ML20129G157

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NRC-Agreement State Working Group to Evaluate Control & Accountability of Licensed Devices
ML20129G157
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Issue date: 07/02/1996
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NRC - RADIOACTIVE DEVICE REVIEW GROUP
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NUDOCS 9610300024
Download: ML20129G157 (96)


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l NRC-Agreement State Working Group to Evaluate Control and Accountability of Licensed Devices i

July 2,1996 l

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<. 1 NRC-Agreement State Working Group to Evaluate Control and Accountability of Licensed Devices CONTENTS 1.0 EXECUTIVE

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l 2.0 THE PROBLEM PRESENTED TO THE WORKING GROUP .............. 2 I

l 3.0 APPROACH AND EVALUATION PROCESS FOLLOWED BY THE WORKING GROUP . . . . . 5 l

3.1 Charter . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.2 Working Group Meetings 6

..................... 6 3.2.1 October 24-25, 1995, First Meeting ........... 7 3.2.2 December 19-21, 1995, Second Meeting .......... 7 3.2.3 January 18-19, 1996, Public Workshop .......... 8 3.2.4 March 5-6, 1996, NRC/AS Technical Workshop ....... 9 3.2.5 March 7, 1996, Third Meeting .............10 3.2.6 April 16-17, 1996, Fourth Meeting . . . . . . . . . . . 10 3.2 7 Ma, 6-8, 1996, CRCPD Annual Meeting . . . . . . . . . . 10 3.2.3 May 9-10, 1996, Fifth Meeting . . . . . . . . . . . . . 11 3.3 Identification of Stakeholders ................11 3.4 Importance of the General Licensing Program . . . . . . . . . . 12 3.5 Evaluation of Stakeholders' Recommendations for Improvements . 13 4.0 WORKING GROUP RECOMMENDATIONS . . . . . . . . . . . . . . . . . . . . 15 4.1 Increased Regulatory Oversight ................16 4.2 Penalties for Lost Devices ..................20 1 4.3 Disposition of Orphaned Devices. ...............20 4.4 Recommendations for State Regulatory Programs . . . . . . . . . 22 4.5 Recommendations for Non-Licensed Stakeholders . . . . . . . . . 22 5.0 ISSUES AND CONCERNS . . . . . . . .................23 5.1 NRC and AS Compatibility .. . . . . . . . . . . . . . . . . 23 5.2 Cost and Fee Considerations . . . . . . . . . . . . . . . . . . 24 5.3 Radiation Exposure Savings ..................25

5. 4 Devi ce Design . . . . . . . . . . . . . . . . . . . . . . . . . 26 5.5 Changes That Affect All Devices Versus Only Newly Acquired Devices i

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 i 5.6 Device Di spos al . . . . . . . . . . . . . . . . . . . . . . . . 28 5.7 Device Identification . . . . . . . . . . . . . . . . . . . . . 29 C.8 Devices Requiring Increased Oversight . . . . . . . . . . . . . 30 5.9 beneral-Licensed versus Specific-Licensed Devices . . . . . . . 31 5.10 Identification of Current Users and Devices .........32 5.11 Imposing Restrictions on Portable Devices and Storage of Devices

..............................32 Appendix A: PROTECTION OF PROPERTY ...................34 Appendix B: WORKING GROUP CHARTER . . . . . . . . . . . . . . . . . . . . 37 Appendix C: JOHN DUKES' JANUARY 20, 1996, PROPOSAL . . . . . . . . . . . 40 i

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. . j Appendix D: TABLE OF IS0 TOPES TYPICALLY USED IN DEVICES . . . . . . . . . 44  !

Appendix E: CRCPD SURVEY '

........................45 Appendix F: OVERSIGHT PROGRAM COSTS AND EXPECTED BENEFITS . . . . . . . 51 Appendix G: ESTIMATED COSTS OF DISPOSAL OF A SOURCE . . . . . . . . . . . 56 i e

Appendix H: TEXAS RADIOGRAPHY INCIDENT

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l 1.0 EXECUTIVE

SUMMARY

The U.S. Nuclear Regulatory Commission staff acknowledged that licensees are having problems maintaining control over and accountability for devices t

contarning radioactive material. In June 1995, the Commission approved the staff's suggestion to form a joint NRC-Agreement State Working Group (WG) to evaluate the problem and propose solutions. The staff indicated that the formation of the WG was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State (AS) input, and to reflect their experience. AS participation in the process is essential since some AS already have implemented effective programs for oversight of device

! users.

l To obtain information that would allow the WG to address the problem adequately, the WG held public meetings, workshops, and made formal and informal presentations to professional and public groups. Participants in the meetings and workshops included AS, vendors, specific- and general-licensed device users, metal manufacturers and recyclers, insurance companies, the U.S.

Department of Energy (DOE), the U.S. Envire,nental Protection Agency (EPA),

waste compact representatives, and members of the public.

The WG determined that the problem it was addressing has four parts:

1) inadequate regulatory oversight; 2) inadequate control over and '

accountability for devices by users; 3) improper disposal of devices; and 4) 1 problems associated with " orphaned devices." Orphaned devices are those  !

devices that make it into the public domain and are discovered by someone i i other than the rightful owner, usually a non-licensee.

i The WG proposes five recommendations to increase regulatory oversight,  ;

increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the WG recommends that: 1)

NRC and AS increase regulatory oversight for users of certain devices; 2) NRC and AS impose penalties on persons losing devices; 3) NRC and AS ensure proper disposal of orphaned devices; 4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator-Produced Material (NARM); and, 5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification.

The WG evaluated the costs of its recommendations against both the costs of radiation exposures, based on $2,000 per person-rem,3 and property damage?

associated with the loss of control over and accountability for devices. The WG determined that the costs to implement its recommendations does not exceed the expected benefits. 4 l

2 Based on Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission, NUREG/BR-0058, Revision 2.

2 Appendix A includes the WG's justification for including protection of property.

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l 2.0 THE PROBLEM PRESENTED TO THE WORKING GROUP The WG examined the information provided by NRC and determined that the problem facing the WG was a lack of licensee oversight by the regulators.

ReguTators have not had an active role in ensuring that licensees maintain control over and accountability for devices, and in ensuring that licensees possess, use, and transfer devices in accordance with the regulations. The WG

determined that the problem needed to be separated into four parts
1. Inadequate Regulatory Oversight -- Regulators do not routinely inspect t

or have contact with general licensees and users of certain specific-licensed devices.

2. Inadequate Control Over and Accountability For Devices by Users -- Both general and specific licensees have demonstrated loss of control over and accountability for devices. The WG believes that there are losses of devices that are not reported.
3. Improper Disposal of Devices -- Even licensees who maintain control over and accountability for devices may not be aware of the requirements for proper disposal or may have only limited options for disposal. In addition, the high cost of disposal may discourage licensees from acting responsibly.
4. Orphaned Devices -- Orphaned devices will continue to present problems.

No program for ensuring proper control over and accountability for devices would be 100 percent effective. The WG believes that some devices already are lost and will become orphaned.

In its May 31, 1995, memorandum, the NRC staff indicated that the following seven issues should be addressed by the WG:

1. NRC and AS Compatibility -- NRC and AS regulations need to be compatible since approximately two-thirds of the devices are used by AS licensees.
2. Cost and Fee Considerations -- There are various options for licensing devices that would provide better control and accountability. The cost of implementation to NRC and AS and the appropriate cost recovery method need to be considered.
3. Radiation Exposure Savings -- The savings in radiation exposures resulting from better control over and accountability for devices need to be considered in the selection of the method for liceasing of devices.
4. Device Design -- Currently, the design requirements for general-licensed l

devices are more stringent than those for specific-licensed devices.

The safety impact of using a different licensing method, which may rely

! on administrative controls rather than the design of the devices, must be evaluated.

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5. Changes That Affect All Devices Versus Only Newly Acquired Devices --

Since there are currently about 1.5 million general-licensed devices in

! NRC and AS, changes in the licensing of devices need to address both new 1

requirements for devices currently possessed by licensees and newly acquired devices.

6. Device Disposal -- Options for the disposal of devices need to be delineated. Many current general licensees may wish to dispose of the devices rather than be subjected to increased regulation.
7. Device Identification -- Added requirements to ensure that device labels l could better withstand harsh, unexpe:ted environments may enhance the ability to identify devices that are disposed of or improperly transferred.

The WG agreed with the NRC staff that these seven issues were important. The  !

WG identified four additional issues.

1. Devices Requiring Increased Oversight -- Many of the devices currently '

in use present a low risk even if improperly disposed of and handled by l members of the public. Therefore, only a portion of devices were of -

concern to the WG. i

2. General-Licensed versus Specific-Licensed Devices -- Restricting all devices to possession and use under a specific license does not )

j necessarily resolve the problem. <

3. Identification of Current Users and. Devices -- Since regulators do not have a complete listing of all users and devices, it is important to address how to identify all current users and devices. i
4. Imposing Restrictions on Portable Devices and Storage of Devices --

Portable devices frequently are handled and moved and are very susceptible to loss of control and accountability. Devices in long-term storage frequently are subject to loss of control and accountability.

The WG also discussed regulating sources rather than devices. In looking at current practices, the WG determined that persons licensed to handle sources, separated from devices, are specific licensed and are inspected on at least a two year frequency. This type of licensee, that handles unshielded sources, performs frequent inventories and has a good record of control over and accountability for their sources. Additional oversight of these users does not appear necessary.

There are similar problems associated with loss of control over and accountability for NARM. Many of the radioactive sources found in the public domain are NARM. The WG did not examine regulations of these devices since j NRC does not have the authority to regulate NARM. Many stakeholders also '

indicated that there are problems associated with contaminated metals, i unauthorized import of devices, and contaminated baghouse dust as a result of 1 smelting a device. These present similar obstacles to the stakeholders, but 3

o 0 associated with these situations.the WG did not addr I

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3.0 APPROACH AND EVALUATION PROCESS FOLLOWED BY THE WORKING GROUP The formation of the WG was recommended by the NRC staff in response to the Staff Requirements Memorandum of October 18, 1994. The staff indicated that the f~ormation of the WG was necessary to address the concerns from a national perspective. The WG would allow for a broad level of AS input and reflect their experience. This was essential since some AS already have implemented effective programs for oversight of general and specific licensees using devices.

The WG was formed in July 1995 with the intent to have three members from NRC, three from AS, and one alternate from an AS. NRC worked with the Organization of Agreement States to have the following persons included as members of the WG:

Nuclear Regulatory Commission Agreement State Representatives' Representatives Joel Lubenau, Robert Free, 4 Office of Nuclear Material Safety and Texas Department of Health l Safeguards (NMSS)

Lloyd Bolling, Martha Dibblee, I Office of State Programs Oregon Department of Human Resources '

John Telford, J. Robin Haden, Office of Nuclear Regulatory Research North Carolina Department of Environment, Health and Natural Resources Rita Aldrich (alternate),

New York State Department of Labor Joel Lubenau and Robert Free acted as co-Chairs for the WG. In March, co-Chair Lubenau accepted a position with Commissioner Dicus' staff. He was replaced by John Lubinski, NMSS, who then served as co-Chair.

In addition to the members of the WG identified above, Mr. James Yusko, l Pennsylvania Department of Environmental Protection, and Mr. Donald Bunn, California Department of Health Services, served as liaisons for the Conference of Radiation Control Program Directors (CRCPD) E-23 Resource Recovery Radioactivity Committee. Also, Mr. James Richardson, Nuclear Safety Attach 6, U.S. Mission to the United Nations System Organizations, served as liaison for the International Atomic Energy Agency.

Some AS, including Oregon and Texas, have implemented programs for increased regulatory oversight of general- and specific-licensed device users. Oregon implemented rules requiring registration, including a registration fee, for each device. This provided the State with 1) discrete inventory statewide;

2) annual contact with licensees; and 3) increased licensee accountability.

Oregon's implementation costs were amortized over 10 years. Oregon expends 5

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i approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> annually to manage 1,000 selected licensees. Annual costs include mail and on-site inspections and collection of fees.

Texas already had established a program to improve control over certain general.-licensed devices. The program is intended to improve licensee control i i

over devices and enforcement for users that violate regulatory requirements. .

Those that are added to a specific license are still identified separately.  !

Users pay fees and submit self inspection reports for agency review. They  ;

currently are required to maintain transfer and receipt records and complete i an inventory worksheet annually. The program was evolving when the WG was formed. It is anticipated that the program will include devices covered by the WG recommendations. A great deal of time was spent in contacting general licensees and developing a database of vendors and users.

l The WG attempted to achieve consensus among all members to develop its recommendations and report. In cases where full agreement could not be l

reached, the WG relied on the consensus of the majority of its members.

! 3.1 Charter i

The first task of the WG was to develop a charter that detailed the mission of the WG. The charter was reviewed and approved by the WG at its first meeting.

i A copy of the charter is included in Appendix B. The charter clearly defines i the problem facing the WG and includes the seven issues and concerns l l identified by the NRC staff in its May 31, 1995, memorandum to the Commission.

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' Once the WG started to perform a detailed examination of the problem, it quickly determined that in addition to the seven issues and concerns identified in its charter, it also needed to address the 'four items listed l

below:

Devices Requiring Increased Oversight '

General-Licensed versus Specific-Licensed Devices Identification of Current Users and Devices Imposing Restrictions on Portable Devices and Storage of Devices I

In performing its analysis and evaluation, the WG concentrated on identifying effectiveness indicators for regulatory options, agreeing on goals, and obtaining input from interested parties, to develop regulatory options.

Consensus among WG members was seen as the most significant indicator when addressing specific issues.

3.2 Working Group Meetings To achieve its goals, the WG held public meetings, a public workshop, participated in an NRC and AS Technical Workshop, and presented for comment preliminary recommendations during the CRCPD annual meeting. A summary of each meeting is listed below. All meetings of the WG were open to the public and announced on the NRC Public Meeting Notice System. The meetings were desicned to encourage open communications between the WG and stakeholders and to allow for interested parties to express their opinions.

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3.2.1 October 24-25, 1995, First Meeting The WG held its initial public meeting October 24-25, 1995, at the Doubletree Hotel, Rockville, Maryland. The first part of the meeting focused on devel5 ping background information for the WG. The second portion of the meeting centered on further defining the problem (inadequate inventory control and improper disposal of licensed devices), regulatory options, agreeing on goals (minimize the negative indicators, maximize the positive indicators),

and how to develop regulatory options. Agenda planning for the next WG meeting and organization of the public workshop scheduled for January 1996 also was covered.

The WG heard introductory remarks from Carl Paperiello, Ph.D., Director, NMSS. l Dr. Paperiello challenged the group to determine how regulatory agencies could !

control the entry of radioactive devices into scrap streams while minimizing demands on government resources. Presentations from the Steel Manufacturers Association (SMA) described the steel industry's participation in the discovery of these devices in scrap streams and the costs in millions of l

dollars to a group that should be considered innocent bystanders.

An overview of the current experience with radioactive materials in recycled metals was provided by James Yusko. l The overall approach taken by the co-Chairs was to reach out to as many stakeholders as possible and to maximize the opportunity for exchange of views and concerns between the stakeholders (including the regulators). Ample i opportunity was provided in the conduct of the meeting and this was favorably  ;

commented upon, particularly by the vendor representatives. Vendor representatives offered to provide additional statistical information to ,

define the population of radioactive devices. The SMA submitted written l recommendations for regulatory action at the meeting. SMA representatives urged swift regulatory action by NRC to address the problem.

To assist the WG effort to identify other regulatory options for consideration, the attendees were invited and agreed to submit their l suggestions no later than December 1,1995. Other stakeholder groups were  !

identified and well represented at the public workshop.

l 3.2.2 December 19-21, 1995, Second Meeting l

The second public meeting was held on December 19-21, 1995, at the Doubletree l

, Hotel, Rockville, Maryland. Prior to this meeting, a questionnaire was i developed and mailed to AS to determine their views of the problem.

The first day's activities included finalizing the minutes of the first meeting. The WG then reviewed some recent events involving radioactive devices, and reviewed NRC's databases for licensing, inspection, enforcement, and events related to radioactive devices. Recent trends in NRC's budget also were discussed.

i The second day of the meeting covered the review of the regulatory exemption criteria and a risk assessment study. Oregon's recent experience in 7

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implementing an expanded regulatory oversight program for general licensees was discussed. The remainder of the meeting covered the planning of the public workshop scheduled for January 18-19, 1996. This discussion extended into the morning of December 21, 1995, and included review of "strawmen" submi-tt.ed by stakeholders and development of a conceptual outline for the workshop agenda.

As in the first meeting, the overall approach taken by the co-Chairs was to maximize opportunity for stakeholders to participate in the meeting.

3.2.3 January 18-19, 1996, Public Workshop The Public Workshop was held as scheduled at NRC Headquarters, Rockville, Maryland, with opening remarks by Chairman Shirley Jackson, NRC. There were 16 panelists and 35 others in attendance. There also were several State programs listening in on a bridge line. The panelists represented a variety of interests including State and Federal regulatory agencies, manufacturers and distributors of radioactive devices, steel manufacturers, and professionals from health physics and industrial hygiene, as well as a union representative.

There were a number of descriptions of the problems associated with radioactive devices reaching the public sector. Costs incurred by the steel manufacturing and metal scrap processing industries were discussed and suggestions for improving control of these devices were made.

The discussions centered primarily on identifying the problems. There appeared to be broad agreement that the problems with the loss of devices revolved around accountability and improper disposal. Additional concerns were expressed about orphaned devices encountered in the metal recycling process and how to fund their disposal. For certain devices constituting greater than Class C waste, DOE may be able to provide assistance. For other devices, no standard approach or formal assistance is available.

A proposal was presented by a panelist that addressed the problems. The proposal included six itums for consideration (see Appendix C). They were:

1. A'l licensees maintain current records of inventory (i.e., a continual inventory),
2. All licensees perform semi-annual inventories to verify the running inventory,
3. Regulatory agencies must identify the radioisotopes and quantities of concern for the problem under discussion,
4. All licensees report annually to their regulatory authority, those isotopes of concern. This would be signed by and name the radiologically responsible person in the organization and a back-up person, 8
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This and should be a Division-1 item of compatibility to achieve uniformity,

6. Regulators should maintain a database of the reported inventories.

' Regulatory agencies should enforce the rules. l This proposal was widely accepted by the panelists and the audience participants, as it appeared to contain elements for addressing and solving I the problems associated with loss of control and accountability. It became '

the focus of the discussion for the first day. It also became the center point for the WG in future meetings and discussions because of its wide acceptance at the public workshop.

The workshop was summarized at the end of the second day with the commitment of the WG to follow up on the proposal discussed at the meeting cad to address l several issues not fully discussed at the workshop such as labeling, possible technological solutions to melting sources, review detection capabilities for scrap and metal manufacturers, and continue to explore solutions for orphaned devices. The WG also asked that any additional public comments or proposed solutions be submitted to the WG by January 31, 1996.

l 3.2.4 March 5-6, 1996, NRC/AS Technical Workshop This meeting was set up to get technical input for the WG to consider. It was conducted as part of the Organization of Agreement States' meeting in Vancouver, WA. The meeting was a technical session and the WG 1ed a breakout i i

session for the first day, March 5, 1996. The second day, March 6, was a '

plenary session and Robert Free presented an overview of the breakout session and the WG's future plans.

