IR 05000193/2009201

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IR 05000193-09-201, on 02/16-19/2009, for Rhode Island Nuclear Science Center Research Reactor
ML090610105
Person / Time
Site: Rhode Island Atomic Energy Commission
Issue date: 03/05/2009
From: Johnny Eads
Research and Test Reactors Branch B
To: Tehan T
State of RI, Atomic Energy Comm
DONOHUE J, NRC/NRR/DPR/PRTB 415-3163
References
IR-09-201
Download: ML090610105 (15)
v • d • e


Text

March 5, 2009 Dr. T. Tehan, Director Rhode Island Nuclear Science Center Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882-1165 SUBJECT: RHODE ISLAND ATOMIC ENERGY COMMISSION - NRC ROUTINE INSPECTION REPORT NO. 50-193/2009-201 The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on February 16-19, 2009, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2009-201). The inspection included a review of activities authorized for your facility. The enclosed report presents the results of that inspection.

This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations. 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 safety concern or noncompliance of requirements was identified. No response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations 2.390 Inspections, examinations, requests for withholding, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or the NRCs document system (Agencywide Document Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room)

http://www.nrc.gov/reading-rm/adams.html.

Should you have any questions concerning this inspection, please contact Marcus Voth at 301-415-1210 or electronic mail at Marcus.Voth@nrc.go

Sincerely,

/RA/

Johnny H. Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-193 License No. R-95 Enclosure: As stated cc w/ encl: See next page

Rhode Island Atomic Energy Commission Docket No.: 50-193 cc:

Governor Donald Carcieri State House Room 115 Providence, RI 02903 Dr. Stephen Mecca, Chairman Rhode Island Atomic Energy Commission Providence College Department of Engineering-Physics Systems River Avenue Providence, RI 02859 Dr. Harry Knickle, Chairman Nuclear and Radiation Safety Committee University of Rhode Island College of Engineering 112 Crawford Hall Kingston, RI 02881 Dr. Andrew Kadak 253 Rumstick Road Barrington, RI 02806 Dr. Bahram Nassersharif Dean of Engineering University of Rhode Island 102 Bliss Hall Kingston, RI 20881 Dr. Peter Gromet Department of Geological Sciences Brown University Providence, RI 02912 Dr. Alfred L. Allen 425 Laphan Farm Road Pascoag, RI 02859 Mr. Jack Ferruolo, Supervising Radiological Health Specialist Office of Occupational and Radiological Health Rhode Island Department of Health 3 Capitol Hill, Room 206 Providence, RI 02908-5097 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Dr. T. Tehan, Director

March 5, 2009 Rhode Island Nuclear Science Center Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882-1165 SUBJECT: RHODE ISLAND ATOMIC ENERGY COMMISSION - NRC ROUTINE INSPECTION REPORT NO. 50-193/2009-201 The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on February 16-19, 2009, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2009-201). The inspection included a review of activities authorized for your facility. The enclosed report presents the results of that inspection.

This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations. 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 safety concern or noncompliance of requirements was identified. No response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations 2.390 Inspections, examinations, requests for withholding, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or the NRCs document system (Agencywide Document Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room)

http://www.nrc.gov/reading-rm/adams.html.

Should you have any questions concerning this inspection, please contact Marcus Voth at 301-415-1210 or electronic mail at Marcus.Voth@nrc.go

Sincerely,

/RA/

Johnny H. Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-193 License No. R-95 Enclosure: As stated cc w/ enclosure:

See next page DISTRIBUTION:

PUBLIC PRTB/rf RidsNrrDprPrtb RidsOgcMailCenter JDonohue MVoth GWertz BDavis (Ltr only O13-E19)

GLappert ADAMS ACCESSION NO.: ML090610105 TEMPLATE #: NRR-106 OFFICE PRT:RI PRT:RIIT PRT:LA PRT:BC NAME MVoth mhv JDonohue jd GLappert gkl JEads jhe DATE 3/3/09 03/4/09 3/3/09 3/5/09 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-193 License No: R-95 Report No: 50-193/2009-201 Licensee: Rhode Island Atomic Energy Commission Facility: Rhode Island Nuclear Science Center Research Reactor Location: Narragansett, Rhode Island Dates: February 16 to 19, 2009 Inspectors: Marcus H. Voth (Lead)

