ML20317A194

University of Massachusetts Lowell Routine Reactor Inspection Report - October 2020

ML20317A194
Person / Time
Site:	University of Lowell
Issue date:	04/13/2021
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Prosanta Chowdhury Univ of Massachusetts - Lowell
Takacs M
References
IR 2020201
Download: ML20317A194 (12)

Text

April 13, 2021 Dr. Partha Chowdhury, Director Nuclear Radiation Laboratory University of Massachusetts - Lowell One University Avenue Lowell, MA 01854

SUBJECT:

UNIVERSITY OF MASSACHUSETTS LOWELL - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 05000223/2020201

Dear Dr. Chowdhury:

From October 20 - 22, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the University of Massachusetts Lowell Research Reactor facility. The enclosed report presents the results of the inspection which were discussed on October 22, 2020, with you and members of your staff.

The inspection examined activities conducted under your license as they relate to public health and safety, and to confirm compliance with the Commissions rules and regulations, and with the conditions of your license. Within these areas, the inspection consisted of selected review of procedures and records, observations of activities, and interviews with personnel. Based on the results of this inspection, no findings of non-compliance 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 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).

P. Chowdhury If you have any questions concerning this inspection, please contact Mr. Michael Takacs at (301) 415-2042, or by electronic mail at Michael.Takacs@nrc.gov.

Sincerely,

/RA/

Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-223 License No. R-125

Enclosure:

As stated cc: See next page

University of Massachusetts - Lowell Docket No. 50-223 cc:

Mayor of Lowell City Hall Lowell, MA 01852 Mr. Leo Bobek Reactor Supervisor University of Massachusetts - Lowell One University Avenue Lowell, MA 01854 Department of Environmental Protection One Winter Street Boston, MA 02108 Jack Priest, Director Radiation Control Program Department of Public Health Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129 Ms. Samantha Phillips, Director Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Test, Research and Training Reactor Newsletter Attention: Ms. Amber Johnson Department of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115

ML20317A194 *concurrence via email NRC-002 OFFICE NRR/DANU/UNPO/SS* NRR/DANU/UNPO/LA* NRR/DANU/UNPO/BC NAME MTakacs NParker TTate DATE 11/16/2020 11/16/2020 4/13/2021 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.: 50-223 License No.: R-125 Report No.: 05000223/2020201 Licensee: University of Massachusetts Lowell Facility: University of Massachusetts Lowell Research Reactor Location: Lowell, Massachusetts Dates: October 20 - 22, 2020 Inspector: Michael Takacs Approved by: Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Enclosure

EXECUTIVE

SUMMARY

University of Massachusetts Lowell Research Reactor Facility Inspection Report No. 05000223/2020201 The primary focus of this routine inspection at the University of Massachusetts Lowell (the licensee) Research Reactor facility was the onsite review of selected aspects of the safety programs for this Class II research reactor including: (1) procedures; (2) experiments; (3) health physics; (4) design changes; (5) committees, audits and reviews; and (6) transportation. The U.S. Nuclear Regulatory Commission (NRC) staff determined that the licensees programs were acceptably directed toward the protection of public health and safety and in compliance with NRC requirements.

Procedures

• Procedures were current and were reviewed and approved as required by technical specifications (TS) and the licensees administrative procedures.

Experiments

• Experiments were performed in accordance with TS requirements, the licensees procedures, and NRC regulations.

Health Physics

• The radiation protection program was effective in minimizing radiation doses to individuals; radiation surveys were completed and documented as required; postings met regulatory requirements; personnel dosimetry was worn and recorded doses were within the NRCs regulatory limits; radiation safety refresher training was administered biennially as required by the radiation protection program; radiation monitoring equipment was maintained and calibrated as required by procedures and the radiation protection program; and environmental monitoring satisfied regulatory requirements.

Design Changes

• The design change program met regulatory requirements, TS, and the licensee procedure.

Committees, Audits and Reviews

• The Reactor Safety Subcommittee (RSSC) met quarterly and provided the oversight required by TS.

Transportation

• The program for transportation of radioactive materials (RAM) satisfied regulatory requirements.