Many of the participants in the first day session were AS personnel who had not attended the previous WG meetings. The WG technical session began with an overview of the WG's previous meetings and a description of the problem of accountability, improper disposal, and orphaned devices. A background paper previously prepared for the public workshop was provided to the participants.

Because of its wide acceptance, the proposed solutions presented at the public workshop were presented and discussed. A presentation of Oregon's general license registration program was presented and generated a lot of discussion because of cost and concerns about the implementation of such a program.

A discussion of the need to prioritize the devices into those that were of more concern for health, safety, and disposal considerations resulted in development of a table that has been used to develop the WG recondnendations for devices of concern (see Appendix D).

i The WG participants continued discussion of issues after the AS meeting ended and turned to issues of registration of devices, compatibility, and orphaned devices.

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3.2.5 March 7, 1996, Third Meeting The WG held its third meeting in Vancouver, WA, following the NRC/AS Technical Workshop. This would encourage persons attending the workshop also to attend the WG~ meeting. Holding the meeting in Vancouver facilitated the inclusion of l stakeholders located on the west coast.

Once the meeting was called to order, Joel labenau announced that he would be leaving the WG and that John Lubinski would succeed him as co-Chair. The meeting agenda included: ensuring all avenues for information gathering had been explored; ensuring that the WG was in a position to address all issues identified in the charter; reviewing information for possible WG recommendations; and, developing a workplan for finalizing the recommendations and writing a final report. ,

A waste compact representative, David Stewart-Smith, Northwest Compact, was invited to attend the WG meeting. Mr. Stewart-Smith discussed the options available for device disposal and indicated that the Northwest Compact might ,

be willing to provide assistance for emergency situations. The details, including the legal and financial ramifications, had to be clarified. No solutions were identified, but the WG was encouraged by the fact that a compact may be willing provide assistance.

To enhance communications among the WG, it was decided that the WG would participate in weekly conference calls. These calls were in addition to the '

public meetings.

3.2.6 April 16-17, 1996, Fourth Meeting The fourth WG meeting was held at the Doubletree Hotel, Rockville, Maryland.

The purpose of the meeting was to discuss the draft of the WG's recommendations and rationale for its evaluation of the issues and concerns.

The WG concentrated on the recommendations, including rationale and the compatibility issues associated with each recommendation. The WG had supported a Division-1 item of compatibility but, after two days of discussion, it appeared that the WG had changed direction on the issue and now believed that regulation of devices should be a Division-2 item of compatibility for AS. The WG concentrated on recommendations necessary to ensure adequate control and accountability of devices.

During the conference calls folliowing the meeting, the WG reached a consensus and concluded that its recommendations should be a Division-2 item of compatibility for AS. The WG reached consensus on most of the critical elements of its recommendationi and solidified its list of devices that it believed should be subject to hncreased oversight.

3.2.7 May 6-8, 1996, CRCPD Annual Meeting As a result of information gathered during the NRC/AS Technical Workshop, and the fact that the WG decided to recommend that AS implerdent the recommendations as a Division-2 item of compatibility, the WG decided to present its preliminary recommendations at the CRCPD Annual Meeting. The WG 10

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l co-Chairs presented the recommendations in the form of a poster session on 1 May 6-8, 1996. This allowed interested parties to converse one-on-one with l the co-Chairs. In addition to the poster session, the co-Chairs also held an impromptu meeting on May 7, 1996. During the meeting the co-Chairs briefly descr4 bed the activities and preliminary recommendations of the WG and provided time for an open discussion.

The WG co-Chairs also presented a survey to the CRCPD participants and its voting members. The co-Chairs asked that written responses be provided by May 31, 1996. The majority of the responses supported the WG's preliminary recommendations. A summary of the responses is included in Appendix E.

3.2.8 May 9-10, 1996, Fifth Meeting The fifth WG meeting was held at the Albuquerque Hilton and Fairfield Inn, Albuquerque, NM, following the CRCPD Annual Meeting. The WG believed this would encourage persons participating in the CRCPD Annual Meeting, including l - persons from both AS and non-AS radiation control programs, to attend the WG

meeting.

The purpose of the meeting was to finalize the details of the WG recommendations and discuss the structure of the final report. The WG agreed that the additional details could be finalized during the weekly conference calls.

3.3 Identification of Stakeholders Early in the project, the WG identified persons affected by the loss of

' control over and accountability for devices. The following persons were identified as stakeholders:

l AS - The AS are obvious stakeholders as evidenced by their inclusion on the

! WG. AS regulate both the distribution and use of devices containing byproduct material and regulate NARM. They will be affected by the WG recommendations since any regulatory changes implemented by NRC could ultimately be a matter of compatibility. Some AS have been active in implementing programs to i increased control over and accountability for devices. Their experience is reflected in the WG recommendations.

I Specific-Licensed Users - Specific-licensed users already are responsible for maintaining control and accountability of devices during possession and use.

l Any changes implemented by NRC and AS would require specific-licensed users to l

implement additional regulatory requirements.

l General-Licensed Users - General-licensed users also are responsible for i

maintaining control and accountability of devices during possession and use.

General licensees have fewer regulatory requirements than specific licensees.

Any WG recommendation to increase accountability requirements would have a significant impact on general licensees.

! Vendors - Vendors have a significant stake in the WG activities. If their customers, both general and specific licensees, are subject to increased 11

regulation, it would have a direct effect on their sales and servicing busines:;. Vendors also would be affected by recommended changes to device design and distribution procedures. Vendors also are affected by the uniformity of regulations since most vendors distribute devices across reguTatory jurisdictions. Non-uniform regulation of devices presents high administrative costs to vendors.

Metal Recyclers - The WG recommendations will have a large impact on recyclers. Metal recyclers are likely recipients of lost devices. They may unknowingly receive a device as part of a load of scrap metal. Once they take possession of the device, they may be subject to radiation exposures and costs of disposal. Metal recyclers will continue to be affected negatively by loss of control over and accountability for devices if regulatory changes are not implemented.

Metal Manufacturers - Metal manufacturers are using more recycled materials.

It is possible for manufacturers to receive unknowingly a device from a recycler. If the device is smelted by the manufacturer, the manufacturer will incur high costs associated with decontamination, disposal, facility down-time, and loss of business.

Insurance Companies - The WG invited insurance companies to meetings since some insurance companies may provide policies for persons who receive radioactive devices unkno~wingly. No representatives from the insurance industry attended the meetings.

DOE and EPA - Both DOE and EPA have responsibilities for devices found in the public domain. Decreasing the occurrences of loss of devices will have an affect on their responsibilities.

Waste Disposal Sites - Waste disposal sites may be able to provide assistance for disposal of orphaned devices. A representative from a waste compact attended a WG meeting.

General Public - All meetings were announced on the NRC Public Meeting Notice System to allow for public participation. Representatives from labor unions and professional societies attended the meetings.

International Organizations - Other countries experience similar problems with loss of control over and accountsbility for devices. The WG informed regulatory agencies in other countries and professional organizations that represent stakeholders of its activities.

3.4 Importance of the General Licensing Program Many persons commented, either during the WG meetings or at other times to WG members, that they believe the problem of control over and accountability for devices is most prevalent to general-licensed devices. To ensure control over and accountability for devices, they felt the general-licensing propiin sh' ould

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be abolished.

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I While it is true that some general licensees have lost control over and accountability for devices, abolishing the general-licensing program would not ensure total control and accountability (see Section 5.9). The WG believes it is imgortant to note the general-licensing program has provided, and continues l to provide, a benefit to both licensees and regulators. '

The general-licensing program saves resources for both licensees and regulators. Since the users are not required. to apply for a license, no effort is expended completing and filing a license application. A regulator does not have to expend resources to evaluate the application and issue a specific license. The general license allows the users to take possession and use the devices without having to wait for the licensing process to be completed. This saves the users of the devices from having costly down-time.

General licensees also save resources by not having to implement the requirements of 10 CFR Parts 19, 20, and 21. These requirements are not necessary based on the engineered safe design of the devices.

It is estimated that there are almost six times as many general licensees as specific licensees in the United States. Even though it is not appropriate to l estimate that NRC and AS resources would need to increase by six times their current amount to regulate general licensees as specific licensees, it would be a significant increase in resources.

The WG believes that simply abolishing the general-licensing program would cause significant increases to regulatory budgets and impose significant  !

costs, both direct and indirect, on licensees and would provide only a small '

benefit to public health and safety.

1 3.5 Evaluation of Stakeholders' Recommendations for Improvements '

l During its public meetings and workshop, the WG suggested that stakeholders l provide their proposed solutions. The WG received more than 20 responses that outlined several different proposals. One of the proposals, submitted by John i Dukes, ABB Industrial Systems, Inc., received relatively wide acceptance. Mr.  !

Dukes presented this proposal during the public workshop. The propcsal was formally submitted on January 20, 1996. A copy of Mr. Dukes' proposal is included in Appendix C.

Mr. Dukes' proposal identified the need for a national inventory of all devices, whether general- or specific-licensed. It required, in part, users of devices to perform semi-annual inventories and report their inventories

, annually, including transfers of products during the reporting period, to the

! regulators. For the proposal to be effective, Mr. Dukes indicated that regulation of the devices must be uniform (i.e., a Division-1 item of compatibility for AS) and the national inventory must be maintained as a centralized database. I Mr. Dukes' proposal also introduced the philosophy of " devices of regulatory concern." In talking through his proposal during the third WG meeting, Mr. Dukes indicated that NRC needed to identify which devices, based on the ,

i risk associated With the devices, are of regulat5Fy concern and er.sure, at a l minimum, that these devices are included in the national inventory program. j l

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He indicated that identification of such a category of devices would allow for the regulatory authorities to determine the level of effort needed to follow up on reports of loss or theft of the devices. Mr. Dukes indicated that the goal of the program should be to have all devices included in the program.

Many of the proposals submitted by stakeholders supported Mr. Dukes' proposal with only minor modifications. Most agreed that the program only would be effective if it were implemented as a Division-1 item of compatibility for AS.

The WG decided to use the proposal as its basis for providing recommendations-to the Commission.

A modification of Mr. Dukes' proposal that included certain recommendations discussed during the third WG meeting, was drafted for discussion during the fourth WG meeting. After lengthy discussion, the WG determined that it would be impractical to have the regulation of devices as a Division-1 item of compatibility for AS. The WG had to determine minimum aspects of the draft proposal that were necessary to ensure adequate control over and accountability for devices. Once this was established, it constitutes the criteria for a Division-2 item of compatibility. Many of the stakeholders disagreed with the WG and strongly believed implementation should be a Division-1 item of compatibility. Further discussion on the compatibility issue is included in Section 5.1.

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4.0 WORKING GROUP RECOMMENDATIONS

1 After conducting public meetings and workshops, and attending Organization of Agree _ ment States and CRCPD meetings, the WG considered all oral and written input provided and identified the problems and strawman solutions listed in Table 1.

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Table 1 - Overview of Problems and Solutions Problems Strawman Solutions Inadequate Regulatory -

Increase contact between users and l Oversight regulators (e.g., user provide annual l reports of inventories, regulators verify).

I Identify early warning signs (i.e., ,

I regulators track transfers of devices).

! Inadequate Control and Accountability of Devices Require devices to have labels or tags that '

contain certain information and maintain durability.

Require users to perform six month inventories.

Require users to maintain current inventory records.

l l Require users to assign Responsible  !

Individual and backup.

Improper Disposal 'of -

Require users to demonstrate evidence of Devices proper disposal or face significant penalty. Include an initial grace period  ;

! for enforcement. -

Require vendors to provide disposal  !

information prior to initial transfer of the device.

Orphaned Devices -

Define responsibilities for DOE and EPA acceptance of orphaned devices.

Ensure that all orphaned devices are disposed of properly.  !

Recommend training to non-licensed stakeholdars (e.g., health and safety risk, economic consequences, how to identify '

devices, who to contact if a device is located).

Require devices to have permanent labeling that indicates that the device contains radioactive material.

The WG evaluated the problems and strawman solutions and developed the

{ following recommendations that it believes will adequately address the j problems. ,

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4.1 Increased Regulatory Oversight The WG recommends that both NRC and the AS implement programs for increased regulatory oversight of general and specific licensees who possess and use l certarn devices.

To implement these programs, NRC should promulgate the recommended requirements as regulations and the AS should adopt these requirements as Division-2 items of compatibility. This action is necessary to ensure that the users maintain adequate control over and accountability for the devices and comply with recommended requirements.

The WG believes there are a number of reasons that licensees lose control over and accountability for devices. These include the loss of licensee personnel who had knowledge of the devices or applicable regulations, the loss of or illegible warning labels, and the fact that the licensee loses an awareness ,

that radioactive material is present. The WG agrees that a major contributing '

factor to licensees losing control and accountability is the lack of adequate  ;

oversight by regulatory authorities. Specifically, many users do not have '

routine contact with the regulatory authorities. In many cases, specific licensees obtain prior approval for use of the devices and then may not have contact with the regulatory authority until an inspection occurs, which may be up to five years later. In some cases, the contact may not come until renewal of their license.

i For almost all general licensees, the only connection l between the licensee and the regulatory authority is through the vendor of the i device. For possession and use of devices, general licensees are not required '

to obtain prior approval from the regulators and they are rarely inspected.

Due to the large population of devices, both specific- and general-licensed, and the low risk associated with the design of many of the devices, the WG believes that the increased oversight program should only be implemented for users of certain devices. Specifically, the WG believes the increased I oversight program should only be implemented for licensees using devices I containing at least 370 MBq (10 mci) of cesium-137, 3.7 MBq (0.1 mci) of strontium-90, 37 MBq (1 mci) of cobalt-60, or 37 MBq (1 mci) of any transuranic. Section 5.8 of this document provides the detail, including the WG's justification, for including only these devices as part of the increased oversight program.

The WG considers this program to be a minimum set of standards that needs to be implemented to provide an adequate level of protection of health and safety, property, and environment. There are three distinct parties that will  ;

be affected by the requirements of the oversight program: users of the devices; vendors of the devices; and the regulatory authorities, that is, NRC and AS.

For users of the devices, the WG reviewed the current NRC regulations for both general- and specific-licensed devices. Many of the requirements currently in place, either through the regulations or through license ccnditions are appropriate. However, in some cases, additional requirements are necessary.

l The WG recommends that users of the identified devices be required to meet the following:

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Licensees must assign a Responsible Individual (RI) and a Backup Responsible Individual (BRI). The RI and BRI must each be an individual that has the authority and responsibility for complying with the regulations and license conditions for possession and use of the

- devices. This will provide assurance that at least one individual employed by the licensee has current knowledge of the devices and the regulatory requirements.

Licensees must perform physical inventories and inspections of each device at intervals not to exceed six months. The physical inventories must confirm the physical location of each device within the facility and whether the device is in use or in storage. The physical inventory assures the licensee can still account for the device. In addition, the licensee must inspect each device to confirm that the labeling is still visible and legible and that the label includes the model number and serial number of the device, the isotope and quantity of the radioactive material, and the name of device vendor. If the labeling remains visible and legible, it can provide important information to persons working around the device.

inventories and inspections. Licensees must maintain records of the Licensees must keep current inventory records, including the physical location of each device within the facility, whether the device is in use or in storage, the model number and serial number of each device, l

the isotope and quantity of the radioactive material included in each

! device, the name of device vendor, the name, title, and telephone numbers of the RI and BRI for each device, the name of the individual performing the inventory, the date of the inventory, and a list of any devices received, transferred, or disposed since the previous inventory.

Licensees must compare the results of each inventory with the previous inventory and reconcile any discrepancies.

Any deficiencies with the device labeling found during the inspection must be corrected to ensure that the labeling is legible and visible and includes the required infcrmation.

Licensees must report changes concerning the RI and BRI and transfers or disposals of devices from their facility. This report of any change must be made to their regulatory authority within 30 days of the event.

The report must show that the recipient is authorized to receive the material. If the device is transferred to a licensee who is under a different regulatory authority, the licensee also must report the transfer to that regulatory authority. The WG determined that many of i

the problems with loss of devices occurs when changes take place at the licensees' facilities. This provides early notification to the l regulators.

I Licensees must report annually to the appropriate regulatory authority a listing of their current inventory of devices. This allows the regulator to verify independently that the licensee has maintained accountability and control of the devices.

17 l

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Licensees must report to their regulatory agencies immediately following the filing of a voluntary or involuntary petition for bankruptcy.

Specific licensees already are required to file such reports.

The HG. recognized that general-licensed devices are adequately labeled to ensure proper identification and vendors are required to report, quartarly, l transfers of devices to general licensees. The reports should include  ;

additional information needed to track the users and devices. Vendors of specific-licensed devices are not required to provide such reports. All vendors should be required to report, and keep records of, transfers of all devices covered by the oversight program. Vendors should report certain information to the users of the devices and ensure devices are adequately labeled to ensure proper identification.

The WG recommends that vendors of devices subject to th: oversight program be required to do the followinc:

Vendors must report transfers of each device covered by the oversight program. The transfer reports must be submitted quarterly to the regulatory authority responsible for the recipient of the devices. The transfer reports must include the name, telephone number, and complete mailing address of the recipient of the device, the address of use of ,

the device, the model number and serial number of the device, the isotope and activity of the radioactive material contained in the device, any intermediate holders of the device, including the function of the intermediate holders, the specific reporting period covered by the report, and the name and license number of the reporting company.  !

Regulators could verify that users maintain control and accountability of devices by comparing this information with the reports provided by users.

Vendors must maintain records of transfer for all devices they have  !

distributed, including final disposition, if known. The records must be maintained for three years after final disposition of the device. i

- l Vendors must provide recipients with disposal information prior to transfer of the device to the recipient. Providing this information allows the potential possession user to make an informed decision prior to taking of the device.

Vendors must ensure that each device is labeled with the device model number and serial number, the isotope and activity of the radioactive naterial, the trefoil symbol, the words " Caution - Radioactive ,

Material,"3 and the name of the device vendor. The labeling must be durable and capable of withstanding likely conditions associated with handling, storage, and use of the device and must be visible to users of the devices.

If the device is not the source housing (i.e., the smallest separable part of the device that still provides the primary shielding for the source), vendors must ensure the source housing also is labeled with the i or similar wording pursuant to 10 CFR 20.1902(e).

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device model number and serial number, the isotope and activity of the '

radioactive material, the trefoil symbol, the words " Caution -

Radioactive Material,"' and the name of the device vendor. The labeling

.must be durable and capable of withstanding likely conditions associated with handling, storage, and use of the device and must be visible to ,

users of the device. Since source housings provide the primary shielding, they typically are removed from the device when servicing is performed and usually transported separately from the rest of the device. Labeling the source housing will ensure that it can be identified as containing radioactive material and can be uniquely tracked by the licensee.

