ML19242C878
| ML19242C878 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 08/10/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Newacheck R AEROTEST OPERATIONS, INC. |
| References | |
| NUDOCS 7908140076 | |
| Download: ML19242C878 (1) | |
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August 10, 1979 0
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A' ro tes t Opara tions, Inc.
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5465 Fostoria Way San Ramon, California J4533 Attention R. L. Newacheck President Genti cr.1an :
Enclosed is IE dulletin No. 70-19 whico requires action by you tiith regard to your reactor facility (ics) with an 0;;;ra.iing license.
k Should you have questions regarding this Bulletin or the actions renuired j
of you, please contact this office.
Sincerely, Jti i
I R. II. Engelken Director g
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Enclosures:
1.
IE Culletin No. 79-19 i!
2.
List of Bulletins Issued j
in Last Six Months 1
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Accession No:
7908070515 SSINS No:
6320 UNITED STATES NUCLEAR REGULATORY C0"f1ISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 10, 1979 IE Bulletin No. 79-19 PACKAGING OF LOW-LEVEL RADI0 ACTIVE WASTE FOR TRANSPORT AND BURIAL Description of Circumstances:
Low-level radioactive waste is that waste which can be transferred and shipoed to one of three waste burial facilities which are located in and licensed by the Agreenent States of Nevada, South Carolina, and Washington.
On July 10 1979, the Governors of the three states notified NRC Chairnan Hendrie of the serious and repeated disregard for rules coverning the shipnents of low-level radioactive wastes to these burial facilities.
Examples of violations of Agreement State, DOT and NRC rules follow:
Inproperly packaged uraniun fines ianiting packaged liquid scintillation vials in combustible waste is believed to have caused a fire and destruction of a truck at the Beatty, Nevada burial facility on May 14, 1979.
On July 2,1979, three of twelve steel containers shipped to the Beatty burial facility were found to be leaking radioactive material.
The material was described on the bill of lading as being a solid inoraanic salt (evaporator concentrates solidified with urea formaldehyde) from a reactor facility.
The Governor of the State of Nevada ordered the drums to be shipped out of the state and the burial facility was temporarily closed.
On July 30, the first shipment into the reopened Beatty facility contained free liquid in " solid" material. The radioactive contents were sand filters
~ used at an insitu leaching process at a uranium mill.
Forty-three shipments with sixty-three deficiencies were observad during the package inspection program between April 10 and July 5,1979, by the Agreement State of South Carolina, at the Barnwell, S.C. burial facility. The shipments were fron reactor, nedical, industrial and military facilities.
On June 28, 1979, the Federal Highway Administration issued a Notice of Violation to a reactor facility proposing a $10,000 fine for truck contamina-tion resulting f rcn improper closures on SS-gallon drums of LSA material and for improper loading of the drums on the vehicle.
These are a few examples of shipnents of radioactive raterial to burial facilities which did not fully reet NRC, 00T and Agreement State requirements which were developed to protect the health and rafety of the public. The Governors of the three States with licensed burial facilities have indicated that if the situation is not rectified, they may have to initiate actions which would deny use of the three burial sites by violators.
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IE Bulletin No. 79-19 August 10, 1979 Page 2 of 3 Sources of Information:
The DOT regulatory requirements can be found in 49 CFR Parts 170-179.
The NRC regulatory recuirenents can be found in 10 CFR Parts 19 to 71. The NRC regu-latory requirements for Agreement State licensees in non-agreement s tes are in 10 CFR Part 150.
Copies of the regulations nay be purchased from the Superintendent of Documents, U. S. Government Printing Office, Washinoton, D.C. 20402.
Information about licensing requirenents for NRC packages can be obtained from the NRC Transportation Branch (301-427-4122).
Information about DDT packaging and transport requirenents can be obtained a calling the DDT Office of Hazardous Materials (202 a26-2311).
Actior To Be Taken By Licensees:
To assure the safe transfer, packaging, and transport of low-level radioactive wdste, each licensee is expected to:
1.
Maintain a current set of DOT and NRC regulations concerning the transfer, packaging and transport of low-level radioactive waste naterial.
2.
Maintain a current set of requirerents (license) placed on the uaste burial firm by the Agreenent State of Nevada, South Carolina, or Washington before packaging low-level radioactive waste naterial for transfer and shipment to the Agreenent State licensee.
If a waste collection contractor is used, obtain the appropriate requirements from the contractor.
3.
Designate, in writing, people in your organization v.ho are responsible for the safe transfer, packaging and transport of low-level radioactive naterial.
4.
Provide managenent-approved, detailed instructions 'nd operating procedures ta all personnel involved in the transfer, packaging and transport of low-level radioactive naterial.
