IR 05000193/2012202
| ML12292A008 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 10/22/2012 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Tehan T State of RI, Atomic Energy Comm, State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| Bassett, Craig 301-466-4495 | |
| References | |
| IR-12-202 | |
| Download: ML12292A008 (20) | |
Text
October 22, 2012
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. 50-193/2012-202
The U.S. Nuclear Regulatory Commission (NRC or the Commission) conducted an inspection from October 1 to 4, 2012, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2012-202). The enclosed report documents the inspection results, which were discussed with you and other members of your staff on October 4, 201 The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your licens The inspector reviewed selected procedures and records, observed various activities, and interviewed personne Based on the results of this inspection, no findings of significance were identifie No response to this letter is require Based on the results of this inspection, the NRC has determined that one Severity Level IV violation of NRC requirements occurre Because this violation was licensee identified, promptly corrected, non-repetitive and non-willful, it is being treated as a non-cited violation (NCV), consistent with Section 2.3.2.b of the Enforcement Polic The NCV is described in the subject inspection repor If you contest the violation or the significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Director, Office of Nuclear Reactor Regulation, and Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-000 In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, and 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).
T. Tehan
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Should you have any questions concerning this inspection, please contact Craig Bassett at (301) 466-4495 or electronic mail at Craig.Bassett@nrc.go
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Docket N License N R-95
Enclosure: NRC Inspection Report No. 50-193/2012-202 cc w/ encl: Please 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. Peter Gromet Department of Geological Sciences Brown University Providence, RI 02912
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. Tony Nunes University of Rhode Island Department of Physics 210 East Hall Kingston, RI 02881
Dr. John Breen, Chairman Nuclear and Radiation Safety Committee Providence College 549 River Ave Providence, RI 02918
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
T. Tehan
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Should you have any questions concerning this inspection, please contact Craig Bassett at (301) 466-4495 or electronic mail at Craig.Bassett@nrc.go
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Docket N License N R-95
Enclosure: NRC Inspection Report No. 50-193/2012-202 cc w/ encl: Please see next page
DISTRIBUTION:
PUBLIC RidsNrrDprPrta Resource RidsNrrDprPrtb Resource PROB r/f MNorris (MS T3B46M)
MCompton (Ltr only O5-A4)
GLappert, NRR CBassett, NRR XYin, NRR DHardesty, NRR WKennedy, NRR
ACCESSION NO.: ML12292A008 *concurrence via e-mail TEMPLATE #: NRC-002 OFFICE PROB:RI *
PRPB:LA PROB:BC NAME CBassett GLappert GBowman DATE 10/11/2012 10/18/2012 10/22/2012 OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No:
50-193
License No:
R-95
Report No:
50-193/2012-202
Licensee:
Rhode Island Atomic Energy Commission
Facility:
Rhode Island Nuclear Science Center Research Reactor
Location:
Narragansett, Rhode Island
Dates:
October 1-4, 2012
Inspector:
Craig Bassett
Approved by:
Gregory T. Bowman, 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 Report No.: 50-193/2012-202
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Rhode Island Atomic Energy Commission (the licensees) two megawatt Class I research reactor safety program, including: (1) organizational structure and functions, (2) review and audit and design change functions, (3) reactor operations, (4) operator requalification, (5) maintenance and surveillance, (6) fuel handling, and (7) emergency preparednes The review covered the period of time from the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas to the presen The licensees program was acceptably directed toward the protection of public health and safety and was in compliance with the NRC requirement One non-cited violation was identifie Organizational Structure and Functions
The organization structure and staff functions were observed to be generally in accordance with Technical Specification (TS) requirement Review and Audit and Design Change Functions
The Nuclear and Radiation Safety Committee was meeting as required and reviewing the topics outlined in the TS Reviews and audits were being completed as require Design changes were being completed as require The change review process was being revised to ensure that such reviews satisfy all the requirements specified in Title 10 of the Code of Federal Regulations Section 50.5 Reactor Operations
Reactor operations, as well as operator cognizance of facility conditions during startup and routine operation, were acceptabl Operator Requalification
Operator requalification was being completed as required by the licensees requalification program and the program was being maintained curren Operators were receiving their biennial physical examinations as require Maintenance and Surveillance
The program established and implemented by the licensee was being used to complete maintenance activities at the facilit The surveillance program currently in use by the licensee satisfied TS requirement Fuel Handling
Fuel movements were conducted in accordance with TS and procedural requirement Fuel inspections were being completed as require Emergency Preparedness
The emergency preparedness program was conducted in accordance with the Emergency Pla Training for all facility personnel was being conducted annually as require Emergency response equipment was available and was being maintained and inventoried as require Emergency drills were being conducted annually as required by the Emergency Plan and critiques were held following the drill REPORT DETAILS
Summary of Facility Status
The Rhode Island Atomic Energy Commissions (RIAECs or the licensees) Rhode Island Nuclear Science Center (RINSC) two megawatt Class I research reactor continued to be operated in support of research, service, education, training, and surveillanc During the inspection the inspector observed reactor operations being conducted to irradiate samples as part of its research and service missio.
