IR 015000019/1997004
| ML20199A810 | |
| Person / Time | |
|---|---|
| Site: | 15000019, 015000019 |
| Issue date: | 01/20/1998 |
| From: | Raymond Gibson, Johansen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20199A798 | List: |
| References | |
| 15000019-97-04, 15000019-97-4, NUDOCS 9801280092 | |
| Download: ML20199A810 (7) | |
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i U.S. NUCLEAR REGULATORY COMMISSION ;
REGION I ,
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Docket No.: 150 0001 '
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- License No.: MD 31025 01
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Report No.: 97 004 Licensee: Neutron Products, incorporated Facility: Adelphi Laboratory Center, Building 504
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Location: 2800 Powder Mill Road, Adelphi, Maryland i Date: November 20 and 21,1997
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Inspectors: (
Richard Gibson, Jr, bbN\ .
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Health Physicist #
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Approved by:
yey Johagen, t' g Chief Nuclear Materials ety Branch 3 J
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REGlON I
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9901290092 990120 PDR STPRO ESOMD PDR _
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EXECUTIVE SUMMARY ;
- Neutron Products, incorporated '
NRC Inspection Report 15000019/97 004 '
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A special, announced safety inspection was conducted on November 20 and 21,1997 at the Army Research Laboratory, Building 504, Adelphi Laboratory Center,2800 i Powder Mill Road, Adelphi, Maryland. The inspection was limited to observations by the inspector, interviews with personnel and selective examination of records related
) ; to activities within the NRC's jurisdiction. Surveys were performed to independently _
evaluate radiation levels during the removal of cobalt 60 source pencils from the pool ,
- irradiator located at building 504. Surveys were also performed on package and 6
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vehicle, and for the labeling of package and placarding of veh!cle prior to shipment of
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- the package by Neutron Products, Incorporated. The inspector's survey results agreed .
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with measurements made by the licensee. No violation was identified.
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BEPORT DETAILS 1. Background insoection Scope Neutron Products, Incorporated (NPI) is ar. Agreement State Licensee from the State of Maryland (License No. MD 31025 01) who was granted recognition for reciprocity (NRC Form 241) on November 17,1997 by the Nuclear Regulatory Commission, Region I to perform licensed activities at the Army Research Laboratory, Building 504, Adelphi Laboratory Center, Adelphi, Maryland, an NRC jurisdiction. The licensee was authorized to remove cobalt 00 source pencils from a pool irradiator at the Army Research Laboratory from November 20 to 25,199 I Observations and Findinas
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' On the days of the inspection, Thursday and Friday, November 20 and 21,1997, representatives from NPI were at building 504, Army Reseirch Laboratory, Adelphi, Maryland when the inspector arrived. The inspector met with the representatives from NPI to discuss the plan for cource removal. The licensee stated that the cask (WR 1) was a smaller version of their casks and that it would take them three phases over three days to remove the sources, removing a 1/3 of the sources at each phase. The licensee was informed that the inspector planned to observe the first two phase Building 504 pooi irradiator room was controlled by the Radiation Safety Officer (RSO) for the Army Research Laboratory (ARL) No licensed activities were conducted by the ARL during this inspection. The RSO for the Army Research Laboratory stated that the letter dated September 8,1997 to the NRC Ret,lon I, not!fied the NRC that licensed activities under NRC License No. 1917250-05 for the pool irradiator had permanently ceased, Conclusions The licensee discussed the plan for the removal of the cobalt 60 sources and the surveys to be conducted with the inspector. The inspector did not identify any violations in the licensee's plan to remove the cobalt 60 sources and perform surveys, ll. Facilhles and Equipment Insoection Scoce The inspector planned to observe the licensee remove the sources in accordance with Neutron Products, incorporated procedure " Loading of Radioactive Sources into Neutron WR 1 Shipping Package and Transfer to Transport Vehicle",
Procedure NR 2024, Revision /97 004 . -_ _ - _ _ _ _ . - _ - _ _ - - . _- _ - - - _ _
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While, the Army Research Laboratory (ARL)is authorized to use byproduct materials at building 504 for panotarnic irradiation operations under NRC License No.1917250 05, no irradiation operations were conducted at the f acihty at the time of this inspectio b. Qbservations and Findinos Access to the pool irradiator was controlled by the Army Research Laboratory RSO. No irradiation operations were conducted at the time of this inspection. The cobalt 60 sources (e.g. 40 pencils, containing a total activity of approximately 10,000 curies) were in storage at the bottom of the pool in a stainless steel basket. All alarm and interlock systems were still operational at the time of the it'spection. Above the pool in the overhead, was a heavy load crane that is used for loading and unloading items in and out of the poo Equipment used by the licensee to remove the cobalt 60 sources were a Neutron-WR 1 shipping cask nested in a steel overpack (OP 2, RQ Radioactive Material, Special Form N.O.S. UN 2974, USA DOT 20WC 6, Type B, with a volume of 96 cubic feet) and extended tongs. The overpack was removed from the t' aller of the truck and placed at the entry to building 504 by the truck driver. The cask was removed from the overpack by the licensee, place on a dolly and transported inside of the cell near the pool irradiator. With the use of the overhead crane, the licensee lif ted the cask, removed the top plug and the drain plug, and lowered the cask into the pool. With the extended tongs, the licensee removed 14 cobalt 60 sources totalling 3,646 curies (135 TBq) on Thursday. On Friday, the licensee removed 13 cobalt 60 sources of 3,370 curies (125 TBq) from the pool, c. Conclusions Based on observation of facilities and equipment, no violations or safety significant items were identifie Ill. Surveys During Source Removal a. insoection Sqgpa The inspector evaluated the licensea radiation measurements and contamination surveys during the source remova: Yne licensee performed radiation measurements and contamination sveys of the truck and trailer, the overpack for the shipping cask and the NeutronMR 1 shipping cask prior to the removal of the
