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| number = ML18163A239 | | number = ML18163A239 | ||
| issue date = 06/18/2018 | | issue date = 06/18/2018 | ||
| title = 18-2018 Colorado Proposed Final Impep Report | | title = 6-18-2018 Colorado Proposed Final Impep Report | ||
| author name = Michalak P | | author name = Michalak P | ||
| author affiliation = NRC/NMSS/DMSST/ASPB | | author affiliation = NRC/NMSS/DMSST/ASPB | ||
| addressee name = Campbell T | | addressee name = Campbell T, Dapas M, Dorman D, Roberts D | ||
| addressee affiliation = NRC/EDO, NRC/NMSS, NRC/OGC, NRC/RGN-III/ORA | | addressee affiliation = NRC/EDO, NRC/NMSS, NRC/OGC, NRC/RGN-III/ORA | ||
| docket = | | docket = | ||
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=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 2018 MEMORANDUM TO: Daniel H. Dorman Deputy Executive Director for Materials, Waste, Research, State, Tribal, Compliance, Administration, and Human Capital Programs Office of the Executive Director for Operations Tison A. Campbell, Acting Assistant General Counsel for Reactor and Materials Rulemaking Office of the General Counsel Marc L. Dapas, Director Office of Nuclear Material Safety and Safeguards Darrell J. Roberts, Deputy Regional Administrator Region III FROM: Paul Michalak, Chief /RA/ | ||
Agreement State Programs Branch Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards | |||
==SUBJECT:== | |||
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF COLORADO This memorandum transmits to the Management Review Board (MRB) a proposed final report (Enclosure 1) documenting the Integrated Materials Performance Evaluation Program (IMPEP) review of Colorado. The review was conducted by a team of U.S. Nuclear Regulatory Commission (NRC) and Agreement State technical staff during the period of April 9 - 12, 2018. | |||
The teams preliminary findings were discussed with Colorado on the last day of the review. | |||
The team issued a draft report to Colorado on May 9, 2018, for factual comment. Colorado had no comments on the draft report. | |||
CONTACT: Lance Rakovan, NMSS/MSST (301) 415-2589 | |||
MRB Members Overall, the team is recommending that Colorados performance be found satisfactory for all performance indicators reviewed. Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with the NRC's program. The team recommends that the next IMPEP review take place in approximately four years with a periodic meeting in approximately two years. | |||
The MRB meeting to consider the Colorado report is scheduled for Tuesday, June 26, 2018, from 1:00 p.m. to 4:00 p.m. ET. In accordance with Management Directive 5.6, the meeting is open to the public. The agenda for the meeting is enclosed (Enclosure 2). | |||
==Enclosures:== | |||
: 1. Colorado Proposed Final Report | |||
: 2. Agenda for MRB Meeting cc: Jennifer Opila, Program Manager Radiation Program Hazardous Materials & Waste Management Division Colorado Department of Public Health & Environment BJ Smith, MS Organization of Agreement States Liaison to the MRB | |||
MRB Members | |||
==SUBJECT:== | |||
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF COLORADO. | |||
Date: June 18, 2018 DISTRIBUTION: (SP08) | |||
RidsEdoMail RidsOgcMailCenter RidsNmssOd RidsRgn3MailCenter RErickson, RSAO/RIV SFlahtery, MN GFlanders, TX RParsons, TN FTran, RIII OMasnyk-Bailey, RI LRoldan-Otero, NMSS AKock, NMSS OAS Board State of CO ML18163A239 OFFICE ASPB ASPB:BC NAME LRakovan PMichalak DATE 6/14/18 6/18/18 OFFICIAL RECORD COPY | |||
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF THE COLORADO AGREEMENT STATE PROGRAM April 9 - 12, 2018 PROPOSED FINAL REPORT Enclosure | |||
EXECUTIVE | |||
** | ==SUMMARY== | ||
** | |||
***** | This report presents the results of the Integrated Materials Performance Evaluation Program (IMPEP) review of the Colorado Agreement State Program. The review was conducted during the period of April 9 - 12, 2018, by a team comprised of technical staff members from the U.S. Nuclear Regulatory Commission (NRC) and the States of Minnesota, Tennessee, and Texas. | ||
****** | Based on the results of this review, Colorados performance was found satisfactory for all performance indicators reviewed, including the finding for the non-common performance indicator, Compatibility Requirements, improving from unsatisfactory during the previous IMPEP review to satisfactory during this review. | ||
* | The team did not make any recommendations and there were no open recommendations from previous reviews for the team to consider. | ||
***** | Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with the NRC's program. The team recommends that the next IMPEP review take place in approximately four years with a periodic meeting in approximately two years. | ||
* | |||
******* | Colorado Proposed Final IMPEP Report Page 1 | ||
* | |||
******** | ==1.0 INTRODUCTION== | ||
**}} | |||
This report presents the results of the review of the Colorado Agreement State Program radioactive materials safety program. The review was conducted during the period of April 9 - 12, 2018, by a team comprised of technical staff members from the U.S. | |||
Nuclear Regulatory Commission (NRC) and the States of Minnesota, Tennessee, and Texas. Team members are identified in Appendix A. The review was conducted in accordance with the Agreement State Program Policy Statement, published in the Federal Register on October 18, 2017, and NRC Management Directive (MD) 5.6, Integrated Materials Performance Evaluation Program (IMPEP), dated February 26, 2004. Preliminary results of the review, which covered the period of April 12, 2014, to April 12, 2018, were discussed with Colorado managers on the last day of the review. | |||
In preparation for the review, a questionnaire addressing the common performance indicators and applicable non-common performance indicators was sent to Colorado on November 21, 2017. Colorado provided its response to the questionnaire on March 22, 2018. A copy of the questionnaire response is available in the NRCs Agencywide Documents Access and Management System (ADAMS) using the Accession Number ML18082A369. | |||
The Colorado Agreement State Program is administered by the Radiation Control Program (the Program). The Program is part of the Hazardous Materials & Waste Management Division (the Division), within the Department of Public Health and Environment (the Department). Organization charts for Colorado are available in ADAMS (Accession Number ML18082A357). | |||
At the time of the review, the Colorado Agreement State Program regulated 316 specific licenses authorizing possession and use of radioactive materials. The review focused on the radioactive materials program as it is carried out under the Section 274b. (of the Atomic Energy Act of 1954, as amended) Agreement between the NRC and the State of Colorado. | |||
The team evaluated the information gathered against the established criteria for each common and the applicable non-common performance indicators and made a preliminary assessment of the Colorado Agreement State Programs performance. | |||
2.0 PREVIOUS IMPEP REVIEW AND STATUS OF RECOMMENDATIONS The previous IMPEP review concluded on April 11, 2014. The final report is available in ADAMS (Accession Number ML14192A009). The results of the review are as follows: | |||
Technical Staffing and Training: Satisfactory Status of Materials Inspection Program: Satisfactory Technical Quality of Inspections: Satisfactory Technical Quality of Licensing Actions: Satisfactory | |||
Colorado Proposed Final IMPEP Report Page 2 Technical Quality of Incident and Allegation Activities: Satisfactory Compatibility Requirements: Unsatisfactory Sealed Source and Device Evaluation Program: Satisfactory Uranium Recovery Program: Satisfactory Overall finding: Adequate to protect public health and safety and not compatible with the NRC's program. | |||
3.0 COMMON PERFORMANCE INDICATORS Five common performance indicators are used to review the NRC regional and Agreement State radioactive materials programs. These indicators are: (1) Technical Staffing and Training; (2) Status of Materials Inspection Program; (3) Technical Quality of Inspections; (4) Technical Quality of Licensing Actions; and (5) Technical Quality of Incident and Allegation Activities. | |||
3.1 Technical Staffing and Training The ability to conduct effective licensing and inspection programs is largely dependent on having a sufficient number of experienced, knowledgeable, well-trained technical personnel. Under certain conditions, staff turnover could have an adverse effect on the implementation of these programs, and could affect public health and safety. Apparent trends in staffing must be explored. Review of staffing also requires consideration and evaluation of the levels of training and qualification. The evaluation standard measures the overall quality of training available to, and taken by, materials program personnel. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-103, Reviewing the Common Performance Indicator: Technical Staffing and Training, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
* A well-conceived and balanced staffing strategy has been implemented throughout the review period. | |||
* Agreement State training and qualification program is equivalent to NRC Inspection Manual Chapter (IMC) 1248, Formal Qualifications Program for Federal and State Material and Environmental Management Programs. | |||
* Qualification criteria for new technical staff are established and are followed or qualification criteria will be established if new staff members are hired. | |||
* Any vacancies, especially senior-level positions, are filled in a timely manner. | |||
* There is a balance in staffing of the licensing and inspection programs. | |||
* Management is committed to training and staff qualification. | |||
* Individuals performing materials licensing and inspection activities are adequately qualified and trained to perform their duties. | |||
Colorado Proposed Final IMPEP Report Page 3 | |||
* License reviewers and inspectors are trained and qualified in a reasonable period of time. | |||
: b. Discussion The team determined that the Program has sufficient staff to carry out the responsibilities of the Agreement State Program and a good balance between licensing and inspection staffing levels. The Colorado Agreement State Program is comprised of 13 staff members, which is equivalent to 12.25 full-time equivalents (FTE) for the radioactive materials program when fully staffed. The Radiation Management Program Manager oversees both radioactive materials and machine regulation. The Radioactive Materials Unit Leader supervises the unit responsible for radioactive materials licensing and inspection. The Compliance Lead oversees inspection-related activities in the unit, while the Licensing Lead overseas the licensing activities of the unit. | |||
At the time of the review, there were no vacancies. During the review period, six staff members left the program and seven staff members were hired. Three of the staff members retired, two staff members moved from Colorado due to personal reasons, and one staffer left for a career change. The positions were vacant from less than a month to approximately 6 months. Vacancies had minimal impact on the Programs performance. | |||
The Program has a training and qualification manual compatible with the NRCs IMC 1248. The training program is managed by the Radioactive Materials Unit Leader and the Compliance and Licensing Leads who set personal training goals for staff, as well as document and discuss progress with staff. The Radioactive Materials Unit Leader and the Compliance and Licensing Leads also determine when staff are sufficiently trained to work independently while performing licensing and inspection-related activities, including partial qualification for certain activities. | |||
Staff understand training expectations and are qualified in an appropriate amount of time. All staff receive training and experience to become qualified to perform both inspection and licensing activities. Staff spoke highly of the Programs commitment to training, especially support to attend NRC-sponsored training, the use of on-the-job training, and peer assistance while learning new duties. Experienced staff also receive support for refresher training that is compatible with the expectations detailed in IMC 1248. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.1.a. and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Staffing and Training, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
Colorado Proposed Final IMPEP Report Page 4 3.2 Status of Materials Inspection Program Periodic inspections of licensed operations are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. The frequency of inspections is specified in IMC 2800, Materials Inspection Program, and is dependent on the amount and kind of material, the type of operation licensed, and the results of previous inspections. There must be a capability for maintaining and retrieving statistical data on the status of the inspection program. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-101, Reviewing the Common Performance Indicator: Status of the Materials Inspection Program, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
* Initial inspections and inspections of Priority 1, 2, and 3 licensees are performed at the frequency prescribed in IMC 2800. | |||
* Candidate licensees working under reciprocity are inspected in accordance with the criteria prescribed in IMC 1220, Processing of NRC Form 241, Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, and Offshore Waters, and Inspection of Agreement State Licensees Operating Under Title 10 of the Code of Federal Regulations 150.20. | |||
* Deviations from inspection schedules are normally coordinated between technical staff and management. | |||
* There is a plan to perform any overdue inspections and reschedule any missed or deferred inspections; or a basis has been established for not performing any overdue inspections or rescheduling any missed or deferred inspections. | |||
* Inspection findings are communicated to licensees in a timely manner (30 calendar days, or 45 days for a team inspection, as specified in IMC 0610, Nuclear Material Safety and Safeguards Inspection Reports). | |||
