IR 05000193/2010201
| ML100750335 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 03/30/2010 |
| From: | Johnny Eads Research and Test Reactors Branch B |
| To: | Tehan T State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| DONOHUE J, NRC/NRR/DPR/PRTB 415-3163 | |
| References | |
| IR-10-201 | |
| Download: ML100750335 (15) | |
Text
March 30, 2010 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. 50-193/2010-201 The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on March 1-4, 2010, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2010-201). 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 Jack Donohue at 301-415-3163 or electronic mail at Jack.Donohue@nrc.go
Sincerely,
/RA/
Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch 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
March 30, 2010 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. 50-193/2010-201 The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on March 1-4, 2010, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2010-201). 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 Jack Donohue at 301-415-3163 or electronic mail at Jack.Donohue@nrc.go
Sincerely,
/RA/
Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch 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 DISTRIBUTION:
PUBLIC PROB/rf RidsNrrDprPrtb JDonohue, NRR WKennedy, NRR MCompton (Ltr only O13-E19) GLappert, NRR MRoss-Lee, NRR ADAMS ACCESSION NO.: ML100750335 TEMPLATE #: NRC-002 OFFICE PROB:RI PRPB:LA PROB:BC NAME JDonohue GLappert JEads DATE 3/16/2010 3/29/2010 3/30/2010 OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-193 License No: R-95 Report No: 50-193/2010-201 Licensee: Rhode Island Atomic Energy Commission Facility: Rhode Island Nuclear Science Center Research Reactor Location: Narragansett, Rhode Island Dates: March 1 to 4, 2010 Inspector: Jack Donohue Accompanied by: Mary Jane Ross-Lee, Chief Research and Test Reactor Projects Branch Approved by: Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch 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. 50-193/2010-201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Rhode Island Atomic Energy Commission (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, the licensee) 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 inspector reviewed the following as a limited review of this area:
- Reactor logbook #57, June 17, 2009 to present
- Maintenance logbook
- H. Bicehouse (RINSC) to W. Kennedy (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2008 to June 30, 2009], dated July 31, 2009
- Shift Staffing
- Form NSC-1, Pre-Start Check Sheet, dated December 10, 2008 Observations and Findings The inspector 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 thru power operations, verifying compliance with the staffing requirements of Technical Specifications (TS) Sections 6.1.2 and 6.1.3 and that the Reactor Operator (RO) in training and the Senior Reactor Operator (SRO) on duty were designated by name in the logboo During operations, off site power was lost causing a scram. The diesel generator automatically started and provided emergency lighting and backup electrical power. Power was restored within one hour and the reactor shutdown was complete 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 Conclusions Organization and Operations and Maintenance Activities remain in compliance with the requirements specified in TS. The reactor was being maintained per TS requirements. Staffing was compliant with 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) Section 50.59 were being implemented effectively:
- File of Nuclear and Radiation Safety Committee (NRSC) Meeting Minutes from 2008 to 2009
- H. Bicehouse (RINSC) to W. Kennedy (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2008 to June 30, 2009], dated July, 2009
- Review of 10 CFR 50.59 file, December 2006 through September 2009 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 inspector verified that the NRSC had reviewed the three changes reported in the most recent annual report, improvements to the Secondary Water Analysis, the special nuclear material (SNM) Accounting and changes to the reactor Experimental Approval Procedur Conclusions Within the scope of this review, the licensees review and design change program was found in conformance with TS and regulatory requirements.
3. Experiments Inspection Scope (IP 69005)
The inspector 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 XP-04, Incore Irradiations, Rev 1, dated December 4, 2009
- Appendix XP-12, Glory Tube Gamma Irradiations, Rev 1, dated December 4, 2009
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- Appendix XP-02, Reactor Experiment Approval, Rev 4, dated March 10, 2009
- Appendix XP-01, Reactor Experiment Request, Rev 1, dated September 29, 2008
- NSC (Nuclear Science Center) - Form 42, Reactor Experiment Request Form
- NSC Form 47, Attachment C, Reactor Experiment Approval
- Form NSC - 49, Rev 2, Reactor Operation Request
- RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, dated March 10, 2009
- RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, dated July 22, 2009
- RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, dated October 30, 2009 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 inspector reviewed evidence that experiments were reviewed and approved in accordance with TS requirement The inspector observed reactor operations in support of a user performing an experiment involving the irradiation of numerous samples using the pneumatic transfer system. The RO 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 procedure. The experiment was not completed due to the inadvertent scram on loss of powe 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 inspector reviewed the following to ensure that the requirements of TS Sections 6.4, Review and Audit, and 6.5, Operating Procedures, were being met:
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- Procedures Manual, desk copy maintained by M. J. Davis
- Appendix OP-2, RINSC Pre-Start Checkout, Rev 13, dated December 10, 2008
- Appendix OP-3, Reactor Power Changes, Rev 4, dated December 10, 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
