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# NMSS Licensee Newsletter September 1999 - October 1999

NUREG/BR-0117; No. 99-3
        - Public Meetings on Control of Solid Materials
        - Public Invited to Workshops on Spent Fuel Shipping Container Accident Studies
        - New NRC Fuel Cycle Facility Inspection Program
        - KAY-RAY/SENSALL, INC., Notifies Its Customers About Potential Mechanical Failure on Gauges with Source Housing Models 7062b and 7062bp
        - Revision to 10 CFR Part 35
        - NRC Threat Assessment Program and Threat Analysis Team
        - Significant Enforcement Actions
        Gauges
Medical
Other
Radiography

        - Generic Communications Issued(July 1, 1999-September 30, 1999)
        Administrative Letters (ALs)
Information Notices (INs)

        - Selected Federal Register Notices(July 1, 1999-September 30, 1999)
        Final Rules
Proposed Rules
Notices

## Public Meetings on Control of Solid Materials

On September 15 and 16, 1999, the first of four facilitated public meetings to discuss issues and alternatives related to control of solid materials at licensed facilities was held in San Francisco, California. Attendance at the meeting included representatives from licensees and licensee organizations; the Health Physics Society; the U.S. Environmental Protection Agency; the U.S. Department of Energy; State agencies; scrap and recycling companies; steel manufacturers; sanitary waste facilities; a newspaper; and Indian tribes. There were no representatives from other citizen groups; however a letter from 12 citizen groups explaining why they did not attend was delivered to the meeting and copies were provided to attendees.

The meeting agenda consisted of seven sessions corresponding to the content of the Issues Paper. The first session focused on the need for a national standard for control of solid materials and the process being used. There was discussion on ways to enhance public input, via community meetings. The second session focused on the types of materials and licensees, potential radiation doses, and efforts of other Federal, State, and international agencies and organizations. There were concerns raised about the need to consider naturally occurring and accelerator-produced material as well as mixed-waste issues. There was also a discussion about State, local, and Tribal authorities, and associated constraints. After a discussion of the U.S. Nuclear Regulatory Commission's (NRC's) current approach for handling control of solid materials, several potential alternatives for addressing this issue were discussed. The alternatives identified in the issues paper included: (1) continue current approach; (2) unrestricted use; (3) restricted use: and (4) prohibition. Other alternatives discussed were: (1) adopt the American National Standard Institute standard; (2) combine restricted- unrestricted-use option to allow flexibility; (3) have material-specific controls; (4) use general licensing; (5) use an interim storage facility; (6) have a buy-back program of contaminated materials during first-use processing; and (7) guarantee that a dedicated steel mill is not responsible for financial losses if contamination occurs at the mill from the material received. There were extensive discussions on the potential health and environmental impacts to be considered in addition to the potential economic and cost-benefit considerations. The last session focused on implementation aspects to ensure control of solid materials under various alternatives. There was general consensus among the participants during this discussion that measurement and implementation methods are essential but will be difficult to develop.

The discussions provided useful information that the staff will use as part of developing a paper for the Commission in March 2000.

Additional public meetings were scheduled as follows:

Atlanta, GA, October 5-6, 1999; Crown Plaza Atlanta Powers Ferry, 6345 Powers Ferry Road NW;

Rockville, MD, November 1-2, 1999; NRC Auditorium, 15545 Rockville Pike; and

Chicago, IL, December 7-8, 1999; Palmer House Hilton, 17 East Monroe St.

Current information about this work can be found on the NRC webpage.

