NMSS Licensee Newsletter September 1998 - October 1998
NUREG/BR-0117; No. 98-3
Electronic Access to Rulemaking
In an effort to further public access to, and participation in, its rulemaking activities, the U.S. Nuclear Regulatory Commission (NRC) has developed a World Wide Web site that contains proposed rulemakings which NRC has published in the Federal Register, as well as petitions for rulemakings that NRC has received and docketed. Through this website, the public is able to learn about and officially comment on these petitions and proposed rulemakings electronically. This website replaces the use of the FedWorld Bulletin Board services for publishing and receiving comments on rulemakings.
Proposed rules and petitions are placed on the website when the comment period opens. Background files on the proposed rule or petition are available for viewing or downloading from the file libraries. Comments on the proposed rulemakings and petitions can be uploaded, as files, by members of the public, in lieu of sending in written comments to NRC.
From the NRC home page, select "Rulemaking" from the toolbar. The interactive rulemaking website can then be accessed by selecting Rulemaking Forum .
(Contact: Carol Gallagher, ADM, 301-415-5905, or e-mail: firstname.lastname@example.org)
Development of Policy And Guidance Directive For Processing Licensee Requests to Postpone Initiation of Decommissioning Activities
The U.S. Nuclear Regulatory Commission's (NRC's) "Timeliness in Decommissioning of Materials Facility" rule (hereafter Timeliness Rule), became effective on August 15, 1994. Before issuance of the Timeliness Rule, there was a lack of definitive criteria that specified acceptable time periods for decommissioning of nuclear material facilities after licensed activities had ceased. This lack of criteria resulted in instances where NRC had to issue orders to establish schedules for timely decommissioning. The Timeliness Rule established the definitive criteria necessary to avoid future problems resulting from delayed decommissioning of contaminated inactive facilities, separate buildings, and outdoor areas.
In May 1996, the Nuclear Energy Institute (NEI) filed a petition for rulemaking to amend the Timeliness Rule. NEI contended that the current Timeliness Rule is too restrictive since it requires decommissioning of any facility, separate building, or outdoor area that has been inactive for at least 24 months and is unsuitable for unrestricted release. NEI believes the Timeliness Rule should contain provisions that allow facilities to operate on "standby" mode without having to decommission. In its petition, NEI stated that without a provision for a standby mode, a licensee's ability to make commercial decisions is impacted, and there is the potential to significantly impact important components of the nuclear industry that may be needed in future years.
The Office of Nuclear Material Safety and Safeguards (NMSS) believes the Timeliness Rule contains provisions that allow licensees to request delays or postponement of decommissioning, provided they can demonstrate that the delays are not detrimental to the public health and safety and are otherwise in the public interest. During a public meeting with NEI on September 2, 1998, NRC and NEI agreed that guidance was required to identify the acceptance criteria necessary to demonstrate that postponement of decommissioning activities will not be detrimental to the public health and safety and is otherwise in the public interest. The staff is currently preparing a policy and guidance directive on this issue. It is anticipated that the guidance will be available for staff use in 1999.
(Contact: John Buckley, NMSS, 301-415-6607, e-mail: email@example.com)
Interim Staff Guidance For The Review of Dry Cask Storage System Applications
In January 1997 and March 1998, respectively, the staff issued its Standard Review Plan (SRP) for "Dry Cask Storage Systems," NUREG-1536, and the draft SRP for "Transportation Packages for Spent Nuclear Fuel" (NUREG-1617). The SRPs provide guidance to the NRC staff in the Spent Fuel Storage Project Office (SFPO), for performing safety reviews of dry cask storage systems. The SRPs are intended to ensure the quality and uniformity of the staff reviews. The SRPs present a basis for the technical review scope and provide clarification of the regulatory requirements.
The SFPO staff has gained experience in using the SRPs in the review of current dry cask storage and transportation applications. Further, it has found areas for which the SRPs do not provide adequate guidance. SFPO has recently issued Interim Staff Guidance (ISG) on seven topics to ensure consistent reviews by the staff until the guidance can be incorporated in the next revision of the SRPs.