Vendors also must ensure that source housings are permanently marked (e.g., engraved or embossed) with the trefoil symbol and the words ,

l

' " Caution - Radioactive Material," as practicable. This will increase the likelihood of identifying that the device contains radioactive if it is lost.

Increased regulatory oversight, requires that there are certain actions both NRC and AS must perform. Therefore, the WG recommends that both NRC and each AS implement the following measures:

Verify that all transfers by their users are in accordance with their regulations and license conditions.

Compare the annual inventories reported by their users against previous l  :

l inventories and against transfer reports from vendors and other users.

l This provides an independent verification that licensees have maintained l accountability and control of the devices.

Resolve any discrepancies in the information with the assistance of the licensees.

1 Acknowledge to their licensees that the transfers and inventories have been reviewed.

l These four recommendations should be adopted as essential program elements l within all radiation control programs. Also, the WG evaluated the need for AS l compatibility of regulation of devices and concluded that the regulation of l the devices should include all of the recommendations listed in this section. i The WG believes that the AS must continue to have flexibility in the methods l l they use to implement the oversight program. The WG recommends that these requirements for users and vendors be adopted by the AS as a Division-2 item l of compatibility. This would ensure that the minimum requirements would be 1

implemented but would allow the AS to be more stringent.

The WG was asked to provide and consider the costs of any program it i recommended. The WG developed expected cost tables for the oversight program and has included this information in Appendix F. In addition, Appendix F includes an estimate of the benefit that could be expected as a result of NRC i and AS implementing increased regulatory oversight.

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The WG's estimated costs includes the costs for both NRC and AS to implement I the oversight program. However, the costs for AS to implement the program I were derived by assuming that AS would implement annual registratbn programs. '

In actuality; the WG expects that each AS would implement an oversight program l l that best fits its own regulatory structure. Since som AS already have  :

i implemanud registration programs for general licensees that meet our l recommendations, the costs estimated for AS are conservativa.

The annual operating costs .f an increased oversight prog' cam, including the costs to licensees and regulators, is estimated to be approximately $5 million (see Table F.1). This cost is offset by an estimated anneal benefit, from l Table F.2, of approximately $12 to $14 millica. If only the property savings t to the affected non-licensees is considered, there st 11 is an estimated l benefit of approximately $12 million.

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4.2 Penalties for Lost Devices l To make the oversight program described in Section 4.1 effective, NRC must ensure that licensees are discouraged from losing devices. Therefore, the WG recommends that NRC establish a significant penalty for persons who have lost a device, that is, failure to provide written evidence of proper disposal.

A review of enforcement actions for persons improperly disposing of devices shows that the typical civil penalty is $2,500. This penalty does not provide a sufficient disincentive since proper disposal can cost up to $20,000 (see Appendix C). The WG recommends that NRC establish severe civil penalties for persons who lose control over and accountability for devices. The civil i penalty should be sufficient to deter loss. A penalty much higher (2 to 3 l times the costs of authorized disposal of the device) should be assessed. The l WG believes the severity of the penalty recommended is warranted based on the possible consequences associated with loss of a device.

The baseline information provided by licensees must be complete and accurate. ,

l The WG recommended a severe penalty for persons losing a device; however, the l WG believes that NRC should exercise discretion during the first year of implementation of the oversigSt program. This will encourage licensees to report accurately. In addition, subjecting licensees to harsh penalties without allowing an amnesty period would encourage licensees to provide false information and to dispose of devices in an unauthorized manner.

The WG also encourages each AS to implement severe penalties for loss of a l l device and a discretionary period for the first year of implementation. If an l

AS cannot impose a civil penalty, the WG recommends that it impose a penalty that has the same impact and effect as a civil penalty equal to 2 to 3 times the costs of authorized disposal of the device.

4.3 Disposition of Orphaned Devices.

With the implementation of an increased oversight program and increased penalties, regulatory authorities still will be faced with the problem of orphaned devices. Many devices already are lost or cannot be accounted for.

These devices may find their way into the public domain. NRC must ensure that

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a program is implemented to properly handle and dispose of all orphaned devices found within its jurisdiction. The program should include even those devices not subject to increased oversight since these devices still would represent a risk to public health an.1 safety.

The WG understands that DOE and EPA currently have some responsibilities for orphaned devices. However, the scope of these responsibilities is unclear.

It appears that DOE will take possession and provide for the ultimate disposal of devices that cannot be traced to a licensee and pose an eminent threat to 4

public health and safety. The responsibilities of EPA are unclear. The WG reconnends that NRC work with both DOE and EPA to clearly define the respor.sibilities of each agency. The responsibilities should be delineated in

a memorandum af understanding among the agencies.

l There mey be some category of orphaned devices for which neither DOE nor EPA t

will tasc responsibility. If so, the WG recommends that NRC take resper.sibility for this category of orphaned devices, including funding for  :

the ultimate disposal of the devices. This action will ensure public health I and safety. If no agency takes responsibility for the devices, the finders of 1 the devices may eventually be held responsible for the costs of handling and '

disposal. This would provide a disincentive for the finder to act

! responsibly. It may encourage the finder to transfer tha device to an )

l unknowing pcrty. In doing so, the device may continue to be handled by '

members of the put,lic, could become damaged causing higher radiation exposure ratos from the ievice, or could find its way into the metal scrap stream. ]

, Devices msking it through the scrap metal stream undetected have caused i i

unnecessary py p osures and millions of dollars in damage end lost revenue. l 1

The WG understands that it may require changes to legislation for NRC, or DOE ,

or EPA, to provide funding for handling and ultimate disposal of orphaned '

devices. However, the WG believes that NRC should be the cognizant agency since NRC is responsible for ensuring public health and safety. As stated, l not having a program for handling and disposing of the devices may lead to  ;

exposures to the public and high costs to industry. Almost all orphaned i devices were at one time possessed by general or specific licensees. One of  ;

the reasons for the loss of control and accountability of devices is the lack j of oversight of the licensees by NRC. Since NRC is partially responsible for the inadequate control over and accountability for the devices, it must have l some responsibility in resolving the problem. l The WG discussed how to fund a program for disposal of orphaned devices. This included talks with waste compacts about managing and supporting a disposal fund. The WG reached two conclusions about funding. First, finders of devices should not be responsible for supporting the disposal of orphaned devices. This could lead to devices remaining in the public domain and possible exposures to members of the public. Second, the mechanisms for supporting the program will be complex and will probably require legislation.

NRC needs to investigate and determine the most effective method of collecting and managing a fund for disposal of orphaned devices.

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The WG also encourages each AS to implement a fund to support the handling and disposal of orphaned devices not accepted by DOE or EPA. Each AS would to l

determine the most effective method of supporting disposal. l I

4.4 Recommendations for State Regulatory Programs '

The WG encourages all State regulatory programs to implement the recommendations provided in Sections 4.1, 4.2, and 4.3 for devices containing NARM.

States should use the same criteria used by the WG to determine which devices should be subject to the increased oversight program. These actions are necessary since many of the devices found each year contain NARM material.

Devices containing NAR11 h::ve caused exposures to members of the public and also have caused industry to experience high costs for clean up and disposal.

4.5 Recommendations for Non-Licensed Stakeholders Problems associated with lost devices affects many non-licensees.

Specifically, persons finding lost devices face radiation exposures and expenses associated with handling and disposing of devices. The radiation exposures and expenses may be significant, especially if the containment integrity of the source is breached. The WG recommends that NRC provide non-licensees who are likely to come in contact with lost devices with information that provides guidance. This would include the health and safety risk, economic consequences, identification of lost devices, and whom to contact if the devices are found.

NRC cannot require this recommendation to be implemented since it suggests non-licensees provide training to their employees. NRC can provide the information to the non-licensees and encourage the non-licensees to provide this information to its employees. This includes notices, posters, or training materials. The WG believes that added guidance will encourage the finders to act properly, notify the proper authority, and help ensure the device gets out of the public domain.

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5.0 ISSUES AND CONCERNS i

Sections 5.1 through 5.7 include the seven issues and concerns raised.by the NRC staff in its May 31, 1995, memorandum to the Commission. The WG agreed that e~ach of these concerns needed to be addressed in detail. However, the WG identified other aspects of the problem that needed to be addressed. These are included in Sections 5.8 through 5.11.

5.1 NRC and AS Compatibility -- NRC and AS regulations need to be compatible since approximately two-thirds of the devices are used by AS licensees.

The WG considered all possibilities of compatibility for its recommendations.

These included Divisions-1, 2, and 3 items of compatibility. Division-1 means AS must adopt requirements that are essentially identical to NRC's i requirements. Division-2 means AS must adopt the same requirements but may be 1 more stringent than NRC. Division-3 means AS do not have to adopt the same requirements.

In considering a Division-3 item of compatibility, the WG determined that if the AS did not implement these recommended requiremeni.s, then the nation-wide program would be ineffective because the devices lost by users in States not having the program could be expected to turn up in the scrap stream of other States.

In considering a Division-2 item of compatibility, the WG determined that since AS would need to adopt the same requirements the nation-wide program would be at least as effective as NRC's program with respect to protection of health and safety, property, and environment. The WG could not identify any negative consequences associated with allowing AS to have more stringent requirements.

The WG determined that a Division-1 item of compatibility also would ensure an j effective nation-wide program. However, the WG could not identify any advantages with respect to increasing protection of health and safety and property when comparing a Division-1 with a Division-2 item of compatibility.

The WG identified that a Division-1 item of compatibility would not allow an AS to exercise local control and be more stringent.

The WG recommends a Division-2 item of compatibility for its recommendations.

The WG also would like to note the following recommendations and comments that it received during the open meetings:

The majority of vendor and user comments received by the WG indicated that regulations covering the possession and use of devices should be uniform nation-wide, i.e., a Division-1 item of compatibility. Their reasons centered on ease of doing business nation-wide with a single set of requirements. Vendors believe that if requirements were not uniform nation-wide, they would have to track 30 sets of regulations and it would not be possible to have a national inventory, as described in Mr.

Dukes' proposal. If a few AS have more stringent requirements, the cost ,

of using the devices in those AS could be adversely affected.

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AS were asked to provide input on this issue. Eleven AS provided input.

The majority were not averse to increasing the oversight of certain devices.

Some believed the cost-benefit may be difficult to justify and most were opposed to establishing a national inventory and database. Of  ;

! ' those reporting, one supported a Division-1, nine supported a  !

Division-2, and one supported a Division-3 item of compatibility. '

The WG noted that at least six AS had adopted more stringent 1 requirements for these devices including annual registration, annual )

fees, or restricting their use to a specific license. The WG could not identify any benefits by requiring these AS to change their programs )

l with respect to increasing protection of health and safety, property, and environment. i

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l 5.2 Cost and Fee Considerations -- There are various options for licensing devices that would provide better control and accountability. The cost of implementation to NRC and AS and the appropriate cost recovery method need to be considered.

I The WG addressed funding of the program, estimated costs, and attempted to i minimize the overall cost of its recommendations.

The WG considered all of the general- and specific-licensed devices as possible candidates for increase oversight. The WG used a rationale based on health and safety principles to identify the minimum set of these devices to be subject to increased oversight. By focusing the requirements on only i l

certain devices, identified in Table 2, Section 5.8, this has the effect of minimizing the overall cost of a nation-wide program.

The WG est0 meted the cost of a nation-wide program. Estimated costs include the costs cf implementation of regulations by NRC and each AS, start-up cost, annual operating cost, and licensee record keeping and reporting re Total costs for all parties are approximately $5 million per year. quirements.

These costs are described in Appendix F, Table F.1.

The WG noted that all AS that have currently implemented increased oversight programs for these type devices have supported such programs with annual user fees. Since NRC is funded by user fees for cost recovery, it also could charge an annual fee to device users. The WG has assumed that n.a t AS would charge such a fee and the remaining AS would support their program through other funding. 1 The WG concluded that the nation-wide program could be supported by user fees.

The WGpossessed devices recommends that the annual user fees should be based on the number of by a licensee. This would encourage users to report promptly device.

transfers of devices and evaluated annually whether to keep the 24

5.3 Radiation Exposure Savings -- The savings in radiation exposures resulting l from better control over, and accountability for, devices need to be i considered in the selection of the method for licensing of devices.

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The WG-identified a limited number of references that contained estimated

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radiation exposures attributable to lost devices. The WG also used 1

. information on actual exposures based on reported licensee events. From this '

information, the WG estimated the expected benefit due to exposure savings l that would accrue from adoption of the recommendations. i The WG noted that data to provide estimates of exposures were insufficient.

The information that is available is based on best estimate calculations using plausible assumptions. Therefore, the WG estimates should not be interpreted as having high precision or accuracy. I l

The radiation exposures are estimated to range from about 70 mSv to 10.53 Sv (7 to 1053 rem) annually. These estimates are included in Appendix F, l Table F.2, and were reported by Pacific Northwest Laboratory (PNL) in " Peer Review of Improper Transfer / Disposal Scenarios for Generally Licensed Devices," June 1994. The estimates are for devices containing cesium-137 and are based on time and proximity assumptions developed by PNL using data from '

known incidents. PNL estimated the likely source strength and number of i

annual events using assumptions about the numbers of devices distributed in 4 NRC States. '

] The WG considered likely scenarios based on recent incident experiences. In 1

Texas an incident involving stolen radiography devices and the subsequent i

transfer of the devices between scrap yards highlighted potential consequences of lost devices (see Appendix H). The radioactive devices were sold as scrap and were transferred between several scrap dealers before they were recognized as being radioactive. The lack of detection or identification capability in

i. the scrap yards prevented scrap dealers from taking appropriate safety measures. In this incident total estimated exposures equaled 1.85 person-Sv (185 person-rem).

1 Another incident in Illinois was discovered when a scrap dealer purchased a i

radiation detection instrument and found a radioactive source buried on the i site. The source was discovered in backfill used to re-grade the site.

Excavation of the area by an incident response team recovered the source. It was determined to be cesium-137 with an activity of approximately 13.7 GBq l (370 mci). Exposure rates were calculated to be approximately 1.45 Sv/hr (145 mrem /hr) at 0.91 m (3 ft). There is no way of knowing how long the source had been on the site or whether it may have been exposing workers and other individuals prior to being discovered.

4 The two incidents described above illustrate the mechanisms and potential harm i that s.ould occur to scrap workers and other members of the public. These sources could have caused serious exposure if located near individuals.

There is insufficient information to determine the probability of loss of a device requiring increased regulatory oversight, the probability of an event 1 such as containment shielding breach from such a lost source, and the l 25 l

probability of either external or internal radiation exposures from this type of event. Information available indicates that for at least a few incidents (e.g., Goiania, Estonia), significant exposures or even fatalities have occurred as a result of loss of a device. Radiation exposures associated with the loss of a device may be significant both in terms of individual dose or population dose. The WG believes that many exposures occurred that were not reported to regulatory authorities. There are too many uncertainties to estimate adequately the total exposures attributable to the loss of a devices.

The WG notes that the estimated economic benefits resulting from protection of property and environment outweigh the benefits of exposure savings. This information is presented in Appendix F.

5.4 Device Design -- Currently, the design requirements for general-licensed devices are more stringent than those for specific-licensed devices. The safety impact of using a different licensing method, which may rely on administrative controls rather than the design of the devices, must be evaluated.

The two main issues discussed by the WG concerning device designs were changes to designs that could increase control over and accountability for the devices and whether certain device designs should no longer be authorized for use under a general license.

Suggestions for changing designs to increase control and accountability centered on identification of devices or sources. Specifically, persons attending the open meetings suggested including dye packets that are released if the device is crushed, mechanisms that would alarm at timed intervals to alert licensees to inventory the device, designing sources so they would survive smeltings of the device, and designing device labeling that would withstand conditions encountered after the device is lost. ,

1 The WG believes that most of these suggestions would increase costs for industry but would not provide a commensurate increase in protection of health and safety, property, and environment. Many of the suggestions only provide for identification of a device after loss but do not provide increased control or accountability. The WG believes the only reasonable change to device designs that would improve control and accountability, and identification of devices after the loss, is that all devices incorporate labeling that contains sufficient information to identify the device as radioactive, provide a method of identifying the last licensee who possessed the device, and that the labeling is sufficient to withstand conditions associated with loss of the l device.

The WG evaluated use af devices under a specific license, rather than a '

general license. Supporters indicated that this would increase regulators' oversight and licensees' accountability of devices. The WG does not believe '

this would result in an increase in safety for the following reasons:

Information reviewed by the WG indicates that simply moving the devices to specific licenses does not provide adequate assurance of control and 26

accountability. This is supported by the fact that many of the devices found in the public domain can be traced to a specific-licensed user.

Currently, regulators plan to inspect specific licensees on a 5 year frequency. However, inspections can, and do, extend to 6 or 7 year intervals due to resource constraints. If a number of general-licensed devices were moved to use under a specific license, this would increase NRC and AS staff workload without a commensurate increase in staff.

Therefore, this would lead to a decrease in inspection frequencies for specific licensees.

The WG concluded that marginal improvements could be made regarding design of devices (i.e., label information) but requiring specific licenses, rather than general licenses, would not result in an increase in protection of health and safety, property, and environment.

As instructed, the WG considered the design of general-licensed devices in light of recent changes to 10 CFR Part 20. Specifically, the NRC staff's May 31, 1995, paper discussed whether general licensees should be considered a special class of occupational worker, between occupational workers and members of the public, since the dose limit for general-licensed devices is 5 mSv (0.5 rem). Since the Office of Nuclear Regulatory Research, NRC, is currently assessing the design dose criteria in 10 CFR Part 32 for general-licensed devices, the WG did not address this issue.

5.5 Changes That Affect All Devices Versus Only Newly Acquired Devices --

Since there are currently about 1.5 million general-licensed devices in NRC and AS, changes in the Ifcensing of devices need to address both new l requirements for devices currently possessed by licensees and newly acquired l devices.

The WG focused its recommendations on certain devices as identified in Section 5.8, Table 2, which would amount to approximately 126,000 devices rather than increasing regulatory oversight for the estimated 1.5 million devices used under NRC and AS general licenses. The justification for this limited focus is discussed in Section 5.8.

The WG agrees that it is necessary to address devices both currently possessed and those to be distributed in the future. If only future devices are subject i to increased regulatory oversight, the existing 126,000 devices would not be  !

i subject to adequate oversight and there would be no effect on the expected number of lost devices. Since the likelihood of a lost device increases the longer the licensee has possessed the device without being subject to inspection, the number of lost devices could not be expected to decrease. It is necessary to include both under the WG recommendations.

The WG notes that even if all current and future devices are subject to increased oversight, there may be devices that today are not accounted for.

These devices could be expected to show up in the public domain in the future as orphaned devices. Discussion of orphaned devices is provided in Section 5.6. It should be noted that the work to identify current users of f

27 l

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devices will costs approximately $2.7 million for NRC and AS. Discussion of '

the cost is provided in Section 5.1.

