IR 05000193/2012201

IR 05000193-12-201 on April 9-12, 2012 at the Rhode Island Atomic Energy Commission, NRC Routine Inspection Report No. 50-193/2012-201

ML121160233
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	04/26/2012
From:	Johnny Eads Research and Test Reactors Branch B
To:	Tehan T State of RI, Atomic Energy Comm, Nuclear Science Ctr
Lichatz, Taylor NRR/DPR
References
IR-12-201
Download: ML121160233 (17)

Text

April 26, 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. 50-193/2012-201

The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on April 9 - 12, 2012, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2012-201). The inspection included a review of activities authorized for your facilit The enclosed report presents the results of that inspectio This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulation Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations of activities in progres Based on the results of this inspection, no safety concern or noncompliance of requirements was identifie No response to this letter is require In accordance with Title 10 of the Code of Federal Regulations Section 2.390 Inspections, exemptions, 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.htm Should you have any questions concerning this inspection, please contact Patrick Isaac at 301-415-1019 or electronic mail at Patrick.Isaac@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 N License N R-95

Enclosure: As stated cc w/ encl: See next page

Rhode Island Atomic Energy Commission

Docket No.: 50-193

cc:

Governor 222 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

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

April 26, 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. 50-193/2012-201

The U.S. Nuclear Regulatory Commission (NRC, the Commission) conducted an inspection on April 9 - 12, 2012, at the Rhode Island Nuclear Science Center Reactor facility (Inspection Report No. 50-193/2012-201). The inspection included a review of activities authorized for your facilit The enclosed report presents the results of that inspectio This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulation Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations of activities in progres Based on the results of this inspection, no safety concern or noncompliance of requirements was identifie No response to this letter is require In accordance with Title 10 of the Code of Federal Regulations Section 2.390 Inspections, exemptions, 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.htm Should you have any questions concerning this inspection, please contact Patrick Isaac at 301-415-1019 or electronic mail at Patrick.Isaac@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 N License N R-95

Enclosure: As stated

cc w/ encl: See next page DISTRIBUTION:

PUBLIC PROB/rf RidsNrrDprPrtb

TLichatz, NRR XYin, NRR MCompton (Ltr only O13-E19)

GLappert, NRR

ADAMS ACCESSION NO.: ML121160233 TEMPLATE #: NRC-002 OFFICE PROB:RI PROB:RI PROB:LA PROB:BC NAME TLichatz PISAAC GLappert JEads DATE 4/25/2012 4/25/2012 4/25/2012 4/26/2012 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

Docket No:

50-193

License No:

R-95

Report No:

50-193/2012-201

Licensee:

Rhode Island Atomic Energy Commission

Facility:

Rhode Island Nuclear Science Center Research Reactor

Location:

Narragansett, Rhode Island

Dates:

April 9-12, 2012

Inspector:

Patrick Isaac, Lead

Taylor Lichatz, Inspector Trainee

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. 50-193/2012-201

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 transportatio The licensees programs were acceptably directed toward the protection of public health and safety, and in compliance with U.S. Nuclear Regulatory Commission (NRC) requirement Organization and Operations and Maintenance Activities

• Organization and Operations and Maintenance Activities generally remain in compliance with the requirements specified in Technical Specification Review and Audit and Design Change Functions

• Within the scope of this review, the licensees review and design change program was generally found in conformance with Technical Specification and regulatory requirement Experiments

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

• Written procedures were being maintained in accordance with Technical Specification requirement 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 user Effluent and Environmental Monitoring

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

• The licensee shipment of radioactive material under the reactor license was generally compliant with NRC (Title 10 of the Code of Federal Regulations Parts 20 and 71) and Department of Transportation (DOT) (49 CFR Parts 171-178) regulation 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 surveillanc During the inspection, the reactor was operated to irradiate samples as part of its research missio.