Organization Structure and Functions Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the following regarding the licensees organization and staffing to ensure that the requirements of Sections 6.1, Organization and Management, and 6.2, Qualification of Personnel, of the RINSC Technical Specifications (TS), Amendment No. 29, dated December 28, 2004, to Facility License No. R-95 were being met:
- RINSC organizational structure and staffing
Resume of the current facility Assistant Director for Radiation and Reactor Safety/Radiation Safety Officer
RINSC Annual Report for the period from July 1, 2010, through June 30, 2011, submitted to the NRC on July 28, 2011
RINSC Annual Report for the period from July 1, 2011, through June 30, 2012, submitted to the NRC on August 30, 2012 Observations and Findings
The inspector reviewed facility staffing with the RINSC Directo He indicated that since the last inspection, a change had occurred in one of the key positions at the facilit The individual who had held the position of Assistant Director for Radiation and Reactor Safety/Radiation Safety Officer had retire The inspector noted that a staff member, the facility Health Physicist, had been promoted to fill the vacant positio The inspector reviewed the background of the newly promoted individual and determined that this individual had the work experience required by TS 6.2.2; however, it was also noted that the person did not yet have a Masters degree, as required by the T The individual had prepared his thesis and was scheduled to defend the thesis at the end of Octobe The inspector evaluated this issue and determined that it represented a minor violation of TS 6. The licensee was informed that the successful completion of this process and the obtaining of a Masters degree by the new Assistant Director for Radiation and Reactor Safety will be followed by the NRC as an Inspector Follow-up Item (IFI) and will be reviewed by the NRC during a future inspection (IFI 50-193/2012-202-01).
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The organization structure and staff functions were observed to be in general accordance with TS requirement.
Review and Audit and Design Change Functions Inspection Scope (IP 69007)
The inspector reviewed the review and audit and design change functions and selected aspects of the following to ensure compliance with TS 6.4:
- Nuclear and Radiation Safety Committee (NRSC) Charter, Revision (Rev.) 1, approval dated April 25, 2011
NRSC meeting minutes from July 2010 through the present
50.59 Screen/Review Forms for the following modifications or changes:
-
Neutron Flux Monitor, review completed February 28, 2011
-
Thermal Column Upgrade, review completed April 21, 2011
-
Installation of Digital Instrumentation and Control for the Reactor Cooling System, review completed April 21, 2011
-
Neutron Flux Monitor Non-Op System, review completed January 11, 2012
-
Installation of Digital Instrumentation and Control for the Reactor Cooling System, review completed February 17, 2012
RINSC Annual Report for the period from July 1, 2010, through June 30, 2011, submitted to the NRC on July 28, 2011
RINSC Annual Report for the period from July 1, 2011, through June 30, 2012, submitted to the NRC on August 30, 2012 Observations and Findings
(1)
Review and Audit Functions
The inspector reviewed the NRSC meeting minutes and associated records from July 2010 through the presen The records showed that meetings were being held and safety reviews and audits were conducted by various members of the NRSC or other designated persons as required and at the TS-required frequenc Topics of these reviews and audits were consistent with TS requirements to provide guidance, direction, and oversight for the facility, and acceptable use of the reacto No significant problems or deficiencies were found during the audits, but some areas for improvement were note Corrective actions were taken as neede (2)
Design Change Functions
Through interviews with licensee personnel, the inspector determined that various changes had been initiated and/or completed at the facility since the last NRC inspectio The inspector reviewed the Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59 review process used at the facilit The reviews had been presented to the NRSC for review and approva It was noted that none of the reviews that had been completed required that a full safety evaluation be conducte It was also noted that none of the changes required NRC approval prior to implementatio In reviewing the process used by the licensee to conduct some of their 10 CFR 50.59 reviews, the inspector noted that it was a process that had been acceptable prior to the current revision of 10 CFR 50.59, which was promulgated by the NRC in 199 The licensee indicated that they were in the process of finalizing a procedure to be used for completing changes or modifications to the facility or reactor systems that could have a significant effect on reactor safet The licensee was informed that the implementation of a facility modification procedure, to include the 50.59 review process, will be followed by the NRC as an IFI and will be reviewed during a future inspection (IFI 50-193/2012-202-02). Conclusion
The NRSC was meeting as required and reviewing the topics outlined in the T Audits were being completed as require Design changes were being completed, but the modification review process was being revised and the revised process will be reviewed by the NRC during a future inspectio.