: b. Discussion Over the course of the review period, Colorado conducted two percent, or one inspection out of 45, of Priority 1, 2, 3, and initial inspections overdue. The only overdue inspection involved a major change to a license. At the time the initial inspection was due, the Program contacted the licensee to determine if material was being used under the new authorization. The licensee indicated it was not, so the Program postponed the initial inspection. Shortly after that communication, the Compliance Lead retired and no transfer of this communication was made to the new Lead. It was discovered at the next routine inspection that the material for the new authorization was in use and the initial inspection was considered overdue. | |||
Colorados inspection frequencies are the same for similar license types in IMC 2800. | |||
Colorado Proposed Final IMPEP Report Page 5 A sampling of 24 inspection reports that were reviewed solely for the purpose of tracking the communications of inspection results indicated that two were communicated to the licensees beyond Colorados goal of 30 days after the inspection exit. Neither of these communications were more than 45 days after the inspection exit. | |||
Each year of the review period, Colorado performed greater than 20 percent of candidate reciprocity inspections. | |||
Colorado inspectors are required by their individual position descriptions to perform at least 50 percent of assigned inspections before or by the inspection due date and all other inspections before the overdue date. Having this requirement tied to job performance appears to ensure the Program performs nearly all inspections within the allotted time. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.2.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Status of Materials Inspection Program, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
3.3 Technical Quality of Inspections Inspections, both routine and reactive, provide assurance that licensee activities are carried out in a safe and secure manner. Accompaniments of inspectors performing inspections, and the critical evaluation of inspection records, are used to assess the technical quality of an Agreement States inspection program. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-102, Reviewing the Common Performance Indicator: Technical Quality of Inspections, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
* Inspections of licensed activities focus on health, safety, and security. | |||
* Inspection findings are well-founded and properly documented in reports. | |||
* Management promptly reviews inspection results. | |||
* Procedures are in place and used to help identify root causes and poor licensee performance. | |||
* Inspections address previously identified open items and violations. | |||
* Inspection findings lead to appropriate and prompt regulatory action. | |||
Colorado Proposed Final IMPEP Report Page 6 | |||
* Supervisors, or senior staff as appropriate, conduct annual accompaniments of each inspector to assess performance and assure consistent application of inspection policies. | |||
* For programs with separate licensing and inspection staffs, procedures are established and followed to provide feedback information to license reviewers. | |||
* For Agreement States, inspection guides are consistent with NRC guidance. | |||
* An adequate supply of calibrated survey instruments is available to support the inspection program. | |||
: b. Discussion The team evaluated the quality of inspection reports and enforcement documentation, and interviewed inspectors involved in 25 materials inspections conducted during the review period. The casework reviewed included inspections conducted by 10 of Colorados inspectors and covered medical, industrial, commercial, academic, research, and service licenses. | |||
Team members accompanied four Program inspectors the week of February 26, 2018, and on April 2, 2018. No performance issues were noted during the inspector accompaniments. The inspectors were well-prepared and thorough, and assessed the impact of licensed activities on health, safety, and security. The team noted that nearly all Colorado inspections are announced and many are compliance-based inspections. | |||
The inspector accompaniments are identified in Appendix B. | |||
The team identified that Colorados inspection results were well documented and violations were well supported. The Program follows its own documented inspection and enforcement procedures. The Compliance Lead or Radioactive Materials Unit Leader performed supervisory accompaniments for each inspector annually each year of the review period. | |||
The team noted that Colorado has ample supplies of radiation survey instruments such as Geiger-Mueller meters, scintillation detectors, ion chambers, micro-R meters, and neutron detectors to support its inspection program. The portable instruments used during the inspector accompaniments were operational and calibrated. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.3.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Inspections, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
Colorado Proposed Final IMPEP Report Page 7 3.4 Technical Quality of Licensing Actions The quality, thoroughness, and timeliness of licensing actions can have a direct bearing on public health and safety, as well as security. An assessment of licensing procedures, actual implementation of those procedures, and documentation of communications and associated actions between the Colorado licensing staff and regulated community is a significant indicator of the overall quality of the licensing program. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-104, Reviewing the Common Performance Indicator: Technical Quality of Licensing Actions, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
* Licensing action reviews are thorough, complete, consistent, and of acceptable technical quality with health, safety, and security issues properly addressed. | |||
* Essential elements of license applications have been submitted and elements are consistent with current regulatory guidance (e.g., financial assurance, increased controls, pre-licensing guidance). | |||
* License reviewers, if applicable, have the proper signature authority for the cases they review independently. | |||
* License conditions are stated clearly and can be inspected. | |||
* Deficiency letters clearly state regulatory positions and are used at the proper time. | |||
* Reviews of renewal applications demonstrate a thorough analysis of a licensees inspection and enforcement history. | |||
* Applicable guidance documents are available to reviewers and are followed (e.g., | |||
NUREG-1556 series, pre-licensing guidance, regulatory guides, etc.). | |||
* Licensing practices for risk-significant radioactive materials are appropriately implemented including increased controls and fingerprinting orders (Part 37 equivalent). | |||
* Documents containing sensitive security information are properly marked, handled, controlled, and secured. | |||
: b. Discussion During the review period, Colorado performed 1,099 radioactive materials licensing actions. The team evaluated 27 of those licensing actions. The licensing actions selected for review included: five new applications; 11 amendments; four renewals; five terminations; and two decommissioning financial assurance actions. The team evaluated casework which included the following license types and actions: medical broad scope, academic broad scope, medical diagnostic and therapy, byproduct material produced using an accelerator, commercial manufacturing and distribution, industrial radiography, research and development, nuclear pharmacy, gauges, self-shielded irradiators, well-logging, service providers, decommissioning actions, and financial assurances. The casework sample represented work from eight license reviewers. | |||
Colorado Proposed Final IMPEP Report Page 8 Licensing actions were well documented. Each completed licensing action was reviewed by the Licensing Lead in its entirety. In the last step, the Radioactive Materials Unit Leader administratively reviewed and signed the license. The team noted that the incorporation of a licensing action peer review process has led to consistently high quality products. | |||
The team evaluated the pre-licensing guidance and the pre-licensing site visit aspect of the new license application process. The Program conducted pre-licensing site visits for all unknown entities in accordance with the checklist. The Program only issued a license once the applicant had, as a minimum, adequate facilities and equipment, as well as a qualified Radiation Safety Officer(s) and user(s). In addition, a new applicant with licensed radioactive material quantity equal to or exceeding Category 2 has to implement increased security measures in accordance with Colorados requirement prior to the issuance of the new license. Moreover, any licensee at a new location that will possess Category 2 quantities of radioactive material and above also has to implement increased security measures before the location will be authorized to possess the Category 2 quantities and above in the license. | |||
With regard to the licensing record management, the Program has used the NRCs Web-Based Licensing to maintain the licensees data and licenses, as well as to track licensing actions. All other documentation related to each licensing action are electronically stored in the Colorado Department of Public Health and Environment Record Management database under a unique control number assigned to each licensing action. | |||
All generally-licensed devices in Colorado are controlled by the Program. The Program requires all generally-licensed devices to be registered and the licensees must update their inventory and self-certification annually. In addition, the Program requires holders of any generally-licensed device with a quantity exceeding 1/10 of Category 3 radioactive material to have a specific license. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.4.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Licensing Actions, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
3.5 Technical Quality of Incident and Allegation Activities The quality, thoroughness, and timeliness of response to incidents and allegations of safety concerns can have a direct bearing on public health and safety. An assessment of incident response and allegation investigation procedures, actual implementation of these procedures, internal and external coordination, and investigative and followup | |||
Colorado Proposed Final IMPEP Report Page 9 actions, are a significant indicator of the overall quality of the incident response and allegation programs. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-105, Reviewing the Common Performance Indicator: Technical Quality of Incident and Allegation Activities, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
* Incident response, investigation, and allegation procedures are in place and followed. | |||
* Response actions are appropriate, well-coordinated, and timely. | |||
* On-site responses are performed when incidents have potential health, safety, or security significance. | |||
* Appropriate followup actions are taken to ensure prompt compliance by licensees. | |||
* Followup inspections are scheduled and completed, as necessary. | |||
* Notifications are made to the NRC Headquarters Operations Center for incidents requiring a 24-hour or immediate notification to the Agreement State or NRC. | |||
* Incidents are reported to the Nuclear Material Events Database (NMED). | |||
* Allegations are investigated in a prompt, appropriate manner. | |||
* Concerned individuals are notified of investigation conclusions. | |||
* Concerned individuals identities are protected, as allowed by law. | |||
: b. Discussion During the review period, 67 incidents were reported to the NMED database by Colorado. The team selected 18 events to evaluate. The casework reviewed included: | |||
three radiography events involving the inability to retract the source; three radiography events involving source disconnects (all different licensees); one failed attempted break-in of a radiography truck; four medical events; one unplanned contamination event involving technetium-99m; two damaged portable gauge events; one leaking electron capture device foil; one self-shielded irradiator exposure drawer failure; a failure of a room mounted radiation exposure detector; and one event involving contamination from water treatment. | |||
The team found that inspectors properly evaluated each event, interviewed involved individuals, and thoroughly documented their findings. Enforcement actions were taken where appropriate. | |||
When an event is reported to the Program, staff and management collectively evaluate the information received to determine its health and safety significance and then decide on the appropriate response. That response can range anywhere from responding immediately to reviewing the event during the next inspection. For each incident that was determined to have potential health and safety significance, the Program responded immediately. The team also found that the Program responded to events in accordance with their established procedure. | |||
Colorado Proposed Final IMPEP Report Page 10 The team evaluated the Programs reporting of events to the NRCs Headquarters Operations Officer (HOO). The team noted that in each case reviewed where HOO notification was required, the Program reported all events within the required timeframe. | |||
Additionally, an evaluation was made to determine if the Program had failed to report any events to the HOO where reporting was required, but none were found. | |||
During the review period, 12 allegations were received directly by Colorado with 2 additional allegations referred by the NRC. The team evaluated 10 of the allegations and found that the Program took prompt and appropriate action in response to the concerns raised. All of the allegations reviewed were appropriately closed, concerned individuals were notified of the actions taken, and allegers identities were protected whenever possible. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.5.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Incident and Allegation Activities, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
4.0 NON-COMMON PERFORMANCE INDICATORS Four non-common performance indicators are used to review Agreement State programs: (1) Compatibility Requirements; (2) Sealed Source and Device (SS&D) | |||
Evaluation Program; (3) Low-Level Radioactive Waste Disposal (LLRW) Program; and (4) Uranium Recovery Program. All four non-common performance indicators applied to this review. | |||