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 #58, August 16, 2010 to December 2, 2011

Reactor logbook #59, December 6, 2001 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, 2010 to June 30, 2011, dated July 30, 2011

Form NSC-1, Pre-Start Check Sheet, dated March 22, 2011 Observations and Findings

The inspectors observed a reactor checkout, startup, approach to critical, escalation to full power, and a shutdow The Reactor Logbook entries were reviewed satisfactorily with key information documented during reactor operations including start-up and thru power operation The inspectors verified compliance with staffing requirements of Technical Specifications (TS) Sections 6.1.2 and 6.1.3 and that the 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 system Conclusion

Organization and Operations and Maintenance Activities remain in compliance with the requirements specified in T The reactor was being maintained per TS requirement Staffing was compliant with TS requirement.

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

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

• RINSC Nuclear and Radiation Safety Committee (NRSC) Full committee Meeting Minutes, dated April 25, 2011

RINSC NRSC Full committee Meeting Minutes, dated February 22, 2012

H. Bicehouse (RINSC) to W. Kennedy (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2010 to June 30, 2010], dated July 30, 2011

Review of 10 CFR 50.59 file, December 2007 through present 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 Audi Specifically, the inspector verified that the NRSC had reviewed the reactor instrumentation upgrad The following changes were reviewed: a digital power trend display, a ventilation system annunciator, a vital area alarm annunciator, a digital area radiation level display, and a digital core and experiment status displa The master switch is also to be replace None of the safety related equipment will be affecte Additionally, through interviews with licensee personnel, the inspectors determined that other various changes had been initiated and/or completed at the facility since the last NRC inspectio The inspectors reviewed the 10 CFR 50.59 review process used at the facilit It was noted that the reviews had been presented to the NRSC for review and approva It was also noted that none of the changes required NRC approval prior to implementatio However, as there remained to be no formal 10 CFR 50.59 review process developed since the previous inspection and only four questions were being asked instead of the required eight for 10 CFR 50.59 changes, the licensee was informed that this issue would be identified as an Inspector Follow-Up Item (IFI) by the NRC and will be reviewed during a future inspection (IFI 50-139/2012-201-01). Conclusion

Within the scope of this review, the licensees review and design change program was generally found in conformance with TS and regulatory requirement.

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

Experiment Procedure XP-10, Dry Irradiation Facility Irradiations, Rev. 0, approval dated November 2, 2011

Experiment Procedure XP-04, Incore Irradiations, Rev. 1, approval dated December 4, 2009

Experiment Procedure XP-12, Glory Tube Gamma Irradiations, Rev. 1, approval dated December 4, 2009

Experiment Procedure XP-02, Reactor Experiment Approval, Rev. 4, approval dated March 10, 2009

Experiment Procedure XP-01, Reactor Experiment Request, Rev. 1, approval dated September 29, 2008

Experiment Procedure XP-01 Attachment D, NSC (Nuclear Science Center) - Form 42, Reactor Experiment Request Form

Experiment Procedure XP-02 Attachment C, NSC - Form 47, Reactor Experiment Approval

RINSC NRSC Full committee Meeting Minutes, dated April 25, 2011

RINSC NRSC Full committee Meeting Minutes, dated February 22, 2012 Observations and Findings

The licensee had approved five new experiments in the last calendar yea Experiments were screened pursuant to 10 CFR 50.59 requirement Legacy experiments being done routinely had been subjected to the new review process to assure that safety considerations were known, documented, and properly applie The inspectors reviewed evidence that experiments were reviewed and approved by the NRSC and in accordance with TS requirement The inspectors specifically reviewed Experiment Procedure XP-10 Dry Irradiation Facility (DIF) Irradiations as part of the procedure deals with moving the core from the high power end of the pool to the low power en Corrective actions had been properly implemented since the previous inspection in which a gate was added to prevent inadvertent access to the DI Additionally, a strobe light warning system was added so that individuals in the area would be aware whenever the dose rate inside the DIF would reach 100 mR/hr or greater at the radiation window inside the facilit This experiment procedure was properly reviewed and approved by the NRS The inspectors observed reactor operations in support of a user performing an experiment involving the irradiation of numerous samples using the pneumatic transfer syste 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.. Conclusion

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

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 OP-2, RINSC Pre-Start Checkout, Rev. 15, approval dated April 25, 2011

Appendix OP-3, Reactor Power Changes, Rev. 4, approval 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 NRSC Full Committee Meeting Minutes, dated April 25, 2011

RINSC NRSC Full Committee Meeting Minutes, dated February 22, 2012 Observations and Findings

The inspectors observed that the licensee maintained written procedures covering the areas specified in TS Section 6.5, Operating Procedure A systematic approach was being used to update and reissue procedure Newly revised procedures and major changes were reviewed and approved by the NRSC in accordance with TS Section 6.4, Review and Audi The reviews and approvals were documented in the minutes of the NRSC meeting The inspector noted that no major changes had been made since the previous inspectio Conclusion

The licensee was maintaining and implementing written procedures in accordance with TS requirement.