5.6 Device Disposa) -- Options for the disposal of device.; need to be delineated. Many current general licensees may wish to dispose of the devices rather than be subjected to increased regulation.

Many of the stakeholders involved in the WG meetings were concerned with the cost of disposal options, insolvent and bankrupt users, and orphaned devices.

The responsibility for the ultimate disposition of devices should continue to rest with the users of the devices. Many users may not be aware of all their regulatory responsibilities when they acquire a device. Vendors should provide users with options, including costs, for final disposal of devices, allowing them to make better informed decisions prior to obtaining devices.

The WG debated over ehether it could make any recommendations that affect insolvent or bankrupt users. The only recommendation is for general licensees to report to regulatory agencies immediately following the filing of a voluntary or involuntary petition for bankruptcy.

Proper disposal of orphaned devices was of great concern to the WG and stakeholders. As stated, orphaned devices will continue to exist. This is -

due to some licensees already having lost devices, licensees not ever knowing of the existence of the devices, or NRC and AS not being aware of some general <

licensees which increases the likelihood that a device will be lost. NRC and AS must implement procedures that will ensure that orphaned devices will not present a hazard.

Currently, few options exist when someone finds an orphaned device. If the device meets the criteria established by DOE or EPA, the respective agency will assume responsibility for disposal. A few AS, including Texas and Oregon, may assume responsibility for an orphaned device at no cost to the person finding the device. However, additional options are needed because those currently available don't provide for the disposal of all orphaned devices.

If finders of devices know that they may be held responsible for disposal of the device, then finders may attempt to transfer the device to an unknowing party. In doing so, the device may be handled by members of the public, may become damaged causing radiation exposures, or it may find its way into the '

metal scrap stream. Devices coming through the metal scrap stream undetected have caused millions of dollars in damage and lost revenue. An example of a device that continued to be passed around once the scrap dealer found out it contained radioactive material was the incident that occurred in Texas (see Appendix H).

Although notification procedures (e.g., to State radiation control programs, shippers, and originators of the load) exist for Department of Transportation exemption E10656, not every detection of radioactive material in scrap leads to notification. In cases where scrap recyclers have installed monitors to detect devices, those recyclers will not take possession of the device since 28

they may become responsible for its disposal. The possessor taker the device l back into the public domain and may attempt to sell the load to a facility that does not have monitoring devices.

The WG believes' that all orphaned devices must be properly disposed. NRC must work with DOE and EPA to solicit their help. A memorandum of understanding must be developed among NRC, DOE, and EPA to delineate each agency's role in disposing of orphaned devices. Based on what has historically happened with orphaned devices, there may be some category of orphaned devices that will not be disposed of by either DOE or EPA. NRC and AS each should accept the responsibility for disposal of all other devices that are found within their jurisdictions. One possibility for NRC is to contract with one or more waste compacts for the disposal program. A funding method must be identified for

such a disposal program. The NRC may already have such authority. If not, it should be sought through congressional legislation.

Finders of devicer, should not be held responsible for the cost of disposal of orphaned devices.

5.7 Device Identification -- Added requirements to ensure that device labels could better withstand harsh, unexpected environments may enhance the ability to identify devices that are disposed of or improperly transferred.

Device control would be improved and devices would be more likely to be identified after loss, if device labels are durable and contain sufficient information to identify the device as radioactive, the label provides identification of the last licensee that possessed the device, and the labeling is sufficient to withstand conditions associated with loss. For example:

Devices must be labeled with the device model number and serial number, the isotope and activity of the radioactive material, the trefoil rymbol, the words " Caution - Radioactive Material,"' and the name of the device vendor. The labeling must be durable and capable of withstanding likely conditions associated with handling, storage, and use of the l device and must be visible to users of the device.

If the device is not the source housing (i.e., the smallest separable part of the device that still provides the primary shielding for the source), the source housing also must be labeled with the device model l

number and serial number, the isotope and activity of the radioactive i material, 'the trefoil symbol, the words " Caution - Radioactive Materiai,' and the name of the device vendor. The labeling must be durable and c.apable of withstanding likely conditions associated with handling, storage, and use of the device and must be visible to users of the device. Since source housings provide the primary shielding, they typically are removed from the device when servicing is performed and usually transported separately from the rest of the device. Labeling

29

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.. j the source housing _will ensure that it can be identified as containing i radioactive material and can be uniquely tracked by the licensee.

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! _The source housings must be permanently marked (e.g., engraved or embossed)'with the trefoil symbol and the words " Caution - Radioactive '

Material," as practicable ~. This will increase the likelihood of i -identifying that the device contains radioactive material even if the i device is lost.

1 i The WG notes that it is not necessary to provide recommendations for identification and labeling of sources for the following reasons:  ;

General licensees, and most specific-licensed device users, are not  !

- authorized to remove sources from devices. These users ensure control >

and accountability of the devices, not sources. Having users remove or j view the sources would be costly, result in unnecessary exposures, and I would not be consistent with as low as reasonable achievable l (radiation). j If users and regulators tracked sources, it would require removal of a l source from a lost device to trace it to the last responsible licensee. i c This would result in both high handling cost and unnecessary exposures.  !

The devices can be traced to the last responsible licensee by'their  !

. serial numbers. [

. l 5.8 Devices Requiring Increased Oversight In evaluating the isotopes and activities contained in devices currently used by both specific and general licensees and after reviewing documentation, the WG determined that only a small percentage of the total number of radioactive sources in the United States would cause detrimental effects to the population. Of these, only a very small fraction actually were smelted or created health and safety, property, or environmental problems.

The WG reviewed two operts by ERC ' contractors, the " Improper  !

Transfer / Disposal Scenarios for Generally Licensed Devices," Oak Ridge l Associated Universities (0RAU), April 1987, and " Peer Review of Improper i Transfer / Disposal Scenarios for Generally Licensed Devices," PNL, June 1994. l The WG concurred with NRC staff that ORAU's findings were unreasonably i conservative. Even though the WG agreed with the methodology used in the PNL i study it couldn't entirely agree with its conclusions since it only examined j the radiation exposures associated with known accidents and did not consider j the damages to property associated with loss of a device. However, the PNL  !

study does support the WG's conclusion that the increased oversight should i only apply to a subset of devices. Specifically, PNL concluded that 83 i percent of all general-licensed devices, excluding tritium exit signs,  !'

represent a small risk, due to radiation exposure, even if the general-licensed devices are improperly disposed of and handled by members of the i public.  ;

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The.following parameters were used to define a subset of devices

l i the hazard from external and internal exposure, l l .the typical quantity of isotope contained in a device, l costs and' availability of disposal of the devices, i l

the half-life of the isotope, and l l

the cost associated with clean-up and disposal from accidents resulting i j from loss.

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l Isotopes used in measuring, gauging, and controlling devices were ranked for  !

i each of these parameters. An overall ranking was established for each isotope  !

(Appendix D). This ranking process was conducted during the March 5, 1996, open meeting with the assistance of NRC and AS personnel, vendors,  ;

users, and other health physicists. The ranking process relied on the collective education, training, and experience of this group. Devices  !

containing cobalt-60, cesium-137, strontium-90, and all transuranics were -

identified as the subset that should be subject to increased oversight. .

Isotopes less than 1000 times the activity specified in 10 CFR 30.71, I appendix B, " Exempt Quantities," were excluded from the subset. Transuranic i isotopes that are not included in 10 CFR 30.71, appendix B, with an activity of less than 37 MBq (1 mci), also were excluded. The result of using both the parameter ranking, and the activity criteria, is provided in Table 2. l i

T ole 2  ;

-Isotopes and Activities I

' Selected for Increased Oversight Activity Isotopes (MBq) (mci)

Cesium-137 370 10 Cobalt-60 37 1 ,

Strontium-90 3.7 0.1 All Transuranics 37 1 If an isotope in a device meets or exceeds the criteria provided in Table 2,

! it must be subject to increased regulatory oversight. Notwithstanding the o increased oversight for these isotopes, there still exists the possibility for ,

loss of other devices. These losses are not expected to result in significant health, safety, or environmental concerns based on the WG parameter ranking.

l The Commission should review and determine if this is an acceptable approach.

! 5.9 General-Licensed versus Specific-Licensed Devices Some persons attending WG meetings suggested that the general-licensing j program be abolished and that specific licenses be required for possession and

, use of all devices. The WG addressed this issue as follows:

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, . . .- _.m- -, . - - .

Data show that metal manufacturers and recyclers find devices that can be traced to both general and specific licensees. Allowing use of these devices only under a specific hense would not prevent loss. '

'The subset of detices identified is a small fraction of the total number of general license devices. Subjecting all general-licensed devices to a specific license would impose unnecessary burdens without a commensurate increase in protection. Users also would incur costs to implement measures that address issues not identified by the WG.

5.10 Identification of Current Users and Devices There is no complete list of current users or devices. NRC and AS could develop such a list. The following are elements required for its development:

NRC should update the computerized database of general licensees and devices. This should begin by reconciling the information in the database with information from vendors. Vendors should be required to submit information about devices that they distributed to general licensees within the last five years.

NRC should recommend that vendors provide as much information as practicable on a voluntary basis to the regulatory agencies.6 Voluntary dissemination of information would be less costly in terms of time and resources than formal surveys requiring responses from each individual general licensee. -

AS should follow the same process. The information from the vendors should serve as the initial database of general licensees and devices for AS.

NRC and AS should contact each user to establish a baseline database.

Given that general license distribution was started in 1956, the WG would expect that not all devices will be accounted for. However, establishing a current baseline is essential. This process will provide most of the required information.

5.11 Imposing Restrictions on Portable Devices and Storage of Devices Some people attending the open meetings suggested that both possession and use of portable devices and long-term storage of any device should be restricted l l to a specific license. Portable devices used at temporary job sites are more l l susceptible to loss or theft. Devices stored for long time periods are l equally susceptible to being forgotten. The WG agrees with these concerns. 1 Restricting possession and use to a specific license will not necessarily '

q 6

, During the open meetings, several vendors indicated that they retain '

this information until a device is returned or they become aware of its )

disposal.

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. o i prevent loss. Unless a device meets the specific criteria provided in l Table 2, Section 5.8, the device should not be subject to increased oversight.  !

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Appendix A: PROTECTION OF PROPERTY The goal of minimizing hazard to property is contained in the Atomic Energy Act at Section 161 and the Commission has made use of it in several Parts of 10 CTR including Parts 20, 30, 40, 61 and 70. Notably, with respect to byproduct, source, and special nuclear materials, and radioactive waste, the Commission has used it in 33 instances as a decision criterion regarding enforcement actions, exemptions, general requirements for issuance of specific licenses, standards for issuance of a license, conditions of licenses, contents of applications, and requirements for the approval of applications.

The WG recommends using this as a decision criterion for the issues surrounding conditions of use, control over, and accounting for, certain devices containing specific isotopes and activities of byproduct material.

The following is a listing F the Commission's use of this criterion.

II. Statutory Authority and Procedural Framework A. Statutory Authority The NRC's enforcement jurisdiction is drawn from the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act (ERA) of 1974, as amended.

Section 161 of the Atomic Energy Act authorizes NRC to conduct inspections and investigations and to issue orders as may be necessary or desirable to promote the common defense and security or to protect health or to minimize danger to life or property.

10 CFR Part 2, Appendix C -- General Statement of Policy and Procedure for NRC Enforcement Actions 10 CFR 19.31 Application for exemptions --  :

...will not result in undue hazard to life or property."

10 CFR 20.2301 Applications for exemptions -- i

...would not result in undue hazard to life or property."  !

I 10 CFR 20.2302 Additional requirements --

...necessary to protect health or to minimize danger to life or property."

10 CFR 21.7 Exemptions --

. . .will not endanger life or property. . . "

l 10 CFR 30.11 Specific exemptions --

j

. . .will not endanger life or property. . ."

l 10 CFR 30.20 Gas.and aerosol detectors containing byproduct material --  !

...to protect life or property..."

{

1 10 CFR 30.33 General requirements for issuance of specific licenses -- I (a)(2) "... adequate to protect health and minimize danger to life or property;"

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(a)(3) "....to protect health and minimize danger to life or property;"

(e)(2) " Protect health or to minimize danger to life or property;"

10 CFR 32.26 Gas and aerosol detectors containing byproduct material:

Requirements for license to manufacture, process, produce, or initially transfer --

. ..to protect life or property. . ."

10 CFR 32.210 Registration of product information --

(c) "... adequate to protect health and minimize danger to life and property."

(d) "... minimize danger to life and property."

10 CFR 34.51 Applications for exemption --

...will not result in undue hazard to .ife or property."

10 CFR 35.19 Specific exemptions --

" . .will not endanger life or property. . ."

10 CFR 36.17 Applications for exemptions --

. . .will not endanger life or property. . ."

10 CFR 39.91 Applications for exemptions --

. . .will not endanger life or property.. ."

10 CFR 40.14 Specific exemptions --

. . .will not endanger life or property.. ."

10 CFR 40.28 General license for custody and long-term care of uranium or thorium byproduct materials disposal sites --

(f) "...to minimize or eliminate danger to life or property..."

10 CFR 40.32 General requirements for issuance of specific licenses --

(b) "...to protect health and minimize danger to life or property;"

(c) "...to protect health and minimize danger to life or property;"

(e)(2) " Protect health or to minimize danger of life or property;"

10 CFR 61.6 Exemptions --

. . .will not endanger life or property. . ."

10 CFR 61.23 Standards for issuance of a license --

... minimizes danger to life or property."

10 CFR 61.24 Conditions of licenses --

(h)(2) " Protect health or to minimize danger to life or property;"

10 CFR 70.14 Specific exemptions --

(a) ". . .will not endanger life or property. . ."

10 CFR 70.22 Contents of applications --

(a)(7) ". . . minimize danger to life or property. . ."

(a)'(8) ". . . minimize danger to life or property. . ."

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10 CFR 70.23 Requirements for the approval of applications --

(a)(3) "... minimize danger to life or property;"

(a)(4) "... minimize danger to life or property..."

10 CfR.70.32 Conditions of licenses --

(b)(2) "...to minimize danger to life or property;"

10 CFR 71.7 Specific exemptions --

...will not endanger life or property..."

10 CFR 71.65 Additional requirements --

"... minimize danger to life or property."

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. . _ __._. . _ . . . . _ __ _ _~~. _ . _ _ _ . . .m _ ~ . _ _ _ _ . _ ...

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[ Appendix B: WORKING GROUP CHARTER 1

l CHARTER Scope A working group of Federal.and State regulators is to evaluate current regulations concerning the-control of and accountability for generally and

=specifically licensed devices and develop recommendations for alternative' regulatory approaches, as appropriate, taking into consideration the costs of any recommended changes. A part of the effort should be devoted to defining a method of measuring.the effectiveness of the current and proposed programs.

l Backaround On June 20,1995, .the Commission approved a staff plan to contact the Organization of Agreement States (OAS) to form a working group (WG) to evaluate current regulations concerning generally and specifically licensed l devices.

l l The Problem

. Inadequate control of licensed devices by licensees has lead to radioactive materials being included in metal . scrap intended for recycling. Inadvertent smeltings of radioactive materials in mills have occurred resulting in contamination of mills, mill products and byproducts. Subsequent costs _.for i.

each incident that required decontamination, waste disposal and mill shutdown have totaled as much as $ 23 million. While exposures to radiation from radioactive sources in metal scrap in the U.S. have been minimal, significant l radiation exposures of workers and the public resulted from incidents which l occurred in Mexico and in Estonia,. in the latter case causing one death.

I "Near-misses" have occurred in the U.S.: In 1994-95 an unshielded 14 GBq (370 mci) .*Cs source was found buried at a scrap yard in Illinois, a 12GBq (330 mC1) *Cs became separated from its shielded ho through a shredder at a scrap yard in Kentucky, and ] der when the holder went'Cs cont was found at a scrap yard in Michigan.

L While various types of radioactive material have been found in metal scrap, i

the principal source of concern are devices such as nuclear gauges. Under NRC regulations specifically licensed gauge users are subject to annual fees and a schedule calling for inspections every 5 years while general licensees are not j subject to fees nor to routine inspections.

I 'The Task The task of the WG is to assess the current regulatory programs for generally  ;

, and specifically licensed devices and determine the baseline for regulating these devices. The assessment should address the question of whether there is l an adequate level of assurance that these devices are properly controlled and

accounted fpr by licensees, and that they do not present unacceptable levels t

37 l l

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of risk of exposure to radiation to workers and the public or financial risk i to the metal recycling industry.' An integral part of this assessment is to determine how to measure the success or failure of a regulatory program. The l WG should examine _ regulatory alternatives including the costs of the  !

alternatives for device vendors and users, tha regulating agencies and other j potentially_affected groups and provide a recommendation to the Commission. i

, The Issues Seven issues were identified by NRC staff that require a coordinated Agreement State and NRC review, i.e._ addressed by the WG:

1. NRC and Aareement State Compatibility -- NRC and Agreement State regulations need to be compatible since approximately 2/3 of the devices are used by Agreement State _ licensees and loss of a device will often have effects in States other than the licensing State.

l 2. Cost and Fee Considerations -- There are various options for licensing l devices that would provide better control and accountability. The cost of i

implementation to the NRC and Agreement States and the appropriate cost

recovery method need to be considered.
3. Radiation Exoosure Savinas -- The savings in radiation exposures resulting .

l from better control over, and accountability for, devices need to be i considered in the selection of the method for licensing of devices.

! 4. Device Desian -- Currently, the design requirements for generally licensed l devices are more stringent than those for specifically licensed devices. The i safety impact of using a different licensing method, which may rely on administrative controls rather than the design of the devices, must be evaluated.

5. Chanaes That Affect All Devices-Versus Only Newly Acauired -- Since there are currently about 1.5 million generally licensed devices in NRC and Agreement States, changes in the licensing of devices need to address both new requirements for devices currently possessed by licensees and newly acquired devices.
6. Device Disposal -- Options for the disposal of devices need to be delineated. Many current general licensees may wish to dispose of the devices rather than be subjected to increased regulation.
7. Device Identification -- Added requirements to ensure that methods of identification are used that could better withstand harsh, unexpected environments. Such requirements may enhance the ability to identify devices that are disposed of or improperly transferred.

In addition to these issues the WG should also answer the following question which is central to evaluating both the present regulatory program and any contemplated changes:

4 38

How can the success (or failure) of a regulatory program for ensuring adequate control and accountability of licensed sources be most effectively measured?

Committee Oraanization and Operations i

Joel 0. Lubenau, Senior Health Physicist, NMSS/IMNS/SCDB and Robert Free.  !