(Contact: Frank Cardile, NMSS, 301-415-6185; e-mail: fpc@nrc.gov)

## Public Invited to Workshops on Spent Fuel Shipping Container Accident Studies

The U.S. Nuclear Regulatory Commission's (NRC's) Spent Fuel Project Office is initiating a new study on spent nuclear fuel cask responses to severe transportation accidents. The NRC previously studied this issue in the 1980s (see NUREG/CR-4829 and NUREG/BR-0111-- called the modal study). The modal study looked at possible railway and highway accidents and concluded that spent nuclear fuel cask designs would survive nearly all transportation accidents without releasing radioactive nuclear material. The shipment of spent nuclear fuel in NRC- certified packages has an exceptional safety record of no releases from accidents. However, the NRC recognizes that the characteristics of the fuel and cask systems being reviewed by the NRC have changed since the 1987 study was published, and analytical techniques have also evolved. In addition, a near-term increase in the number of shipments is likely, and this has focused increased NRC and public attention on spent nuclear fuel shipment safety. Despite the previously aforementioned research, NUREGs, and exceptional safety record, some stakeholders may have questions or concerns about spent nuclear fuel transport package safety.

As part of the modal study, over the next few years, the NRC will revisit the conclusions of the 1987 Modal Study, to assure its continued validity. Risk insights obtained using modern analysis techniques, physical testing, and interaction with stakeholders and public, will support the NRC's ongoing efforts to assure that its regulatory actions are risk-informed. Ongoing public interactions throughout this project will help ensure that public concerns are effectively identified and that the project is designed to address these issues.

As the first step, the NRC will conduct two public meetings (planned for November in the Washington, DC, area, and December in the Las Vegas, Nevada, area). The NRC's goal for the meetings is to have open, constructive discussions by stakeholders so that we can listen to, discuss, and better understand any public concerns about spent nuclear fuel transport package safety. Information obtained will be used to further develop this project.

A World Wide Web site is being established for dissemination of project information to the stakeholders and interested members of the public. This site can be found at http:// ttd.sandia.gov/nrc/modal.htm. Additional information on the public meetings can currently be found on the NRC's Web site.

(Contact: Robert Lewis, SFPO, 301-415-8527, e-mail: rxl1@nrc.gov)

## New NRC Fuel Cycle Facility Inspection Program

The U.S. Nuclear Regulatory Commission (NRC) plans to make substantial revisions to its baseline safety inspection program that applies to fuel cycle facilities. The facilities include gaseous diffusion plants, highly enriched uranium fuel fabrication facilities, low-enriched uranium fuel fabrication facilities, and one uranium hexafluoride (UF6 ) production facility. These facilities possess large quantities of materials that are potentially hazardous (i.e., radioactive, toxic, and/or flammable) to the workers, public, and environment.

This initiative resulted from the staff's fundamental reviews of its regulatory program, as part of the "reinventing government" process and consideration of lessons learned, from several NRC initiatives for improving regulatory oversight, including process improvements for oversight of reactors.

The goals are to have objective indications of acceptable and changing safety performance; increase stakeholder confidence in NRC; increase regulatory effectiveness and efficiency; and reduce unnecessary regulatory burden. In this regard, the staff plans to revise the fuel cycle facility safety inspection program to use: (1) a more risk- informed, performance-based approach to focus on the more significant risks at fuel cycle facilities; (2) more objective safety performance indicators (PIs) with accompanying performance thresholds; and (3) NRC safety inspections. The PIs, together with risk-informed inspection findings, are intended to provide an objective and reliable basis to determine if a fuel cycle facility is safe, and provide early indications of declining safety performance. The Licensee Performance Review (assessment) process will integrate information from PIs and safety inspection findings. This will facilitate clear and predictable regulatory decisions such as determining overall safety performance; identifying needed changes in Agency inspection emphasis; and supporting enforcement actions. Corresponding changes in the enforcement program are also under consideration.

A task force consisting of two teams will evaluate and propose inspection program revisions: (1) a program framework development team, consisting of branch chiefs from Headquarters and regions, responsible for fuel cycle facility inspection activities; and (2) an inspection procedure writing team consisting of fuel facility inspectors representing Headquarters and regions. Where appropriate, lessons learned from NRC's ongoing improvement of the reactor oversight process will be used by the teams. The activities of the task force are being closely integrated and involve frequent stakeholder interactions, through public meetings and workshops, to provide opportunities to exchange and explain information and receive feedback. Public meetings are being held on a monthly basis to exchange views concerning the inspection program, its revision, and implementation. Public workshops are planned, so staff can discuss, with fuel cycle facility licensees and other interested stakeholders, development and implementation of the revised inspection program. Inspector training is planned, for implementing the revised inspection program.