The ISGs were issued on September 28, 1998, for SFPO management approval,and the Director of SFPO approved the ISGs in early October. The ISGs covered such diverse topics as:
- "Damaged Fuel"
- "Fuel Retrievability"
- "Post Accident Recovery and Compliance with 10 CFR 72.122(l)"
- "Cask Closure Weld Inspections"
- "Normal, Off-Normal, and Hypothetical Accident Dose Estimate Calculations for Whole Body, Thyroid, and Skin"
- "Establishing Minimum Initial Enrichment for the Bounding Design Basis Fuel Assembly(ies)"
- "Potential Generic Issue Concerning Cask Heat Transfer in a Transportation Accident."
The ISGs are available in the Public Document Room as well as on the NRC/SFPO web site.
(Contact: Eric Leeds, NMSS, 301-415-8540, e-mail: firstname.lastname@example.org)
NRC Staff Efforts to Develop Guidance for the License Termination Rule
U.S. Nuclear Regulatory Commission (NRC) regulations require that a decommissioning plan be submitted by a licensee to support the decommissioning of its facility when it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC, and these procedures could increase the potential health and safety impacts on the workers or the public. The objective of the decommissioning plan is to describe the activities and procedures that the licensee intends to undertake to remove residual radioactive material at the facility to levels that meet NRC criteria for release of the site and termination of the radioactive materials license. In July 1997 NRC amended its regulations regarding decommissioning of licensed facilities to provide specific radiological criteria for the decommissioning of lands and structures.
In July 1998, NRC staff completed development of Draft NUREG-1549, "Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination" and in August the staff completed draft regulatory guidance in DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination" for a 2-year review and comment period. DG- 4006 and NUREG-1549 are intended to provide an overall framework for dose assessment and decision-making at sites undergoing decommissioning.
NRC staff is currently developing a Standard Review Plan (SRP) for evaluating information submitted by licensees and other responsible parties to support the decommissioning of fuel cycle and materials facilities. The goal of the SRP is to enable NRC staff to evaluate information submitted by licensees in a timely, efficient, and consistent manner, to determine if the decommissioning will be conducted in such a manner that the public health and safety is protected and the facility can be released in accordance with NRC's requirements.
To obtain input from interested stakeholders on the issues that will need to be addressed in the SRP and final Regulatory Guide, the staff will hold monthly conference calls with interested stakeholders to identify these issues. The staff will also hold workshops, with the stakeholders, on dose-modeling, and surveys, demonstrating as-low-as-is-reasonably achievable, and restricted use/alternate criteria, and will discuss the issues in detail before it develops resolutions to them. Workshops were held on December 1-2; 1998 and January 21-22, 1999, and will be held on March 18-19, 1999, June 16-17, 1999; August 18-19, 1999, and October 20-21, 1999.
The staff has also established a Website (http://techconf.llnl.gov/cgi-bin/topics) and is requesting that interested individuals communicate their concerns by posting the concerns on the website. Finally, the staff will provide interested stakeholders with the opportunity to review and comment on the SRP by posting the drafts of the SRP on the website at periodic intervals during the project.
The staff expects to complete development of the SRP and publish the final Regulatory Guide in July 2000.
(Contact: Dominick A. Orlando, NMSS, 301-415-6749, e-mail: email@example.com)
Status of Previous Guidance on Former Burials
On November 4, 1996, the U.S. Nuclear Regulatory Commission (NRC) published a draft Branch Technical Position (BTP), entitled "Branch Technical Position on Screening Methodology for Assessing Prior Land Burials of Radioactive Waste Authorized under Former 10 CFR 20.304, and 20.302," in the Federal Register. The draft BTP was issued to assist licensees in evaluating formal burials and in complying with the "Final Rule on Timeliness in Decommissioning Nuclear Facilities" (Timeliness Rule).