Branch Administrator, Emergency Response and Incident Investigation, Texas Bureau of Radiation Control have been named WG co-chairs by the NRC and 0AS respectively. Other 0AS members are Martha Dibblee, Manager, Radioactive Materials Program, Oregon Radiation Protection Services, J. Robin Haden, Chief, Radioactive Materials Section and Rita Aldrich, Principal Radiophysicist, New York State Department of Labor (alternate). Other NRC members are Lloyd A. Bolling, Office of State Programs and John L. Telford, Office of Nuclear Regulatory Research.

l The Conference of Radiation Control Program Directors, Inc. (CRCPD) has tasked its E-23 Committee on Resource Recovery and Radioactivity to review the issue of radioactive materials in metal scrap and develop recommendations. The committee has worked closely with the metal recycling industries and State and Federal agencies to develop guidance particularly for educational efforts and protective measures. The WG co-chairs will request the CRCPD to designate an E-23 representative to serve as liaison to the WG.

l The International Atomic Energy Agency (IAEA) has reported on the problem of assuring adequate controls and disposal of " spent" radiation sources, i.e.,

sources that are no longer needed or usable. The NRC co-chair will request l

the NRC Nuclear Safety Attache assigned to the U.S. Mission to the UN System

Organizations (James Richardson) to serve as liaison to the WG. l l 1 l The co-chairs will be jointly responsible for developing a work plan for the i

WG, monitoring progress, preparing minutes of WG minutes and drafting a report of the WG's work and recommendations. Secretarial, logistical and travel support for WG meetings will be provided by the NRC. WG meetings are not subject to the requirements of the Federal Advisory Committee Act (FACA) but )

they will be publicly announced in advance through the NRC Public Meeting l Notice System. Maximum use will be made of other appropriate media, e.g.,  !

professional and trade newsletters, to announce meetings to as broad an l audience as possible. WG meetings will be open to the public and will be held in the Washington, DC area. NRC will fund the travel and per diem costs for i the OAS co-chair and two additional 0AS members. The CRCPD liaison is welcome '

to attend all meetings but NRC will not fund the travel costs.

I Persons attending WG meetings will be welcome to provide comments to the WG for its consideration in either written form or orally at times specified by the WG, co-chairs. A public workshop will be held to enable stakeholders to participate more directly in this process. The WG will be responsible for i developing a plan for the workshop. NRC will provide the logistical and associated funding support for the workshop. The workshop will be held in the

DC area.

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Appendix C: JOHN DUKES' JANUARY 20, 1996, PROPOSAL ABB January 20,1996 l

Mr. Joel Lubenau USNRC Of5ce of Nuclear Materials Safety and Safeguards M/S T-8FS Washmgton, DC 205554001 l

l Ref; NRC/ Agreement State Working Group - Radioactive Materials in the Scrap Stream ,

l

Dear Joel & Working Group Members:

l 1

Thank you for the opportunity to be a panelist at the January 18-19, 1996 public workshop in Rockvine. I felt this was a very productive session. I was pleased with the positive response to the 6-point proposal I presented for reducing the potential of radioactive sources and devices from accsdentally getting into the metal scrap and other public waste streams. There appeared to be a strong consensus among the interested parties that this could be a viable approach to achieve improved ac:ountability and control of sources and devices containing radioactive materials.

I gave you a pnnted copy of the 6-point proposal which I presented. This was in a very abbreviated form. I thought it might be useful for the Working Group if I expanded this outline with more detailed recommendations, some of which we did not discussed at the meeting. (Some of these details were in my letter of January 2,1996). The expanded proposal is attached for your further consideration.

I hope this more detasted proposal will be helpful in your ongoing review and finalic.cc,,n.c.endations to the Comtnession. Since NORM and NARM have been identified as problems in this issue I would hope that the NRC could at least recommend these materials be included in the national data base.

This would facilitate the effort of agreement states in exercis'mg greater control over these non-AEA radioactive materials.

Sincerely, (Jack) R. Dukes Director Nucleonics and Radiological Operations waconos.coc ABB Industrial Systems Inc.

"*o Unaso" CoewmiuL Ohm 43202-1502

!Mooo n  !OE.rir,

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a NRCIAGREEMENT STATE WORKING GROUP PUBUC WORKSHOP  ;

January 18-19,1996 ,

Panenst Jack Dukes ABB Industrial Systems Inc. 1 Issue: improper skapa==8 of radroachve matenais (RAM) and donces containing RAM that (1) result in entry of RAM into the metal scrap recychng streams and then being acadentally smoked (primanly an economic issue) l (2) represents potenhal health & safety hazards to indmduals involved and the public. l Cause. Primarily an accountability and control problem

[An awareness (or lacdc of awareness) problem that results in unedentified, I l r*ps.me, lost, abandoned, and stolen dowcas/ sources. Dismcentives may l l also contnbute to wiuful improper ,sepnang ,

1) Inadequate inventory control of RAM & devices contamang RAM (2) Improper disposal of RAM & devices containsng RAM l l

Recommended Solution:

(1) Require alliconeses to mamtaan current records of aH RAM in their panamammq and aH RAM that has been transferred or otherwise n'apaad of. l

- aR GL as wet as au SL licensees under NRC and agreement state junsdicbon

- all radioactsve matenais, incdoding NORf I & NARM l -inantory records to show devsee name, model number, and serial number (if

apphe=hia) and manufacturer, source form; source serial number; isotope, quanthy, and j date of manufacture; device / source use and whether fixed or portable; physacal locahon(s); date of last locobon venficahon; name of person venfymg its locahon; an l transfers or disposals of devicas/ sources to other licensees; and the name of the current radiologicaey responsible person (and a backup person).

- the *radiologicany responsible persons' can be anyone in authonty who has responsibitty for complying with radiological reguiabons and license condibons such as the radiation safety officer, the plant safety officer, the firm's regulatory compliance officer, L- t t- =P corporate olhoers, etc.

-inventory records to be available at at times for inspechon by regulatory auttoities.

(2) Require at licensees to perform narm-annual physical mventones

- must account for an inventory dumges since the last physical inventory and report any unresolved descrepancies to the appropnate authonbes maat .sto NRC01188. doc i

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- physecal irwentones might lopcally be done in conjunction with the requwed penodic source leak testing and radiological safety feature checks of devices (shutter mechanisms, ON-OFF indicators, shielding, labels, etc.).

-if the radeologicat inspectens, physmalinventory and inventory records are done under 3rd party service contracts, the licensee (RAM possessor) must G-:": f.+

complebon and concurrence with the results by affhnng signature of the radmiogmany responsible person or backup persort (3) The regulatory authonty (NRC) must identify the radiossotopes and quantibes which are to be of regulatory concem for annual reporting (see point (4) below)..

(4) Requre al licensees to report annualhr to their appropnate regulatory authonty

- as a manwnum, they must report au devees/ sources which are of regulatory concem ,

(see point (3) above). [From the broader concem of accountatulity and control of RAM l for health and safety of the public it would be desirable to consider reportmg all RAM i that could get into the various waste streams and the environment.]

- report rnust include the cummt inventory, and al transfers to other licensees, disposals, '

methods of disposal, etc. since the last annual report. '

- report must also include the names of the current radelopcaly responsable persons (pnmary and backup).

- reports should be in a standardized format suitable for electrone transfer or, if on paper,

=d=hl= for scanrung and electronic processang

-if these reports are w,a= 1 and submitted under 3rd party service contracts, they '

must be venfied/authentested by the radelogicaNy responsible person (or backup) of the licensee possessmg the RAM and idenbfy the mennce orgamtsbon sutmthng the report.

(5) Make this a Category 1 level requrement for comandituhty hahween the agreement states and the NRC.

(6) Regulators must maintain a current database and anforce the rules

- a single nabonal regestry of devees/ sources should be implemented and contaen aN of the information identsfied in point (1) above.

- using a 3rd party to maintain the data base was suggested by George Brown, Ohman Corp., at the public workshop This might ease NRC manpower and priority issues and facilitate joint fundmg by aR involved regulatory agencies (federal and state)

- the data base program should be ev=hi of findmg disaepancies between consecutive inventory reports sutmutted by each licensee; detechng differences between the manufacturer's and destributor's quarterly GL distribubon reports and the licensees inventory reports; and, prepanng reports for follow-up review and schons by the appropnate enforcement agency.

. follow up with licensees could be by phora, mail, visit or other means which is determined to be appropnate on a case-by-case basis.

Ass: .lRD 2- 91RC011ss. OOC 42

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- Related requirements:

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  • good communications between vendors, customers, regulatory agencies, and other l

stakeholders

  • proper incentwes for regulatory compliance and removal of disincentwes

!

  • appropriate penalties for norH:ompliance  :

1

  • means of funding l

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Appendix D: TABLE OF ISOTOPES TYPICALLY USED IN DEVICES Table D.1

_ Table from March 5,1996, Meeting IS0 TOPE EXT. INT. QTY DISP Ty COST OVERALL 30.71 x1000 (mci)

Cs-137 H M H M H H H 10 H-3 L L H L M L L 1000 Co-60 H L H L M H H 1 Am-241 L H H H H H H Cm-244 M H H H H M H Ni-63 L X L L H X L 10 Ir-192 H L H L L H M 10 Sr-90 M H M M H H H 0.1 I-125 L M L L L M L 1 PU-238 L H H H H H H Kr-85 L L H L L L L 100 Pm-147 L L L L M L L 10 Po-210 L X M L L L L 0.1 Legend for Table D.1 H - liigh M - Medium L - Low X - Unknown EXT. - potential hazard from extemal exposure to the material.

INT. - potential hazard from internal exposure to the material.

QTY - typical quantity of the isotope when used in a device.

DISP - availability of disposal.

T - half-life of the isotope.

COST - costs associated with clean-up and disposal from incidents involving the isotope.

OVERALL - the overall rankmg assigned to the isotope based on the six factors identified.

44

__7_

Appendix E: CRCPD SURVEY' RADIOACTIVE DEVICE WORKING GROUP QUESTIONNAIRE The Working Group reviewed information from a number of sources.

They included; steel manufacturers, metal scrap processors and users of the radiological devices potentially encountered in scrap and waste streams. To. approach a solution, the working group separated the problems into three groups. They are  !

inadequate accounting, improper disposal and orphaned devices. '

The working group also attempted to identify devices of greater  ;

concern and developed a table with assistance from agreement state and vendor participants. ,

Inadeounte accountino includes the loss of devices due to inaccurate inventories or no inventory.

Imoroner disoosal includes the disposal, knowingly or unknowingly, so that a device reaches an area that is no longer controlled to prevent exposure to members of the public. This may be non radiation workers within plants where devices are used or areas outside the boundaries of the facility where the source was to be used.

Orohaned devices include sources that are no longer in the.

control of a person licensed to possess or use them.

The following survey questions are categorized to address each of the problem areas. Please indicate a Yes, No or Undecided '

response by marking the box after each question with a Y, N or U.

Feel free to use the space between statements or the back of the page for comments.

KEY:

Y = YES C = MADE COMMENT N = NO  ? = ASKED FOR CLARIFICATION i U = UNDECIDED 1,2,3 = COMPATIBILITY LEVEL RECOMMENDED l 0 = NO RESPONSE Inadequate accountability:

The following applies to devices identified as " higher concern".

l Do you agree with the following statements?

1. Semiannual inventories would improve accountability.

Y=12 N=1 U=1 l

45 I

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- . .-. - - - - - - ~ _ _ - - - . - - -.

f

~~

2. Annual reporting of inventories to regulatory agencies by '

users would improve accountability.

Y=12 .N=1 U=1

3. Users must maintain current inventory records.

Y=14 N=0 U=0

4. General licensees must assign a Radiologically Responsible Person and a backup as contacts. l (The duties of the RRP will be to assure accuracy of '

inventory, sign off on or perform leak tests and report i inventories and losses.)

Y=13 N=1 U=0 1

5. The durability of the label on the device should meet or l exceed the durability of the device.

l Y=11 N=1 U=2

6. The label should contain the currently required information and a serial number. l (Current rules require, on the label, instructions and  ;

precautions for safe installation, leak test requiremencs, j testing on-off system, radioisotope, activity, date of assay  !

as well as a statement indicating the devices are under NRC I and Agreement state jurisdiction, that labels are to be l maintained in a legible condition, removal of labels is prohibited. the words " caution - radioactive material" are to be included and the name of the manufacturer or initial transferor.)

Y=14 N=0 U=0

)

Improper Disposal:

Do you agree with the following statements?

7. Annual reporting of inventories should be required of users.

Y=13 N=0 U=1 '

8. Users must be able to demonstrate proper disposal or pay penalty.

Y=12 N=2 U=0 j i

46

9. Regulatory agencies should review reports of device l transfers and receipts.

Y=13 N=0 U=1 i -

! 10. Users should provide worker training to improve knowledge of health and safety risks, penalties for violations, identification and locations of devices.

Y=10 N=0 U=4 l

11. Distributors should provide disposal information to include options, costs, etc. to users at the time of initial transfer.

Y=13 N=0 U=1 Manufacturers and some agreement state representatives have suggested the creation of a national inventory for the devices included in the WG recommendations. The database for such an l inventory would receive reports from regulatory agencies and would identify discrepancies from previous submittals.

In light of the preceding suggestion, do you agree with the following statements?

12. A national database is necessary to adequately track devices in distribution.

Y=5 N=6 U=3

13. A national database would benefit state regulatory programs' attempts to track devices?

Y=10 N=1 U=3

14. A national database for tracking devices of higher risk should be established by the NRC.

Y=8 N=3 U=3 Anticipated Orphaned Devices:

Do you agree with the following statements?

15. In addition to current labeling requirements, labels l conspicuously identifying the device as radioactive should l

be affixed to devices in the most likely visible location if the device is lost.

l Y=11 N=0 U=3 47

-..; . - - . - - . ~ . .. . . . - . . - , -

l. .*
16. Labels should be permanently affixed'to the device, e.g., l embossed, engraved, etc. and the strength and durability of  !

the label must meet or exceed that of the device. '

i Y=1F N=2 U=1 )

1

17. Innocent " finders" of orphaned devices should not be )

required to take responsibility for possession,-storage and/or disposal of radioactive materials. l' Y=14 N=0 U=0 '

NRC should take the lead in the followinc oronosed solutions-

, 18. Arrange for manufacturer to recycle or DOE / EPA disposal of orphaned sources (can be accomplished via MOU between NRC,.

DOE and EPA).

Y=13 N=0 U=1

19. A fund should be established to pay for disposal of orphaned i l

i sources under certain circumstances, Y=12 N=0 U=2

20. Develop nonuser training recommendations to improve safety  !

and recognition of devices. The Institute of Scrap Recycling Inc.(ISRI) has done this for its membership, but its members do not include all recyclers.  !

l Y=13 N=0 U=1 The Working Group, with assistance from some agreement state representatives and vendors, attempted to derive a table expressing the isotopes and factors of concern for radioactive. l devices. The resulting table attached to this page is the result of the participants' work experience in dealing with radioactive devices.

The table represents isotopes'of concern versus factors of concern and ranks the isotopes as high, medium or low level of concern.

The fact. ors of concern are:

EXT. EXP. = external exposure INT. EXP. = internal exposure QTY = quantities most commonly encountered DISP DIFF = Disposal difficulty l T1/2 = half life COST DISP = cost of disposal l

48 l

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.6 The Working Group has also attempted to identify activities of concern at this time two options are being considered. One is to use 1000 times the exempt quantity limits in 30.71 (10 CFR 30.71) and the other is to use 1 mci for the isotopes in the table with i a limi.t to be determined later for the transuranics. '

Please review the attached table and respond to the questions following it:

-= =

.j ISOTOPE EXT. INT. QTY DISP Tn i COST OVERALL 30.71 i EXP. HXP. DIFF DISP RATING x1000 l (mci) 'l CS137 H M H M H H H 10 CO60 H L H L M H H 1 AM241 L H' H H H H H -

SR90' M H M M H H H 0.1 PU L H H H H H H' -

IR192 H -L H L L H M 10 H3 L L H L M L L 1000 N163 L X L L L X L 10 I125 L M L L L M L 1 KR85 L L H L L L L 100 PM147 L L L L M L L 10 PO210 L X M L L L L 0.1 l-i ALL _

TRANS i LEGEND:

H = HIGH M = MEDIUM L = LOW

! X = UNKNOWN l

21. Do you agree with the Working Group's ranking of isotopes of concern? Please indicate changes you would make.

Y=14 N=0 U=0

22. Do you agree with the " Factors of Concern"? Please indicate your suggested changes.

Y=12 N=1 U=1 49 ll

_ . _ . . _-- _ ~ _ _ _. -- . - _ - - _

23. What suggestions would you make for activities of concern?

Y=4 N=0 U=0 O=5 C=5 24.- What other suggestions would you make?

O=9 C=4  ?=1 f The questions and statements above lead to a possible set of recommendations that would address the three problems stated at the beginning of this questionnaire.

25. What comments would you offer relating to implementation of the implied solutions.

< O=3 C=9  ?=2 The following questions are an attempt to gather information on issues for the solutions we have identified.

Compatibility with NRC rules is a major concern for these recommendations in terms of the way states accept and implement them because due consideration should be given to the transboundary impacts of placing radioactive devices into interstate commerce.

26. In light of the above statements, what compatibility level would you recommend?

1=3 2=9 3=1 C=1

27. With individual states taking independent action to control the problems mentioned at the beginning, do you feel that this would lead to one state's rules effectively overriding another state's rules when devices cross state boundaries?

4 Y=4 N=5 U=1 C=4

28. What other reciprocity issues do you see as concerns?

Y=1 N=0 U=0 O=9 C=4 4

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l 50

Appendix F: OVERSIGHT PROGRAM COSTS AND EXPECTED BENEFITS Costs Table F.1 includes the overall costing for NRC, AS, and licensees to develop and implement an oversight program for certain devices. The WG has determined  !

that both general- and specific-licensed devices incorporating the isotopes l listed in Table 2 included in Section 5.8 must be subject to the oversight program. The costing and benefits in this appendix are based on regulation of these devices. The WG estimates that 24,000 general licensees, possessing a l

total of 90,000 devices, and 6,000 specific licensees, possessing a total of  !

36,000 devices, would be subject to the increased oversight program. In addition, approximately 50 vendors would be subject to increased requirements.6 i l

Table F.1  !

Estimated Costs of Increased Oversight Programs j NRC AS Affected Totals {

($) ($) Licensees ($) l

($) l A. First Year of 985,000 2,400,000 0 3,385,000 j Implementation '

B. Annual Operating Costs 246,000 492,000 4,305,000 5,043,000 C. Annual Operating Costs 6 6 34 40 l per Device (B./ Number of Devices)

D. Annual Operating Costs 25 25 144 168 per Licensee (B./ Number of Licensees)

The WG estimated that it will costs NRC $75,000 to setup its initial database. '

It is estimated that it will cost each AS $20,000 for this activity. The WG estimates that during the first year of implementation of this program approximately 25 percent of the licensees will not respond or will provide an inadequate response and another 30 percent will call the regulators for technical assistance. During the first year, regulators must expend l

$2.73 million (based on a rate of $54/ unloaded hour) of additional resources to follow up with these licensees. It is estimated that two-thirds of the cost will be expended by AS since there are aoproximately twice as many AS licensees as NRC licensees.

' Estimates of affected licensees are based on information from the NRC general license database and information from a 1990 survey of NRC specific licensees.