(Contact: Walter Schwink, 301-415-7253, e-mail: wss@nrc.gov)

## KAY-RAY/SENSALL, INC., Notifies Its Customers About Potential Mechanical Failure on Gauges with Source Housing Models 7062b and 7062bp

Kay-Ray/Sensall, Inc. (KSI) manufactures a variety of gauging devices for use in industrial applications. Certain U.S. Nuclear Regulatory Commission (NRC) and Agreement State licensees possessing Models 7062B and 7062BP source housings have been experiencing damage to the shutter mechanisms and welds on the mounting plates because gauges were installed in areas where they were exposed to excessive vibration.

Models 7062B and 7062BP should not be installed in environments that exceed the level stated in Method 201A of Military Standard 202F. Models 7062B and 7062BP have been tested and meet this standard. Method 201A states that displacement during vibration is not to exceed 0.1524-cm (0.06-inch) maximum total excursion in the frequency range of 10 to 55 Hertz in each of the three mutually perpendicular directions. If vibration levels exceed these limits, KSI recommends that the gauge be mounted in a manner that isolates the unit from the source of vibration.

In 1992, KSI agreed to provide notifications to all customers with these models to apprise them of the situation; offer retrofit kits to provide additional support to the housing; maintain customer questionnaires about gauge environments; and improve the welds on the source housing. Recently, KSI agreed to provide another notification to customers and regulatory agencies. The Illinois Department of Nuclear Safety is also in the process of amending the sealed source and device registry to include more substantial source housings, vibration monitoring at installation, and permanent tags, on the source housings, warning of vibration hazards.

Third-party service vendors/consultants and gauge licensees authorized to perform their own installations should not install these devices in environments that exceed the specified vibration standards. If you have questions about your process startup/routine operation, or are aware of abuses of this requirement, you should contact your local regulatory agency--the Illinois Department of Nuclear Safety at 217-785-9947, and Kay-Ray/Sensall, at 847-803-5100.

(Contact: Roberto J. Torres, NMSS, 301-415-8112, e-mail: rjt@nrc.gov)

## Revision to 10 CFR Part 35

In a Staff Requirements Memorandum, COMSECY-96-057, "Materials/Medical Oversight (DSI 7)," dated March 20, 1997, the Commission directed the revision and restructuring of 10 CFR Part 35, "Medical Use of Byproduct Material" into a risk-informed, more performance-based regulation. Members of the public, stakeholders, Agreement States, non- Agreement States, and the Advisory Committee on the Medical Uses of Isotopes were given the opportunity to provide input and to discuss the proposed requirements for medical use licensees on numerous occasions. Since August 1997, the staff has held seven facilitated public workshops with stakeholders, four of which were held during the public comment period on the proposed rule, and has made formal presentations at approximately 20 professional society meetings.

Nuclear Regulatory Commission (NRC) staff submitted a paper (SECY-99-201), dated August 3, 1999, to the Commissioners, that provided: (1) draft final rule language for the revision of Part 35; (2) a summary of the public comments received on the proposed rule, the staff's draft responses to the comments, and resulting changes made in the proposed rule; and (3) a comparison of the requirements in the current Part 35, as codified in Title 10, and the draft final rule. NRC staff discussed this document with the Commission on October 21, 1999, at a public briefing. The rulemaking action will be finalized pending further Commission direction.