NRC issued Administrative Letter Notice 96-05, entitled "Compliance with the Timeliness Rule in Decommissioning of Material Facilities,"which in part presented NRC's position that former burials were covered by the Timeliness Rule. NRC also issued Information Notice 96-47, entitled "Recordkeeping, Decommissioning Notifications for Disposal of Radioactive Waste by Land Burial Authorized under Former 10 CFR 20.304, 20.302, and Current 20.2002." This Information Notice required licensees to notify NRC of former burials by October 15, 1996, and either begin decommissioning or submit, within 12 months of notification, a decommissioning plan, or to request an extension of the time periods by September 15, 1996. The notice also notified licensees that NRC was developing a methodology that could be used to determine the acceptability of prior burials. The methodology would be used as a screening tool to determine which burials have the greatest potential to impact public health and safety.
The draft BTP was issued for public use and comment for 90 days. At the end of the 90-day period, comments were evaluated to determine if the BTP should be revised. It was noted that since there was a possibility that the comments could result in a substantial change to the draft BTP, NRC would not make any decisions regarding the assessment of prior burials until after the public comments were evaluated. NRC received five comments on the draft BTP. Subsequent to the close of the public comment period and NRC revising the BTP, the Rule "Radiological Criteria for License Termination" was finalized and published. This rule established a 0.25-mSv/year dose limit for unrestricted use and release of sites. Staff determined that the BTP methodology would not always be conservative enough for all radionuclides or combinations of radionuclides, using a more robust modeling approach. Therefore, it was decided not to finalize the BTP.
Instead, staff decided to provide guidance on evaluating former burials as part of the guidance development to implement the License Termination Rule. Parts of this guidance have been issued for interim use. A computer code, DandD, was also developed as a screening tool. Under certain circumstances and assumptions, the DandD code could be used to evaluate former burials. Should sites fail to meet screening using the DandD code, site-specific analysis would be required. Staff continues to develop this guidance with respect to site-specific analysis and evaluating former burials. Licensees should continue to submit their assessments of onsite burials, using DandD or other appropriate code, as required by the Timeliness Rule, to NRC, for review.
(Contact: Tim Harris, NMSS, 301-415-6613, e-mail: firstname.lastname@example.org)
Use of Proper Protective Clothing
For those licensees, such as hospitals and radiopharmacies, that use unsealed radioactive materials, the use of protective clothing is essential to prevent unnecessary exposure to radioactive materials. In most cases, the licensee has committed to specific uses of protective clothing, in its license. In addition, after an individual's use of protective clothing, radiological surveys should be performed to ensure that the individual's clothing is not contaminated. The combination of protective clothing and personal surveys will help maintain exposures to radioactive materials as low as is reasonably achievable. Failure to wear the proper protective clothing and to properly survey, after the use of unsealed radioactive materials, can lead to unnecessary personnel exposures and the spread of contamination.
The U.S. Nuclear Regulatory Commission recently became aware of two instances where licensees' workers failed to wear the proper protective clothing and were contaminated. In both instances, the workers were required, by license condition, to wear shoulder-length gloves when working with unsealed radioactive materials. However, both individuals wore only wrist-length gloves.
In the first instance, the individual believed that nothing abnormal happened during the work. The worker did perform a personal survey before leaving the restricted area. However, this survey was inadequate and did not identify contamination on the individual's arms and clothing, which subsequently resulted in the spread of contamination in the licensee's facility and the individual's home. Fortunately, the exposure to the individual did not result in an overexposure.
In the second instance, an incident occurred, that resulted in contamination of the individual's arm, lab coat, and the licensee's facility. The individual took immediate actions to decontaminate the area. However, the individual failed to perform an adequate personal survey before leaving the licensee's facility. In this case, the exposure to the individual did result in an overexposure to an extremity.
(Contact: Brian Smith, NMSS, 301-415-5723, e-mail: email@example.com)
Damaged Iridium-192 Radiography Source Caused by Electrical Short Circuit
The Texas Department of Health, Bureau of Radiological Control, notified the U.S. Nuclear Regulatory Commission (NRC) that on June 19, 1998, a radiography was attempted while an energized welding lead was still attached to the vessel. As the exposure device was lowered into the vessel by crane, the guide tube came in contact with the vessel wall. Contact between the guide tube and the vessel provided a current pathway, and as a result, the Ir-192 sealed source and a portion of the guide tube melted. The radiographers noted that the guide tube and drive cable were severed, with the end of the guide tube fused because of heat damage. The radiographer placed the camera in a plastic bag and returned it to the licensee's facility. However, five workers were found contaminated as a result of this incident.