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sources on November 20 and 21,1997. Surveys were conducted to establish base line contamination levels prior to the placing of the cask at the bottom of the
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pool. Continuous radiation monitoring was performed by the licensee in the pool i irradiator cell, the console area of building 504 and at the 2 mr/hr boundaries on
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Thursday, November 20 and Friday, November 21,1997. The licensee's personnel each had a whole body film badge and wrist TLDs for both hand The !icensee posscsses a Ludlum Model 14C, Serial No. 53894, an Eberline Model l
E 600, Serial No. 00287 last calibrated on May 30,1997 and a Bicron Micro R-4- 15000019/97-004
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, meter, Serial No. B 354A last calibrated on November 11,1997. The following
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instrument was used by the inspector for radiation measurements during source i removel: a Ludlum Model 14C, NRC Serial No. 033508 with a calibration date of
.i 9/18/9 Observations and Findinas l I
The licensee rigged the WR 1 cask above the water level of the pool after loading l a 1/3 of the cobalt 60 sources. All unnecessary personnel were evacuated from the cell. The licensee wiped residual water from the outside of the cask, allowed the cask to draln and then installed the top and drain plugs.
I Radiation measurements were taken by the licensee on contact with the cask j containing the first 14 sources on Thursday, November 20,1997 (Phase 1). The i radiation levels indicated 1,200 millirem per hour (mr/hr) on contact with the cask j
and 15 to 17 mr/hr at approximately 8 feet away. Measurements by the inspector
- at approximately 12 feet from the cask indicated 4 mr/hr. The 14 cobalt 60 sources removed on Thursday, totalled 3,646 curies (135 TBq).
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On Friday, November 21,1997, the licensee performed radiation measurements l on contact with the cask containing 13 sources (Phase ll). The radiation levels '
indicated 1,200 millirem per hour on contact with the cask. The 13 cobalt 60
sources removed on Friday, totalled 3,370 curies (125 TBq).
During both sources removal, the cask readings on contact were 1,200 mr/hr.
, The licensee's procedure states that if the contact reading on the cask exceeds 500 mr/hr, to stop work and contact management for further instruction. The
- licensee contacted a Mr. Marv Turkanis, Vice President of Neutron Products, Inc.,
, who gave instructions that if the 2mr/hr boundaries are established and if it is safe i to move the source to the overpack, to continue with the source removal. Based
on the observation by the inspector of the source removal procedure and instructions by the licensee's management, no violations or safety significant
- items were Identifie The licensee covered the cask with a PVC bag and transported it to the exit from the building where the overpack was placed. The cask was rigged from the i
- building and placed in the overpack. Surface measurements on the outside of the overpack indicated approximately 300 mr/hr on contact and a transport index of 50 mr/hr at 1 meter on Thursday, November 20,1997 (Phase 1). Surface :
measurements on the outside of the overpack on Friday, November 21,1997 g (Phase ll), indicated approximately 250 mr/hr on contact and a transport index of 35 mr/hr at 1 mete The licensee bolted the cover on the overpack and the truck driver rigged the overpack containing the WR 1 cask on the back of the trailer. The trailer was made of wooden siding and a tarp for covering the top rst the trailer. The truck 4 driver tied the tarp to the sides of the traile .
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Radiation measurements were taken by the licensee and the inspector on the outside of the trailer. The radiation levels indicated approximately 70 to 80 mr/hr on contact with the outside of the trailer,0.3 mr/hr in the cab of the truck and approximately 6 to 8 mr/hr at 2 meters from the vehicle on both Thursday and Friday shipment The licensee transported the package for both shipments as an exclusive use closed vehicle with a Yellow Illlabe c. Conclusiong Based on observation of the radiation surveys, packaging of the shipping cask and the transport of the package, no violatiorts or safety significant items were identified. On November 24,1997, thu licensee made the final 1/3 shipment of the cobalt 60 sources. There were no safety inspection coverage by the NR /97 004
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l PARTIAL LIST OF PERSONS CONTACTED -
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Licensee
- Dale L. Repp, Representative Supervisor, Neutron Products, incorporated ,
Michael Repp, Assistant Radiation Sciety Officer, Neutron Products, Incorporated l j Richard Demony, Representative Technician, Neutron Products, incorporated ;
j Edward Koontz, Truck Driver, Neutron Products, Incorporated j
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Michael Borisky, Radiation Safety Officer, Army Research Laboratory l David Conrad, Facility Operator, Army Research Laboratory i
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