(Contact: Cathy Haney, NMSS, 301-415-6825, e-mail: cxh@nrc.gov)

## NRC Threat Assessment Program and Threat Analysis Team

The U. S. Nuclear Regulatory Commission (NRC) threat assessment program performs a variety of threat-related activities in support of NRC's primary mission to protect public health and safety. This multifaceted threat assessment program is the responsibility of the Threat Analysis Team (TAT) located within the Office of Nuclear Material Safety and Safeguards. The team is comprised of four people and is on call 24 hours a day. Working with the Office of Nuclear Reactor Regulation and the regions, the team assesses all reported threats involving NRC- licensed facilities or materials (i.e., power or research reactors, fuel cycle facilities, and nuclear or radioactive byproduct materials). NRC TAT also issues coordinated NRC threat advisories to selected NRC licensees when a credible threat is received or there is a heightened domestic threat environment. The team's other operational responsibility involves responding to all reported incidents of nuclear smuggling and trafficking, black-market activities, and scams. On the regulatory side, the team supports NRC safeguards policy review and development and validates NRC Design Basis Threat Statements (10 CFR 73.1). The staff's conclusions about the adequacy of the design basis threat statements, based on the results of interagency liaison and intelligence traffic review and assessment, are documented every 6 months and provided to the Commission. The TAT should be viewed as an NRC-wide resource to support NRC programs and activities, as well as providing support to other Federal agencies.

The team works extensively with the national law enforcement and Intelligence communities and receives hundreds of classified reports, messages, and publications each week from a number of sources on a variety of topics. Agencies with which the team interacts, provides technical support, and exchanges information include: the Federal Bureau of Investigation (FBI); U.S. Customs; Central Intelligence Agency; Defense Intelligence Agency; Department of State; and Department of Energy. The team is currently involved in a number of interagency Federal efforts related to threats and incidents involving the criminal use of nuclear or radiological materials in weapons of mass destruction. These effort were directed by various Presidential Decision Directives and Department of Justice direction. In addition, Title 18, of the U.S. Criminal Code, has been amended and provides punishment for numerous unlawful acts involving any nuclear material or nuclear byproduct material (emphasis added). Byproduct material now also includes accelerator- produced materials in addition to that produced in a reactor, and this significantly expands the jurisdiction of the FBI to investigate cases involving NRC-licensed materials, and increases the need for close coordination between the two agencies.

(Contacts: Roberta (Bobbi) Warren, NMSS, 301-415-8044, email: rsw@nrc.gov; John Davidson, NMSS, 301-415-8130, e-mail: jjd@nrc.gov; or Aaron Danis, NMSS, 301-415-6393, e-mail: aad@nrc.gov)

## Significant Enforcement Actions

Detailed information about these enforcement actions can be accessed via the U.S. Nuclear Regulatory Commission (NRC) homepage. Click on "Nuclear Materials," then "Enforcement," then "Enforcement Actions." Cases are listed alphabetically. To access the complete enforcement action, click on the highlighted text after the name of the case.

**Gauges**

Material Testing Consultants, Grand Rapids, Michigan, EA 98-107. A Severity Level III violation was issued based on loss of a moisture- density gauge that fell from a truck while being transported on a public highway.

**Materials Testing Laboratory**, Inc., New Hyde Park, New York, EA 99-60. A $2750 civil penalty was assessed based on deliberately allowing a field technician to use a nuclear gauge without being properly certified and without wearing appropriate dosimetry.

**Medical**

Aharon Ben-Haim, Ph.D., IAs 97-065 and 97-068. An Order was issued prohibiting Dr. Ben-Haim's involvement in NRC-licensed activities for a period of 5 years, beginning July 31, 1997. The action was based on deliberate actions by Dr. Ben-Haim that caused the licensee to order and administer radiopharmaceuticals without the involvement of an authorized user physician. After a hearing, the Atomic Safety and Licensing Board reduced the prohibition period from 5 years to 3 years.

**Other**

Coriell Institute for Medical Research, Camden, New Jersey, EA 99-060. A $4400 civil penalty was assessed based on discrimination against a former employee for engaging in protected activities. The employee was terminated as a result of raising safety concerns to his management and the NRC regarding unnecessary exposure to employees from the use of phosphorus-32 in a laboratory.

**Medi-Physics, Inc**., Livingston, New Jersey, EA 99-093. A Notice of Violation was issued for a Severity Level III problem consisting of three violations. The violations involved shipment of a package with the gasket and absorbent pad missing from the primary shielding container, and failure to properly label the package and ensure that radiation and contamination levels at the package surface were within the regulatory limits.