In addition to this incident, a radiography licensee has indicated to NRC that he is aware of two other similar incidences that have occurred within the past 20 years, in which a radiography source had ruptured as a result of an electrical short involving the intermingling of the radiographer's control assembly with the welders' cables.
Because of the design and construction of radiography cameras of various conductive metals, conduction through the camera itself is quite possible. However, considering the frequency of these incidents, it appears that this is a unique and relatively uncommon event. NRC suggests that radiography licensees review their protocols and take actions, appropriately, to avoid the unforeseen possibilities of electrical short circuits with welding equipment.
(Contact: Eric Compton, NMSS, 301-415-5799, e-mail: firstname.lastname@example.org)
Significant Enforcement Actions
Detailed information regarding these enforcement actions can be accessed via the NRC homepage. Click on "About NRC"; click on "Enforcement Program"; click on "Enforcement Actions Issued"; and click on either "Escalated Enforcement Actions Issued to Materials Licensees Since March, 1996"; or "Enforcement Actions Issued to Individuals."
U. S. Enrichment Corporation, Bethesda, Maryland, EA 98-156. A Confirmatory Order Modifying the Certificate for the Paducah, Kentucky, Gaseous Diffusion Plant was issued to require seismic modifications and to place restrictions on certain operations, in the interim.
J&L Testing Company, Inc., Canonsburg, Pennsylvania, EA 96-110. An Order Revoking License was issued based on deliberate and widespread wrongdoing by J&L, including unauthorized use of byproduct material, inaccurate statements, violations of license conditions, and deliberate destruction of records.
Altoona Hospital, Altoona, Pennsylvania, EAs 98-194 and 98-202. A $2750 civil penalty was assessed for failure to complete written directives before the administration of iodine-131 to patients.
Jose M. Colon Vaquer, Manati, Puerto Rico, EA 98-183. A Confirmatory Order Modifying License was issued to require that the use of a Strontium-90 eye applicator cease and that the device be placed in safe storage. The device had been used after the license expired and two misadministrations occurred.
Washington Hospital Center, Washington, DC, EA 98-145. A $2750 civil penalty was assessed for six violations related to the control of radioactive waste.
Wood River Medical Center, Sun Valley, Idaho, EA 97-613. A $2750 civil penalty was assessed for 21 violations indicative of a breakdown in control of licensed activities.
(Contact: Joseph DelMedico, OE, 301-415-2739, e-mail: email@example.com)
Generic Communications Issued (May 1, 1998 - August 31, 1998)
Note that these are only summaries of U.S. Nuclear Regulatory Commission 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.
Generic Letters (GLs)
GL 98-03, "NMSS LICENSEES' AND CERTIFICATE HOLDERS' YEAR 2000 READINESS PROGRAMS," was issued on June 22, 1998, to all uranium hexafluoride plants, uranium enrichment plants, and uranium fuel fabrication plants. It notifies them of the need for Year 2000 readiness programs to address problems with computer systems; requests them to implement the actions described; and requires them to provide NRC with a written response to the letter. Contacts: Gary Purdy, NMSS, 301-415-7897, e-mail: firstname.lastname@example.org; Harry Felsher, NMSS, 301-415-5521, e-mail: email@example.com.
Information Notices (INs)
IN 98-17, "FEDERAL BUREAU OF INVESTIGATION'S (FBI's) AWARENESS ON NATIONAL SECURITY ISSUES AND RESPONSE (ANSIR) PROGRAM," was issued on May 7, 1998, to all fuel cycle, power reactor, and non-power reactor licensees. It informs them about the ANSIR program and its availability to corporate security professionals. Contacts: John Davidson, NMSS, 301-415-8130, e-mail: firstname.lastname@example.org; Robert Skelton, NRR, 301-415-3309, e-mail: email@example.com.
IN 98-18, "RECENT CONTAMINATION INCIDENCES RESULTING FROM FAILURE TO PERFORM ADEQUATE SURVEYS," was issued on May 13, 1998, to all medical licensees. It alerts them to recent incidents of radiopharmacies receiving contaminated packages from client facilities when the clients failed to resurvey packages after a spill. Contact: Torre Taylor, NMSS, 301-415-7900, e-mail: firstname.lastname@example.org.
