.
On November 23, 1987 and December 15, 1987, a confirmatory survey of Building 731-F was performed by the NRC inspectors. The inspectors observed that the building was empty and that some areas of surface concrete had been removed during decontamination efforts.
3.
Instrumentation Used In Survey . ~ t Radiation level measurements were made with a Ludlum Model 12 Count Rate Meter and gas-flow proportional floor monitor (Serial Number 011847) which was sensitive to alpha radiation.
This instrumentation has a background count rate of 40 counts per minute (cpm), an efficiency of 16%, and a 600 square centimeter surface area.
A Ludlum Model 19 Micro-R-meter (Serial Number 019636), which was last calibrated on September 27, 1987, was used to measure the gamma dose rate in the building. Wipes were analyzed for alpha activity on a Tennelec Model LB 5100 gas flow propor-tional counter in the NRC Regional Office Laboratory. This instrumentation had a minimum detectable activity of 25 disintegrations per minute (dpm).
Soil samples and wipes were analyzed in the NRC Regional Office Laboratory for gamma activity using a detector and a multichannel analyzer.
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Radiation Survey Results Radiation levels in' Building 731-F varied from 40-65 micro R per hour around the outside of the building and were measured using the Ludlum 19 micro R meter.
These levels were created by the thorium nitrate stored in Buf1 dings 911-8, 912-8 and 913-B.
The areas surveyed using the gas-flow proportional floor monitor are shown on Attachment 8.
All radiation levels measured with the floor monitor were less than 500 dpm per 100 square centimeters, except one small area , of between 810 and 1020 dpn.
5.
Survey for Removable Contamination Fif teen wipes were taken from floor areas in Building 731-F in the locations marked on Attachment C.
The wipes were analyzed in the Region I Laboratory in King of Prussia, Pennsylvania. No removable contamination was detected.
. 6.
Transfer of Licensed Material Records of disposal of waste materials from the thorium-nitrate repackaging project and decontamination of Building 731-F were reviewed.
The records indicated that the licensed material was packaged by the contractor and shipped to Hanford as described in the licensee's closeout report.
' No violations were identified.
7.
Exit Interview The scope and results of the inspection were discussed at the conclusion of the inspection with the individual identified in Section 1.
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