Reactor Operations Inspection Scope (IP 69006)
To verify that the licensee was operating the reactor and documenting activities in accordance with TS 6.1 and 6.2, and procedural requirements, the inspector reviewed selected portions of the following:
- Reactor Logbook No. 58, covering the period from August 16, 2010, through December 2, 2011
Reactor Logbook No. 59, covering the period from December 6, 2011, through the present
Periodic Maintenance Notebook containing the documentation of maintenance items
RINSC Reactor Operating Procedure (OP) OP-01, Reactor Operation Request, Rev. 2, NRSC approval dated December 4, 2009, which included RINSC Form NSC-49, Reactor Operations Request
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RINSC OP-02, RINSC Pre-Start Checkout, Rev. 15, NRSC approval dated April 25 2011, which included RINSC Form NSC-1, Pre-Start Check Sheet
RINSC OP-03, Reactor Power Changes, Rev. 4, NRSC approval dated December 10, 2008, which included the following:
-
RINSC Form NSC-11, Shift Record Data Sheet
-
RINSC Form NSC-18, RINSC Reactor Operations Data
-
RINSC Form NSC-1C, Shutdown Check Sheet
RINSC OP-04, Abnormal Procedures, Rev. 2, NRSC approval dated April 25, 2011
RINSC Annual Report for the period from July 1, 2010, through June 30, 2011, submitted to the NRC on July 28, 2011
RINSC Annual Report for the period from July 1, 2011, through June 30, 2012, submitted to the NRC on August 30, 2012 Observations and Findings
The inspector observed reactor operations which included a reactor checkout, startup, approach to criticality, and escalation to full powe The senior reactor operator (SRO) followed procedure and was cognizant of facility conditions as require The inspector also reviewed portions of the two most recent Reactor Logbooks to verify compliance with the staffing requirements of TS 6.1.2 and 6. The reactor operator on duty was designated by name in the reactor logbook as was the second person at the facilit Conclusion
Reactor operations, as well as operator cognizance of facility conditions during startup and routine operation, were acceptabl.
Operator Requalification Inspection Scope (IP 69003)
The inspector reviewed selected aspects of the following to ensure compliance with the licensees operator requalification program outlined in RINSC Administrative Procedure AP-02, Reactor Operator Requalification, NRSC approval dated June 29, 2005:
- Reactor Logbook No. 58, covering the period from August 16, 2010, through December 2, 2011
Reactor Logbook No. 59, covering the period from December 6, 2011, through the present
Individual operator requalification files containing copies of the following:
-
Operator Requalification Program Checklist
-
Annual Operational Requalification Exam forms
-
Biennial Operator Requalification Examinations
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-
Letters from the NRC to the licensed operators documenting the issuance of a reactor or senior reactor operator license
Copies for each individual of their respective NRC Form 396, Certification of Medical Examination by Facility Licensee
American National Standards Institute/American Nuclear Society 15.4-2007, Selection and Training of Personnel for Research Reactors, Section 7, Medical Certification and Monitoring of Certified Personnel, for use as the basis for determining adequate physical fitness to serve as a reactor operator or senior reactor operator Observations and Findings
There were five qualified SROs on staff at the facilit The licensee indicated that there were various people in training to become operators and two individuals who had taken the NRC license examination, but the results were not yet formally availabl A review of the logs and records showed that training was being conducted in accordance with the licensees requalification and training progra Procedure reviews and examinations had been documented as require Information regarding facility changes and other relevant information had been routed for review and licensed operators acknowledged their review of this informatio The inspector verified that quarterly reactor operations, reactivity manipulations, and Reactor Supervisor activities were being completed as required and the appropriate records were being maintaine Records indicating the successful completion of the annual operations tests and supervisory observations were also maintaine The program was being maintained curren Biennial written examinations were being completed by the SROs as require The inspector reviewed the last biennial requalification examination, which had been administered in March of this yea It was noted that the exam was similar in its level of difficulty as compared to NRC-administered examination The inspector also noted that all operators were receiving biennial medical examinations within the allowed time frame as require Conclusion
Operator requalification was being conducted in accordance with the licensees operator requalification progra Operators were receiving their biennial physical examinations as require.