IN 98-20, "PROBLEMS WITH EMERGENCY PREPAREDNESS RESPIRATORY PROTECTION PROGRAMS," was issued on June 3, 1998, to all power reactors, non-power reactors, and all fuel cycle and materials licensees required to have an NRC-approved emergency plan. It alerts them to multiple weaknesses discovered in respiratory protection programs supporting emergency preparedness. Contacts: James E. Wigginton, NRR, 301-415-1059, e-mail: email@example.com; Lawrence K. Cohen, NRR, 301-415-2923, e-mail: firstname.lastname@example.org; Michael A. Lamastra, NMSS, 301-415-8139, e-mail: email@example.com.
IN 98-26, "SETTLEMENT MONITORING AND INSPECTION OF PLANT STRUCTURES AFFECTED BY DEGRADATION OF POROUS CONCRETE SUBFOUNDATIONS," was issued on July 24, 1998, to all power reactors, all independent spent fuel storage installations (ISFSIs), and all designers and fabricators of ISFSIs. It informs them of the possibility of degradation in porous concrete subfoundations. Contacts: R. Pichumani, NRR, 301-415-2734; e-mail: firstname.lastname@example.org; H. Asher, NRR, 301-415-2851, e-mail: email@example.com; W. Burton, NRR, 301-415-2853, e-mail: firstname.lastname@example.org.
Supplement 1 to IN 97-91, "RECENT FAILURES OF CONTROL CABLES USED ON AMERSHAM MODEL 660 POSILOCK RADIOGRAPHY SYSTEMS," was issued on August 10, 1998, to all industrial radiography licensees. It alerts them to the results and recommendations from a special inspection of source disconnects resulting from the control (drive) cables breaking during routine operations. Contacts: Larry W. Camper, NMSS, 301-415-7231, e-mail: email@example.com; Doug A. Broaddus, NMSS, 301-415-5847, e-mail: firstname.lastname@example.org; John M. Pelchat, RII, 404-562-4729, e-mail: email@example.com; Deborah A. Piskura, RIII, 630-829-9867, e-mail: firstname.lastname@example.org.
IN 98-30, "EFFECT OF YEAR 2000 COMPUTER PROBLEM ON NRC LICENSEES AND CERTIFICATE HOLDERS," was issued on August 12, 1998, to all material and fuel cycle licensees. It reminds them of the potential problems their computer systems and software may encounter as a result of the change to the year 2000. Contact: Gary Purdy, NMSS, 301-415-7897, e-mail: email@example.com.
IN 98-33, "NRC REGULATIONS THAT PROHIBIT AGREEMENTS THAT RESTRICT OR DISCOURAGE AN EMPLOYEE FROM PARTICIPATING IN PROTECTED ACTIVITIES," was issued on August 28, 1998, to all NRC licensees. It informs them that NRC regulations specify that any agreement with an employee, including an agreement to settle a discrimination complaint, may not prohibit, restrict, or otherwise discourage an employee from participating in protected activities such as providing information to NRC on potential violations or other matters within NRC's regulatory responsibilities. Contact: James Lieberman, OE, 301-415-2741, e-mail: firstname.lastname@example.org.
(General Contact: Kevin Ramsey, NMSS, 301-415-7887, e-mail: email@example.com)
Selected Federal Register Notices (June 1, 1998 - September 30, 1998)
NOTE: U.S. Nuclear Regulatory Commission (NRC) contacts may be reached by mail at the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
"Self-Guarantee of Decommissioning Funding by Nonprofit and Non-Bond-Issuing Licensees," 63 FR 29535, June 1, 1998.Contact: Dr. Clark Prichard, NMSS, 301-415-6203, e-mail: firstname.lastname@example.org.
"License Term for Medical Use Licenses," 63 FR31604, June 10, 1998.
Contact: Jayne M. McCausland, NMSS, 301-415-6219, e-mail: jmm2@ nrc.gov.
