IR 05000252/2016201
| ML16273A155 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 10/05/2016 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Branch |
| To: | Busch R Univ of New Mexico |
| Eads J | |
| References | |
| IR 2016201 | |
| Download: ML16273A155 (15) | |
Text
ber 5, 2016
SUBJECT:
UNIVERSITY OF NEW MEXICO - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-252/2016-201
Dear Dr. Busch:
From August 22 - 25, 2016, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the University of New Mexico Research Reactor facility. The inspection included a review of activities authorized for your facility. The enclosed report presents the results of that inspection.
Areas examined during the inspection are identified in the enclosed report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations of activities in progress. Based on the results of this inspection, no findings of safety concern or noncompliance of requirements were identified.
No response to this letter is required.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390 Public inspections, exemptions, requests for withholding a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Should you have any questions concerning this inspection, please contact Johnny Eads at (301) 415-0136 or by electronic mail at Johnny.Eads@nrc.gov.
Sincerely,
/RA/
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-252 License No. R-102 Enclosure:
As stated cc w/enclosure: See next page
University of New Mexico Docket No. 50-252 cc:
City Manager City of Albuquerque City Hall Albuquerque, NM 87101 Dr. Anil Prinja, Reactor Administrator Chemical and Nuclear Engineering Department University of New Mexico 209 Farris Engineering, MSC 01-1120 Albuquerque, NM 87131-0001 Mr. James De Zetter, Radiation Safety Officer Safety, Health, Environmental Affairs University of New Mexico 1801 Tucker NE, Bldg. 233MSC 07-4100 Albuquerque, NM 87131-0001 Chief, Radiation Control Bureau Field Operations Division Environment Department Harold S. Runnels Bldg.
1190 St. Francis Drive, Rm S2100 Santa Fe, NM 87505-4173 Deputy Secretary, Office of the Secretary New Mexico State Environment Dept.
1190 St. Francis Drive, Suite 4050N Sante Fe, NM 87502-6110 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
ML16273A155; *concurrence via e-mail NRC-002 OFFICE NRR/DPR/PROB* NRR/DPR/PROB/LA* NRR/DPR/PROB/BC NAME JEads NParker AMendiola DATE 9/29/16 9/29/16 10/5/16
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No. 50-252 License No. R-102 Report No. 50-252/2016-201 Licensee: University of New Mexico Facility: AGN-201M Reactor Facility Location: Albuquerque, New Mexico Dates: August 22-25, 2016 Inspector: Johnny Eads Approved by: Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Enclosure
EXECUTIVE SUMMARY University of New Mexico AGN-201M Research Reactor Facility NRC Inspection Report No. 50-252/2016-201 The primary focus of this routine, announced inspection included onsite review of selected aspects of the University of New Mexico (UNM, the licensee) Class II research reactor safety program including: (1) Procedures, (2) Operator Requalification, (3) Experiments, (4) Health Physics, (5) Design Changes, (6) Committees, Audits, and Reviews, and (7) Transportation activities since the last U.S. Nuclear Regulatory Commission (NRC) inspection. The licensees programs were acceptably directed toward the protection of public health and safety, and in compliance with the NRC requirements.
Procedures
- Procedural control and implementation satisfied Technical Specification (TS) requirements.
Requalification Training
- The licensees requalification program was up-to-date and plan requirements were generally met.
Experiments
- The approval and control of experiments met TS requirements.
Health Physics
- The radiation protection program was being maintained and implemented as required.
Design Changes.
- The licensee's design change program was being implemented as required.
Committees, Audits, and Reviews
- Review and oversight functions required by the TS were acceptably completed by the Reactor Safety Advisory Committee.
Transportation of Radioactive Materials
- The licensee did not ship any radioactive material from the facility using the reactor license.
REPORT DETAILS Summary of Facility Status The University of New Mexico (UNM, the licensee) Aerojet General Nucleonics-201 Modified (AGN-201M) research reactor was licensed to operate at a maximum steady-state thermal power of 5 Watt. The licensee continued to operate the reactor in support of operator training, surveillances, and teaching and classroom experiments/demonstrations. During the inspection, the reactor was shutdown.
1. Procedures a. Inspection Scope (Inspection Procedure (IP) 69001)
The inspector reviewed the following to ensure that the procedural control requirements of Technical Specifications (TS) Section 6.6 were being met:
- Records of changes to procedures
- Reactor Safety Advisory Committee (RSAC) meeting minutes dated December 11, 2015 and June 17, 2016
- Selected procedures from the Reactor Operation and Training Manual, revised January 2013 b. Observations and Findings The inspector reviewed the licensees written procedures and revisions to procedures. The procedures were organized to address the full scope of activities conducted at the reactor facility. The inspector noted that procedural changes were being reviewed and approved as required by TS. Training of personnel on procedures and changes was acceptable. Through observation of various activities at the facility, including reactor operation, the inspector determined that licensee personnel conducted activities in accordance with applicable procedures.
c. Conclusion Procedural control and implementation satisfied TS requirements.