51

o -

The annual operating costs for NRC and AS are based on the WG's estimate of the time required for each agency to compare annually users reported inventories against its records and to update its listing of users' inventories. The annual operating costs for affected licensees are based on the WG's estimate of the time required for each user to assign an RI and BRI, perform semi-annual inventories and inspections, maintain current inventory records, annually report inventories to regulators, and report changes in RI and BRI and transfers of devices to regulators. It also includes an estimate of the time required for vendors to provide disposal information to potential users and meet the additional labeling requirements. The costs were determined using a rate of $48/ unloaded hour for licensees.

Benefits Both exposure and property benefits may result from increased oversight of device users. In 1987, NRC issued a contract to ORAU to determine the likelihood of exposure associated with improper transfer or disposal of general-licensed devices. ORAU estimated exposure savings from additional oversight of devices and concluded, in part, that there was a potential for significant doses from several types of general-licensed devices.

In 1991, the Commission suggested a peer review of the ORAU study. Another contractor, PNL, performed a peer review of the ORAU study, which concluded that the ORAU study provided a good start for assessing worst-case consequences of improper transfer and disposal scenarios for general-licensed devices. However, PNL showed that the study did not provide an adequate basis for regulatory decisions for the following reasons:

The study did not include probabilities of the scenarios occurring on a per device, per year basis; The study did not include a complete enough enumeration of the numbers of devices, and the distribution of source activities, within each category of device; and The study did not include the probabilistic distributions of outcomes needed to assess realistically assess the probable human health consequences of such scenarios.

PNL attempted to address the shortcomings of the ORAU study but concluded that it had neither enough information nor adequate time and resources to predict doses expected from an accident resulting from improper transfer or disposal of a general-licensed device.

The WG reviewed both stuaies and concluded the following:

The conclusions of the ORAU study were conservative due to the reasons cited by PNL.

The PNL study provides an appropriate method for determining likely exposures associated with loss of control and accountability of devices but additional work in this area is needed. .

52

Neither study accounts for the probability or consequences of loss due to property damage.

From the data available, the WG concluded increased oversight of device users will-result in significant savings both for property and the environment. An estimate of the radiation exposure savings and property damage savings is included in Table F.2.

Table F.2 Estimated Annual Exposure and Property Damage Savings Number of Number of Number of Average Average Byproduct Years Smeltings/ Costs / Annual Material (1983-1995) Year Smelting 7 Savings Smeltings Prcperty 20 13 1.54 $8,000,000 $12,320,000 Damage Savings to Steel Mills 8 Average Maximum Average Maximum Annual Annual Dose Annual Dose Annual Annual Savings From From Savings Savings Incidents Incidents Exposure 7 rem 1053 rem $14,000 $2,106,000 $14,000-Savings for (70 mSv) (10.53 Sv) $2,106,000 1 Devices Containing Cesium-137,  !

i Annual $12,334,000- 4 Savings: $14,426,000 l l

Table F.2 is an estimate of the savings that may result from increased l oversight. The following should be noted about the estimates: '

The estimates for radiation exposures are from the preliminary analysis i included in the PNL study. PNL provided the analysis to demonstrate its I methodology and has indicated that further review and calculations are necessary.

7 the average cost is based on smeltings that have occurred. It should be noted that cost could be as high as $100 million if a larger integrated I steel mill smelted a source.

a from a database maintained by James Yusko.

' PNL, " Peer Review of Improper Transfer / Disposal Scenarios for Generally Licensed Devices," June 1994.

53

9 Factors that may increase the estimated benefit include property damage savings by metal mills as a result of not smelting a device and intermediate costs savings as a result of fewer lost sources.

- T.he average costs / smelting is based on smeltings that have occurred.

All- of these smeltings were at small steel making facilities. With larger steel mills now using more r' ecycled materials, .the probability of a larger steel mill smelting a source will increase. It is estimated that the average costs (including costs for facility decontamination, facility down-time, and costs for material disposal) for a larger

integrated steel mill smelting a source could be 5100 million.

[ -

The PNL study concentrated only on a sample of NRC general-licensed e devices. Exposure estimates to the public would increase if the study included all general-licensed devices, all specific-licensed devices, and all AS devices.

The exposure savings included only estimates for incidents involving cesium-137. The WG's recommendations included increase oversight for other isotopes that may be ir.volved in incidents.

The exposure savings were from the analysis included in the PNL report.

Although the United States has never had an exposure from an out-of-control source that caused death among a large population, worldwide, individuals have received high exposures due to loss of a device. The pathways taken by the devices after loss of control and accountability have been similar.

As examples of loss of control and accountability, a cobalt-60 teletherapy unit was removed from storage in Ciudad Juarez, Mexico. It was disassembled and sold to a scrap yard. As a result, the source was breached, causing exposures to some workers and the public and significant contamination of metal products from the thousands of millimeter-sized pellets containing radioactive material. In this case, a limited study by the ORAU of 10 workers and residents using blood chromosomal aberration techniques showed that the most likely doses received by these individuals ranged from 0.13 Gy (13 rad) to 5.5 Gy  :

(550 rad).

In 1987, a cesium-137 source was breached in Goinai, Brazil, and the {

resulting dispersion of the cesium chloride powder (the physical form of '

the isotope) contaminated a large portion of one district of the city l and caused at least one death attributed to radiation exposure as well l as radiation injuries to others.'"

Other factors that may affect the dose savings:

i i

l' Lubenau, J. O., and Yusko, J. G. , " Radioactive Materials in Recycled i

Metals, " Health Physics, Vol. 68, p440 (April,1995).

54  ;

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Metal manufacturers and recyclers are becoming more aware of the ,

problems associated with loss of control over and accountability for devices and the effects these have on their industry. The use of radiation monitors and programs to identify sources is becoming more

-common. This cautious approach of monitoring should decrease the number '

of smeltings but still represents a significant cost to the industry.

The oversight program implemented by NRC and AS will not be 100 percent effective at stopping loss of control and. accountability of devices.

Some devices are already lost and carry the possibility of causing exposures or property damage.

Comparison:

Table F.3 - Costs Comparison i Year NRC AS Licensee Total Benefit 0 1,231,000 2,400,000 4,305,-)00 8,428,000 14,426,000 1-10 246,000 492,000 4,305,000 5,043,000 14,426,000 Present Worth 1,728,000 3,456,000 30,236,000 35,420,000 101,322,000 Flow of Total

, Funds years 1_lo n Present Worth 2,959,000 5,856,000 34,541,000 43,848,000 115,748,000 Flow of Total l Funds 0-10" years l

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" Based on Regulatory Analysis Guidelines of the U.S. Nuclear

Regulatory Commission, NUREG/BR-0058, Revision 2.

55 l

Appendix G: ESTIMATED COSTS OF DISPOSAL OF A SOURCE The following is an estimate of the costs of disposal of a 37 GBq (1 Ci), i cesium-137 sealed source at a waste disposal site. The costs were provided in  ;

June 1994 by a. waste disposal site.  ;

Estimated Costs j

($)  !

Pre-encapsulation Drum 600.00 I

Pre-encapsulation Charge 250.00 1 Transportation )

7,134.00  :

(based on 1000 miles one-way)

Broker Charge _ 2,600.00 Out of Compact Surcharge 1,650.00 Disposal Charge 7,405.50 TOTAL: 19,639.50 t

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Appendix H: TEXAS RADIOGRAPHY INCIDENT On February 27, 1996, two cobalt-60 cameras and an iridium-192 camera were stolen from a location in Houston, Texas. The company it in bankruptcy and the sources had been impounded in place by the Texas Department of Health, Bureau'of Radiation Control (BRC). The Ir-192 had decayed to minimal .

activity. The Co-60 cameras, one large, 755 kg (1665 lbs), and one small, 286 kg (631 lbs), contained 1.3 TBq (35.3 Ci) and 0.32 TBq (8.6 C1) of Co-60 respectively. The following chronology of events occurred after the devices were stolen.

February 27, 1996 -- The three individuals who stole the cameras stripped the i cameras of their caution radiation labels and took the cameras to a scrap l metal dealer (A) where they were sold as scrap. The dealer sold the small 00-60 camera to a second dealer (B) the same day.

February 28, 1996 -- Dealer A sold the large Co-60 camera to Dealer B. The  :

Ir-192 camera remained at Dealer A. Dealer B determined the cameras were not j stainless steel. ,

I February 29, 1996 -- Dealer B shipped both co-60 cameras to a third scrap dealer (C) in a large load of scrap. Dealer C has radiation detectors at i their plant entry and detected the radiation from the cameras. The manager of dealer C and his two assistants were not at the site when the cameras arrived.

A trainee was on duty when the cameras arrived. They segregated the cameras 1 from the rest of the scrap shipment and returned the cameras to dealer B informing them that the cameras contained radioactive materials.

The large camera's lock box, holding the pigtail and the 35.3 curie Co-60 source, was torn loose by a forklift as it was being loaded onto a pallet for loading onto a truck at dealer B for return to dealer A on the afternoon of the 29th. The lockbox, with pigtail and source, was loaded on to the pallet with one of the forks of the forklift. The exposed radioactive source and lock box remained on the pallet with the cameras.

4 Dealer B attempted to return the cameras to dealer A on the afternoon of February 29th, but the site had closed for the day. The manager of dealer A showed up and the dealer B driver informed him that the cameras were radioactive and that dealer B was returning the cameras. The dealer B driver i returned to his facility and parked the truck containing the cameras and the '

exposed source in a remote area of the scrap yard.

March 1,1996 -- Dealer B returned the cameras to dealer A. While unloading the cameras from the truck, the lock box and source fell through the pallet and remained on the truck. It was then picked up by the driver, at the source capsule, and thrown to the side after the cameras were unloaded. It was then kicked under the corner of the office building located at dealer A. by an employee. Neither individual was aware that what they were handling and l kicking around was an unshielded source.

l l The owner of dealer A was told that the cameras were radioactive. He then

( sold the large camera, without the source inside, to another scrap yard (D) 57

p and sold the small camera, with the source inside and shielded, to a fifth I scrap dealer (E) without advising anyone that the cameras contained -I radioactive materials. Dealer E in turn sold the small camera to another recycling co. (F). The manager was unaware that the Co-60 source was on the ground at his scrap yard. The BRC was never notified by any of these companies that they were in possession of radioactive sources. I March 5, 1996 -- The 1.3 TBq.(35.3 Ci)'Co-60 source remained unshielded at dealer A until March 5,1996, where it was located by BRC Health Physicists at i 1:30 pm. The_ scrap yard was evacuated and secured and the source was l recovered and secured later that evening. Eleven adults and two children were exposed to high levels of radiation at the scrap yard and one adult from .

dealer B was exposed when he transported and handled the camera and source. l Five Houston Police Officers were exposed to low radiation levels when they )

conducted interviews at dealer A. Dose assessment of the incident are l

. included in' Table H.1.

]

I Table H.1 l DOSE ASSESSMENTS OF THE INCIDENT Estimated Dose (mSv) (rem)

Scrap Yard Owner 180 18 l Scrap Yard Manager 530 53 Scrap Yard Manager's Wife 550 55  ;

Two Children at Scrap Yard 390 39 .

I Workers at Scrap Yard 150 15 Customers at Scrap Yard 1.6 0.16 j A Scrap Yard Worker - wholebody: 5.0 0.50 l

- extremity: 25,000/30,000 2500/3000  ;

Police Officers 5.0/30 0.5/3  ;

i In this case, BRC was notified by the Texas Natural Resources Conservation  :

Commission, which was working at the site of the bankrupt company, that the  !

door from the building where the devices were stored was removed. Upon investigation, BRC determined that the three devices had been removed. On  :

March 4,1996, BRC issued a news release that was highly publicized by the i local media. This assisted in BRC eventually locating the devices. i l

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4

l NRC/ AGREEMENT STATE WORKING GROUP TO REVIEW DEVICES CONTAINING RADI0 ACTIVE MATERIALS Minutes for March 5, 1996 1

The Working Group (WG) session began with an overview of incident data by Joel '

Lubenau. The data included known source meltings in the U.S. and worldwide, which included about 1700 documented detections of radioactivity at scrap yards and steel mills in the U.S. Most of these are NORM. 168 are Atomic i Energy Act materials (AEA). Issues included the obvious disincentives that  !

now are associated with NRC licensed materials. l Attendees reinforced the fact that stakeholders have no regulatory incentive l for identification and recovery of renegade sources that are found during the l scrap metal recycle process. As compared with other hazardous materials and l

their responses, some Agreement States' and the NRC's response automatically '

pronounces the possessor ' guilty' before any research can show that there was 1 or was not a hazard.

The overview of this meeting included a review of previous presentations at WG i meetings and discussion of the WG charter. Co- Chairs Lubenau and Free explained the focus of the working group, which included impacts of the source i meltings, discoveries of devices in scrap recycling facilities, and '

disincentives for proper disposal of radioactive devices. These topics have been recorded and can be reviewed in previous meeting minutes.

Much of the information was included in a background information paper i (attachment 1) originally prepared for the Public Workshop in January 18-19, l 1996 and provided to the participants in this meeting.

Strawman proposals had been presented in earlier meetings and workshops by working group members: '

Robin Haden, who described the North Carolina GL program; i Bob Free, who presented Texas' general licensee acknowledgement (GLA) I program; Rita Aldrich, who provided the WG with copies of New York's proposed licensing plan for GLs; and Martha Dibblee, who presented Oregon's device licensing and registration program.

Bob Free presented and discussed Jack Dukes' proposal to the Group. This proposal was suggested at the public workshop in Washington, D.C. in January and was widely accepted by the panelists and participants. During the presentation, par _ticipants asked a number of questions related to accuracy of the Oregon information, start up problems, and cost and fee considerations.

Martha Dibblee presented a description of the Oregon program, which includes both Specific License (SL) and General License (GL) devices. She discussed in some detail associated " start up" costs and fees associated with the implementation of this program. As stated:

In 1995, Oregon began licensing and registering each measuring, gauging, or

1 controlling device (" device" means both specific and general license devices, excluding those that produce light or an ionized atmosphere) in the state.

Each device, either licensed (specific license device) or registered (general license device) in the state was charged either a license or registration fee.

The fees did not impact the licensing aspect of the program because initially they provoked an intense negative response from General License device manufacturers.

The Oregon Plan required approximately 1.5 FTE to develop fees and create a database of devices, which now tracks both physical locations and revenues.

1.5 FTE now are supported from revenues generated from license and registration fees. The Oregon Plan appears to have met the accountability criterion, which stakeholders put high on their agenda of recommendations.

Oregon's license fees for specific license devices are $174 per device for fixed gauge specific license; $464 for portable gauge specific license; $116 for specific license XRF or ECD; and $100 for general license ECD, fixed gauge, or ECD. All portable devices are specifically licensed, regardless of their SS&D status.

As background, Oregon began mailout inspections (self-inspection) to GLs and SLs over 10 years ago. Mail inspections of general license XRFs and gauges, and specific license portable and fixed gauges were done approximately biannually. Oregon observed that this frequency (of contact) was essential in retaining current inventory, use, and management information among licensees.

Inventory information received from mail inspections was collected for follow up for discrepancies.

Jack Dukes' proposal (attached 2) recommended a system of regulation to bring radioactive device inventories under a national database that would track device inventories for ALL radioactive materials.There was no specific proposal on the table for implementing this database, but it was assumed that the NRC would take the lead in developing it. The scope of the database required additional discussion.

The proposal recommends:

1) ALL licensees maintain current records of all radioactive materials in their possession, that those records contain specific information identifying the radioactive source and device, the name of the person verifying its location and name of the radiologically responsible person (RRP);
2) ALL licensees conduct semi annual physical inventories. In the case of third party inventories require the RRP to acknowledge and concur by affixing signature;
3) The regulatory authority must identify the radioisotopes and quantities which are to of concern for annual reporting;
4) All licensees report inventories to regulatory authority annually including current inventory, transfers disposals and method of disposal since last report, name of current '

, and 3rd party inventories i verified by RRP;  !

5) Should be category I level of compatibility;
6) Regulators must maintain a current database and enforce rules.

The proposal explained the scope of the recommended database and suggested that a third party could manage it. The proposal further recommended that the database should be capable of finding discrepancies in inventory reports, detecting differences between the manufacturers' and distributors' quarterly GL distribution reports and the licensees inventory reports and preparing i reports for follow-up review and action by appropriate regulatory agency. l The preceding is not a complete reproduction of the proposal and the attachment should be reviewed to understand the complete scope of the recommendations. 1 The working group, with participation of representatives from agreement states and device manufacturers, discussed the need to prioritize devices into those of concern for being encountered in the public sector. Joel Lubenau devised a chart (attachment 3) that listed several isotopes including cesium-137, cobalt-60, iridium 192, iodine 125, strontium-90, americium-241, and some others. Radium-226 was not on the list because the WG only is addressing Atomic Energy Act materials.

The workshop group ranked isotopes by hazard category. Hazards included cost  :

of disposal and decontamination as well as health risk. They were ranked as high, medium or low relative hazard. The hazard categories included internal and external exposure, half life, difficulty of disposal in terms of cost and l availability of disposal facilities, and activity. By using this l participatory method, the group came up with a scheme that ranked the isotopes '

according to their relative concern. Highest on the list were cesium-137 and cobalt-60. Iridium-192 was next because of the activity of some of the sources that may be encountered. Strontium- 90 was included because of the internal hazard and americium-241 because of its internal hazard and the 1 difficulty of disposing of it.

l This was a brainstorming session to get a ranking that most could agree on.

However, the participants agreed that a pathway analysis and risk assessment should be performed to refine the list and determine the activities of l concern.  ;

The next discussion dealt with identification of devices and sealed sources.

Possible improvements in labeling were discussed to determine whether l improvements could be made to make devices more easily recognized when l encountered in the public sector. The discussion then centered around the definition of " device". Some devices are contained in housings that, if labeled, would not contribute much to identification. Some devices have associated equipment attached that create the same set of problems. The discussion did not resolve the definition, but helped clarify the labeling issue so that it could further be address by the WG.

The discussions then addressed the unique identification of sealed sources and devices to make them more easily tracked. The participants seemed to agree that unique identification was necessary. Bryan Baker of Amersham pointed out that some of the sources were too small to engrave. Don Bunn from the state of Cali.fornia suggested a bar code marking on the devices that would be made durable. Another idea included an " explosive charge" that would release a dye if sources were crushed. The working group will attempt to address labelling in its recommendations.

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NRC/ AGREEMENT STATE WORKING GROUP TO REVIEW DEVICES CONTAINING RADI0 ACTIVE MATERIALS

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] Minutes of the 4th Meeting of the Working Group - March 7,1996 j

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1. Call to Order j The meeting was called to order on the morning of March 7, 1996. Joel Lubenau !

announced that he was leaving the working group to take a position on the  !

staff of Commissioner Greta Dicus. Mr. John Lubinski would assume the position of co-chairman. This action would be formal on Monday, March 12, 1996. Effectively, beginning at this meeting, Mr. Lubenau allowed Mr. i j Lubinski to assume the role of co-chair.