4.1 Compatibility Requirements State statutes should authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the agreement. The statutes must authorize the State to promulgate regulatory requirements necessary to provide reasonable assurance of protection of public health, safety, and security. The State must be authorized through its legal authority to license, inspect, and enforce legally binding requirements, such as regulations and licenses. | |||
NRC regulations that should be adopted by an Agreement State for purposes of compatibility or health and safety should be adopted in a time frame so that the effective date of the State requirement is not later than three years after the effective date of the NRC's final rule. Other program elements, as defined in Appendix A of State Agreements procedure SA-200, Compatibility Categories and Health and Safety Identification for NRC Regulations and Other Program Elements, that have been designated as necessary for maintenance of an adequate and compatible program, | |||
Colorado Proposed Final IMPEP Report Page 11 should be adopted and implemented by an Agreement State within 6 months following NRC designation. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-107, Reviewing the Non-Common Performance Indicator: Compatibility Requirements, and evaluated Colorados performance with respect to the following performance indicator objectives. | |||
A complete list of regulation amendments can be found on the NRC Web site at the following address: https://scp.nrc.gov/regtoolbox.html. | |||
* The Agreement State program does not create conflicts, duplications, gaps, or other conditions that jeopardize an orderly pattern in the regulation of radioactive materials under the Atomic Energy Act, as amended. | |||
* Regulations adopted by the Agreement State for purposes of compatibility or health and safety were adopted no later than 3 years after the effective date of the NRC regulation. | |||
* Other program elements, as defined in SA-200 that have been designated as necessary for maintenance of an adequate and compatible program, have been adopted and implemented within six months of NRC designation. | |||
* The State statutes authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the agreement. | |||
* The State is authorized through its legal authority to license, inspect, and enforce legally binding requirements such as regulations and licenses. | |||
* Impact of sunset requirements, if any, on the States regulations. | |||
: b. Discussion Colorado became an Agreement State on February 1, 1968. The Department is authorized as the States radiation control agency under the Colorado Revised Statutes Title 25, Article 11, known as the Radiation Control Act. | |||
As noted in Section 2.0, Colorado was found unsatisfactory for this indicator during the 2014 IMPEP review, largely due to a number of modifications to Colorado statutes prior to that review which were not compatible with NRC requirements. These modifications were initiated by parties outside the Department and were made by the State Legislature without concurrence by Colorados Radiation Control Program. To resolve the issue, Colorado management obtained permission from the Governors Office to conduct a stakeholder process in the summer of 2014 to address incompatible sections of the Radiation Control Act. Following this process, the Department submitted the legislation changes to NRC for review, and, as noted in the July 15, 2016, letter from NRC to Colorado (Accession Number ML16162A165), the NRC indicated that it had no further comments on Colorados legislation. The revised legislation is compatible with NRC requirements. | |||
Colorado Proposed Final IMPEP Report Page 12 All Colorado State agencies are required to plan for future regulatory changes at least one year in advance through establishment of a regulatory agenda which is issued in November of each year. Whether a rulemaking activity will take place in the second or possibly third year following NRC issuance is dependent upon the date of the NRC rule change. Most rulemaking efforts are completed in approximately 12-14 months. On average, the State can promulgate regulations in six to 12 months, depending on the resolution of comments received during the various comment periods. Comments are requested from a Radiation Advisory Committee, the NRC, and the affected community. | |||
Under the Colorado Administrative Procedure Act, all regulations in the State expire on May 15 of each year unless that expiration is postponed by the legislature (C.R.S. | |||
§24-4-103(8)(c)(I)). Each year, the legislature initiates a bill postponing nearly all regulatory expirations, including those of the Program. Those regulations required for compliance with Federal requirements are typically renewed annually, although this is at the discretion and purview of the legislature. Historically, the Colorado Rules and Regulations Pertaining to Radiation Control have been approved each year, especially since such regulations are necessary for Colorado to maintain its authority under the agreement with the NRC which is the States policy (C.R.S. §25-11-102). | |||
At the time of the prior IMPEP review in 2014, Colorado had a backlog of regulatory changes, some of which were dependent upon changes to the statute. Some of this backlog continued into the current review period, with some regulatory changes requiring coordination of regulatory and statutory efforts. During the review period, Colorado submitted 10 proposed regulation amendments, 25 final regulation amendments, 11 revised final regulation amendments, and the previously mentioned legislation to the NRC for a compatibility review. Portions of two of the amendments were overdue for State adoption at the time of submission, from 4 months to nearly 2 years delayed. The primary reason for the delay was due to the focus of resources on addressing prior NRC regulatory comments and to initiate changes to the enabling legislation associated with NRC comments. At the time of this review, no amendments were overdue. | |||
: c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 4.1.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Compatibility Requirements, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
4.2 Sealed Source and Device (SS&D) Evaluation Program Adequate technical evaluations of SS&D designs are essential to ensure that SS&Ds will maintain their integrity and that the design is adequate to protect public health and safety. NUREG-1556, Volume 3, Consolidated Guidance about Materials Licenses: | |||
Applications for Sealed Source and Device Evaluation and Registration, provides | |||
Colorado Proposed Final IMPEP Report Page 13 information on conducting SS&D reviews and establishes useful guidance for teams. | |||
Under this guidance, three sub elements: Technical Staffing and Training, Technical Quality of the Product Evaluation Program, and Evaluation of Defects and Incidents Regarding SS&Ds, are evaluated to determine if the SS&D program is satisfactory. | |||
Agreement States with authority for SS&D evaluation programs who are not performing SS&D reviews are required to commit in writing to having an SS&D evaluation program in place before performing evaluations. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-108, Reviewing the Non-Common Performance Indicator: Sealed Source and Device Evaluation Program, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
Technical Staffing and Training | |||
* A well-conceived and balanced staffing strategy has been implemented throughout the review period. | |||
* Qualification criteria for new technical staff are established and are being followed or qualification criteria will be established if new staff members are hired. | |||
* Any vacancies, especially senior-level positions, are filled in a timely manner. | |||
* Management is committed to training and staff qualification. | |||
* Individuals performing SS&D evaluation activities are adequately qualified and trained to perform their duties. | |||
* SS&D reviewers are trained and qualified in a reasonable period of time. | |||
Technical Quality of the Product Evaluation Program | |||
* SS&D evaluations are adequate, accurate, complete, clear, specific, and consistent with the guidance in NUREG-1556, Volume 3. | |||
Evaluation of Defects and Incidents | |||
* SS&D incidents are reviewed to identify possible manufacturing defects and the root causes of these incidents. | |||
* Incidents are evaluated to determine if other products may be affected by similar problems. Appropriate action and notifications to NRC, Agreement States, and others, as appropriate, occur in a timely manner. | |||
: b. Discussion Technical Staffing and Training Colorado has six staff qualified to perform SS&D reviews with one in training and no vacancies at the time of the review. During the review period two qualified SS&D reviewers left the program and two staff members were hired. The positions were | |||
Colorado Proposed Final IMPEP Report Page 14 vacant for less than a month. Colorado has a training program for SS&D reviewers equivalent to the NRC training requirements listed in IMC 1248, Appendix D. | |||
Technical Quality of the Product Evaluation Colorado currently has two SS&D registrants. The Program completed no SS&D actions during the review period. The team evaluated an SS&D action that was pending during the onsite review. This pending action is an amendment. The pending review is technically sound; proper checklists are being used and meet the criteria of NUREG-1556 Volume 3 Revision 1. | |||
When Colorado completes all SS&D casework, any changes to the updated SS&D registration are tied to the applicants radioactive materials license. | |||
Due to the lack of review actions, Program management noted that Colorado may use alternate technical assistance for review of complex SS&D actions should it receive one. | |||
Evaluation of Defects and Incidents Regarding SS&Ds The team received no incidents involving SS&D registered products during the review period. Incident procedures are in place should an SS&D-related incident occur. | |||
: c. Evaluation The team determined that, during the review period, Colorado has met the performance indicator objectives listed in Section 4.2.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Sealed Source and Device Evaluation Program, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
4.3 LLRW Disposal Program In 1981, the NRC amended its Policy Statement, Criteria for Guidance of States and NRC in Discontinuance of NRC Authority and Assumption Thereof by States Through Agreement, to allow a State to seek an amendment for the regulation of LLRW as a separate category. Those States with existing Agreements prior to 1981 were determined to have continued LLRW disposal authority without the need of an amendment. Although the Colorado Agreement State Program has authority to regulate a LLRW disposal facility, the NRC has not required States to have a program for licensing a disposal facility until such time as the State has been designated as a host State for a LLRW disposal facility. When an Agreement State has been notified or becomes aware of the need to regulate a LLRW disposal facility, it is expected to put in place a regulatory program that will meet the criteria for an adequate and compatible LLRW program. There are no plans for a commercial LLRW disposal facility in Colorado. Accordingly, the team did not review this indicator. | |||
Colorado Proposed Final IMPEP Report Page 15 4.4 Uranium Recovery Program The objective is to determine if Colorados uranium recovery Program is adequate to protect public health and safety. Five sub-elements are used to make this determination: (1) Technical Staffing and Training; (2) Status of Uranium Recovery Inspection Program; (3) Technical Quality of Inspections; (4) Technical Quality of Licensing Actions; and (5) Technical Quality of Incident and Allegation Activities. | |||
: a. Scope The team used the guidance in State Agreements procedure SA-110, Reviewing the Non-Common Performance Indicator: Uranium Recovery Program, and evaluated Colorados performance with respect to the following performance indicator objectives: | |||
Technical Staffing and Training | |||
* Qualified and trained technical staff is available to license, regulate, control, inspect, and assess the operation and performance of the uranium recovery program. | |||
* Qualification criteria for new uranium recovery technical staff are established and are being followed or that qualification criteria will be established if new staff members are hired. | |||
* Any vacancies, especially senior-level positions, are filled in a timely manner. | |||
* There is a balance in staffing the uranium recovery licensing and inspection programs. | |||
* Management is committed to training and staff qualification. | |||
* Individuals performing uranium recovery licensing and inspection activities are adequately qualified and trained to perform their duties. | |||
* Uranium recovery license reviewers and inspectors are trained and qualified in a reasonable period of time. | |||
Status of Uranium Recovery Inspection Program | |||
* The uranium recovery facility is inspected at prescribed frequencies. | |||
* Statistical data on the status of the inspection program are maintained and can be retrieved. | |||
* Deviations from inspection schedules are coordinated between uranium recovery technical staff and management. | |||
* There is a plan to reschedule any missed or deferred inspections or a basis has been established for not rescheduling any missed inspections. | |||
* Inspection findings are communicated to licensees in a timely manner. | |||
Technical Quality of Inspections | |||
* Inspections of uranium recovery licensed activities focus on health, safety, and security. | |||
* Inspection findings are well-founded and properly documented in reports. | |||
* Management promptly reviews inspection results. | |||
Colorado Proposed Final IMPEP Report Page 16 | |||
* Procedures are in place and used to help identify root causes and poor licensee performance. | |||
* Inspections address previously identified open items and violations. | |||
* Inspection findings lead to appropriate and prompt regulatory action. | |||
* Supervisors, or senior staff as appropriate, conduct annual accompaniments of each uranium recovery inspector to assess performance and assure consistent application of inspection policies. | |||
* For Agreement States, inspection guides are consistent with NRC guidance. | |||
* An adequate supply of calibrated survey instruments is available to support the inspection program. | |||
Technical Quality of Licensing Actions | |||