Maintenance and Surveillance Inspection Scope (IP 69006 and 69010)
The inspector reviewed the following to verify compliance with TS Section 3.0, Limiting Conditions for Operation, and to ensure that periodic surveillance tests on safety systems were performed as stipulated in TS Section 4.0, Surveillance Requirements:
- RINSC Reactor Operating Data Notebook for 2011 and to date in 2012
RINSC Calibration Procedure (CP), CP-01, Primary Temperature Channel Calibration, Rev. 1, NRSC approval dated July 29, 2010
RINSC CP-04, Alarm, Scram, and Interlock Checks, Rev. 7, NRSC approval dated July 29, 2010
RINSC CP-06, Stack Monitor Calibration, Rev. 0, NRSC approval dated July 2, 2003
RINSC Maintenance Procedure (MP), MP-01, Confinement System Surveillance, Rev.0, NRSC approval dated November 20, 2001
RINSC MP-03, Primary Water Analysis, Rev.3, NRSC approval dated April 25, 2011
RINSC MP-04, Secondary Water Analysis, Rev. 1, dated July 22, 2009
RINSC Reactor Parameter Testing Procedure (TP) TP-01, Shim Safety Rod Drop Time Measurement, Rev. 1, NRSC approval dated July 29, 2010
RINSC TP-03, Control Rod Reactivity Worths, Rev. 0, NRSC approval dated December 4, 2009
RINSC TP-04, Control Rod Reactivity Insertion Rates, Rev. 2, NRSC approval dated December 4, 2009
RINSC Annual Report for the period from July 1, 2010, through June 30, 2011, submitted to the NRC on July 28, 2011
RINSC Annual Report for the period from July 1, 2011, through June 30, 2012, submitted to the NRC on August 30, 2012 Observations and Findings
(1)
Maintenance
The inspector reviewed the chart or spreadsheet which the licensee had developed to track maintenance and surveillance activitie The program was designed to ensure that all maintenance activities were completed as scheduled and that the entire process was documented appropriatel The maintenance records indicated that problems were addressed and preventive maintenance operations completed as required by procedur Records showed that routine maintenance activities were conducted at the required frequencies and in accordance with the TS and/or the applicable procedur (2)
Surveillance
Various periodic surveillance verifications and calibration of equipment, including the testing of various reactor systems, instrumentation, auxiliary systems, and security systems and alarms, were reviewed by the inspecto As noted above, the licensee used a spreadsheet to track these verifications and calibrations and followed the same established schedule each year. The data recorded in the reactor logbooks and on the surveillance records indicated that the verifications and calibrations had been completed on schedule and in accordance with licensee procedure The results reviewed by the inspector were noted to be within the TS and procedurally prescribed parameter Maintenance and surveillance activities ensured that equipment remained consistent with the Safety Analysis Report and TS requirement Conclusion
The program for conducting maintenance and completing surveillance activities was being carried out in accordance with TS and procedural requirement.