**Philadelphia Health and Education Corporation**, Philadelphia, Pennsylvania, EA 99-096. A Severity Level III violation was issued for use of licensed material by an unauthorized individual.

**SibTech, Inc**., Elmsford, New York, EA 99-123. A Severity Level III violation was issued for importing and distributing licensed material without a license.

**Radiography**

Sheila N. Burns, IA 98-067. An Order prohibiting involvement in NRC-licensed activities for a period of 3 years was issued April 29, 1999, because the individual continued to conduct radiography without a radiation survey instrument after she had indications of a potentially significant radiation exposure, and provided the licensee with false information about the incident.

**James S. Dawson**, IA 99-002. An Order prohibiting involvement in NRC-licensed activities for a period of 5 years was issued April 29, 1999, because the individual continued to conduct radiography without a radiation survey instrument after he had indications of a potentially significant radiation exposure, and provided the licensee with false information about the incident.

**Peter Kint**, IA 99-001. An Order prohibiting involvement in NRC-licensed activities for a period of 1 year was issued March 1, 1999, because the individual deliberately failed to wear an alarming ratemeter as required.

(Contact: Joseph DelMedico, OE, 301-415-2739, e-mail: rjd@nrc.gov)

## Generic Communications Issued (July 1, 1999-September 30, 1999)

Note that these are only summaries of U.S. Nuclear Regulatory Commission (NRC) generic communications. If one of these documents appears relevant to your needs and you have not received it, please call one of the technical contacts listed below.

**Administrative Letters (ALs)**

AL 99-04, "Availability of Revised NRC Form 3, Notice to Employees," was issued on September 10, 1999. This letter was issued to all NRC licensees to notify them that NRC Form 3 had been revised and to transmit a copy of the new version.

(Contact: Carl Mohrwinkel, NRR, 301-415-1293, e-mail: cam@nrc.gov)

AL 99-05, "Amended Regulations Governing Timepieces Containing Tritium," was issued on September 13, 1999. This letter was issued to all exempt distribution licensees to inform them of recent changes to 10 CFR Part 32. The changes simplify the licensing process for timepieces containing tritium gas. (Contact: Anthony S. Kirkwood, NMSS, 301-415-6140, e-mail: ask@nrc.gov)

**Information Notices (INs)**

IN 99-23, "Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices," was issued on July 6, 1999. This notice was issued to all medical licensees authorized to use these devices, to alert them to ongoing control unit failures and corrective measures being developed by the manufacturer. (Contact: Robert L. Ayres, NMSS, 301-415-5746, e-mail: rxa1@nrc.gov)

IN 99-24, "Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unrestricted Sealed Sources and Devices," was issued on July 12, 1999. This notice was issued to all medical licensees of broad scope and all master material licensees to alert them to NRC's expectations about their uses of either sealed sources or devices that are not listed in the registry of sealed sources and devices. (Contact: Robert L. Ayres, NMSS, 301-415-5746, e-mail: rxa1@nrc.gov)

IN 99-25, "Year 2000 Contingency Planning Activities," was issued on August 10, 1999. This notice was issued to all power reactor and fuel cycle licensees to inform them about contingency planning activities being undertaken by the NRC in response to potential disruptions of telecommunications and electrical distribution systems that could occur during the Year-2000 transition period. (Contacts: Joseph Giitter, IRO, 301-415-7485, e-mail: jgg@nrc.gov; John Jolicoeur, IRO, 301-415-6383, e-mail: jrj1@nrc.gov)

IN 99-26, "Safety and Economic Consequences of Misleading Marketing Information," was issued on August 24, 1999. This notice was issued to all distributors and manufacturers of generally licensed devices to alert them to a possible threat to public safety caused by misleading marketing information and lack of end-user understanding of regulatory requirements. (Contact: Ujagar S. Bhachu, NMSS, 301-415-7894, e-mail: usb@nrc.gov)