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2. Registration Program i Implementing a system to register devices will be costly. The State of Oregon implemented a registratior program. The costs were significant and 20 percent to 40 percent of the general licensees (GLs) did not initially respond.

Should NRC implement a nation-wide registration system, the agency would have

. to follow up on the non-responses. This could be costly. Although NRC is a j j 100% fee-recoverable agency, Congress must approve NRC's budget. This means  !

j an increase in budget may not be approved. Many questions remain on how to implement and maintain a registration system.

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Under what regulatory level of compatibility should a registration  ;

system be implemented and maintained?  ;

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Should the registration system be maintained by the NRC or a non-

governmental organization?

How would a non-governmental organization be funded?

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Should the licensees supprrt the system?  !

What sealed sources or devices should be included in the registration system?

What information about the devices should be reported? l Should the registration system be implemented only for new devices or i should it be retrofitted to existing devices?  !

l' 2.1. Compatibility A registration system must be uniform and compatible among the Agreement States. The level of compatibility will be a large issue. However, some  ;

Agreement States, and the industry, may not want to collect information that 1 has no readily apparent use.

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i 2.2. Funding Several vendors had no objections to small fees being added to the cost of their products. A fee for each device may get a user to think about getting or keeping'a device; some devices are-in storage and not in use. A way to get an idea of-the funding necessary to maintain a system is to construct a mathematical model of costs. Spreading the costs in an equitable way will be difficult. A fee on a device is not only to register a device but to follow-up on other lost devices. But should a licensee pay for the mistakes and carelessness of anothsr licensee who may not even be in business anymore?

Direct fees might be charged for follow-up. The cost of follow-up includes both the cost of finding who is responsible and the cost of finding the device. Organizations who are irresponsible with devices should be paying more than a' responsible organization. These costs are approximately

$125/ hour. Charging a fee for follow-up and inspections would make the licensees more responsible. For NRC to impose a fee, formal changes to regulations would have to go through the rulemaking process. It is fair to charge whoever made the mistake of failing to report or of losing a-device.

Another aspect of the cost issue is the extent to which to bring a problem through the regulatory process. Each discovery of a problem should not have to go through an enforcement action; the regulators should be allowed some enforcement discretion.

The American Iron and Steel Institute said that the costs of a registration system are minuscule compared to the cost of an integrated mill smelting a sealed source. The costs to a mini-mill have ranged from $2 million to $23 million. While an integrated mill has not smelted a sealed source, the estimated cost is $100 million.

2.3. Devices to Register Determining which devices to register is difficult. Only devices containing AEC material would be registered because that is what NRC is charged to regulate; radium would not be registered, even though it can be a problem.

Most devices- are self-luminous exit signs and static eliminators. Registering all devices, even exit signs, is less cost effective for both licensees and regulators. However, from a regulatory view, losing even an exit sign indicates neglect. Devices should be registered according to some, as yet undefined, priority. The Working Group made a first attempt at identifying these devices at the March 5,1996, Agreement State technical workshop. But there is no reason to spend resources on registering devices that pose little risk. Following up on a report of even a lost exit sign can be costly, or it can be as little as the cost of a telephone call.

At one of .the sessions of the Agre'ement State technical workshop on March 5, 1996, a non-mathematical assessment of " risk" was done. In general, devices were ranked as followsl :

"Co > 132Cs > "Sr > TRU But phasing in a registration system by device, not by radionuclide, would be easier than by radionuclide, for both the vendors and the users.

The problem with assessing risks is that the risks of the same device may differ from one population to the next. Krypton is not a hazard to the steel mills. However, devices containing krypton should be to registered because dose rates can be high. There was an incident where, at a plastic extruding facility, a krypton device was taken apart; the source was placed on a desk, leading to unnecessary exposure.

i SL Gauges Also Are a Problem There is a disparity across the nation on how states deal with GL gauges.

A part of the solution to improving controls is to have annual reporting.

At a facility, an radiation safety officer insisted that a nuclear gauge had been removed. An inspector insisted on seeing the location where the i gauge had been. After an hour of searching for keys to an old building, the gauge was found on an old pipe. .

l The criteria for assessing risks or hazards needs to be examined. Maybe the working group will be unable to decide upon an exhaustive list of criteria or a ranking of risk. Maybe only recommendations can be made.

Regulations need to include existing devices. However, registering devices that are already missing will be difficult. To do this a licensee had to know of the device, know that it is missing, and know that the missing device needs to be reported. But retrofitting a registration system would find at least some of the lost devices and prevent other from being lost. NRC has given consideration to a bounty program as an interim measure to find lost devices while the rulemaking process occurs. The objections were that the draft bounty program had the finders of devices (e.g., the steel mills) establishing a fund to reward a person for finding a source and paying for disposal.

Static eliminators present a problem for registration because of their short half-life compared to the suggested reporting interval of a year.

2.4. Location of a Registration System Idaho National Engineering Laboratory might be a choice for maintaining a registration system. The laboratory currently is developing AEOD's system for recording events, the Nuclear Material Events Database.

I see minutes from the March 5,1996, Agreement State technical workshop meeting.

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2.5. Implementation Establishing a registration system will take years. A nation-wide system will have to be phased into operation. During the phase-in period, problems requiring regulatory action will be encountered. But a way to implement the program without high start-up costs in some form is not evident. The State of Oregon took 10 years to establish their registration system; the system appears to be paying off in one form or another. Maintenance costs have come down from the start-up costs.

Another benefit of a registration system is a basis for determining devices to inspect. A list of devices can be randomly sampled. From the sample, inspections can be arranged. Given the outcome of the inspections, the extent to which there is compliance can be determined.

2.6. Model Registration System A registration system that was discussed is in Reference 1. The reference discusses what should be done as a minimum. The term minimum has regulatory significance.

The registration system should also record transfers of the sealed sources themselves. The sealed source is the hazard, not the device. But placing a identification number on the sealed source may be difficult for two reasons:

Some are sealed sources are small.

Reading the serial number off of a sealed source would require locating a facility that can do the work.

2.7. Summary GLs should pay a " fair share".

GLs and specific licensees (SLs) should pay some costs for follow-up.

How much should NRC/ States pursue a problem when it is no longer cost effective?

l The working group needs to make recommendations in general terms and identify details that need to be worked out.

NRC must recover costs.

The working group needs to decide if registration system is to be l forward looking or retrofitted.

The working group needs to determine which licensees and which devices to register.

The beginning of a registration system can be the records of vendors l

A registration system will be phased-in to use

3. Insurance Options The working group attempted to involve the insurance industry with little success. A steel mill that smelted a devi .e was insured by Lloyd's of London; the claim was paid and the staff person of Lloyd's who issued the policy was let go from the company. Reasons for asking insurance companies to

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' ' " I participate in the working group are as follows An insurance company might write a rider to defray the cost of disposal. l Insurance companies may place financial pressure on scrap yards and steel mills.by giving discounts when monitors are used. Many small i scrap yards are reluctant to invest in expensive monitoring equipment.  !

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Many companies are self-insured, such as U.S. Steel, Honeywell. and 3M. l Integrated mills are self insured because of large premiums. Insurance boards  !

are not interested in insurance as a solution to the problem of radioactive  !

material is scrap metal. The Steel Manufacturers Association (SMA) is looking into joint. insurance. In general, insurance companies fear accidents with '

radioactive material; they do not give out information on paid claims.

Amersham Corporation belongs to an association that explored getting under the

Price Anderson Act.

i 4. Nuclear Gauges Using Exempt Sources ,

i A company was distributing nuclear gauges without the sealed sources. The l user would then go to a source distributor and obtain exempt sources. NRC had questioned the vendor, who claimed that there was nothing in the regulations  !

l to preclude this practice. The NRC Office of the General Council agreed with l

r the vendor. and the NRC is bound to the interpretation of its legal staff.

A licensee cannot physically combine check sources. Check sources can be l stacked (not legally viewed as combining). NRC allows stacking of sources, l l

J e.g., during storage, l l 1 l

The risk from exempt sources is much lower than the risk from GL and SL I l sources. But the practice of stacking exempt sources is of concern ~to the NRC l for other reasons besides risk.

A nuclear gauge with exempt sources may be a concern because it would yet contain, say 100 mci, of radioactive material. NRC's Office of Research is looking into the hazard associated with this practice.

Check sources, like other benign sources such as refractory brick, create false alarms during monitoring, increasing the difficulty in detecting hazardous sealed sources.

1 Many stacked exempt source may contaminate the furnace dust of small mills to unacceptable levels.

The WG agreed not to address the issue of exempt sources. I

5. Removing Disincentives for Disposal i David Stewart-Smith, Administration of Energy Resources, Oregon Department of

{ Energy, and Oregon's delegate to the Northwest' Compact, discussed how the 1

compact might be of some use in addressing the problem of radioactive material '

j in scrap metal. The State of Washington leases land from DOE. Part of this i j {  !

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land is leased to U.S. Ecology, which operates the compact for the State of Oregon. Operators of the Oregon compact are regulated by the state utility commission. The Hanford facility is regulated, so disposal costs will stay down. The Hanford site in Washington State has a long term arrangement; the Barnwell site, in North Carolina, has a year-to-year arrangement. The fees at the Hanford facility are determined by both the volume and the activity of radioactive material. Licensees in the State of Oregon pay because there are no general state funds for this purpose.

A means to manage a general fund would have to be established. This too could be discussed with the compact. A general fund could be maintained by licensing fees, as the SMA proposed. Formal rulemaking would be needed to impose a fee.

The compacts cannot help in short term, especially for states not having access to a compact. Opening a compact to non-member states defeats the purpose of a compact. Mr. Stewart-Smith will ask the compact about accepting devices on a case-by-case basis during an emergency. The conditions under which devices would be accepted would have to be clearly defined.

Examples of difficulty of disposal include the following:

A Sr-90 source was found on the floor of a tavern. The State took possession of the source at no charge to the tavern. The disposal cost to the tavern ownar could be significant. This might be a case for the compact to accept the sealed source.

A bank may own a company going into receivership. The cost for disposing of the source might be considered a part of the liquidation cost.

If a resident were to come out of their home in the morning for the l newspaper and find a bomb on their front lawn, they would call the 911 l

emergency number. The authorities would come and take the bomb away, asking only enough questions to complete a policy report.

If the same person were to find a device that had been improperly l disposed, the authorities would tell the resident to cordon off the l area. The resident would be issued a possession-only license, but the licensing fee would be waived. The resident would have to pay for disposal.

While the story exaggerates the difficulty of disposing radioactive material, it underscores the lack of a system to readily address the problem.

Waste compacts have provisions for emergencies. DOE is called to take a device only when there are no other options and it presents an eminent threat to health and safety.

If a state, for example Oregon, can respond easily, then the state will do so.

Large sealed sources are another matter because they are difficult to shield.

l.e Two concerns are securing an uncontrolled source and then disposing of it.

Disposing may be less expensive that trying to find the owner of an sealed  ;

source having a serial number if there is a general fund to pay the costs.

Getting to a facility with a hot cell that will look at the sealed source, and paying for the work, may be expensive. ,

l Who_should pay for disposal? The victim, e.g., the scrap dealer, should not pay. The disposal cost to a state is not the same as the cost to the NRC. A l state is a small fraction of the problem. NRC represents a much large

! jurisdiction. Because equity is a problem, and everyone benefits from the use ,

and safe disposal of devices, NRC might pursue getting general funds to l dispose of devices. t l Disposal might also be funded with a bond that is purchased at the time a device is purchased. This would give some assurance of funds being available l for disposing of a devices should a licensee become bankrupted. Utilities are i responsible for decommissioning. But NRC is not responsible for funding  !

disposal.

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6. Review of the Charter i ihe working group has gathered much information. The next question is what to do with the information. The Commission expects a report by the end of June )

1996. The current schedule is very tight. The working group should not slip '

the schedule, as delays will de-emphasize the importance of the report. All aspects of the final report should be referenced. The issues that need to be addressed are as follows:

NRC and Agreement State Compatibility Cost and fees considerations Expected reductions in radiation exposure Design of devices Devices effected by regulatory changes Disposal Identification and labeling of devices Other issues are accountability and what to do about orphan devices.

The working group needs to determine if it has enough information to discuss the problem and make recommendations where possible. Although the problem was stated in the meeting of October 1995 (Ref. 2), constraints need to be discussed, given the information that has been collected. The working group needs to establish assurances that something obvious has not been overlooked.

For example, a registration system, such as in Reference 1, addresses future orphaned devices, but not currently orphaned devices. More discussion will be needed, such as the possibility of converting some GL devices to SL devices.

Guidelines on the form of the recommendations need to be established.

Compatibility may be difficult to address. If tt.e Commission agrees with the recommendations made by the working group, the staff will have to develop a l rulemaking plan. Workshops can be conducted to introduce the plan. The 1

workshops would have to address why recommendations are at a specified level of compatibility. Unless compatibility issues are addressed, the process will i not work. States will need time to phase in programs, such as a registration  ;

system, due to the expected high implementation costs. l

References:

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1. Letter from John (Jack) R. Dukes, Director, Nucleonics and Radiological Operations, ABB Industrial Systems, Inc., to Joel Lubenau, USNRC, Office i of Nuclear Materials Safety and Safeguards, dated January 20, 1996.  !

Re: NRC Agreement State Working Group--Radioactive materials in the Scrap Stream. l l

2. Minutes October 1995 WG meeting.  ;

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" Working Group Members'and' Mailing List-August- 29,'1996 i

A-Robert Free; Co chair ,

Bureau of Radiation Control, '

' Robin Haden, Engineer, Low Level Radioactive 4

' Texas Department' of Health Waste .

i 1100 West 49th Street Division'of Radiation Protection . -)

L Austin, TX 78756 3189 Department of Environment, Health'and Natural-1 Resources-

' P.O. Box 27687 Raleigh, NC 27611-7687

' ~ = Martha Dibblee' Rita Aldrich

-Radiation Protection Services Radiological Safety Unit State Health Division New York ~ State Dept. of Labor Dept. of Human Resources . NYS Office Campus, Bldg.12, Room 457 800 N.E. Oregon St. - Albany, NY 12240 i i

Portland, OR 97232 j L i l

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James Yusko. .

James Richardson  :

Field Operations Radiation Protection Nuclear Safety Attache  !

Department of Environmental Resources U.S. Mission to.the UN System Organizations'  !

400 Waterfront Drive Obersteinergasse 11/1 '

Pittsburgh, PA 15222 4745 1190 Vienna '

Austria l-I I

l i l James Collins, President .

Michael Mattia i

Steel Manufacturers Association Institute of Scrap Recycling Industries i 1730 Rhode Island Avenue NW 1325 G Street'NW i Washington, DC 20036 Suite 1000

[ Washington, DC 20005 3104 1 '

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1 L Walt:r M. Rebovich James R. Schlaegle i Electric Metal Makers Guild Koppel Steel I

c/o A..Finkl and Sons P.O.-Box _750 l

-308 N. Westminster-Beaver Falls, PA 15010 i

Palatine IL 60045 '

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Stev2 Lsrick Tony LaMastra Structural Metals, Inc. 1005 Old Route 22

! P.O. Box 911 Lenhartsville, PA 19534 1

! Sequin, TX 78155 '

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Carlos Stern Stan Huber i Carlos Stern Assoc. Stan A. Huber Consultants l 1406 N. Johnson St. 200 North Cedar Road  !

Arlington, VA 22201 New Lenox, IL 60451 1

1 Dennis Clark Rob Roy Marion Environmental Adaptive Technologies, Inc.

'.1914 Polymer Drive 5330 D S metrum Drive Chattanooga, TN 37421 Frederic(, MD 21.703 Elsa Nimmo Duane C. Hall Measurex Corp. 3M Company l

One Results Way 3M Center, 220 3W 06 Cupertino.CA 95014 P.O. Box 33283 St. Paul, MN 55133-3283  ;

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I Mary Dedola Ralph S.-Heyer l Apgee/Berthold Systems, Inc. TN Technologies Inc. 1 103/101 Cor> oration Drive

  • 2555 North IH 35

-Aliquippa, 'A 15001 4863 Round Rock, TX 78680 0800 1

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i George Brown J. David McGraw i Ohmart Corp. NRD Inc.  !

4241 Allendorf Drive 2937 Alt Blvd.

Cincinnati, OH 45209 Grand Island, NY 14072 1

l Fred Axmacher John Meaney

DMC Beveradge & Diamond 4 P.O. Box 490 1350 I Street NW  !

l Gaithersburg, MD 20884 Washington, DC 20005 l l

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Bryan Baker Ed Worden Amersham American Metal Market i 2636 S. Clearbrook Dr. 825 7th Avenue Arlington Heights, IL 60005 New York, NY 10019 l

I Shih Yew Chen John R. Dukes  !

Environmental Assessment Division ABB Industrial Systems Argonne National Laboratory 650 Ackerman Road 9700 South Cass Ave. Columbus, OH 43202-1502

Argonne, IL 60439 4832 i

._ _ _ _ . _ . _ _ - m _. ._ .

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Gari Borras

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Pat Pausta, News Director Pan American Health Organization . Technical Association of the Pulp and Paper

'525 Twenty third Street, NW' Industry-Washington, DC 20037-2895 15 Technology Park South Norcross, GA 30092 Mary Norton Terry Bradway. >

Steel Recycling Institute, Inc. Environmental Manager Foster Plaza American Steel Foundries 680 Anderson Drive P.O. Box 2060 ,

Pittsburgh, PA 15220-2700 Alliance, OH 44601-0060 Thomas J. Benton Seymour Epstein Chief Metallurgist Aluminum Association, Inc.

American Steel Foundries 900 19th Street NW P.O. Box 2060 Washington, DC 20006 Alliance,.0H 44601-0060 ,

Genevieve Roessler Editor Charles Hardin HPS Newsletter CRCPD Rt. 1 Box 139H 205 Capital Avenue ,

Elysian, MN 56028 Frankfort, KY 40601 '

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Charles Meinhold James Dacey l

NCRP Auburn Steel Radiological Sciences Div P.O. Box 2008 Building 703M Auburn.NY 13021 Brookhaven National Laboratory Upton, NY 11973 l i l

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i Dr. Lenhard-J. Holschuh .

Dr. Veys  !

International Iron and Steel Institute Bureau International de la Recuperation  !

Rue. Colonel Bourg 120 Rue du Lombard i B 1140 Brussels j

. 24 Bte'14 ,

Belgium B 1000 Brussels Belgium

' David B1ackwell Joseph Damiano l l

Auburn Steel ALC0A  !

i P.O. Box 2008 1501 ALC0A Building, Room 636 I

' Auburn, NY 13021 Pittsburgh, PA 15259 l

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i i- Holmes Brown Chet Thompson Afton Associates Collier, Shannon, Rill & Scott 236 Massachusetts Ave., NE 3050 K Street, NW Washington, DC 20002 Washington, DC 20007 James Turner James Schultz AmeriSteel Corporation North Star Steel Co.