2. Operator Requalification a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 55, Operators'
Licenses, and the requalification program:
-2-Operator active license status University of New Mexico AGN-201M Requalification records 2015-2016 Training requirements stipulated in American Nuclear Society Institute/American Nuclear Society 15.4-1977, Standards for the Selection and Training of Personnel for Research Reactors b. Observations and Findings At the time of the inspection, there were three qualified senior reactor operators (SROs) working at the facility and two qualified Reactor Operators (ROs).
The inspectors verified the operating licenses were current for the SROs and ROs. It was also noted that annual operating examinations and biennial written examinations had been generally completed by the operators as required.
However, one SRO had not completed the required annual operational examinations in 2015 as required and was placed in an inactive status by the licensee.
The Operator and Senior Operator Requalification Program for the UNM reactor facility requires that each certified individual take an annual operational examinations to demonstrate competency.
c. Conclusion The licensees requalification program was up-to-date, and plan requirements were generally met.
3. Experiments a. Inspection Scope (IP 69005)
The inspector reviewed selected aspects of the following to verify compliance with TS Sections 3.8, 4.8, and 6.5:
Request for Use Authorizations No. 535, AGN-1, for the period January 2015 to present.
b. Observations and Findings The UNM AGN-201M reactor was primarily used as a training reactor for undergraduate and graduate students. Experiments that had been performed typically consisted of operations performed for semester coursework, including:
sample activation, approach to critical, reactor period and reactivity measurements, control rod calibrations, importance function measurements, and transfer function measurements.
No experiments were performed during the inspection. The inspector reviewed how experiments are performed in order to verify compliance with the TS and procedures. Additionally, from a random sampling of forms for experiments performed since the previous inspection, the inspector found that experiments
-3-were being reviewed and performed in accordance with TS requirements and the licensees written procedures.
c. Conclusion The program for reviewing and conducting experiments satisfied TS and procedural requirements.
4. Health Physics a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with TS Section 4.4 as well as 10 CFR Part 19, Notices, Instructions and Reports to Workers:
Inspection and Investigations, and 10 CFR Part 20, Standards for Protection against Radiation, requirements:
Radiological signs and posting and area control Quarterly dosimetry records for the reactor room for 2015 and 2016.
Quarterly dosimetry records for reactor staff and students for 2015 and 2016 Maintenance and calibration of portable radiation survey instruments, records for 2015 and 2016 Completed AGN-201 Monthly Non-Operational Radiation Survey forms, which included documentation of an inventory of decontamination equipment, for the period from January 2015 to present Nuclear Engineering AGN-201 Reactor Radiation Surveys during periods of operation and for laboratory preparation b. Observations and Findings The inspector toured the Nuclear Engineering Laboratory (NE Lab) and observed the use of dosimetry and radiation monitoring equipment. Licensee personnel were interviewed as well. The inspector also discussed the subjects of surveys, dosimetry, training, and radioactive effluents with UNM Department of Safety &
Risk Services (SRS), Radiation Safety Division representatives.
(1) Surveys The inspector reviewed monthly radiation and contamination surveys of the licensees controlled areas completed by the SRS Radiation Safety Division personnel. The surveys had been completed in accordance with procedure and the results were documented on the appropriate forms and evaluated as required. It was noted that the SRS Radiation Safety Division personnel also completed an annual radiation survey of the facility while the reactor was at power in accordance with TS. No readings in excess of those noted in the past were discovered. The inspectors noted that the surveys clearly included the date, survey instrument used with calibration date, reactor power level and the type of survey.
-4-(2) Postings and Notices The inspector toured the NE Lab and reviewed the postings required by 10 CFR Parts 19 and 20 at the entrances to various controlled areas including the Reactor Facility, the Reactor Room, and radioactive material storage areas. The postings were acceptable and indicated the radiation and contamination hazards present. The facilities radioactive material storage areas were noted to be properly posted. No unmarked radioactive material was found in the facility. Control of radioactive material and control of access to radiation and high radiation areas were acceptable.
(3) Dosimetry The inspector determined that the licensee typically used thermoluminescent dosimeters (TLD) for whole body monitoring of beta and gamma radiation exposure. The TLDs also contained a component to measure neutron radiation. The dosimetry was supplied and processed by a National Voluntary Laboratory Accreditation Program accredited vendor, Landauer. An examination of the TLD results indicating radiological exposures at the facility for the past two years showed that the highest occupational doses, as well as doses to the public, were within 10 CFR Part 20 limitations.