* Licensing action reviews are thorough, complete, consistent, and of acceptable technical quality with health, safety, and security issues properly addressed. | |||
* Applicable uranium recovery guidance documents are available to reviewers and are followed (e.g., pre-licensing guidance, regulatory guides, etc.). | |||
* Essential elements of license applications have been submitted and meet current NRC or Agreement State regulatory guidance (e.g., financial assurance, increased controls, etc.) | |||
* Uranium recovery license reviewers, if applicable, have the proper signature authority for the cases they review independently. | |||
* License conditions are stated clearly and can be inspected. | |||
* Deficiency letters clearly state regulatory positions and are used at the proper time. | |||
* Reviews of renewal applications demonstrate a thorough analysis of a licensees inspection and enforcement history. | |||
* Licensing practices for risk significant radioactive materials are appropriately implemented including increased controls and fingerprinting orders (Part 37 equivalent). | |||
* Documents containing sensitive security information are properly marked, handled, controlled, and secured. | |||
Technical Quality of Incident and Allegation Activities | |||
* Uranium recovery Incident response, investigation, and allegation procedures are in place and followed. | |||
* Response actions are appropriate, well-coordinated, and timely. | |||
* On-site responses are performed when incidents have potential health, safety or security significance. | |||
* Appropriate followup actions are taken to ensure prompt compliance by licensees. | |||
* Followup inspections are scheduled and completed, as necessary. | |||
* Notifications are made to the NRC Headquarters Operations Center for incidents requiring a 24-hour or immediate notification to the Agreement State or NRC. | |||
* Incidents are reported to the NMED. | |||
* Allegations are investigated in a prompt, appropriate manner. | |||
Colorado Proposed Final IMPEP Report Page 17 | |||
* Concerned individuals are notified of investigation conclusions. | |||
* Concerned individuals identities are protected, as allowed by law. | |||
: b. Discussion Technical Staffing and Training The team determined that the Programs qualifications and staffing levels for the uranium recovery program were adequate. At the time of the review, there were no vacancies; one qualified technical staff member performed most of the project management, inspections, and licensing actions for Colorados uranium recovery program. Colorado had two qualified uranium recovery staff over the course of the review period. One of the staff members retired from the program in 2015. That FTE is no longer dedicated to the uranium recovery program. | |||
The uranium recovery program has a training program equivalent to the NRC training requirements listed in IMC 1248, Appendix E. The uranium recovery program staff has training in health physics, geology/geophysics, and inspection procedures. The staff also receive annual facility safety refresher training and attend NRC-sponsored training and webinars. The uranium recovery program technical staff member demonstrated thorough understanding of State regulations and the NRC guidance related to uranium recovery. | |||
The uranium recovery program also has access to individuals from within the Program, staff in the Hazardous Materials and Waste Management Division, and the Department, for technical support. The uranium recovery program has contracts with consulting firms to assist as needed, as well. | |||
Status of Uranium Recovery Inspection Program The uranium recovery program staff performed seven inspections during the review period. The team determined that the program completed the inspections in accordance with the frequency in the NRCs IMC 2800. | |||
Inspection findings for the uranium recovery program were communicated by formal correspondence to the licensee within 30 days following the inspection. Two instances of late reports issued to licensees were noted, sent from 39 to 54 days after the completion of the inspection. The delay was attributed to extra staff time taken to review the inspection report and inspection results letter. | |||
The Program updated the Inspection Procedure for Uranium Recovery Facilities in Closure (revised December 6, 2017) that are licensed under the License Category of 14.A for decommissioning under the State of Colorado Rules and Regulations Pertaining to Radiation Control. Under the updated procedure, these facilities are to be inspected every three years. The facilities are also Uranium Mill Tailings Radiation Control Act Title II sites. The inspector created an Inspection Procedure for Uranium Recovery Facilities in Closure to establish the routine compliance inspection program for conventional uranium mills in closure to be consistent with NRC guidance NUREG-1620 | |||
Colorado Proposed Final IMPEP Report Page 18 Appendix D Guidance to the U.S. Nuclear Regulatory Commission Staff for Reviewing Long-Term Surveillance Plans. | |||
The team identified that one uranium site inspection (Sweeney Mining & Milling Corporation) was, at the time of the review, overdue by nearly 3 years (35 months). This was due to the fact that inspection results from the 2015 inspection had not been presented to the licensee in a manner consistent with the Radiation Control Act. During the onsite review, Program staff noted that a routine inspection is planned in the spring of 2018. In addition, the Program was implementing a plan to ensure that, in the future, no licensee will have an overdue inspection based on an inability to communicate inspection results to a licensee. | |||
Technical Quality of Inspections The team evaluated seven inspection files which included a variety of uranium recovery inspection activities in different stages of license operations, and determined that the inspection reports were thorough, complete, consistent, and had sufficient documentation to ensure that licensee performance with respect to health, safety and security was acceptable. The inspection results were well-founded, supported by regulations, and were appropriately documented. There was no enforcement action for the period of review. | |||
The Programs inspectors followed the radioactive materials unit inspection manual (revised June 2016) for conducting inspections. The Program has inspection procedures specific to the uranium recovery program. The inspector used checklists to document inspections. Inspection reports were well documented and provided suitable depth of coverage, addressed license conditions and the regulations, and demonstrated that the inspector followed corrective actions for items of concerns that were identified. | |||
Some of the inspection files contained photographs supporting both the facility structures and items of concerns. The Programs records indicated that supervisor accompaniments of the inspector were performed annually during the review period. | |||
Technical Quality of Licensing Actions The Program completed seven licensing actions during the review period. The team examined the files and associated documentation related to the licensing of conventional uranium recovery mill facilities which included six amendments, and one renewal. | |||
The uranium recovery program manages the following uranium recovery sites: | |||
: 1. Pinon Ridge Mill, | |||
: 2. Cotter Corporation Canon City Mill, | |||
: 3. Umetco Uravan Mill, and | |||
: 4. Hecla Durita Mill. | |||
The uranium recovery program manages the following contaminated sites: | |||
: 1. Cotter Corporation Schwartzwalder Mine, | |||
: 2. Sweeney Mill, and | |||
: 3. Colorado School of Mines Research Institute Table Mountain Research Center | |||
Colorado Proposed Final IMPEP Report Page 19 There were no operational facilities in the State at the time of the review except for Cotter Corporation Schwartzwalder Mine which is a water treatment facility. The Umetco Uravan Mill and the Hecla Durita Mill are in closure status. | |||
The licensing actions completed during the review period consisted of: | |||
decommissioning plans, modification of the restricted area, designation of radiation safety officer, license transfer, annual financial assurance updates, and compliance monitoring. The team interviewed staff members about the status of each regulated site. | |||
Management and staff were familiar with the technical details and conditions existing at each site. | |||
The team concluded that the licensing actions were complete, consistent, and of acceptable quality. Program staff use a review procedure and checklist for licensing reviews. All response letters for each incoming request or report contained secondary technical or management review and approval. | |||
The team evaluated the decision analysis reports for all the licensing actions which included public comments. The team also evaluated the license for the Cotter Corporation request to change the restricted area specified in the license and release the requested areas to be unrestricted. The Cotter Corporation decision analysis document contained a thorough evaluation of the application, as well as an adequate basis for the staffs licensing decision. | |||
Technical Quality of Incident and Allegation Activities The uranium recovery program did not respond to any incidents and received no allegations during the review period. | |||
: c. Evaluation The team determined that, during the review period, the uranium recovery program met the performance indicator objectives listed in Section 4.4.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Uranium Recover Program, be found satisfactory. | |||
: d. MRB Decision The final report will present the MRBs conclusion regarding this indicator. | |||
5.0 | |||
==SUMMARY== | |||
As noted in Sections 3.0 and 4.0 above, Colorados performance was found satisfactory for all performance indicators reviewed. The team did not make any recommendations regarding program performance and there were no recommendations from the 2014 IMPEP review to be addressed. | |||
Colorado Proposed Final IMPEP Report Page 20 Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with NRC's program. | |||
Based on the results of the current IMPEP review, the team recommends that the next full IMPEP review take place in approximately four years, with a periodic meeting in approximately two years. | |||
LIST OF APPENDICES Appendix A IMPEP Review Team Members Appendix B Inspection Accompaniments | |||
APPENDIX A IMPEP REVIEW TEAM MEMBERS Name Areas of Responsibility Lance Rakovan, NMSS Team Leader Technical Staffing and Training Compatibility Requirements Randy Erickson, Region IV Technical Quality of Incident and Allegation Activities Sherrie Flaherty, MN Status of Materials Inspection Program Technical Quality of Materials Inspections Frank Tran, Region III Technical Quality of Licensing Actions Ron Parsons, TN Sealed Source & Device Evaluation Program Gehan Flanders, TX Uranium Recovery Program Orysia Masnyk-Bailey , Region I Inspector Accompaniments Lizette Roldán-Otero, Ph.D., NMSS Inspector Accompaniments | |||
APPENDIX B INSPECTION ACCOMPANIMENTS The following inspection accompaniments were performed prior to the on-site IMPEP review: | |||
Accompaniment No.: 1 License No.: CO 854-02 License Type: Diagnostic Nuclear Medicine Priority: 5 Inspection Date: 02/26/2018 Inspector: DB Accompaniment No.: 2 License No.: CO 997-01 License Type: Industrial Radiography Priority: 1 Inspection Date: 02/27/2018 Inspector: MD Accompaniment No.: 3 License No.: CO 1139-01 License Type: Portable Gauge Priority: 5 Inspection Date: 02/28/2018 Inspector: TT Accompaniment No.: 4 License No.: CO 038-02 License Type: High Dose Remote Afterloader Priority: 2 Inspection Date: 02/29/2018 Inspector: RL Accompaniment No.: 5 License No.: CO 997-01 License Type: Industrial Radiography (TJS) Priority: 1 Inspection Date: 04/03/18 Inspector: MD | |||
Agenda for Management Review Board Meeting June 26, 2018, 1:00 p.m. - 4:00 p.m. (ET), OWFN-17B04 | |||
: 1. Announcement of public meeting. Request for members of the public to indicate they are participating and their affiliation. | |||
: 2. MRB Chair convenes meeting. Introduction of MRB members, review team members, State representatives, and other participants. | |||
: 3. Consideration of the Colorado IMPEP Report. | |||
A. Presentation of Findings Regarding Colorados Program and Discussion. | |||
- Technical Staffing and Training | |||
- Status of Materials Inspection Program | |||
- Technical Quality of Inspections | |||
- Technical Quality of Licensing Actions | |||
- Technical Quality of Incident and Allegation Activities | |||
- Compatibility Requirements | |||
- Sealed Source & Device Evaluation Program | |||
- Uranium Recovery Program B. IMPEP Team Recommendations. | |||
- Recommendation for Adequacy and Compatibility Ratings | |||
- Recommendation for Next IMPEP Review C. MRB Consultation/Comments on Issuance of Report. | |||
: 4. Request for comments from Colorado representatives, OAS Liaison, and State IMPEP team members. | |||
: 5. Questions/comments from members of the public. | |||
: 6. Adjournment.}} |
Latest revision as of 23:28, 20 October 2019
ML18163A239 | |
Person / Time | |
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Issue date: | 06/18/2018 |
From: | Paul Michalak NRC/NMSS/DMSST/ASPB |
To: | Tison Campbell, Dapas M, Dan Dorman, Darrell Roberts NRC/EDO, Office of Nuclear Material Safety and Safeguards, NRC/OGC, Region 3 Administrator |
Ravokan L | |
References | |
Download: ML18163A239 (29) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 2018 MEMORANDUM TO: Daniel H. Dorman Deputy Executive Director for Materials, Waste, Research, State, Tribal, Compliance, Administration, and Human Capital Programs Office of the Executive Director for Operations Tison A. Campbell, Acting Assistant General Counsel for Reactor and Materials Rulemaking Office of the General Counsel Marc L. Dapas, Director Office of Nuclear Material Safety and Safeguards Darrell J. Roberts, Deputy Regional Administrator Region III FROM: Paul Michalak, Chief /RA/
Agreement State Programs Branch Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards
SUBJECT:
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF COLORADO This memorandum transmits to the Management Review Board (MRB) a proposed final report (Enclosure 1) documenting the Integrated Materials Performance Evaluation Program (IMPEP) review of Colorado. The review was conducted by a team of U.S. Nuclear Regulatory Commission (NRC) and Agreement State technical staff during the period of April 9 - 12, 2018.