"Revision of Fee Schedules: 100 Percent Fee Recovery, FY 1998," 63 FR 31840, June 10, 1998.Contact: Glenda Jackson, Office of the Chief Financial Officer, 301-415-6057.
"Requirements for Shipping Packages Used to Transport Vitrified High-Level Waste," 63 FR 32600, June 15, 1998. Contacts: Earl Easton, NMSS, 301-415-8520, e-mail: email@example.com, or Mark Haisfield, NMSS, 301-415-6196, e-mail: firstname.lastname@example.org.
"License Applications for Certain Items Containing Byproduct Material," 63 FR 32969, June 17, 1998. Contact: Donald O. Nellis, NMSS, 301-415-6257, e-mail: email@example.com.
"Licenses for Industrial Radiography and Radiation Safety Requirements for Industrial Radiographic Operations; Clarifying Amendments and Corrections," 63 FR 37059, July 9, 1998. Contact: Donald O. Nellis, NMSS, 301-415-6257, e-mail: firstname.lastname@example.org.
"Minor Corrections, Clarifying Changes, and a Minor Policy Change (Part 20)," 63 FR 39477, July 23, 1998. Contact: Jayne M. McCausland, NMSS, 301-415-6219, e-mail: jmm2@ nrc.gov.
"Minor Corrections, Clarifying Changes, and a Minor Policy Change; Delay of Effective Date," 63 FR 45393, August 26, 1998. Contact: Jayne M. McCausland, NMSS, 301-415-6219.
"Physical Protection for Spent Nuclear Fuel and High-Level Radioactive Waste: Technical Amendment," 63 FR 49413, September 16, 1998.
Contact: Barry Mendelsohn, NMSS, 301-415-7262, e-mail: email@example.com.
"Transfer for Disposal and Manifests; Minor Technical Conforming Amendment," 63 FR 50127, September 21, 1998. Contact: Mark Haisfield, NMSS, 301-415-6196, e-mail: firstname.lastname@example.org.
"Miscellaneous Changes to Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste," 63 FR 31363, June 9, 1998. Contact: M. L. Au, NMSS, 301-415-6181, e-mail email@example.com.
"Radiation Sources on Army Land (Department of Defense)," 63 FR 37296, July 10, 1998. Contact: Colonel Robert Cherry, 703-695-7291.
"Respiratory Protection and Controls to Restrict Internal Exposures," 63 FR 38511, July 17, 1998. Contact: Alan K. Roecklein, Office of Nuclear Reactor Regulation, 301-415-3883, email: firstname.lastname@example.org.
"Expand Applicability of Regulations to Holders of, and Applicants for, Certificates of Compliance and Their Contractors and Subcontractors," 63 FR 39526, July 23, 1998. Contacts: Anthony DiPalo, NMSS, 301-415-6191, e-mail: email@example.com; Philip Brochman, NMSS, 301-415-8592, e-mail: firstname.lastname@example.org.
"Streamlined Hearing Process for NRC Approval of License Transfers," 63 FR 48644, September 11, 1998. Contact: Joseph R. Gray, OGC, 301-415-1740, e-mail email@example.com.
"Elimination of Reporting Requirement and 30-Day Hold in Loading Spent Fuel After Preoperational Testing of Independent Spent Fuel Storage or Monitored Retrievable Storage Installations," 63 FR 49046, September 14, 1998. Contact: Gordon Gundersen, NMSS, 301-415-6195, e-mail: firstname.lastname@example.org.
"Certification Renewal and Amendment Processes for Gaseous Diffusion Plants," 63 FR 49301, September 16, 1998. Contact: John L. Telford, NMSS, 301-415-6229, e-mail: email@example.com.
"Physical Protection for Spent Nuclear Fuel and High-Level Radioactive Waste: Technical Amendment," 63 FR 49505, September 16, 1998. Contact: Barry Mendelsohn, NMSS, 301-415-7262, e-mail: firstname.lastname@example.org.
Availability and Request for Comments on NUREG-1556, Vol. 7, "Consolidated Guidance About Licensees of Limited Scope," 63 FR 37059, July 2, 1998. Contact: Sally Merchant, NMSS, 301-415-7874, e-mail: email@example.com.