REPORT DETAILS Summary of Facility Status The University of Massachusetts Lowell (UML) 1 megawatt research reactor is operated in support of education, research, commercial service irradiations, reactor operator training, and periodic equipment surveillances. During the inspection, the reactor was operated for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to support a commercial service irradiation.

1. Procedures

a. Inspection Scope (Inspection Procedure (IP) 69001)

The inspector reviewed the following to ensure that the requirements of TS Section 6.3 were met concerning written procedures:

• procedure AP-0, Authority, Revision (Rev.) 3, dated March, 3. 2004

• procedure AP-1, Procedure Control and Distribution, Rev. 1, dated September 18, 2003

• procedure AP-2, Procedure Development, Rev. 1, dated September 18, 2003

• procedure AP-2 (R), Procedure Action Form - Revised Procedure, Rev. 1, dated September 18, 2003

• procedure AP-6, 10 CFR 50.59 Screenings and Evaluations, dated December 16, 2009

• procedure RF-5, Radiation Monitoring System Daily Check, Rev. 20, dated December 2017

• procedure RF-RO-7A, Reactor Operator Instruction Form, Rev. 27, dated October 2015

• procedure RO-5, Reactor Operations, Rev. 3, dated 10/2005

• procedure CP-1, Logarithmic Power Channel Check and Calibration, dated December 13, 2006

• procedure CP-2, Linear Power Channel Check and Calibration, dated December 11, 2006

b. Observations and Findings The inspector determined that procedures were available for the activities specified by TS 6.3. The inspector noted that procedures provided adequate guidance for the performance of reactor operations and other system operations.

The inspector, along with a senior reactor operator (SRO), performed a walk-through of procedures CP-1 and CP-2. The inspector noted that the SRO was knowledgeable on the equipment and instrumentation, and the inspector found no issues during the walk-through of the procedures.

c. Conclusion The inspector determined that procedures were maintained and implemented in accordance with TS requirements and the licensees administrative procedures.

2. Experiments

a. Inspection Scope (IP 69001)

To verify compliance with TS Sections 3.6 and 6.8, and Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, test and experiments, the inspector reviewed selected aspects of the following:

• irradiation request forms from January 7, 2020, to the present

• procedure RO-4, Addition or Removal of Core Samples, Rev. 6, dated June 14, 2005

• procedure AP-6, 10 CFR 50.59 Screenings and Evaluations, dated December 16, 2009

b. Observations and Findings The inspector determined, through discussion with the reactor supervisor and review of the radiation request forms, that no new experiments had been conducted since the last inspection. The inspector noted that experiments performed since the last inspection had been previously approved by the RSSC, and since no changes had been made to the experiments, they were considered routine. The inspector verified that all routine experiments were approved by the reactor supervisor and the radiation safety officer prior to the start of the experiment as required by licensee procedure.

c. Conclusion The inspector determined that the program for the conduct of experiments was in accordance with TS, licensee procedure, and NRC regulations.

3. Health Physics

a. Inspection Scope (IP 69001)

To verify compliance with 10 CFR Part 20, Standards for Protection against Radiation, and TS Sections 3.4 and 4.3, the inspector reviewed the following:

• training records from 2019 to present

• personnel & environmental dosimetry records from 2019 to present

• annual radiation safety program audit for 2019

• annual operating report for 2019 - 2020

• as low as reasonably achievable (ALARA) report for 2018 and 2019

• facility radiological survey and wipe records for 2020

• survey meter calibration records for 2020

• UML Radiation Safety Guide, dated February 2015

b. Observations and Findings The inspector toured the facility with the Radiation Safety Officer (RSO) and noted that the use of personnel dosimetry and protective clothing, radiation monitoring equipment, placement of radiological signs and postings, and the storage of radioactive material, was in accordance with regulatory requirements and the licensees procedures. The inspector also noted that a copy of the current NRC Form 3, Notice to Employees, was posted at both entrances to the reactor bay as required by 10 CFR Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations. The inspector reviewed select portable radiation survey meter calibration records and verified all calibrations were current and that each instrument had a current calibration sticker attached.

The inspector noted that the RSO performed and documented an annual audit of the radiation protection program as a means for assuring radiation exposures were maintained ALARA. The inspector reviewed the UML radiation safety training database and found that the biennial radiation safety refresher training had been completed by all staff and students as required by licensee procedure.

