ML19242C884
| ML19242C884 | |
| Person / Time | |
|---|---|
| Site: | 05000375 |
| Issue date: | 08/10/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Remley M ROCKWELL INTERNATIONAL CORP. |
| References | |
| NUDOCS 7908140083 | |
| Download: ML19242C884 (1) | |
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UNITED STATES
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'1 WAL Ntj T CR f E K. CAlt F ()flNI A 9 0 M August 10, 1979 Docket No. 50-J75 Energy Systems Group Rockwell International Corporation P. O. Box 309 Canoga Park, California 91304 Attention:
Dr. fl. E. Remley, '<anager Health Services and Radiation Safety Gentlemen:
Enclosed is IE Bulletin :;o. 79-19 which requires action by you with regard to your reactor facility (ies) tiith an operating license.
Should you have questions regarding this Bulletin cr the actions required of you, please contact tnis office.
Sincerely, j..,I < u,..
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R. H. E69elken Director
Enclosures:
1.
IE Bulletin ib. 79-19 2.
List of Bullet. ins Issued in Last Six I4cnths 790814 cogs g,
Accession No:
7f38070515 SSIUS No:
6820 UNITED STATES NUCLEAR REGULATORY COV. MISSION OFFICE OF INSPECTION AND ENFORCE!1ENT UASHINGTON, D.C.
20555 August 10, 1979 IE Bulletin No. 79-19 PACKAGING OF LOW-LEVEL RADI0 ACTIVE WASTE FOR TRANSPORT AND CURIAL Description of Circunstances:
Low-level radioactive waste is that waste which can be transferred and shipped 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 Chairman Hendrie of the serious and repeated disregard for rules covernino the shipments of low-level radioactive wastes to these burial facilities.
Examples of violations of Agreement State, DOT and NRC rules follow:
Inproperly packaged uraniun fines igniting 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 fiay 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 beinq a solid inoraanic salt (evaoorator 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 tenporarily closed.
On July 30, the first shipment into the reopened Beatty facility contained free liquid in " solid" naterial. The radioactive contents were sand filters used at an insitu leachinq process at a uranium nill.
Forty-three shipments with sixty-three deficiencies were observed during the package inspection prcgram between April 10 and July 5, 1979, by the Agreement State of South Carolina, at the Darnwell, S.C. burial facility. The shipments were from reactor, nedical, industrial and military facilities.
On June 28, 1979, the Federal Hiahway Administration issued a Motice of Violation to a reactor facility proposing a $10,000 fine for truck contamina-tion resulting frem improper closures on 55-qalion drums of LSA naterial and for improper loading of the druns on the vehicle.
These are a few examples of shipments of radioactive material to burial facilities which did not fully meet NRC, DOT and Agreement State requirements which vere developed to protect the health and safety of the public.
The Governors of the three States with licensed burial facilities have indicated that if the situation is not rectified, they nay 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 requirenents can be found in 10 CFR Parts 19 to 71.
The NRC requ-latory requirements for Agreement State licensees in non-agreenent states are in 10 CFR Part 150.
Copies of the regulations may be purchased from the Superintendent of Docurents, U. S. Government Printinq Office, Washington, D.C. 20402.
Information about licensing requirements for NRC packages can be obtained from the NRC Transnortation Cranch (301-427-4122).
Information about DOT packaging and transporc regt.irenents can be obtained by calling the CGT Of fice of Nazardcus Materials (202-426-2311).
Action To Be Taken Py Licensees:
To assure the safe transfer, packaging, and transport of low-level radioactive waste, each licensee is expected to:
1.
Maintain a current set of DOT and NRC regulations concerninq the transfer, packaqing and transport of low-level radioactive waste naterial.
2.
Maintain a current set of requirements (license) placed on the waste burial firn by the Agreenent State of Nevada, South Carolina, or Washinqton before pacFaging low-level radioactive waste natcrial for transfee and shipnent to the Agreement State licensee.
If a waste collection contractor is used, obtain the appropriate requirements from the contractor.
3.
Designate, in writina, people in your organization who are resporcible for the safe transfer, packaging and transport of low-level radioactive material.
4.
Provide managenent-approved, detailed instructions and operatinq procedures to all personnel involved in the transfer, packaqinq and transport of low-level radioactive naterial.
Special attention should be given to controls on the chenical and physical form of the low-level radioactive material and on the containment integrity of the packaging.
5.