Jack Donohue Approved by: Johnny H. Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

EXECUTIVE SUMMARY Rhode Island Atomic Energy Commission Rhode Island Nuclear Science Center Reactor Facility NRC Inspection Report No. 50-193/2009-201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the licensees Class I research reactor facility safety programs including organization and operations and maintenance activities; review and audit and design change function; experiments; procedures; radiation protection; effluent and environmental monitoring; and transportation. The licensee=s programs were acceptably directed toward the protection of public health and safety, and in compliance with U.S. Nuclear Regulatory Commission (NRC)

requirements.

Organization and Operations and Maintenance Activities

  • Organization and Operations and Maintenance Activities remain in compliance with the requirements specified in Technical Specifications.

Review and Audit and Design Change Functions

  • Within the scope of this review, the licensees review and design change program was found in conformance with Technical Specification and Regulatory requirements.

Experiments

  • Within the scope of this inspection the licensee was observed to be conducting experiments in accordance with regulatory and license requirements.

Procedures

  • Written procedures were being maintained in accordance with Technical Specification requirements.

Radiation Protection

  • The licensee continued to maintain an effective radiation protection program in compliance with regulatory and Technical Specification requirements, resulting in low radiation exposures to facility workers and users.

Effluent and Environmental Monitoring

  • The inspectors found environmental monitoring to conform to Technical Specification requirements and effluents to be in compliance with regulatory limits.

Transportation

  • The licensee did not ship any radioactive material under the reactor license since the previous transportation inspectio REPORT DETAILS Summary of Facility Status The Rhode Island Atomic Energy Commissions (RIAEC) Rhode Island Nuclear Science Center (RINSC) two megawatt research reactor continued to be operated in support of education, research, training, and surveillance. During the inspection, the reactor was operated to irradiate samples as part if its research mission. Organization and Operations and Maintenance Activities Inspection Scope (Inspection Procedure (IP)-69006)

The inspectors reviewed the following as a limited review of this area:

  • Reactor logbook #56, April 4, 2008 to present
  • Maintenance logbook
  • H. Bicehouse (RINSC) to D. Hughes (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2007 to June 30, 2008], August 18, 2008
  • Shift Staffing Observations and Findings The inspectors observed a reactor checkout, startup, approach to critical, escalation to full power, and a typical irradiation. The Reactor Logbook entries were reviewed satisfactorily with key information documented during reactor operations including start-up and shutdown, verifying compliance with the staffing requirements of Technical Specifications (TS) Sections 6.1.2 and 6.1.3 and that the NRC-licensed Reactor Operator (RO) and the Senior Reactor Operator (SRO) on duty were designated by name in the logboo A maintenance logbook had been utilized to document in greater detail than the reactor logbook the nature of significant maintenance performed on the reactor and auxiliary systems. Staffing was compliant within TS requirements and had recent replacements of an Assistant Director for Reactor Operations and a Health Physicis Reactor Power was logged when the required power level was reached, and used to determine the fuel burn-up for the Annual Report required by TS Sec 6.8.4.a. The inspectors questioned the accuracy of fuel burn-up data reported in the Annual Report. RINSC Staff suggested that they review capabilities using newly acquired instrumentation to increase reporting accuracy. The licensee was informed that this issue will be considered an Inspector Follow-up Item (IFI) and will be reviewed during subsequent inspections. (IFI-50-193/2009-201-01).

-2- Conclusions Organization and Operations and Maintenance Activities remain in compliance with the requirements specified in Technical Specifications. The reactor was being maintained per TS requirements.