The teams preliminary findings were discussed with Colorado on the last day of the review.
The team issued a draft report to Colorado on May 9, 2018, for factual comment. Colorado had no comments on the draft report.
CONTACT: Lance Rakovan, NMSS/MSST (301) 415-2589
MRB Members Overall, the team is recommending that Colorados performance be found satisfactory for all performance indicators reviewed. Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with the NRC's program. The team recommends that the next IMPEP review take place in approximately four years with a periodic meeting in approximately two years.
The MRB meeting to consider the Colorado report is scheduled for Tuesday, June 26, 2018, from 1:00 p.m. to 4:00 p.m. ET. In accordance with Management Directive 5.6, the meeting is open to the public. The agenda for the meeting is enclosed (Enclosure 2).
Enclosures:
- 1. Colorado Proposed Final Report
- 2. Agenda for MRB Meeting cc: Jennifer Opila, Program Manager Radiation Program Hazardous Materials & Waste Management Division Colorado Department of Public Health & Environment BJ Smith, MS Organization of Agreement States Liaison to the MRB
MRB Members
SUBJECT:
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF COLORADO.
Date: June 18, 2018 DISTRIBUTION: (SP08)
RidsEdoMail RidsOgcMailCenter RidsNmssOd RidsRgn3MailCenter RErickson, RSAO/RIV SFlahtery, MN GFlanders, TX RParsons, TN FTran, RIII OMasnyk-Bailey, RI LRoldan-Otero, NMSS AKock, NMSS OAS Board State of CO ML18163A239 OFFICE ASPB ASPB:BC NAME LRakovan PMichalak DATE 6/14/18 6/18/18 OFFICIAL RECORD COPY
INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM REVIEW OF THE COLORADO AGREEMENT STATE PROGRAM April 9 - 12, 2018 PROPOSED FINAL REPORT Enclosure
EXECUTIVE
SUMMARY
This report presents the results of the Integrated Materials Performance Evaluation Program (IMPEP) review of the Colorado Agreement State Program. The review was conducted during the period of April 9 - 12, 2018, by a team comprised of technical staff members from the U.S. Nuclear Regulatory Commission (NRC) and the States of Minnesota, Tennessee, and Texas.
Based on the results of this review, Colorados performance was found satisfactory for all performance indicators reviewed, including the finding for the non-common performance indicator, Compatibility Requirements, improving from unsatisfactory during the previous IMPEP review to satisfactory during this review.
The team did not make any recommendations and there were no open recommendations from previous reviews for the team to consider.
Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with the NRC's program. The team recommends that the next IMPEP review take place in approximately four years with a periodic meeting in approximately two years.
Colorado Proposed Final IMPEP Report Page 1
1.0 INTRODUCTION
This report presents the results of the review of the Colorado Agreement State Program radioactive materials safety program. The review was conducted during the period of April 9 - 12, 2018, by a team comprised of technical staff members from the U.S.
Nuclear Regulatory Commission (NRC) and the States of Minnesota, Tennessee, and Texas. Team members are identified in Appendix A. The review was conducted in accordance with the Agreement State Program Policy Statement, published in the Federal Register on October 18, 2017, and NRC Management Directive (MD) 5.6, Integrated Materials Performance Evaluation Program (IMPEP), dated February 26, 2004. Preliminary results of the review, which covered the period of April 12, 2014, to April 12, 2018, were discussed with Colorado managers on the last day of the review.
In preparation for the review, a questionnaire addressing the common performance indicators and applicable non-common performance indicators was sent to Colorado on November 21, 2017. Colorado provided its response to the questionnaire on March 22, 2018. A copy of the questionnaire response is available in the NRCs Agencywide Documents Access and Management System (ADAMS) using the Accession Number ML18082A369.
The Colorado Agreement State Program is administered by the Radiation Control Program (the Program). The Program is part of the Hazardous Materials & Waste Management Division (the Division), within the Department of Public Health and Environment (the Department). Organization charts for Colorado are available in ADAMS (Accession Number ML18082A357).
At the time of the review, the Colorado Agreement State Program regulated 316 specific licenses authorizing possession and use of radioactive materials. The review focused on the radioactive materials program as it is carried out under the Section 274b. (of the Atomic Energy Act of 1954, as amended) Agreement between the NRC and the State of Colorado.
The team evaluated the information gathered against the established criteria for each common and the applicable non-common performance indicators and made a preliminary assessment of the Colorado Agreement State Programs performance.
2.0 PREVIOUS IMPEP REVIEW AND STATUS OF RECOMMENDATIONS The previous IMPEP review concluded on April 11, 2014. The final report is available in ADAMS (Accession Number ML14192A009). The results of the review are as follows:
Technical Staffing and Training: Satisfactory Status of Materials Inspection Program: Satisfactory Technical Quality of Inspections: Satisfactory Technical Quality of Licensing Actions: Satisfactory
Colorado Proposed Final IMPEP Report Page 2 Technical Quality of Incident and Allegation Activities: Satisfactory Compatibility Requirements: Unsatisfactory Sealed Source and Device Evaluation Program: Satisfactory Uranium Recovery Program: Satisfactory Overall finding: Adequate to protect public health and safety and not compatible with the NRC's program.
3.0 COMMON PERFORMANCE INDICATORS Five common performance indicators are used to review the NRC regional and Agreement State radioactive materials programs. These indicators are: (1) Technical Staffing and Training; (2) Status of Materials Inspection Program; (3) Technical Quality of Inspections; (4) Technical Quality of Licensing Actions; and (5) Technical Quality of Incident and Allegation Activities.
3.1 Technical Staffing and Training The ability to conduct effective licensing and inspection programs is largely dependent on having a sufficient number of experienced, knowledgeable, well-trained technical personnel. Under certain conditions, staff turnover could have an adverse effect on the implementation of these programs, and could affect public health and safety. Apparent trends in staffing must be explored. Review of staffing also requires consideration and evaluation of the levels of training and qualification. The evaluation standard measures the overall quality of training available to, and taken by, materials program personnel.
- a. Scope The team used the guidance in State Agreements procedure SA-103, Reviewing the Common Performance Indicator: Technical Staffing and Training, and evaluated Colorados performance with respect to the following performance indicator objectives:
- A well-conceived and balanced staffing strategy has been implemented throughout the review period.
- Agreement State training and qualification program is equivalent to NRC Inspection Manual Chapter (IMC) 1248, Formal Qualifications Program for Federal and State Material and Environmental Management Programs.
- Qualification criteria for new technical staff are established and are followed or qualification criteria will be established if new staff members are hired.
- Any vacancies, especially senior-level positions, are filled in a timely manner.
- There is a balance in staffing of the licensing and inspection programs.
- Management is committed to training and staff qualification.
- Individuals performing materials licensing and inspection activities are adequately qualified and trained to perform their duties.
Colorado Proposed Final IMPEP Report Page 3
- License reviewers and inspectors are trained and qualified in a reasonable period of time.
- b. Discussion The team determined that the Program has sufficient staff to carry out the responsibilities of the Agreement State Program and a good balance between licensing and inspection staffing levels. The Colorado Agreement State Program is comprised of 13 staff members, which is equivalent to 12.25 full-time equivalents (FTE) for the radioactive materials program when fully staffed. The Radiation Management Program Manager oversees both radioactive materials and machine regulation. The Radioactive Materials Unit Leader supervises the unit responsible for radioactive materials licensing and inspection. The Compliance Lead oversees inspection-related activities in the unit, while the Licensing Lead overseas the licensing activities of the unit.
At the time of the review, there were no vacancies. During the review period, six staff members left the program and seven staff members were hired. Three of the staff members retired, two staff members moved from Colorado due to personal reasons, and one staffer left for a career change. The positions were vacant from less than a month to approximately 6 months. Vacancies had minimal impact on the Programs performance.
The Program has a training and qualification manual compatible with the NRCs IMC 1248. The training program is managed by the Radioactive Materials Unit Leader and the Compliance and Licensing Leads who set personal training goals for staff, as well as document and discuss progress with staff. The Radioactive Materials Unit Leader and the Compliance and Licensing Leads also determine when staff are sufficiently trained to work independently while performing licensing and inspection-related activities, including partial qualification for certain activities.
Staff understand training expectations and are qualified in an appropriate amount of time. All staff receive training and experience to become qualified to perform both inspection and licensing activities. Staff spoke highly of the Programs commitment to training, especially support to attend NRC-sponsored training, the use of on-the-job training, and peer assistance while learning new duties. Experienced staff also receive support for refresher training that is compatible with the expectations detailed in IMC 1248.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.1.a. and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Staffing and Training, be found satisfactory.
Colorado Proposed Final IMPEP Report Page 4 3.2 Status of Materials Inspection Program Periodic inspections of licensed operations are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. The frequency of inspections is specified in IMC 2800, Materials Inspection Program, and is dependent on the amount and kind of material, the type of operation licensed, and the results of previous inspections. There must be a capability for maintaining and retrieving statistical data on the status of the inspection program.