"Radiographer Certification-Certifying Entities," 63 FR 32971, June 17, 1998 Contact: J. Bruce Carrico, NMSS, 301-415-7826, e-mail: firstname.lastname@example.org.
"Governors' Designees Receiving Advance Notification of Transportation of Nuclear Waste," 63 FR 35620, June 30, 1998. Contact: Spiros Droggitis, OSP, 301-415-2367, e-mail: email@example.com.
Issuance and Availability of Draft Regulatory Guide, DG-8022, "Acceptable Programs for Respiratory Protection," 63 FR 40141, July 27, 1998.
"Conformance to National Policies for Access to and Protection of Classified Information," 63 FR 41206, August 3, 1998. Contact: Duane G. Kidd, ADM, 301-415-7403, e-mail: firstname.lastname@example.org.
Issuance and Availability of Draft Regulatory Guide, DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination," 63 FR 41604, August 4, 1998.
"Policy on Conduct of Adjudicatory Proceedings; Policy Statement," 63 FR 41872, August 5, 1998. Contact: Robert M. Weisman, OGC, 301-415-1696, e-mail: email@example.com.
"Medical Use of Byproduct Material; Proposed Revisions," 63 FR 43516, August 13, 1998. Contacts: Catherine Haney, NMSS, 301-415-6825, e-mail firstname.lastname@example.org; Diane Flack, NMSS, 301-415-5681, e-mail: email@example.com.
"Medical Use of Byproduct Material; Draft Policy Statement," 63 FR 43580, August 13, 1998. Contacts: Catherine Haney, NMSS, 301-415-6825, e-mail: firstname.lastname@example.org; Marjorie U. Rothschild, OGC, 301-415-1633, e-mail: email@example.com.
"Source Disconnects Resulting from Radiography Drive Cable Failures" (NUREG-1631) 63 FR 43732, August 14, 1998. Contact: Larry W. Camper, NMSS, 301-415-7231; e-mail: firstname.lastname@example.org.
"Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Medical Use Licenses, Availability of Draft" (NUREG-1556, Vol. 9), 63 FR 45270, August 25, 1998. Contact: Sally L. Merchant, NMSS, 301-415-7874; e-mail: email@example.com.
"Consolidated Guidance About Materials Licenses: Applications for Sealed Source and Device Evaluation and Registration" (NUREG-1556, Vol. 3), 63 FR 46494, September 1, 1998. Contact: Sally L. Merchant, NMSS, 301-415-7874, e-mail: firstname.lastname@example.org.
Issuance and Availability of Regulatory Guide 3.71, "Nuclear Criticality Safety Standards for Fuels and Material Facilities," 63 FR 47046, September 3, 1998. "Hazardous Materials: Withdrawal of Radiation Protection Program Requirement" (Department of Transportation) 63 FR 48566, September 10, 1998. Contacts: Dr. Fred D. Ferate II, Office of Hazardous Materials Technology (202) 366-4545; Charles E. Betts, Office of Hazardous Materials Standards (202) 366-8553, RSPA, U.S. DOT, 400 Seventh Street SW, Washington, DC 20590-0001.
American National Standards Institute N43.10 Committee, "Receipt of Petition for Rulemaking to Allow the Operation of Panoramic Irradiator Facilities without Continuous Onsite Attendance" (PRM-36-1) 63 FR 49298, September 15, 1998. Contact: David L. Meyer, ADM, 301-415-7162, or Toll Free: 800-368-5642, or e-mail: email@example.com.
"Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Licenses of Broad Scope," Availability of Draft NUREG-1556, Vol. 11, 63 FR 49615, September 16, 1998. Contact: Sally Merchant, NMSS, 301-415-7874, e-mail: firstname.lastname@example.org.
(General Contact: Paul F. Goldberg, NMSS, 301-415-7842, e-mail: email@example.com)
Comments, and suggestions you may have for information that is not currently being included, that might be helpful to licensees, should be sent to:
NMSS Licensee Newsletter Editor
Office of Nuclear Material Safety
Two White Flint North, Mail Stop 8-A-23
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555-0001
(or send e-mail to: firstname.lastname@example.org
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