2. Review and Audit and Design Change Functions Inspection Scope (IP 69007)

The inspector reviewed the following to ensure that the requirements of TS 6.0, Administrative Controls, and Title 10 of the Code of Federal Regulations (10 CFR) 50.59 were being implemented effectively:

  • File of Nuclear and Radiation Safety Committee (NRSC) Meeting Minutes from 2006 to 2008
  • H. Bicehouse (RINSC) to D. Hughes (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2007 to June 30, 2008], August 18, 2008
  • 10 CFR 50.59 Reviews file, December 2004 through September 2007 Observations and Findings Review of the minutes indicated that the meeting frequency, attendance, and actions met the requirements of TS Section 6.4, Review and Audit. Specifically, the inspectors verified that the NRSC had reviewed the two changes reported in the most recent annual report, improvements to the control rod drive system, and changes to the facility emergency pla Conclusions Within the scope of this review, the licensees review and design change program was found in conformance with Technical Specification and regulatory requirements.

3. Experiments Inspection Scope (IP 69005)

The inspectors reviewed selected portions of the following documents and records to ensure that the requirements of TS Sections 3.8, Limitations on Experiments, 4.8, Surveillance of Experiments, and 6.4, Review and Audit, were being met:

  • Reactor Experiment Notebook, desk copy maintained by M. J. Davis
  • Appendix P, In core Irradiations, Rev 0, August 2, 2006
  • Appendix AE, Glory Tube Gamma Irradiations, Rev 0, October 30, 2006
  • Appendix AF, Reactor Experiment Approval, Rev 3, September 29, 2008
  • Appendix AG, Reactor Experiment Request, Rev 1, September 29, 2008

-3-

  • NSC (Nuclear Science Center) - Form 42, Reactor Experiment Request Form
  • NSC Form 47, Attachment C, Reactor Experiment Approval
  • Form NSC - 49, Rev 0, Reactor Operation Request
  • RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, July 30, 2008
  • RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, September 29, 2008
  • RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, December 10, 2008 Observations and Findings The licensee had made numerous improvements over the past two to three years to assure and document the fact that experiments were given adequate review in accordance with regulatory and TS requirements. Detailed procedures had been reviewed and approved by the NRSC. Experiments were screened pursuant to 10 CFR 50.59 requirements. Legacy experiments being done routinely had been subjected to the new review process to assure that safety considerations were known, documented, and properly applied. The inspectors reviewed evidence that experiments were reviewed and approved in accordance with TS requirement The inspectors observed reactor operations in support of a user performing an experiment involving the irradiation of numerous samples using the pneumatic transfer system. The reactor operator and experimenter maintained appropriate communication during the experiment, were both knowledgeable of their responsibility in executing the experiment, and exercised safety precautions in accordance with the approved procedur Conclusions Within the scope of this inspection the licensee was observed to be conducting experiments in accordance with regulatory and license requirements.

4. Procedures Inspection Scope (IP 69008)

The inspectors reviewed the following to ensure that the requirements of TS Sections 6.4, Review and Audit, and 6.5, Operating Procedures, were being met:

  • Procedures Manual, desk copy maintained by M. J. Davis
  • Appendix V, RINSC Pre-Start Checkout, Rev 12, July 30, 2008
  • Form NSC - 1, Pre-Startup Check Sheet
  • Form NSC - 1C, Shutdown Check Sheet
  • Form NSC - 11, Shift record Data Sheet
  • Form NSC - 18 RINSC Reactor Operations Data

-4-

  • RINSC Nuclear and Radiation Safety Committee Full committee Meeting Minutes, July 30, 2008
  • RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, September 29, 2008
  • RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, December 10, 2008 Observations and Findings The inspectors observed that the licensee maintained written procedures covering the areas specified in TS Section 6.5, Operating Procedures. A systematic approach was being used to update and reissue procedures. Newly revised procedures and major changes were reviewed and approved by the NRSC in accordance with TS Section 6.4, Review and Audit. The reviews and approvals were documented in the minutes of the NRSC meeting Conclusions The licensee was maintaining and implementing written procedures in accordance with TS requirements.