Special attention should be given to controls on the chemical and physical form of the low-level radioactive material and on the containment integrity of the packaging.
5.
Provide trainina and periodic retraining in the DOT and NRC regulatory requirements, the waste burial license requirements, and in your instruc-tions and operating proceduies for all personnel involved in the transfer, packaging and transport of radioactive material.
Maintain a record of training dates, attendees, and subject naterial for future inspections by NRC personnel.
6.
Provide trainina and periodic retraining to those employees who operate the processes which generate waste to assure that the volune of low-level radioactive waste is minimized and that such waste is processed into acceptable chenical and physical form for transfer and shipnent to a low-level radioactive waste burial facility.
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IE Bulletin No. 79-19 At gust 10, 1979 Page 3 of 3 7.
Establish and implement a management-controlled audit function of all transfer, packagino and transport activities to provide assurance that personnel, instructions and procedures, and process and transport equip-ment are functioning to ensure safety and compliance with regulatory requirements.
8.
Perform, within 60 days of the date of this bulletin, a nanagement-controlled audit of your activities associated with the transfer, packaging and trans-port of low-level radioactive waste. Maintain a record of all audits for future inspections by NRC or DOT inspectors.
(Note: If you have an estab-lished audit function and have performed such an audit of all activities in Itens 1-6 within the past six months, this audit requirement is satisfied.)
9.
Report, in writine within 45 days, your plan of action and schedule with regard to the above items.
In addition, provide responses to the three questions below.
Reports should be submitted to the Director of the appropriate NRC Regienal Office and a copy should be forwarded to the NRC Office of Inspection and Enforcenent, Division of Fuel Facility and Materials Safety Inspection, Washington, D.C.
20555.
Provide answers for 1978 and for the first six nonths of 1979 to the following questions:
1.
How many low-level radioactive waste shipments did you make? What was the volume of low-level radioactive waste shipped?
(Power reactor licensees who report this information in accordance with Technical Specifications do not need to respond to this question.)
2.
What was the quantity (curies) of low-leval radioactive waste shipped? What were the major isotopes in the low-level radioactive waste?
(Power reactor licensees who report this information in accordance with Technical Specifications do not need to respond to this question.)
3.
Did you generate liquid low-level radioactive waste?
If the answer is 'yes,' what process was used to solidify the liquid waste?
Licensees who do not generate low-level radioactive waste should so indicate in their responses and do not need to take other actions specified in the above items.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance snecifically for identified qeneric problens.
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IE Bulletin No. 79-19 Enclosure August 10, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-18 Audibility Problems 8/7/79 All Power Reactor Encountered on Evaluation facilities with an of Personnel From High OL Noise Areas 79-17 Pipe Cracks in Stagnant 7/26/79 All PWR's with Borated Water Systems at operating licens'.
PWR Plants 79-16 Vital Area Access Controls 7/26/79 All Holders of and applicants for Power Reactor Operating Licenses who anticipate loading fuel prior to 1981 79-15 Deep Draft Pump 7/11/79 All Power Reactor Deficiencies Licensees with a CP and/or OL 79-14 Seismic Analyses for 6/2/79 All Power Reactor As-Built Safety-Related facilities with an Piping System OL or a CP 79-13 Cracking In Feedwater 6/25/79 All PWRs with an Systen Piping OL for action. All B'ARs with a CP for info rma tion.
79-02 Pipe Support Base Plate 6/21/79 All Power Reactor (Rev. 1)
Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or a CP 79-12 Short Period Scrans at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Davice in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Systens 79-10 Requalification Training 5/11/79 All Power Reactor Progran Statistics Facilities with an OL
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IE Bulletin No. 79-19 Enclosure August 10, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systens OL or CP 79-C3 Even s Relevant to EW3 4/14/79 All SWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Analysis 4/14/79 All Power React.or of Safety-Related Piping Facilities with an OL or CP 79-05C&OSC Muclear Incident at Three 7/26/79 To all PWR Power Mile Island - Supplerent Reactor Facilities with an OL 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and Systen Mis-ing Designed Pressurized alignnents Identified Water Power Reactor During the Three Mile Facilities with an Island Incident Operating License 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and Systen Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilities alignmcats Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident Q> ' b
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IE Bulletin No. 79-19 Enclosure August 10, 1979 Page 3 of 3 LISTING OF IE BULLETIN 5 ISSUED IN LAST SIX MONTliS Bulletin Subject Date Issued Issued To No.79-05B Nuclear Incident at 5/21/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP 79-04 Incorrect Meights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 79-03 Longitudinal Uelds Defects 3/12/79 A1. Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstewn Welding and Engineering Co.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class IE Equipnent Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves)
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