- RINSC Nuclear and Radiation Safety Committee Full committee Meeting Minutes, dated March 10, 2009
- RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, dated July 22, 2009
- RINSC Nuclear and Radiation Safety Committee, Full committee Meeting Minutes, dated October 30, 2009 Observations and Findings The inspector 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
- NRC Form 3, Notice to Employees, dated October 2008
- File of Landauer Dosimetry Reports, Quarterly reports for 2009
- RINSC Radiation Safety Office, SOP Manual
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- RINSC Radiation Safety Office, SOP 101, Radiation Safety Training, dated March 23, 2000
- RINSC Radiation Safety Office, SOP 220, Pocket Dosimeter Calibration, dated March 28, 2003
- RINSC Radiation Safety Office, SOP 300, Routine Surveys, dated February 10, 2004
- RINSC Radiation Safety Office, SOP 801, Instrument Calibration, dated November 6, 2000
- Radiation Safety Training file
- Radiation Safety Training Manual
- 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),
dated November 19, 2008
- Main and Stack [Continuous Air] Monitor file
- Survey Meter Calibration File (for GSM 110) through February 28, 2010
- Air Monitor Data Sheet file through February 28, 2010
- 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, dated July 2, 2003 b. Observations and Findings Radiation Protection Procedures at the facility meet regulatory requirements and license commitments. The inspector verified Form NRC-3 Notice to Employees is posted as required and caution signs, labels and controls were posted as required. The inspector reviewed weekly, monthly, quarterly and annual survey Through the review of procedures and records, observations during facility tours, and discussion with staff personnel, the inspector 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 students (Roger Williams College) 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 inspector 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 has not renewed the Radioactive Material License No. 3K-063-01 (Broad Scope License) due to financial considerations. The facility will use the University License (3K-040-01) to ship non-R-95 reactor license radioactive materia Conclusions The licensee had maintained an effective radiation protection program in compliance with regulatory and TS requirements, resulting in low radiation exposures to facility workers and users.
6. Effluent and Environmental Monitoring Inspection Scope (IP 69004)
The inspector reviewed the following to verify that the requirements of TS Section 4.7, Radiation Monitoring Systems and Effluents, were being met:
- Dosimetry Records for 2009
- H. Bicehouse (RINSC) to W. Kennedy (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2008 to June 30, 2009], dated July 31, 2009 Observations and Findings The inspector 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 .02 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 inspector reviewed the data from a small primary water leak. Analysis over a two year period indicates the leak rate to be about eight gallons/day. Leak collectors have been put into place in the locations where the leaks have typically
-7-occurred. Sodium (Na-24) has not been detected in the water and the Tritium concentration are an order of magnitude below the 10 CFR 20 release limit This event has been reviewed by the Nuclear Radiation and Safety Committee (NRSC). The RINSC staff will continue to monitor the leak and the NRSC will define the magnitude of the leak at which they need to be inform and develop a plan in the event that magnitude is reache 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 inspector found environmental monitoring to conform to TS requirements and effluents to be in compliance with regulatory limits.
7. Transportation Inspection Scope (IP 86740)
The inspector reviewed the following document to determine compliance with NRC (10 CFR Parts 20 and 71) Standards for Protection against Radiation and Packaging and Transportation of Radioactive Material and Department of Transportation (DOT) Title 49 of the Code of Federal Regulations Parts 171-178, transport regulation * RINSC Radiation Protection Annual Audit, H.J. Bicehouse, Radiation Safety Officer, January 26-30, 200 * Staff interviews Observations and Findings The inspector reviewed the RINSC Radiation Protection Audit for radioactive shipments made under the R-95 reactor license, interviewed 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 reactor license since the previous transportation inspectio . Follow up on Previous Identified Items Unresolved item follow-up Inspector Follow-up Item (IFI) 50-193/2009-201-01, 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 determinatio Observation and Finding RINSC has added an integrated megawatt per hour (MWH) feature to the rod drive display system. This feature calculates the MWH of operation by determining reactor power level as measured by the wide range monitor and integrating over time. The display system provides an indication of the lifetime MWH of operation of the facilit Conclusions RINSC staff has improved the accuracy in Reactor Power determination. IFI 50-193/2009-201-01 is considered closed.
9. Exit Interview The inspection scope and results were summarized on March 4, 2010, with members of licensee management. The inspector 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 M. Damato Health Physics Technician and Reactor Operator M.J. Davis Assistant Director for Reactor Operations B. MacGregor Facility Engineer B. Nassersharif Acting Chairman, Rhode Island Atomic Energy Commission T. Nunes Rhode Island Atomic Energy Commission Z. Richards Reactor Operator Trainee T. Tehan Director, Rhode Island Nuclear Science Center C. Waring Health Physicist 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 IP 92701 Follow up ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed 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.
Discussed None
-2-LIST OF ACRONYMS USED ADAMS Agencywide Document Access Management System ALARA As Low As Reasonably Achievable 10 CFR Title 10 of the 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