5. Radiation Protection Inspection Scope (IP 69012)

The following documents were reviewed to determine compliance with 10 CFR 19 and 20 and with TS Sections 3.7.1, Radiation Monitoring Systems, and 4.7, Radiation Monitoring Systems and Effluents, requirements regarding radiation protection:

  • RINSC Radiation Protection Annual Audit, H. Bicehouse, Radiation Safety Officer (RSO), January 26 to 30, 2009
  • Survey Program Summary Data for 2007, printed February 16, 2009
  • Survey Program Summary Data for 2008, printed February 16, 2009
  • File of Landauer Dosimetry Reports, January 11, 2007 to January 11, 2008
  • RINSC Radiation Safety Office, SOP Manual
  • RINSC Radiation Safety Office, SOP 101, Radiation Safety Training, March 23, 2000
  • RINSC Radiation Safety Office, SOP 220, Pocket Dosimeter Calibration, March 28, 2003
  • RINSC Radiation Safety Office, SOP 300, Routine Surveys
  • RINSC Radiation Safety Office, SOP 801, Instrument Calibration, November 6, 2000
  • [Radiation Safety] Training file
  • Radiation Safety Training Manual

-5-

  • Summary of Radiation Area Monitors and Survey Meters as of January 25, 2006
  • Instrumentation Calibration of Area Monitors (for reactor bridge, fuel safe, thermal column, heat exchanger area, and cleanup-demineralizer rooms),

December 27, 2006

  • Instrumentation Calibration of Area Monitors (for reactor bridge, fuel safe, thermal column, heat exchanger area, and cleanup-demineralizer rooms),

November 19, 2008

  • Main and Stack [Continuous Air] Monitor file
  • Survey Meter Calibration File (for GSM 110) through December 21, 2007
  • Air Monitor Data Sheet file through July 30, 2008
  • Camberra Series 5 Low Background Alpha/Beta Counter Quality Control Records
  • RINSC, Operating Procedures, Main Floor Area Monitor Channel Test, Procedure Appendix AB, Rev 1, July 2, 2003 b. Observations and Findings Radiation Protection Procedures at the facility meet regulatory requirements and license commitments. The inspectors verified Form NRC-3 Notice to Employees is posted as required and caution signs, labels and controls were posted as required. The inspectors accompanied a HP technician during weekly surveys. Through the review of procedures and records, observations during facility tours, and discussion with staff personnel, the inspectors had determined that the licensees radiation protection program was in accordance with TS requirement The licensee maintained and adhered to written procedures and instructions for all aspects of the radiation safety program. During tours through the facility the inspectors verified that postings for radiation workers were in accordance with regulations and procedures. Protective clothing was available if needed but areas were maintained in a clean condition such that it was not required during times of routine operatio Workers and visitors (Boy Scouts) were observed wearing appropriate dosimetry throughout the facility. Routine radiation surveys, smear samples, and fixed monitor readings were taken throughout the facility to verify that radiation exposure rates were known and maintained As Low As Reasonably Achievable (ALARA). The licensee made effective use of data bases, monitoring for trends and abnormalitie The inspectors found the scope of the radiation detection equipment calibration program to be sufficiently comprehensive and techniques used to be state-of-the-ar The overall effectiveness of the radiation protection program was monitored with Optically Stimulated Luminescence Devices (OSLD) worn by workers. No worker received any significant exposur It should be noted that RIAEC on October 24, 2008 has requested withdrawal of

-6-the request for renewal of Radioactive Material License No. 3K-063-01 (Broad Scope License) due to financial considerations. The loss of the broad scope license will have no impact on the reactor licens Conclusions The licensee had maintained an effective radiation protection program in compliance with regulatory and Technical Specification requirements, resulting in low radiation exposures to facility workers and users.