Fuel Handling and Movement Inspection Scope (IP 69009)
The inspector reviewed the following to verify compliance with TSs 4.9.b and 6.9.1.g, which require visual inspection of each fuel element every 5 years, with a minimum of a fifth of the fuel elements inspected annually, along with maintenance of operating records of these fuel inventories:
- Reactor Logbook No. 58, covering the period from August 16, 2010, through December 2, 2011
Reactor Logbook No. 59, covering the period from December 6, 2011, through the present
RINSC Inspection Procedure IP-01, Core Element Movement and Inspection, Rev. 0, NRSC approval dated December 4, 2009
RINSC OP-05, Core Refueling, Rev. 2, NRSC approval dated April 25, 2011, including documentation of the core history and projected core lifetime
Selected fuel element inspection sheets for 2011 and 2012 Observations and Findings
(1)
Fuel Movement and Inspection
The inspector reviewed the fuel movement process and verified that fuel was moved according to established procedure and inspected in accordance with a specific inspection schedul The inspector reviewed selected fuel movement sheets for 2011 and to date in 201 They had
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been developed and used for core refueling and performing inspections of fuel element It was noted that fuel inspections had been completed and that the inspection documents contained descriptions of fuel conditions as well as any discolorations and marking The inspector noted new fuel was received and stored in the appropriate storage containe The inspector also compared the location of fuel elements in the reactor core with the information maintained on the fuel status board in the control room, on the current RINSC fuel status map, and on the fuel movement sheet for the latest core, Core Number No problems or anomalies were note (2)
Beryllium Reflector Inspection
TS 4.9.a specifies that the beryllium reflectors shall be visually inspected and functionally fit into the core grid box on a rotating basis not to exceed 5 year The inspector reviewed documentation of the beryllium reflector inspections that were required to be completed by T It was noted that the inspections were typically completed in the past according to the schedule established in RINSC IP-01, Core Element Movement and Inspectio Although changes had been made to IP-01, the inspection schedule for the beryllium reflectors remained constan However, during the reactor fuel change and fuel inspection conducted in August 2012, the licensee found that the rotating schedule for inspection of the beryllium reflectors had not been followed correctl Specifically, in 2008 the appropriate beryllium reflectors were inspected, but in 2009 the inspections for beryllium reflectors B-1, B-10, and B-15 were skipped because licensee staff assumed that the inspection had already been complete On August 29, 2012, the licensee noted that the beryllium reflectors mentioned above had not been inspected since 2003, a period of time exceeding the requirements in TS 4. As a result of this finding, the licensee took immediate correctio On August 30, 2012, inspections of beryllium reflectors B-1, B-10, and B-15 were complete All were found to be suitable for continued us A new inspection schedule was created to include all upcoming inspection requirement In addition to the schedule rotation, the inspection requirements for the next 10 years were pre-planne The inspection schedule was relocated to the reactor data notebook and is now maintained separately from other procedures and attachment The inspector reviewed the corrective actions outlined by the licensee and verified that they had been completed as indicate Based on the results of this inspection, the inspector determined that this issue represented a Severity Level IV violation of NRC requirement However, as indicated above, the inspector determined that the violation had been identified and reviewed by the licensee and appropriate corrective actions had been completed promptl The licensee was informed that because this violation was non-repetitive, non-willful, licensee-identified, and promptly corrected, it would be treated as a non-cited violation (NCV), consistent with Section 2.3.2.b of the NRC Enforcement Policy (NCV 50-193/2012-202-03). This issue is considered close Conclusion
The licensee had made recent reactor fuel movements and had followed written procedures that met TS requirement One NCV was identified and is considered close.
Emergency Preparedness Inspection Scope (IP 69011)
The inspector reviewed the following documents and visited the support organizations discussed below to verify compliance with regulatory requirements and RINSC Emergency Plan (E-Plan), Rev. 3, revised in January 2011 with NRSC approval dated April 25, 2011:
- RINSC Emergency Procedure EP-01, Emergency Plan Implementing Procedures, Rev. 0, dated June 19, 2007, containing:
-
Attachment B, Form NSC-31, Emergency Communications Network
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Attachment E, Emergency Classification Matrix
Documentation of emergency communication tests conducted with various support agencies
Forms documenting the completion of annual emergency equipment inventories
Letter of agreement (LOA) between Narragansett Police Department (NPD) and RINSC, signed by Mr. M. J. Davis and by Chief Hoxie on December 14, 2011
LOA for Medical Services, from Dr. John B. Murphy, Vice President of Medical Affairs Rhode Island Hospital, to Dr. T. Tehan, RIAEC, dated January 31, 2012
LOA between Narragansett Fire Department (NFD) and RINSC, signed by Mr. M. J. Davis and Chief J. Cotter dated December 14, 2011 Observation and Findings