IN 99-27, "Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units," was issued on September 2, 1999. This notice was issued to all medical licensees authorized to conduct teletherapy treatments, to alert them to potential failures in source retraction mechanisms involving the Picker Model C-9 teletherapy unit and the Advanced Medical System Model C-9 teletherapy unit. (Contact: Roberto J. Torres, NMSS, 301-415-8112, e-mail: rjt@nrc.gov)

IN 99-28, "Recall of Star Brand Fire Protection Sprinkler Heads," was issued on September 30, 1999. This notice was issued to all reactor and fuel cycle licensees to alert them to a recall of the Star brand, dry-type, fire protection sprinkler heads manufactured by the Mealane Corporation of Philadelphia, PA. (Contacts: Mark H. Salley, NRR, 301-415-2840, e-mail: mxs3@nrc.gov; Paul W. Lain, NMSS, 301-415-6317, e-mail: pwl@nrc.gov)

(General Contact: Kevin Ramsey, NMSS, 301-415-7887, e-mail: kmr@nrc.gov)

## Selected Federal Register Notices (July 1, 1999-September 30, 1999)

Note: U.S. Nuclear Regulatory Commission (NRC) contacts may be reached by mail at the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

**Final Rules**

"Requirements for Those Who Possess Certain Industrial Devices Containing Byproduct Material to Provide Requested Information," 64 FR 42269, August, 4, 1999.

(Contacts: Catherine R. Mattsen, NMSS, 301-415-6264, e-mail: crm@nrc.gov; Jayne McCausland, NMSS, 301-415-6219, e-mail: JMM2@nrc.gov)

"Certification Renewal and Amendment Processes for Enrichment Plants," 64 FR 44645, August 17, 1999.

(Contact: John L. Telford, NMSS, 301-415-6229; e-mail: jlt@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (HI-STAR 100) Addition," 64 FR 48259, September 3, 1999.

(Contact: Stan Turel, NMSS, 301-415-6234; e-mail: spt@nrc.gov)

"Electronic Availability of NRC Public Records and Ending of Local Public Document Room Program," 64 FR 48942, September 9, 1999.

(Contact: Russell A. Powell, OCIO, 301-415-6527, e-mail: rap1@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (VSC-24) Revision," 64 FR 51187, September 22, 1999.

(Contact: Stan Turel, NMSS, 301-415-6234; e-mail: spt@nrc.gov)

**Proposed Rules**

"Requirements for Certain Generally Licensed Industrial Devices Containing Byproduct Material," 64 FR 40296, July 26, 1999.

(Contact: Catherine R. Mattsen, NMSS, 301-415-6264, e-mail: crm@nrc.gov)

"List of Approved Spent Fuel Storage Casks: Revision, NUHOMS 24-P and NUHOMS 52-B (AG19)," 64 FR 41050, July 29, 1999.

(Contact: Stan Turel, NMSS, 301-415-6234, e-mail: spt@nrc.gov)

"Domestic Licensing of Special Nuclear Material; Possession of a Critical Mass of Special Nuclear Material," 64 FR 41338, July 30, 1999.

Contact: Theodore S. Sherr, NMSS, 301-415-7218, e-mail: tss@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (NAC-MPC) Addition," 64 FR 45918, August 23, 1999.

Contact: Stan Turel, NMSS, 301-4155-6234, e-mail: spt@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (TN-68) Addition," 64 FR 45920, August 23, 1999.

(Contact: Stan Turel, NMSS, 301-4155-6234, e-mail: spt@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (TN-32) Addition," 64 FR 45923, August 23, 1999.

(Contact: Stan Turel, NMSS, 301-4155-6234, e-mail: spt@nrc.gov)

"List of Approved Spent Fuel Storage Casks: (VSC-24) Revision," 64 FR 51270, September 22, 1999.

(Contact: Stan Turel, NMSS, 301-4155-6234, e-mail: spt@nrc.gov)

"List of Approved Spent Fuel Storage Casks: Holtec HI-STORM 100 Addition," 64 FR 51271, September 22, 1999.