The inspector reviewed personnel dosimetry records and found the values for all staff and students to be below 10 CFR Part 20 limits. In addition, the inspector reviewed records regarding effluent releases to the atmosphere and liquid effluent releases (i.e., stack and sewer releases) and found theses values to be below regulatory limits.

c. Conclusion The inspector determined that the radiation protection program was effective in minimizing radiation doses to individuals; surveys were completed and documented as required; postings met regulatory requirements; personnel dosimetry was worn and recorded doses were within regulatory limits; radiation safety refresher training was administered biennially as required; radiation monitoring equipment was maintained and calibrated as required; and environmental monitoring satisfied regulatory requirements.

4. Design Changes

a. Inspection Scope (IP 69001)

To ensure that facility changes were reviewed and approved as required by TS Section 6.2 and 10 CFR 50.59, the inspector reviewed selected aspects of the following:

• annual operating report for 2019 - 2020

• RSSC meeting minutes from June 2018 to June 2020

• procedure AP-6, 10 CFR 50.59 Screening and Evaluations, Rev. 1, dated December 18, 2015

• licensees 50.59 log book

b. Observations and Findings Through interviews with staff, and a review of the licensees 50.59 log book and RSSC quarterly meeting minutes, the inspector found that the licensee documented three changes in their 50.59 log book since the last inspection. The inspector determined that the changes were reviewed and approved in accordance with 10 CFR 50.59, TS, and the licensee procedure, and none required prior NRC approval.

c. Conclusion The inspector determined the licensee acceptably reviewed changes at the facility in accordance with 10 CFR 50.59, TS, and the licensee procedure.

5. Committees, Audits and Reviews

a. Inspection Scope (IP 69001)

The inspector reviewed the following to ensure that the reviews stipulated in TS Section 6.2 were implemented as required:

• RSSC charter Rev. 2, dated July 1, 2014

• RSSC meeting minutes from June 2018 to June 2020

b. Observations and Findings The inspector verified that the RSSC composition, meeting quorums, and meeting frequency were all in accordance with TS. The inspector reviewed the RSSC meeting minutes for the past 2 years and noted that the RSSC provided appropriate guidance and oversight in support of reactor operations.

c. Conclusion The inspector determined that the RSSC provided the appropriate oversight in support of reactor operations as required by TS.

6. Transportation

a. Inspection Scope (IP 86740)

The inspector interviewed the RSO and reviewed the following to verify compliance with regulatory and procedural requirements for shipping of RAM:

• procedure HPP-3, Work Instructions: Shipment of Radioactive Materials, dated November 13, 2015

• form FHPP-3, Radioactive Material Shipment Form

• UML database for transportation of radioactive material

b. Observations and Findings The inspector noted that the RSO was responsible for all of the licensees RAM shipments performed under the reactor license. The inspector reviewed a sample of RAM shipments and noted that all were properly shipped as excepted packages and noted that the associated records and packaging slips were completed as required by regulations. The inspector observed a health physics staff member and the RSO prepare a commercial service irradiated experiment for shipment as RAM and noted that the staff member and RSO were thorough and knowledgeable on the transportation requirements of RAM. The inspector also verified that the licensee had a copy of the offsite recipients RAM license regarding the transfer of the irradiated experiment. The inspector noted that the offsite recipients license was issued by the Commonwealth of Massachusetts, and it allowed for the possession of the specific type, form, and quantity of RAM to be shipped from UML.

c. Conclusion The inspector determined that the program for transportation of RAM satisfied regulatory requirements.

7. Exit Interview The inspector presented the inspection results to licensee management and RSSC members at the conclusion of the inspection on October 22, 2020. The licensee acknowledged the findings presented 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 P. Chowdhury Director, Nuclear Radiation Laboratory L. Bobek Reactor Supervisor S. Snay Radiation Safety Officer D. Lajuenesse Senior Reactor Operator M. Tries Chair, Reactor Safety Subcommittee C. Fontes Radiation Safety Inspector (UML staff)

INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors IP 86740 Inspection of Transportation Activities ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed:

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