Provide training and periodic retraining in the DOT and NRC regulatory requirements, the waste burial license requirements, and in your instruc-tions and operating procedures for all personnel involved in the transfer, packaging and transport of radioactive material. t'.aintain a record of training dates, attendees, and subject naterial for future inspections by NRC personnel.
6.
Provide training and periodic retraininq to those employees who operate the processes which generate waste to assure thet the volume of low-level radioactive waste is minimized and that such waste is processed into acceptable chenical and physical form for transfer and shipment to a low-level radioactive waste burial facility.
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IE Eulletin No. 79-19 Auaust 10, 1979 Page 3 of 3 7.
Estabiish and irolenent a management-controlled audit function of all transfer, packaqino and transport activities to provide assurance that personnel, instructions and procecures, and process and transport equip-cent are functioning to ensure safety and compliance with regulatory requirenents.
8.
Perform, within 60 days of the date of this bulletin, a nanaqerent-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 DDT insoectors.
(Note: If you have an estab-li "ad aLait function and haia performed such an audit of all activities in Items 1-f within the past six rconths, this audit requirement is satisfied.)
9.
Report, in writing within 45 days, your plan of action and schedule with regard to the above items.
In addition, provide responses to the three questions below.
Rer; orts should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the 4RC Office of Inspection and Enforcenent, Division of Fuel Facility and "aterials Safety Inspection, Washincton, D.C.
20555 Provide answers for 1978 and for the first six months of 1979 to the following questions:
1.
How nany low-level radioactive waste shipments did you make? What was the volume of low-level cadioactive waste shipped?
(Power reactor licensee; who repcrt this information in accordance with Technical Specifications do not need to respond to this question.)
2.
What was the quantity (curies) cf low-level 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 dr no _ qenerate 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 (R0372); clearance expires 7-31-80.
Approval was given under a blanket clearance snecifically for identified qeneric problens.
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Enclosure IE Bulletin No. 79-19 August 10, 1979 Pcge 1 of 3 LISTI!!G OF IE CULLETINS ISSUED IN LAST SIX l'.ONTHS Bulletin Subject Date Issued Issued To l'o.
79-18 Audibility Problems 8/7/79 All Power Reactor Encountered on Evaluation facilities with an of Personnel From Hich OL Noise Areas 79-17 Pipe Cracks in Stagnan:
7/E5/79 All PWR's with Borated Water Systems at operating license 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 1991 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 Systen OL or a CP 79-13 Cracking In Feedwater 6/25/79 All PWRs with an Syster Pipinq OL for action. All B'.'Rs with a CP for i nformation.
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 Device in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Systens 79-10 Requalification Traininq 5/11/79 All Power Reactor Program Statistics Facilities with an OL Pb'
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IE Bulletin flo. 79-19 August 10, 1979 Enclosure Page 2 of 3 LISTII;G OF IE BULLETII;S ISSUED It! LAST SIX fiONTHS Bulletin Subject tio.
Date Issued Issued To 79-09 Failures of GE Type AK-2 4/17/79 All Po'ler Reactor Circuit Breaker in Safety Facilities with an Related Systens OL or CP 79-0P Evert: Reim.3nt to F.: -
4/10/79 All BWR Power Reactor Reactors Identified During Three Mile Islend Incident Facilities with an OL 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Pelated Piping Facilities with an OL or CP 79-05C&OSC Tiuclear Incident at Three 7/26/79 To all PWR Power Mile Island - Supplerent Reactor Facilities with an OL 79-OSD Review of Cperational 4/14/79 All Conbustion Engineer-Errors and System Mis-aligrnents Identified ing Designed Pressurized During the Three itile Water Power Reactor Island Incident Facilities with an Operating License 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and Systen Mis-alignments Identified Power Reactor Facilities During the Three Mile of Westinghouse Design Island Incident with an OL 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and Systen Mis-alignments Identified Power Reactor Facilities During the Three fiile of Westinghouse Design Isiand Incident with an OL 79-05 Review cf Operational 4/11/79 All Pressurized Water Errors and System Mis-alignments Identified Power Reactors with an During the Three ' tile OL except RFN facilities Island Incident
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IE Dulletin No. 79-19 Enclosure August 10, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date sued 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 A/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 fluclear Incident at 4/2/79 All Pcvar Reactor Three Mile Islard Facilities with an OL and CP 79-04 Incerrect Weights 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 Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools CL or CP flanufactured by Youngstorin Welding and Engineering Co.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves)
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