- a. Scope The team used the guidance in State Agreements procedure SA-101, Reviewing the Common Performance Indicator: Status of the Materials Inspection Program, and evaluated Colorados performance with respect to the following performance indicator objectives:
- Initial inspections and inspections of Priority 1, 2, and 3 licensees are performed at the frequency prescribed in IMC 2800.
- Candidate licensees working under reciprocity are inspected in accordance with the criteria prescribed in IMC 1220, Processing of NRC Form 241, Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, and Offshore Waters, and Inspection of Agreement State Licensees Operating Under Title 10 of the Code of Federal Regulations 150.20.
- Deviations from inspection schedules are normally coordinated between technical staff and management.
- There is a plan to perform any overdue inspections and reschedule any missed or deferred inspections; or a basis has been established for not performing any overdue inspections or rescheduling any missed or deferred inspections.
- Inspection findings are communicated to licensees in a timely manner (30 calendar days, or 45 days for a team inspection, as specified in IMC 0610, Nuclear Material Safety and Safeguards Inspection Reports).
- b. Discussion Over the course of the review period, Colorado conducted two percent, or one inspection out of 45, of Priority 1, 2, 3, and initial inspections overdue. The only overdue inspection involved a major change to a license. At the time the initial inspection was due, the Program contacted the licensee to determine if material was being used under the new authorization. The licensee indicated it was not, so the Program postponed the initial inspection. Shortly after that communication, the Compliance Lead retired and no transfer of this communication was made to the new Lead. It was discovered at the next routine inspection that the material for the new authorization was in use and the initial inspection was considered overdue.
Colorados inspection frequencies are the same for similar license types in IMC 2800.
Colorado Proposed Final IMPEP Report Page 5 A sampling of 24 inspection reports that were reviewed solely for the purpose of tracking the communications of inspection results indicated that two were communicated to the licensees beyond Colorados goal of 30 days after the inspection exit. Neither of these communications were more than 45 days after the inspection exit.
Each year of the review period, Colorado performed greater than 20 percent of candidate reciprocity inspections.
Colorado inspectors are required by their individual position descriptions to perform at least 50 percent of assigned inspections before or by the inspection due date and all other inspections before the overdue date. Having this requirement tied to job performance appears to ensure the Program performs nearly all inspections within the allotted time.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.2.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Status of Materials Inspection Program, be found satisfactory.
3.3 Technical Quality of Inspections Inspections, both routine and reactive, provide assurance that licensee activities are carried out in a safe and secure manner. Accompaniments of inspectors performing inspections, and the critical evaluation of inspection records, are used to assess the technical quality of an Agreement States inspection program.
- a. Scope The team used the guidance in State Agreements procedure SA-102, Reviewing the Common Performance Indicator: Technical Quality of Inspections, and evaluated Colorados performance with respect to the following performance indicator objectives:
- Inspections of licensed activities focus on health, safety, and security.
- Inspection findings are well-founded and properly documented in reports.
- Management promptly reviews inspection results.
- Procedures are in place and used to help identify root causes and poor licensee performance.
- Inspections address previously identified open items and violations.
- Inspection findings lead to appropriate and prompt regulatory action.
Colorado Proposed Final IMPEP Report Page 6
- Supervisors, or senior staff as appropriate, conduct annual accompaniments of each inspector to assess performance and assure consistent application of inspection policies.
- For programs with separate licensing and inspection staffs, procedures are established and followed to provide feedback information to license reviewers.
- For Agreement States, inspection guides are consistent with NRC guidance.
- An adequate supply of calibrated survey instruments is available to support the inspection program.
- b. Discussion The team evaluated the quality of inspection reports and enforcement documentation, and interviewed inspectors involved in 25 materials inspections conducted during the review period. The casework reviewed included inspections conducted by 10 of Colorados inspectors and covered medical, industrial, commercial, academic, research, and service licenses.
Team members accompanied four Program inspectors the week of February 26, 2018, and on April 2, 2018. No performance issues were noted during the inspector accompaniments. The inspectors were well-prepared and thorough, and assessed the impact of licensed activities on health, safety, and security. The team noted that nearly all Colorado inspections are announced and many are compliance-based inspections.
The inspector accompaniments are identified in Appendix B.
The team identified that Colorados inspection results were well documented and violations were well supported. The Program follows its own documented inspection and enforcement procedures. The Compliance Lead or Radioactive Materials Unit Leader performed supervisory accompaniments for each inspector annually each year of the review period.
The team noted that Colorado has ample supplies of radiation survey instruments such as Geiger-Mueller meters, scintillation detectors, ion chambers, micro-R meters, and neutron detectors to support its inspection program. The portable instruments used during the inspector accompaniments were operational and calibrated.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.3.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Inspections, be found satisfactory.
Colorado Proposed Final IMPEP Report Page 7 3.4 Technical Quality of Licensing Actions The quality, thoroughness, and timeliness of licensing actions can have a direct bearing on public health and safety, as well as security. An assessment of licensing procedures, actual implementation of those procedures, and documentation of communications and associated actions between the Colorado licensing staff and regulated community is a significant indicator of the overall quality of the licensing program.
- a. Scope The team used the guidance in State Agreements procedure SA-104, Reviewing the Common Performance Indicator: Technical Quality of Licensing Actions, and evaluated Colorados performance with respect to the following performance indicator objectives:
- Licensing action reviews are thorough, complete, consistent, and of acceptable technical quality with health, safety, and security issues properly addressed.
- Essential elements of license applications have been submitted and elements are consistent with current regulatory guidance (e.g., financial assurance, increased controls, pre-licensing guidance).
- License reviewers, if applicable, have the proper signature authority for the cases they review independently.
- License conditions are stated clearly and can be inspected.
- Deficiency letters clearly state regulatory positions and are used at the proper time.
- Reviews of renewal applications demonstrate a thorough analysis of a licensees inspection and enforcement history.
- Applicable guidance documents are available to reviewers and are followed (e.g.,
NUREG-1556 series, pre-licensing guidance, regulatory guides, etc.).
- Licensing practices for risk-significant radioactive materials are appropriately implemented including increased controls and fingerprinting orders (Part 37 equivalent).
- Documents containing sensitive security information are properly marked, handled, controlled, and secured.
- b. Discussion During the review period, Colorado performed 1,099 radioactive materials licensing actions. The team evaluated 27 of those licensing actions. The licensing actions selected for review included: five new applications; 11 amendments; four renewals; five terminations; and two decommissioning financial assurance actions. The team evaluated casework which included the following license types and actions: medical broad scope, academic broad scope, medical diagnostic and therapy, byproduct material produced using an accelerator, commercial manufacturing and distribution, industrial radiography, research and development, nuclear pharmacy, gauges, self-shielded irradiators, well-logging, service providers, decommissioning actions, and financial assurances. The casework sample represented work from eight license reviewers.
Colorado Proposed Final IMPEP Report Page 8 Licensing actions were well documented. Each completed licensing action was reviewed by the Licensing Lead in its entirety. In the last step, the Radioactive Materials Unit Leader administratively reviewed and signed the license. The team noted that the incorporation of a licensing action peer review process has led to consistently high quality products.
The team evaluated the pre-licensing guidance and the pre-licensing site visit aspect of the new license application process. The Program conducted pre-licensing site visits for all unknown entities in accordance with the checklist. The Program only issued a license once the applicant had, as a minimum, adequate facilities and equipment, as well as a qualified Radiation Safety Officer(s) and user(s). In addition, a new applicant with licensed radioactive material quantity equal to or exceeding Category 2 has to implement increased security measures in accordance with Colorados requirement prior to the issuance of the new license. Moreover, any licensee at a new location that will possess Category 2 quantities of radioactive material and above also has to implement increased security measures before the location will be authorized to possess the Category 2 quantities and above in the license.
With regard to the licensing record management, the Program has used the NRCs Web-Based Licensing to maintain the licensees data and licenses, as well as to track licensing actions. All other documentation related to each licensing action are electronically stored in the Colorado Department of Public Health and Environment Record Management database under a unique control number assigned to each licensing action.
All generally-licensed devices in Colorado are controlled by the Program. The Program requires all generally-licensed devices to be registered and the licensees must update their inventory and self-certification annually. In addition, the Program requires holders of any generally-licensed device with a quantity exceeding 1/10 of Category 3 radioactive material to have a specific license.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.4.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Licensing Actions, be found satisfactory.
3.5 Technical Quality of Incident and Allegation Activities The quality, thoroughness, and timeliness of response to incidents and allegations of safety concerns can have a direct bearing on public health and safety. An assessment of incident response and allegation investigation procedures, actual implementation of these procedures, internal and external coordination, and investigative and followup
Colorado Proposed Final IMPEP Report Page 9 actions, are a significant indicator of the overall quality of the incident response and allegation programs.
- a. Scope The team used the guidance in State Agreements procedure SA-105, Reviewing the Common Performance Indicator: Technical Quality of Incident and Allegation Activities, and evaluated Colorados performance with respect to the following performance indicator objectives:
- Incident response, investigation, and allegation procedures are in place and followed.
- Response actions are appropriate, well-coordinated, and timely.
- On-site responses are performed when incidents have potential health, safety, or security significance.
- Appropriate followup actions are taken to ensure prompt compliance by licensees.
- Followup inspections are scheduled and completed, as necessary.
- Notifications are made to the NRC Headquarters Operations Center for incidents requiring a 24-hour or immediate notification to the Agreement State or NRC.
- Incidents are reported to the Nuclear Material Events Database (NMED).
- Allegations are investigated in a prompt, appropriate manner.
- Concerned individuals are notified of investigation conclusions.
- Concerned individuals identities are protected, as allowed by law.
- b. Discussion During the review period, 67 incidents were reported to the NMED database by Colorado. The team selected 18 events to evaluate. The casework reviewed included:
three radiography events involving the inability to retract the source; three radiography events involving source disconnects (all different licensees); one failed attempted break-in of a radiography truck; four medical events; one unplanned contamination event involving technetium-99m; two damaged portable gauge events; one leaking electron capture device foil; one self-shielded irradiator exposure drawer failure; a failure of a room mounted radiation exposure detector; and one event involving contamination from water treatment.
The team found that inspectors properly evaluated each event, interviewed involved individuals, and thoroughly documented their findings. Enforcement actions were taken where appropriate.
When an event is reported to the Program, staff and management collectively evaluate the information received to determine its health and safety significance and then decide on the appropriate response. That response can range anywhere from responding immediately to reviewing the event during the next inspection. For each incident that was determined to have potential health and safety significance, the Program responded immediately. The team also found that the Program responded to events in accordance with their established procedure.
Colorado Proposed Final IMPEP Report Page 10 The team evaluated the Programs reporting of events to the NRCs Headquarters Operations Officer (HOO). The team noted that in each case reviewed where HOO notification was required, the Program reported all events within the required timeframe.
Additionally, an evaluation was made to determine if the Program had failed to report any events to the HOO where reporting was required, but none were found.
During the review period, 12 allegations were received directly by Colorado with 2 additional allegations referred by the NRC. The team evaluated 10 of the allegations and found that the Program took prompt and appropriate action in response to the concerns raised. All of the allegations reviewed were appropriately closed, concerned individuals were notified of the actions taken, and allegers identities were protected whenever possible.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 3.5.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Technical Quality of Incident and Allegation Activities, be found satisfactory.