6. Effluent and Environmental Monitoring Inspection Scope (IP 69004)

The inspectors reviewed the following to verify that the requirements of TS Section 4.7, Radiation Monitoring Systems and Effluents, were being met:

  • Dosimetry Records for 2008
  • H. Bicehouse (RINSC) to D. Hughes (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2007 to June 30, 2008, August 18, 2008] Observations and Findings The inspectors toured the facility with a staff member doing a routine weekly facility radiation survey, observing where environmental releases of gaseous, liquid and solid radioactive material are generated and monitore The predominant environmental release from the facility was argon-41 resulting from activated air entrained in the reactor pool water, present in beam tubes, and used for cooling pneumatic transfer tubes. The gaseous release was 8 percent of the regulatory limit based on computations using the COMPLY code with Level 4 input; that is, actual building and effluent stack dimensions with site meteorological dat The license made only one liquid release during the past year, a 450 gallon batch release analyzed to be 3.45 percent of the permissible release concentratio The licensee reported that there were no shipments of solid waste from the facility during the past yea The licensee maintained OSLDs at three locations around the exterior of the facility and sent them to a commercial processor quarterly along with personnel dosimeters. Since the areas monitored had limited public access the licensee adjusted the readings by occupancy times, resulting in dose rates at those locations less than a tenth of the regulatory limi Conclusions The inspectors found environmental monitoring to conform to Technical Specification requirements and effluents to be in compliance with regulatory limits.

7. Transportation Inspection Scope (IP 86740)

The inspectors reviewed the following document to determine compliance with NRC (10 CFR Parts 20 and 71) Standards For Protection Against Packaging Against Radiation and Transportation Of Radioactive Material and Department of Transportation (DOT) (49 CFR Parts 171-178) transport regulation * RINSC Radiation Protection Annual Audit, H.J. Bicehouse, Radiation Safety Officer dated January 26-30, 200 * Staff interviews Observations and Findings The inspectors reviewed the RINSC Radiation Protection Audit for radioactive shipments made under the reactor license (R-95) and staff personnel and found that there were no shipments made since the previous transportation inspectio Conclusions The licensee did not ship any radioactive material under the R-95 license since the previous transportation inspection.

8. Exit Interview The inspection scope and results were summarized on February 19, 2009, with members of licensee management. The inspectors described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee. It was agreed that no proprietary information was addressed and that the results of the inspection are subject to management revie PARTIAL LIST OF PERSONS CONTACTED Licensee H. Bicehouse, Radiation Safety Officer and Assistant Director for Radiation and Reactor Safety M. Damato, Health Physics Technician and Reactor Operator M.J. Davis, Reactor Supervisor S. Mecca, Chairman, Rhode Island Atomic Energy Commission T. Tehan, Director, Rhode Island Nuclear Science Center C. Waring, Health Physicist E. Wentz, Assistant Director for Reactor Operations INSPECTION PROCEDURES USED IP 69004 Class 1 Research and Test Reactor Effluent and Environmental Monitoring IP 69005 Class 1 Research and Test Reactors Experiments IP 69006 Class 1 Research and Test Reactors Organization and Operations and Maintenance Activities IP 69007 Class 1 Research and Test Reactors Review and Audit and Design Change Functions IP 69008 Class 1 Research and Test Reactors Procedures IP 69012 Class 1 Research and Test Reactor Radiation Protection IP 86740 Transportation ITEMS OPENED, CLOSED, AND DISCUSSED Opened 50-193/2009-201-01 IFI Reactor Power was logged when reaching the required power level and used to determine the fuel burn-up for the Annual Report. RINSC Staff will investigate a more accurate determination.

Closed None Discussed None

-2-LIST OF ACRONYMS USED ADAMS Agencywide Document Access Management System ALARA As Low As Reasonably Achievable CFR Code of Federal Regulations IFI Inspector Follow-up Item IP Inspection Procedure NRC Nuclear Regulatory Commission NRSC Nuclear and Radiation Safety Committee NSC Nuclear Science Center OSLD Optically Stimulated Luminescent Device Rev Revision RIAEC Rhode Island Atomic Energy Commission RINSC Rhode Island Nuclear Science Center RO Reactor Operator RSO Radiation Safety Officer SOP Standard Operating Procedure SRO Senior Reactor Operator TS Technical Specification

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