(Contact: Merri Horn, NMSS, 301-415-8126, e-mail: mlh1@nrc.gov)

**Notices**

"Receipt of Petition for Rulemaking from Colorado and Organization of Agreement States," 64 FR 36615, July 7, 1999.

(Contact: David L. Meyer, ADM, 301-415-7162, or Toll-Free: 1-800-368-5642, e-mail: dlm1@nrc.gov)

"Notice of Availability, Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Licenses of Broad Scope," NUREG-1556, Vol. 11, 64 FR 36724, July 7, 1999.

(Contact: Sally L. Merchant, NMSS, 301-415-7874, e-mail: slm2@nrc.gov)

"Notice of Availability, Consolidated Guidance about Change of Control and about Bankruptcy Involving Byproduct, Source, or Special Nuclear Material Licenses," NUREG-1556, Vol. 15, 64 FR 37174, July 9, 1999.

(Contact: Sally L. Merchant, NMSS, 301-415-7874, e-mail: slm2@nrc.gov)

"Notice of Availability, Draft Regulatory Guide (DG)-3014 proposed Revision 1 of Regulatory Guide 3.66, `Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning under 10 CFR Parts 30, 40, 70, and 72,''' 64 FR 38223, July 14, 1999.

(Contact: L.M. Bykoski, NMSS, 301-415-675, e-mail: lmb1@nrc.gov)

"Notice of Availability, Consolidated Guidance about Change of Control and about Bankruptcy Involving Byproduct, Source, or Special Nuclear Material Licenses," NUREG-1556, Vol. 15, 64 FR 37174, July 9, 1999.

(Contact: Sally L. Merchant, NMSS, 301-415-7874, e-mail: slm2@nrc.gov)

"Notice of Availability, Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Well Logging, Tracer, and Field Flood Study Licenses," NUREG-1556, Vol. 14, 64 FR 38223, July 15, 1999.

(Contact: Sally L. Merchant, NMSS, 301-415-7874, e-mail: slm2@nrc.gov)

"Denial of Petition for Rulemaking (PRM 40-26) Chromalloy Tallahassee," 64 FR 40784, July 28, 1999.

Contact: John L. Telford, NMSS, 301-415-6229, e-mail: jlt@nrc.gov)

"Denial of Petition for Rulemaking to Require Shutdown of Nuclear Facilities Not Compliant with Y2K Issues, Nuclear Information and Resource Service (PRM 50-65)," 64 FR 45900, August 23, 1999.

(Contacts: Matthew Chiramal, NMSS, 301-415-2845, e-mail: mxc@nrc.gov; Gary W. Purdy, NMSS, 301-415-7897, e-mail: gwp1@nrc.gov)

"Receipt of Petition for Rulemaking to Prohibit Hand-held Administration of Radiopharmaceuticals by Injection," Jeffrey C. Angel (PRM 35-15)," 64 FR 45907, August 23, 1999.

(Contact: David L. Meyer, ADM, 301-415-7162, e-mail: dlm1@nrc.gov) or Toll-Free: 1-800-368-5642

"Availability of Draft NUREGs on Risk Review of Use of Nuclear Byproduct Material," 64 FR 46456, August 25, 1999.

(Contact: Torre Taylor, NMSS, 301-415-7900, e-mail: tmt@nrc.gov)

"State of Ohio: Discontinuance of Certain Commission Regulatory Authority Within the State," 64 FR 49029, September 9, 1999.

(Contact: Richard L. Blanton, OSP, 301-415-2322, e-mail: rlb@nrc.gov)

(General Contact: Paul Goldberg, NMSS, 301-415-7842, e-mail: pfg@nrc.gov)

Comments, and suggestions you may have for information that is not currently being included, that might be helpful to licensees, should be sent to:

E. Kraus NMSS Licensee Newsletter Editor Office of Nuclear Material Safety and Safeguards Two White Flint North, Mail Stop 8-A-23 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 (or send e-mail to: eek@nrc.gov

Page Last Reviewed/Updated Wednesday, March 24, 2021