4.0 NON-COMMON PERFORMANCE INDICATORS Four non-common performance indicators are used to review Agreement State programs: (1) Compatibility Requirements; (2) Sealed Source and Device (SS&D)
Evaluation Program; (3) Low-Level Radioactive Waste Disposal (LLRW) Program; and (4) Uranium Recovery Program. All four non-common performance indicators applied to this review.
4.1 Compatibility Requirements State statutes should authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the agreement. The statutes must authorize the State to promulgate regulatory requirements necessary to provide reasonable assurance of protection of public health, safety, and security. The State must be authorized through its legal authority to license, inspect, and enforce legally binding requirements, such as regulations and licenses.
NRC regulations that should be adopted by an Agreement State for purposes of compatibility or health and safety should be adopted in a time frame so that the effective date of the State requirement is not later than three years after the effective date of the NRC's final rule. Other program elements, as defined in Appendix A of State Agreements procedure SA-200, Compatibility Categories and Health and Safety Identification for NRC Regulations and Other Program Elements, that have been designated as necessary for maintenance of an adequate and compatible program,
Colorado Proposed Final IMPEP Report Page 11 should be adopted and implemented by an Agreement State within 6 months following NRC designation.
- a. Scope The team used the guidance in State Agreements procedure SA-107, Reviewing the Non-Common Performance Indicator: Compatibility Requirements, and evaluated Colorados performance with respect to the following performance indicator objectives.
A complete list of regulation amendments can be found on the NRC Web site at the following address: https://scp.nrc.gov/regtoolbox.html.
- The Agreement State program does not create conflicts, duplications, gaps, or other conditions that jeopardize an orderly pattern in the regulation of radioactive materials under the Atomic Energy Act, as amended.
- Regulations adopted by the Agreement State for purposes of compatibility or health and safety were adopted no later than 3 years after the effective date of the NRC regulation.
- Other program elements, as defined in SA-200 that have been designated as necessary for maintenance of an adequate and compatible program, have been adopted and implemented within six months of NRC designation.
- The State statutes authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the agreement.
- The State is authorized through its legal authority to license, inspect, and enforce legally binding requirements such as regulations and licenses.
- Impact of sunset requirements, if any, on the States regulations.
- b. Discussion Colorado became an Agreement State on February 1, 1968. The Department is authorized as the States radiation control agency under the Colorado Revised Statutes Title 25, Article 11, known as the Radiation Control Act.
As noted in Section 2.0, Colorado was found unsatisfactory for this indicator during the 2014 IMPEP review, largely due to a number of modifications to Colorado statutes prior to that review which were not compatible with NRC requirements. These modifications were initiated by parties outside the Department and were made by the State Legislature without concurrence by Colorados Radiation Control Program. To resolve the issue, Colorado management obtained permission from the Governors Office to conduct a stakeholder process in the summer of 2014 to address incompatible sections of the Radiation Control Act. Following this process, the Department submitted the legislation changes to NRC for review, and, as noted in the July 15, 2016, letter from NRC to Colorado (Accession Number ML16162A165), the NRC indicated that it had no further comments on Colorados legislation. The revised legislation is compatible with NRC requirements.
Colorado Proposed Final IMPEP Report Page 12 All Colorado State agencies are required to plan for future regulatory changes at least one year in advance through establishment of a regulatory agenda which is issued in November of each year. Whether a rulemaking activity will take place in the second or possibly third year following NRC issuance is dependent upon the date of the NRC rule change. Most rulemaking efforts are completed in approximately 12-14 months. On average, the State can promulgate regulations in six to 12 months, depending on the resolution of comments received during the various comment periods. Comments are requested from a Radiation Advisory Committee, the NRC, and the affected community.
Under the Colorado Administrative Procedure Act, all regulations in the State expire on May 15 of each year unless that expiration is postponed by the legislature (C.R.S.
§24-4-103(8)(c)(I)). Each year, the legislature initiates a bill postponing nearly all regulatory expirations, including those of the Program. Those regulations required for compliance with Federal requirements are typically renewed annually, although this is at the discretion and purview of the legislature. Historically, the Colorado Rules and Regulations Pertaining to Radiation Control have been approved each year, especially since such regulations are necessary for Colorado to maintain its authority under the agreement with the NRC which is the States policy (C.R.S. §25-11-102).
At the time of the prior IMPEP review in 2014, Colorado had a backlog of regulatory changes, some of which were dependent upon changes to the statute. Some of this backlog continued into the current review period, with some regulatory changes requiring coordination of regulatory and statutory efforts. During the review period, Colorado submitted 10 proposed regulation amendments, 25 final regulation amendments, 11 revised final regulation amendments, and the previously mentioned legislation to the NRC for a compatibility review. Portions of two of the amendments were overdue for State adoption at the time of submission, from 4 months to nearly 2 years delayed. The primary reason for the delay was due to the focus of resources on addressing prior NRC regulatory comments and to initiate changes to the enabling legislation associated with NRC comments. At the time of this review, no amendments were overdue.
- c. Evaluation The team determined that, during the review period, Colorado met the performance indicator objectives listed in Section 4.1.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Compatibility Requirements, be found satisfactory.
4.2 Sealed Source and Device (SS&D) Evaluation Program Adequate technical evaluations of SS&D designs are essential to ensure that SS&Ds will maintain their integrity and that the design is adequate to protect public health and safety. NUREG-1556, Volume 3, Consolidated Guidance about Materials Licenses:
Applications for Sealed Source and Device Evaluation and Registration, provides
Colorado Proposed Final IMPEP Report Page 13 information on conducting SS&D reviews and establishes useful guidance for teams.
Under this guidance, three sub elements: Technical Staffing and Training, Technical Quality of the Product Evaluation Program, and Evaluation of Defects and Incidents Regarding SS&Ds, are evaluated to determine if the SS&D program is satisfactory.
Agreement States with authority for SS&D evaluation programs who are not performing SS&D reviews are required to commit in writing to having an SS&D evaluation program in place before performing evaluations.
- a. Scope The team used the guidance in State Agreements procedure SA-108, Reviewing the Non-Common Performance Indicator: Sealed Source and Device Evaluation Program, and evaluated Colorados performance with respect to the following performance indicator objectives:
Technical Staffing and Training
- A well-conceived and balanced staffing strategy has been implemented throughout the review period.
- Qualification criteria for new technical staff are established and are being followed or qualification criteria will be established if new staff members are hired.
- Any vacancies, especially senior-level positions, are filled in a timely manner.
- Management is committed to training and staff qualification.
- Individuals performing SS&D evaluation activities are adequately qualified and trained to perform their duties.
- SS&D reviewers are trained and qualified in a reasonable period of time.
Technical Quality of the Product Evaluation Program
- SS&D evaluations are adequate, accurate, complete, clear, specific, and consistent with the guidance in NUREG-1556, Volume 3.
Evaluation of Defects and Incidents
- SS&D incidents are reviewed to identify possible manufacturing defects and the root causes of these incidents.
- Incidents are evaluated to determine if other products may be affected by similar problems. Appropriate action and notifications to NRC, Agreement States, and others, as appropriate, occur in a timely manner.
- b. Discussion Technical Staffing and Training Colorado has six staff qualified to perform SS&D reviews with one in training and no vacancies at the time of the review. During the review period two qualified SS&D reviewers left the program and two staff members were hired. The positions were
Colorado Proposed Final IMPEP Report Page 14 vacant for less than a month. Colorado has a training program for SS&D reviewers equivalent to the NRC training requirements listed in IMC 1248, Appendix D.
Technical Quality of the Product Evaluation Colorado currently has two SS&D registrants. The Program completed no SS&D actions during the review period. The team evaluated an SS&D action that was pending during the onsite review. This pending action is an amendment. The pending review is technically sound; proper checklists are being used and meet the criteria of NUREG-1556 Volume 3 Revision 1.
When Colorado completes all SS&D casework, any changes to the updated SS&D registration are tied to the applicants radioactive materials license.
Due to the lack of review actions, Program management noted that Colorado may use alternate technical assistance for review of complex SS&D actions should it receive one.
Evaluation of Defects and Incidents Regarding SS&Ds The team received no incidents involving SS&D registered products during the review period. Incident procedures are in place should an SS&D-related incident occur.
- c. Evaluation The team determined that, during the review period, Colorado has met the performance indicator objectives listed in Section 4.2.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Sealed Source and Device Evaluation Program, be found satisfactory.
4.3 LLRW Disposal Program In 1981, the NRC amended its Policy Statement, Criteria for Guidance of States and NRC in Discontinuance of NRC Authority and Assumption Thereof by States Through Agreement, to allow a State to seek an amendment for the regulation of LLRW as a separate category. Those States with existing Agreements prior to 1981 were determined to have continued LLRW disposal authority without the need of an amendment. Although the Colorado Agreement State Program has authority to regulate a LLRW disposal facility, the NRC has not required States to have a program for licensing a disposal facility until such time as the State has been designated as a host State for a LLRW disposal facility. When an Agreement State has been notified or becomes aware of the need to regulate a LLRW disposal facility, it is expected to put in place a regulatory program that will meet the criteria for an adequate and compatible LLRW program. There are no plans for a commercial LLRW disposal facility in Colorado. Accordingly, the team did not review this indicator.
Colorado Proposed Final IMPEP Report Page 15 4.4 Uranium Recovery Program The objective is to determine if Colorados uranium recovery Program is adequate to protect public health and safety. Five sub-elements are used to make this determination: (1) Technical Staffing and Training; (2) Status of Uranium Recovery Inspection Program; (3) Technical Quality of Inspections; (4) Technical Quality of Licensing Actions; and (5) Technical Quality of Incident and Allegation Activities.
- a. Scope The team used the guidance in State Agreements procedure SA-110, Reviewing the Non-Common Performance Indicator: Uranium Recovery Program, and evaluated Colorados performance with respect to the following performance indicator objectives:
Technical Staffing and Training
- Qualified and trained technical staff is available to license, regulate, control, inspect, and assess the operation and performance of the uranium recovery program.
- Qualification criteria for new uranium recovery technical staff are established and are being followed or that qualification criteria will be established if new staff members are hired.
- Any vacancies, especially senior-level positions, are filled in a timely manner.
- There is a balance in staffing the uranium recovery licensing and inspection programs.
- Management is committed to training and staff qualification.
- Individuals performing uranium recovery licensing and inspection activities are adequately qualified and trained to perform their duties.
- Uranium recovery license reviewers and inspectors are trained and qualified in a reasonable period of time.
Status of Uranium Recovery Inspection Program
- The uranium recovery facility is inspected at prescribed frequencies.
- Statistical data on the status of the inspection program are maintained and can be retrieved.
- Deviations from inspection schedules are coordinated between uranium recovery technical staff and management.
- There is a plan to reschedule any missed or deferred inspections or a basis has been established for not rescheduling any missed inspections.
- Inspection findings are communicated to licensees in a timely manner.
Technical Quality of Inspections
- Inspections of uranium recovery licensed activities focus on health, safety, and security.
- Inspection findings are well-founded and properly documented in reports.