P.O. Box 31328 P.O. Box 21 700

, Tampa, FL 33631 Eagan, MN_55121 i

l Clifford Borland Paul Frame NS Group Inc. ORAU P.O. Box 1670 P.O. Box 117 Newport, KY 41072 ,

Oak Ridge, TN 37831 0117 i

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-James Will " Bruce Clemens-Specialty Steel Industries of the' U.S.

1055 Thomas Jefferson Street NW Energy, Environment & Resources Center

' University of Tennessee )

l- Suite 308 326 South Stadium Hall l Washington, DC 20007 Knoxville, TN 37996 0710

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Gerald Hanson James Todd, Jr.

WHO,. Chief of Medicine Birmingham Steel Corporation 1211 Geneva 27 1000 Urban Center Parkway t

Switzerland Suite 1000 Birmingham, AL 35242 2516 t i L l

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Ray Turner Jerry Balbo The David J. Joseph Company Chaparral Steel i 300 Pike Street 300 Ward Road l Cincinnati, OH 45202-4214 Midlothian. TX 76065 9651 )

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.4 Donovan A. Smith. Paul Dobson J 4821 Bel Pre Rd. Factory Mutual Research Corporation j

! Rockville, MD 20853 1151 Boston Providence Turnpike  !

Norwood, MA 02062 l l

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l Holly McKnight Kenneth Feldman NDC. Systems Executive Vice President 730 East Cypress Ave. Ohmart Corp.

Monrovia, CA 91016 4241 Allendorf Drive Cincinnati, OH 45209 l l

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John Quattrocchi John R. Cox Sr. V.P. for. Liability Exploranium American Nuclear Insurers 264 Watline Ave.

Town Center. Suite 300S Mississauga 29 S. Main Street L42 1P4 West Hartford, CT 06107 Canada Peter Hernandez Larry Keating American Iron & Steel Institute NRD Inc.

1101 17th Street NW 2937 Alt Boulevard Suite 1300 Grand Island, NY 14072 Washington, DC 20036 4700 Donnie Dicharry Elmer Eisenhower Source Production and Equipment Corporation 32 Lakeview Circle 113 Teal Street Hanover, PA 17331-9308 St. Rose, LA 70087 9691 Susan J. Engelhardt Dr. Donald Hoops, Executive Director Engelhardt & Associates American College of Occupational &

2800 South Fish Hatchery Road Environmental Medicine Madison, WI 53711 55 W. Ceegers Road Arlington Heights, IL 60005 3919 Tim Fisher, Manager, Government Affairs William R. Prendergast American Society of Safety Engineers LFE Industrial Systems Corporation 1800 East Oakton Street 55 Green Street Des Plaines. IL 60018 2187 Clinton, MA 01510

Dr. Zorach Glaser Board of Certified Safety Professionals American Conference of Governmental Industrial 208 Burwash Avenue Hygienists Savoy. IL 61874-9263 1330 Kemper Drive Cincinnati OH 45240 513 742-2020 Association of Iron & Steel Engineers HYL 3 Gateway Center Ave. Munich 101 Suite 2350 San Nicolas de los Garza Pittsburgh, PA 15222 NL 66452 Mexico Midrex Direct Reduction Corp. Iron & Steelmaker Charlotte Plaza 410 Commonwealth Drive Charlotte NC 28244 Warrendale, PA 15086 Steel Tires International FMJ International Publications Limited Queensway House Surrey RH1 108 England Terry Strong, Chair Charles !4. Hardin. Executive Director Organization of Agreement States Conference of Padiation Control Program Division of Radiation Protection Directors. Inc.

Department of Health 205 Capital Avenue P.O. Box 47827 Frankfort, KY 40601 Olympia, WA 98504-7827 s

Thomas G.~Hobbs William Dornsife Occupational Health & Safety Division ACURI

.NIST Bureau of Rtdiation Protection Gaithersburg, MD 20899 Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105 8469

f Michael T. Ryan Carl Amlanes Chem Nuclear Systems Isoto m Products Laboratories -

100 Murray Vista Circle 3017 4. San Fernando Blvd. .

Lexington, SC 29072-7624 Burbank, CA 91504 '

4 Bruce Terry Robert G. Gallaghar 1 Toled.yne Brown Engineering Applied Health Physics,-Inc 50 Van Buren Avenue 17 Park Avenue Westwood, NJ 07675 1235 E. Greenbush, NY 12061 Kimberly Page Charles T. Gallagher US Ecology NSSI/ Recovery Services 109 Flint Road P.O. Box 34042

! Oak Ridge. TN 37830 Houston, TX 77234 l

l i Gerald Houck Pamela Russell =

l U.S. Bureau of Mines USEPA/0RIA 6603.J

' . Branch of Metals 401 M St. SW .

MS-5208 Washington, DC 20460 i

l Mary Clark John Karhnak USEPA/0RIA USEPA 401 M St. SW 410 M Street SW 4

Washington, DC 20460 Washington, DC 20460 l i

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Wendell Carriker Stephen Warren Radioactive Materials Branch. 0HMT Office of Program Integration, ER U.S. DOT U.S. DOE 400 Seventh Street SW Washington, DE 20585 Washington, DC 20590 Catriona Maloney M. Raul Ortiz Wast:s and Impacts Division Gerencia de Seguridad Radiologica Atomic Energy Control Board Comision Nacional de Seguridad Nuclea y P.O. Box 1046, Station B Salvaguardias Ottawa Ontario K1P SS9 Canada Dr. Barragan Bo. 779 - ler. Piso Vera Kegley Col. Narvarte U.S. Customs Service Delgacion Benito Juarez 1301 Constitution Avenue NW 03020 Mexico, D.F. Room B-102 Mexico Washington, DC 20229 John Jacobus Gary Robertson National Institutes of Health Nuclear Research Corporation Radiation Safety Branch 125 Titus Road l Bethesda, MD 20892 Warrington, PA 18976 l

Jos:ph M. Greco James L. Hoey, Jr.

> Eastman Kodak Company Valmet Automation (USA), Inc.

Building 320 3100 Medlock Bridge Road Kodak Park Suite 250 Rochester, NY 14652 6261 Norcross, GA 30071

Richard F. Murphy Randy S. Stevens Eurotherm Gauging Systems Integrated Industrial Systems, Inc.

900 Middlesex Turnpike 475 Main Street Building 6 Yalesville, CT 06492-1723 Billerica, MA 01821 3930 t

William R. Pendergast Michael L. Green ,

LFE Industrial Systems Corporation Union Carbide Corporation 55 Green Street P.O. Box 8361 Clinton, MA 01510 South Charleston, WV 25303 i

Gary L. Caines Carl E. Miller Honeywell Factory Mutual Research 1190 West Druid Hills Drive Northeast 1151 Boston Providence Turnpike Atlanta, GA 30329 1266 P.O. Box 9102 Norwood, MA 02062 Eli A. Port Jill Lipoti RSSI Radiation Protection Programs 6312 W. Oakton Street Department of Environmental Protection Morton Grove, IL 60053 2723 CN 415 Trenton, NJ 08625 0415 t

George P. Brozowski Air & Waste Management Association ,

USEPA Region II Gateway One Third Floor  !

290 Broadway 21st Floor Pittsburgh, PA 15222 New York, NY 10008-1816 c -,

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Aluminum Association. The Gary Mosher 900 19th Street, N.W. Suite 300 American Foundrymen's Society. Inc.

' Washington, [K: 20006 505 State Street 4 Des Plaines, IL 60016-8399 American Galvanizers Association, Inc. American Gear Manufacturers Association 12220 East Lliff St. Ste. 204 1500 King Street, Suite 201 Aurora, CO 80014 Alexandria, VA 22314 2730 American Institute of Steel Construction. Inc. American Iron Ore Association One East Wacker Drive 915 Rockefeller Bldg.  !

Suite 3100 614 Superior, Ave., West Chicago, IL 60601-2001 Cleveland, OH 44113-1383 l

l American Mining Congress. American Society of Mechanical Engineers. The Suite 300 United Engineering Center 1920 N. St. N.W. 345 East 47th Street Washington, DC 20036 New York, NY 10017 l

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, American Welding Society ASM International 550 N. W. LeJeune Rd. 9639 Kinsman Road l

Miami, FL 33126 Materials Park, OH 44073 0002 i

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l ' Association of Iron and Steel Engineers - Association of Steel Distributors 3 Gateway Center 401 N. Michigan Ave.

Suite 2350- Chicago, IL. 60611 4267 Pittsburgh, PA 15222 '

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Association of Women in the Metal Industries Association Techniques de la Sderurgle 1 (AWHI) -Francaise L National Headquarters lle de France P.O. Box 519 4, Place de la Pyramide

! Artesia, CA 90702-0519 Cedex 33 92070 Paris La Defense. France ASTM Casting Industry Suppliers Association (American Society for Testing & Materials) P.O. Box 286 1916 Race Street Greendale, WI 53129 Philadelphia, PA 19103 l

I Chinese Society for Metals, The Concrete Reinforcing Steel Institute l 46 Dongsixi Dajie 933 N. Plum Grove Road i Bejing 100711,. China Schaumburg. IL 60173 4758 l l

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Electric Metal Hakers Guild, Inc. EPRI Center for Materials Production The P.O. Box 368 Carnegie Mellon Research Institute Eighty Four, PA 15330 0368 Pittsburgh Technology Center 700 Technology Drive Pittsburgh, PA 15219 L

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- Fbrging Industry Association Industrial Heating Equipment Association Suite 300 1901 N. Moore Street  !

, 25 Prospect Ave., West Arlington, VA 22209 '

i Clevaland, OH 44115 l

Institute of Electrical & Electronics Institute of Materials, The

Engineers. Inc. (Formerly The Metiss Society and The 345 East 47th Street Institution of hetallurgists)

New York, NY 10017 1 Carlton House Terrace l London SW1Y SDB, England t .

l Instituto Latinoamericano del Fierro y Acero Iron and Steel Institute of Japan, The '

(ILAFA) Keidanren kaikan, 3rd FL l

Casilla 16065 9 4, Otemachi 1-chome, Chiyoda ku Santiago, 9 Chile Tokyo,.100 Japan i

i Iron and Steel Society Japan Iron and Steel Federation, The  !

, 410 Commonwealth Drive Keidanren Kaikan, 9 4, 1 chome Warrendale PA 15086 Otemachi Chiyoda ku Tokyo, Japan i

i l Jernkontoret Material Handling Industry, The Box 1721 Seite 201 S 11187 Stockholm, Sweden 8720 Red Oak Blvd.  :

Charlotte, NC 28217 4

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l Metal Treating Institute National Slag Association 302 Third Street, suite #1 900 Spring Street Neptune Beach, FL 32266: Silver Spring, MD - 20910 '

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National Society of Professional Engineers Refractories Institute. The i 1420 King Street Suite 326 Alexandria VA 22314 500 Wood Street Pittsburgh, PA 15222-2408 i

Refractory Metals Association Research Institute of Industrial Science l 105 College Road East Technology (RIST)

Princeton, NJ 08540 32 Hyoza dong Pohang 790-330 i Republic of Korea l

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Society of Automotive Engineers, Inc. Society of Tribologists and Lubrication  !

400 Commonwealth Drive Engineers (STLE)  !

Warranedale, PA 15096 840 Busse Highway  :

Park Ridge, IL 60068 2376 l 1

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i South East Asia Iron & Steel Institute Steel Founders Society of America .

GP0 Box 7094 Metals Federation Bldg. l 40702 Shah Alam 345 State Street l 1 Selangor Darul Ehsan Malaysia. Des Plaines, IL 60016 l i

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9 teel Recycling Institute Verein Deutscher Eisenhuttenleute Foster Plaza 10 Postfach 10 51 45

680 Andersen Drive D 40042 Dusseldorf Germany Pittsburgh, PA 15220 Sohnstrass 65 D 40237 Dusseldorf, Germany 1 \

Wire Association International, Inc., The John Masaitis P.O. Box H - 1570 Boston Post Road American Iron & Steel Institute i Guilford, CT 06437 c/o USX US Steel Group 600 Grant Stre -

Pittsburgh.PA 15219 I

Bill Mills, President Robert Cam) bell Health Physics Society U.S. DOE, EM 36. Trevion 2 2915 Ascott Lane 19901 Germantown Road Olney, MD 20832 Germantown, MD 20874-1290 Don Faulkner Stan Huber United Steelworkers of America Stan A. Huber Consultants Center for Worker Health and Safety 200 North Cedar Road 329 Race Street New Lenox, IL 60451 Cincinnati, DH 45202 815 485 6161

, Richard Parham Gordan Banks 600 H:nley Street American Industrial Hygiene Association l Knoxville, TN 37996 2700 Property Avenue Fairfax, VA 22031

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l l m l M chael J. Wright- Kurt Thaus

United Steel Workers of America Waste Management, Inc.

l Five Gateway Center 3003 Butterfield Road Pittsburgh, PA 15222 Oak Brook, IL 60521 I

John Cignan . Dade W. Moeller, Ph.D. I Horsehead Industries 147 River. Island Road i

4th Street & Franklin Avenue New Bern, NC 28562 Palmerton, PA 18071 Gary L. Caines Michael L. Green Honeywell Union Carbide 1190 West Druid Hills P.O. Box 8361 Atlanta, GA 30329 So. Charleston, WV 25303 Pierre Brodeur Richard Byrnes Institute of Paper Science & Technology Crucible Specialty Metals 500 10th Street NW P.O. Box 977 Atlanta, GA 30318 Syracuse, NY 13201 i Floyd Galpin Tom Harrison l Rogers & Assoc. Engineering MrGraw Hill l ' 7204 M111 crest terr. 1200 G Street NW L Derwood, MD 20855 Suite 1600

! Washington, DC 20065 l

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l Kent Kiser Tim Knapp

! ISRI Afftrex, Lmd.

1325 G St NW 600 State Street Suite 1000 Suite 201 Washington, DC 20005 Clairton, CA.15025 Mike Phillips Holmes Brown Jupiter Corp. Afton Associates 2730 900 University Blvd. West 403 E. Capital St. SE Wheaton, MD 20902 Washington, DC 20003 Michael Taylor Executive Director Kenneth L. Miller, Editor National Association of Demolition Contractors Health Physics

-16 N. Franklin Street Hershey Medical Center Suite 200B Hershey PA 17033 Doylestown, PA 18901 3536 l

1 William Morris Patrick Mark Moscato Naval Sea Systems Command Detachment U.S. Army Center for Health Promotion Radiological Affairs Support Office (RAS 0) and Preventative Medicine P.O. Drawer 260 MCHB DS HP  ;

NWS Yorktown, VA 23691-0260 APG, MD 21010 5422  !

l John Feeney Lee Leonard l New Jersey Dept of Environmenta' Protection USD0E RPP/BER/RMS 12800 CN415 Middlebrook Road Trenton,'NJ 08625 0415 Germantown, MD 20874 l

, l Bbb Walker Ramney Koul Aromic Energy Control Board Office of Radiation Control 280 Slater Street Dept. of Public Health Ottawa Ontario P.O.B. 637 .

l K1P SS9 Dover, DE 19903 1

Canada l

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l Ray Manley Phillip A. Olson i Radiological Health Program U.S. General Accounting Office MD Dept. of Environment 7007 Kepner Ct.

! 2500 Broening Highway Lanham, MD 20706

Baltimore, MD 21224 i l

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l David Stewart-Smith Donald Bunn )

Nuclear Safety and Energy Facilities Division Radiologic Health Branch  ;

625 Marion Street, NE State Department of Health Services i Salem, OR 97310 0830 601 North 7th Street Sacramento, CA 9418 0208

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< Jerry O. Richartz Joseph E. Goodwill l Corporate Manager / Environment & Energy EPRI Center for Materials Production l Oregon Steel Mills P.O. Box 2950

- 14400 North Rivergate Boulevard Pittsburgh PA 15230 2950 P.O. Box 2760 l Portland, OR 97208 l

Bryan' Baker John Preston N&B Associates Measurex Corp.

1435 S. County Road 17 One Results Way Berthold, CO 80513 Cupertino CA 95014 s

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'Ghris Stacey, Environmental Manager. Ralph Heyer

~ Steel Manufacturers Association .TN Technologies, Inc.

'1730 Rhode Island Ave,.NW #907 2555 North IH-35 Washington, DC 20036 PO Box 800 Round Rock, TX 78680-0800 Carey A. Johnston Scott Robertson US EPA American Metal Market Radiation Protection Division 3 Gateway Center, Suite 1899 401 M Street, SW (6603J) Pittsburgh, PA 15222 Washington, DC 20460 Reid Harvey Shawn Seeley US EPA Department of Human Services Mail Stop 6603J #10 State House Station 401 M Street. SW Augusta, Maine 04333 Washington, DC 20460 Rodriguez Harrell Steven Baggett Department of Natural Resources USNRC Atlanta Transport, Suite 114 Office of Nuclear Materials Safety &

4244 International Parkway Safeguards

' Atlanta, GA 30354 l-CherylBarnes Paul Goldberg I USNRC USNRC

Office of Nuclear Materials Safety & Office of Nuclear Materials Safety &

Safcguards

! Safeguards a

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%n . Cool Fred Combs  !

! USNRC- USNRC.

NHSS 2 NMSS l 'T:8F5 M/S T 8F5 l

t Paul Lohaus Howard Larson USNRC USNRC ]

Office of State Programs ACNW M/S 0 3D23- M/S T-2E26 l

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! Patricia Holahan Hector Bermudez

USNRC USNRC 1 NHSS Region II M/S T 8F5 101 Marietta Street NW Suite 2900 Atlanta, GA 30323 0199 i

Jack Hornor Lloyd Bolling NRC/RIV/WCF0 Office of State Programs M/S 0 3D23 i

l' John Telford William Lahs Office of Nuclear Regulatory Research M/S T 8F37 M/S T 9F33 l

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Chtherine Mattsen- . . Christopher Ryder  :

Office Nuclear Regulatory Research' -0ffice Nuclear Regulatory Research M/S T-9C24 M/S T-10E50 i

Carl Paperiello R. Joseph De1 Medico M/S T 8A23 Office of Enforcement ,

M/S 0 7H5 l

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Sue Gagner Richard Bangart Office of Public Affairs Office of State Programs M/S 0 2G5 M/S 0 3023 l

Samuel Pettijohn Maria Schwartz l M/S T-4A9 Office of the General Counsel '

M/S 0 15B18 l

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i i Francis X. Cameron Joel Lubenau Office of the General Counsel USNRC M/S 0 15B18 M/S 0 16G15

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! h utron Products, Inc. Roy F. Weston.-Inc.

! ATTN: Alice Cleveland ATTN: Mark Hiller i

22301 Mt. E)hraim Road Suite 800-Dickerson, 10 20842 6501. Americas Parkway. NE .

- Albuquerque, NM 87110 1517-i R. R. Goodwin-

' Ohio Department of Health l

l BurGau of Radiation Protection l :. 35 East Chestnut Street

! Post Office Box 118 l . Columbus, Ohio 43266 0118 i

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