(4) Radiation Monitoring Equipment The calibration of portable survey meters and friskers was completed either by Radiation Safety Division personnel or by a company that specializes in calibrations. Fixed area radiation monitors were calibrated at the facility by reactor staff personnel using a portable source. The calibration records of portable survey meters and fixed radiation detectors in use at the facility were reviewed. The calibration frequencies of the various instruments examined met the requirements established in TS 4.4, Specification a., and records were being maintained as required.
(5) Radiation Protection Program The licensees Radiation Protection Program (RPP) was established through the UNM Radiation Safety Manual. The inspector verified that the RPP was being reviewed annually as required. The review of the program did not identify issues related to radiation protection at the NE Lab.
(6) Training The Radiation Safety Manual required that all personnel who worked with radioactive materials receive training in radiation protection, policies, procedures, requirements, and the facilities prior to having unescorted access at the facility. UNM SRS Radiation Safety Division personnel
-5-were responsible for conducting the training and all of the training was typically conducted by a radiation safety specialist. A test was administered at the end of the training to verify that the individuals understood the material presented. The training covered the topics required to be taught in 10 CFR Part 19 and a review of training materials and tests indicated that reactor staff and student personnel were instructed on the appropriate subjects.
(7) Environmental Monitoring The licensee complied with NRC regulations for environmental monitoring by ensuring that all doses at the site boundary were less than the dose limits specified in 10 CFR 20.1301, Dose limits for individual members of the public. Several TLDs were strategically placed in several locations around the inside perimeter of the facility; there were no abnormal doses noted. There were no liquid or gaseous effluents discharged from the facility since the last inspection.
c. Conclusion The RPP was being maintained and implemented as required.
5. Design Changes a. Inspection Scope (IP 69001)
To verify compliance with the licensees procedures, TSs, and 10 CFR 50.59, Changes, tests and experiments, the inspector reviewed selected aspects of:
2015 Annual Report for the AGN-201M reactor Selected Request for Use forms from January 2015 to the present Completed Reactor Maintenance Log Sheet - The University of New Mexico AGN-201M Reactor Facility, forms for the period from 2015 to the present b. Observations and Findings The inspector reviewed the records related to experiments and requested maintenance since the last inspection. The inspector determined that there were no new experiments or maintenance requests (i.e., design changes) since the last NRC inspection.
The inspector reviewed the Requests for Use forms and maintenance log sheets to determine if they conformed to the screening and vetting process as described under 10 CFR 50.59. None of the changes involved a change to the TSs or met any of the criteria in 10 CFR 50.59(c)(2).
-6-c. Conclusion The licensee's design change program was being implemented as required.
6. Committees, Audits, and Reviews a. Inspection Scope (IP 69001)
To verify that TS requirements were being met since the last inspection, the inspectors reviewed selected aspects of:
RSAC Meeting Minutes dated December 11, 2015 and June 17, 2016 b. Observations and Findings The functions and responsibilities of the RSAC were defined in the TS. The inspector verified that the RSAC held semiannual meetings and a quorum was present as required. The inspector followed up on the RSAC audits required under TS 6.4.3. The audit findings were noted in the meeting minutes.
The inspector determined that the RSAC was performing the audits within the periodicity outlined in TS 6.4.3. Audit results and comments were captured within the meeting minutes and during this inspection it was noted that there were no corrective action items needed to be addressed. The inspector noted that there were no safety significant issues recorded during the audits since the last inspection.
c. Conclusion Review and oversight functions required by the TS were acceptably completed by the RSAC.
7. Transportation a. Inspection Scope (IP 86740)
To verify compliance with procedural requirements for shipping radioactive material, the inspector interviewed licensee personnel, Radiation Safety Division personnel, and reviewed operational logs and records.
b. Observations and Findings Through records review and discussions with licensee and UNM Radiation Safety Division personnel, the inspector determined that the licensee had not shipped any radioactive material from the reactor facility under the auspices of the reactor license. If the licensee needed to ship radioactive material, it would likely be transferred to the UNMs Broad Scope license and shipped or disposed of under that license.
-7-c. Conclusion No radioactive material was shipped from the reactor facility under the reactor license.
8. Exit Meeting The inspector presented the inspection results to licensee management at the conclusion of the inspection on August 25, 2016. The inspector discussed the findings for each area reviewed. The licensee acknowledged the findings and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection.
PARTIAL LIST OF PERSONS CONTACTED Licensee Chief Reactor Supervisor K. Carpenter Reactor Supervisor Other Personnel K. Paffett Radiation Safety INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors ITEMS OPENED, CLOSED, AND DISCUSSED OPENED:
None CLOSED:
None DISCUSSED:
None
LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ANSI/ANS American National Standards Institute/American Nuclear Society IP Inspection Procedure NRC U. S. Nuclear Regulatory Commission ROTM Reactor Operation and Training Manual RSAC Reactor Safety Advisory Committee RO Reactor Operator SRO Senior Reactor Operator TS Technical Specifications UNM University of New Mexico