- Management promptly reviews inspection results.
Colorado Proposed Final IMPEP Report Page 16
- Procedures are in place and used to help identify root causes and poor licensee performance.
- Inspections address previously identified open items and violations.
- Inspection findings lead to appropriate and prompt regulatory action.
- Supervisors, or senior staff as appropriate, conduct annual accompaniments of each uranium recovery inspector to assess performance and assure consistent application of inspection policies.
- For Agreement States, inspection guides are consistent with NRC guidance.
- An adequate supply of calibrated survey instruments is available to support the inspection program.
Technical Quality of Licensing Actions
- Licensing action reviews are thorough, complete, consistent, and of acceptable technical quality with health, safety, and security issues properly addressed.
- Applicable uranium recovery guidance documents are available to reviewers and are followed (e.g., pre-licensing guidance, regulatory guides, etc.).
- Essential elements of license applications have been submitted and meet current NRC or Agreement State regulatory guidance (e.g., financial assurance, increased controls, etc.)
- Uranium recovery license reviewers, if applicable, have the proper signature authority for the cases they review independently.
- License conditions are stated clearly and can be inspected.
- Deficiency letters clearly state regulatory positions and are used at the proper time.
- Reviews of renewal applications demonstrate a thorough analysis of a licensees inspection and enforcement history.
- Licensing practices for risk significant radioactive materials are appropriately implemented including increased controls and fingerprinting orders (Part 37 equivalent).
- Documents containing sensitive security information are properly marked, handled, controlled, and secured.
Technical Quality of Incident and Allegation Activities
- Uranium recovery Incident response, investigation, and allegation procedures are in place and followed.
- Response actions are appropriate, well-coordinated, and timely.
- On-site responses are performed when incidents have potential health, safety or security significance.
- Appropriate followup actions are taken to ensure prompt compliance by licensees.
- Followup inspections are scheduled and completed, as necessary.
- Notifications are made to the NRC Headquarters Operations Center for incidents requiring a 24-hour or immediate notification to the Agreement State or NRC.
- Incidents are reported to the NMED.
- Allegations are investigated in a prompt, appropriate manner.
Colorado Proposed Final IMPEP Report Page 17
- Concerned individuals are notified of investigation conclusions.
- Concerned individuals identities are protected, as allowed by law.
- b. Discussion Technical Staffing and Training The team determined that the Programs qualifications and staffing levels for the uranium recovery program were adequate. At the time of the review, there were no vacancies; one qualified technical staff member performed most of the project management, inspections, and licensing actions for Colorados uranium recovery program. Colorado had two qualified uranium recovery staff over the course of the review period. One of the staff members retired from the program in 2015. That FTE is no longer dedicated to the uranium recovery program.
The uranium recovery program has a training program equivalent to the NRC training requirements listed in IMC 1248, Appendix E. The uranium recovery program staff has training in health physics, geology/geophysics, and inspection procedures. The staff also receive annual facility safety refresher training and attend NRC-sponsored training and webinars. The uranium recovery program technical staff member demonstrated thorough understanding of State regulations and the NRC guidance related to uranium recovery.
The uranium recovery program also has access to individuals from within the Program, staff in the Hazardous Materials and Waste Management Division, and the Department, for technical support. The uranium recovery program has contracts with consulting firms to assist as needed, as well.
Status of Uranium Recovery Inspection Program The uranium recovery program staff performed seven inspections during the review period. The team determined that the program completed the inspections in accordance with the frequency in the NRCs IMC 2800.
Inspection findings for the uranium recovery program were communicated by formal correspondence to the licensee within 30 days following the inspection. Two instances of late reports issued to licensees were noted, sent from 39 to 54 days after the completion of the inspection. The delay was attributed to extra staff time taken to review the inspection report and inspection results letter.
The Program updated the Inspection Procedure for Uranium Recovery Facilities in Closure (revised December 6, 2017) that are licensed under the License Category of 14.A for decommissioning under the State of Colorado Rules and Regulations Pertaining to Radiation Control. Under the updated procedure, these facilities are to be inspected every three years. The facilities are also Uranium Mill Tailings Radiation Control Act Title II sites. The inspector created an Inspection Procedure for Uranium Recovery Facilities in Closure to establish the routine compliance inspection program for conventional uranium mills in closure to be consistent with NRC guidance NUREG-1620
Colorado Proposed Final IMPEP Report Page 18 Appendix D Guidance to the U.S. Nuclear Regulatory Commission Staff for Reviewing Long-Term Surveillance Plans.
The team identified that one uranium site inspection (Sweeney Mining & Milling Corporation) was, at the time of the review, overdue by nearly 3 years (35 months). This was due to the fact that inspection results from the 2015 inspection had not been presented to the licensee in a manner consistent with the Radiation Control Act. During the onsite review, Program staff noted that a routine inspection is planned in the spring of 2018. In addition, the Program was implementing a plan to ensure that, in the future, no licensee will have an overdue inspection based on an inability to communicate inspection results to a licensee.
Technical Quality of Inspections The team evaluated seven inspection files which included a variety of uranium recovery inspection activities in different stages of license operations, and determined that the inspection reports were thorough, complete, consistent, and had sufficient documentation to ensure that licensee performance with respect to health, safety and security was acceptable. The inspection results were well-founded, supported by regulations, and were appropriately documented. There was no enforcement action for the period of review.
The Programs inspectors followed the radioactive materials unit inspection manual (revised June 2016) for conducting inspections. The Program has inspection procedures specific to the uranium recovery program. The inspector used checklists to document inspections. Inspection reports were well documented and provided suitable depth of coverage, addressed license conditions and the regulations, and demonstrated that the inspector followed corrective actions for items of concerns that were identified.
Some of the inspection files contained photographs supporting both the facility structures and items of concerns. The Programs records indicated that supervisor accompaniments of the inspector were performed annually during the review period.
Technical Quality of Licensing Actions The Program completed seven licensing actions during the review period. The team examined the files and associated documentation related to the licensing of conventional uranium recovery mill facilities which included six amendments, and one renewal.
The uranium recovery program manages the following uranium recovery sites:
- 1. Pinon Ridge Mill,
- 2. Cotter Corporation Canon City Mill,
- 3. Umetco Uravan Mill, and
- 4. Hecla Durita Mill.
The uranium recovery program manages the following contaminated sites:
- 1. Cotter Corporation Schwartzwalder Mine,
- 2. Sweeney Mill, and
- 3. Colorado School of Mines Research Institute Table Mountain Research Center
Colorado Proposed Final IMPEP Report Page 19 There were no operational facilities in the State at the time of the review except for Cotter Corporation Schwartzwalder Mine which is a water treatment facility. The Umetco Uravan Mill and the Hecla Durita Mill are in closure status.
The licensing actions completed during the review period consisted of:
decommissioning plans, modification of the restricted area, designation of radiation safety officer, license transfer, annual financial assurance updates, and compliance monitoring. The team interviewed staff members about the status of each regulated site.
Management and staff were familiar with the technical details and conditions existing at each site.
The team concluded that the licensing actions were complete, consistent, and of acceptable quality. Program staff use a review procedure and checklist for licensing reviews. All response letters for each incoming request or report contained secondary technical or management review and approval.
The team evaluated the decision analysis reports for all the licensing actions which included public comments. The team also evaluated the license for the Cotter Corporation request to change the restricted area specified in the license and release the requested areas to be unrestricted. The Cotter Corporation decision analysis document contained a thorough evaluation of the application, as well as an adequate basis for the staffs licensing decision.
Technical Quality of Incident and Allegation Activities The uranium recovery program did not respond to any incidents and received no allegations during the review period.
- c. Evaluation The team determined that, during the review period, the uranium recovery program met the performance indicator objectives listed in Section 4.4.a., and, based on the criteria in MD 5.6, recommends that Colorados performance with respect to the indicator, Uranium Recover Program, be found satisfactory.
5.0
SUMMARY
As noted in Sections 3.0 and 4.0 above, Colorados performance was found satisfactory for all performance indicators reviewed. The team did not make any recommendations regarding program performance and there were no recommendations from the 2014 IMPEP review to be addressed.
Colorado Proposed Final IMPEP Report Page 20 Accordingly, the team recommends that the Colorado Agreement State Program be found adequate to protect public health and safety and compatible with NRC's program.
Based on the results of the current IMPEP review, the team recommends that the next full IMPEP review take place in approximately four years, with a periodic meeting in approximately two years.
LIST OF APPENDICES Appendix A IMPEP Review Team Members Appendix B Inspection Accompaniments
APPENDIX A IMPEP REVIEW TEAM MEMBERS Name Areas of Responsibility Lance Rakovan, NMSS Team Leader Technical Staffing and Training Compatibility Requirements Randy Erickson, Region IV Technical Quality of Incident and Allegation Activities Sherrie Flaherty, MN Status of Materials Inspection Program Technical Quality of Materials Inspections Frank Tran, Region III Technical Quality of Licensing Actions Ron Parsons, TN Sealed Source & Device Evaluation Program Gehan Flanders, TX Uranium Recovery Program Orysia Masnyk-Bailey , Region I Inspector Accompaniments Lizette Roldán-Otero, Ph.D., NMSS Inspector Accompaniments
APPENDIX B INSPECTION ACCOMPANIMENTS The following inspection accompaniments were performed prior to the on-site IMPEP review:
Accompaniment No.: 1 License No.: CO 854-02 License Type: Diagnostic Nuclear Medicine Priority: 5 Inspection Date: 02/26/2018 Inspector: DB Accompaniment No.: 2 License No.: CO 997-01 License Type: Industrial Radiography Priority: 1 Inspection Date: 02/27/2018 Inspector: MD Accompaniment No.: 3 License No.: CO 1139-01 License Type: Portable Gauge Priority: 5 Inspection Date: 02/28/2018 Inspector: TT Accompaniment No.: 4 License No.: CO 038-02 License Type: High Dose Remote Afterloader Priority: 2 Inspection Date: 02/29/2018 Inspector: RL Accompaniment No.: 5 License No.: CO 997-01 License Type: Industrial Radiography (TJS) Priority: 1 Inspection Date: 04/03/18 Inspector: MD
Agenda for Management Review Board Meeting June 26, 2018, 1:00 p.m. - 4:00 p.m. (ET), OWFN-17B04
- 1. Announcement of public meeting. Request for members of the public to indicate they are participating and their affiliation.
- 2. MRB Chair convenes meeting. Introduction of MRB members, review team members, State representatives, and other participants.
- 3. Consideration of the Colorado IMPEP Report.
A. Presentation of Findings Regarding Colorados Program and Discussion.
- Technical Staffing and Training
- Status of Materials Inspection Program
- Technical Quality of Inspections
- Technical Quality of Licensing Actions
- Technical Quality of Incident and Allegation Activities
- Compatibility Requirements
- Sealed Source & Device Evaluation Program
- Uranium Recovery Program B. IMPEP Team Recommendations.
- Recommendation for Adequacy and Compatibility Ratings
- Recommendation for Next IMPEP Review C. MRB Consultation/Comments on Issuance of Report.
- 5. Questions/comments from members of the public.
- 6. Adjournment.