The inspector reviewed the E-Plan in use at the reactor and verified that it was reviewed biennially as require The inspector reviewed the RINSC E-Plan implementing procedures, as wel It was noted that the procedures were also
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reviewed annually and revised as needed to ensure effective implementation of the E-Pla Through record reviews and interviews with SROs and staff personnel (e.g.,
emergency responders), the inspector determined that they were knowledgeable of the proper actions to take in case of an emergenc Training for these individuals and the rest of the staff was accomplished annually through evacuation and emergency drill participatio Training for support organization personnel was provided whenever those organizations schedules would permi The inspector verified that the LOAs that had been established between the RINSC facility and NPD and NFD remained in effec The LOAs stipulated that the NPD and the NFD would be available during an emergency and would provide support for the facilit The inspector also verified that the LOA between the RINSC facility and the Rhode Island Hospital remained in effec That LOA indicated that the hospital would provide RINSC personnel with needed support in case of any event involving a medical emergenc Communications capabilities with support groups were acceptable and the various items of equipment (e.g., telephones and the building public address system) were in use dail Portable radios were also available for use as needed and were checked at least annuall Emergency call lists had been revised and updated as needed and were available in the control room and in the various areas around the facility as require The inspector also verified that emergency equipment, including decontamination material, was available and was being inventoried at least annually as required by the E-Pla The documentation of the training and drills conducted during the past 2 years was reviewe Through drill scenario and record reviews and personnel interviews, off-site emergency responders were determined to be knowledgeable of the proper actions to take in case of an emergenc Emergency and evacuation drills had been conducted annually as required by the E-Pla Drill scenarios and critiques had been written as wel The inspector visited NPD and NF Personnel at these departments were knowledgeable of the emergency preparedness requirements and took an active part in drill preparation and trainin The inspector also visited the licensees emergency support center (ESC). The inspector verified that the emergency supplies, instruments, and information were stored at the ESC as required by the pla The licensee maintained records indicating that the emergency supplies were inventoried annually as require Conclusion
The licensee maintained an effective emergency preparedness program through implementation of the written emergency plan and emergency implementing procedure.
Exit Interview
The inspection scope and results were summarized on October 4, 2012, with members of licensee management and staf The inspector described the areas inspected and discussed in detail the inspection observations and reiterated that the results of the inspection are subject to management revie 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 inspectio PARTIAL LIST OF PERSONS CONTACTED
Licensee
M. Damato
Health Physics Technician and Senior Reactor Operator M.J. Davis
Assistant Director, Rhode Island Nuclear Science Center S. Guarino Assistant Director for Radiation and Reactor Safety and Campus Radiation Safety Officer B. MacGregor Facility Engineer and Senior Reactor Operator S. Mecca
Chairman, Rhode Island Atomic Energy Commission Z. Richards
Reactor Supervisor/ Senior Reactor Operator T. Tehan
Director, Rhode Island Nuclear Science Center
INSPECTION PROCEDURES USED
IP 69003 Class 1 Research and Test Reactor Operator Licenses, Requalification, and Medical Examinations IP 69006 Class 1 Research and Test Reactors Organization and Operations and Maintenance Activities IP 69007 Class I Research and Test Reactor Review and Audit and Design Change Functions IP 69009 Class 1 Research and Test Reactors Fuel Movement IP 69010 Class 1 Research and Test Reactors Surveillance IP 69011 Class 1 Research and Test Reactors Emergency Preparedness
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
IR-50-193/2012-202-01 IFI Follow-up on the successful completion of the process of obtaining a Masters degree by the new Assistant Director for Radiation and Reactor Safet IR-50-193/2012-202-02 IFI Follow-up on the implementation of a facility modification procedure, to include the 10 CFR 50.59 review process, by the license IR-50-193/2012-202-03 NCV Failure to visually inspect and functionally fit the beryllium reflectors into the core grid box on a rotating basis not to exceed five year Closed
IR-50-193/2012-202-03 NCV Failure to visually inspect and functionally fit the beryllium reflectors into the core grid box on a rotating basis not to exceed five year LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Document Access Management System CP
Calibration Procedure E-Plan Emergency Plan ESC
Emergency Support Center IFI
Inspector Follow-up Item IP
Inspection Procedure LCO
Limiting Conditions for Operation LOA
Letter of Agreement MP
Maintenance Procedure NCV
Non-Cited Violation NRC
U. S. Nuclear Regulatory Commission NRSC Nuclear and Radiation Safety Committee NSC
Nuclear Science Center NFD
Narragansett Fire Department NPD
Narragansett Police Department OP
Operating Procedure Re Revision RIAEC Rhode Island Atomic Energy Commission RINSC Rhode Island Nuclear Science Center RSO
Radiation Safety Officer SNM Special Nuclear Material SOP
Standard Operating Procedure SRO
Senior Reactor Operator TP
Testing Procedure TS
Technical Specification