Radiation Protection Inspection Scope (IP 69012)

The following documents were reviewed to determine compliance with 10 CFR Parts 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), February 7-12, 2012

Survey Program Summary Data for 2011, printed April 10, 2012

Survey Program Summary Data for 2012, printed April 10, 2012

NRC Form 3, Notice to Employees, dated August 2011

File of Dosimetry Reports, Quarterly reports for 2011 and 2012

RINSC Radiation Safety Office, Standard Operating Manual (SOP)

Manual

RINSC Radiation Safety Office, SOP 101, Radiation Safety Training, dated March 23, 2000

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

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) to present

Air Monitor Data Sheet file to present

RINSC Operating Procedures, Main Floor Area Monitor Channel Test, Procedure Appendix AB, Rev. 1, dated July 2, 2003 Observations and Findings

Radiation Protection Procedures at the facility met regulatory requirements and license commitment The inspectors verified Form NRC-3 Notice to Employees is posted as required and caution signs, labels and controls were posted as require The inspector reviewed weekly, monthly and quarterly surveys. It was noted that annual surveys were incorporated into quarterly surveys. Through the review of procedures and records, observations during facility tours, and discussion with staff personnel, the inspectors 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 progra During tours through the facility the inspectors verified that postings for radiation workers were in accordance with regulations and procedure 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 The inspectors toured the facility with licensee staff and observed workers wearing appropriate dosimetry throughout the facilit 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 worker No worker received any significant exposur Conclusion

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 user.

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 2011 and 2012 to date

H. Bicehouse (RINSC) to W. Kennedy (NRC), [Annual Report for the RINSC Pursuant to TS 6.8.4 for the period from July 1, 2011 to June 30, 2010], dated July 30, 2012 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 monitored. Survey points were re-designated to conform to new physical access characteristic 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 tube The gaseous release was significantly below the regulatory limi The licensee made one liquid release during the past year, a 50 gallon batch release discharged within permissible release limit The inspectors reviewed the data from an assumed small primary water lea Analysis over several years indicates the leak rate to be about eight gallons/da Leak collectors have been put in the locations where the leaks have typically occurre Sodium (Na-24) has not been detected in the water and the Tritium concentrations are an order of magnitude below the 10 CFR Part 20 release limits. The RINSC staff continues to monitor for leakage daily and the NRSC has defined the magnitude of the leak at which additional actions are neede However, through interviews with licensee personnel, it is believed that the loss of primary water is predominately due to evaporatio The licensee maintained OSLDs at five locations around the exterior of the facility and sent them to a commercial processor quarterly along with personnel dosimeter 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 Conclusion

The inspectors found environmental monitoring to conform to TS requirements and effluents to be in compliance with regulatory limit.

Transportation Inspection Scope (IP 86740)

The inspectors reviewed the following documents 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, February 7-12, 201 *

Radioactive Material (RAM) Shipping Notebook

Fuel Shipment #1, Babcock and Wilcox (B&W) dated September 27, 2010

Cask Shipment from RINSC to B&W dated October 4, 2010

- 8 - Observations and Findings

The last shipment was in September 201 The inspectors reviewed the RINSC Radiation Protection Audit for radioactive shipments made under the R-95 reactor licens Through interviews of staff personnel and observance of transportation records, the inspectors found that shipments were generally in accordance of approved procedure The inspectors noted to the licensee that two individuals had expired transportation training in case future shipments were to be mad Conclusion

The licensee shipments of radioactive material under the R-95 reactor license were generally in accordance with NRC and DOT requirement.

Follow-up on Previous Identified Item Inspection Scope (IP 92701)

The inspectors reviewed the licensees actions taken in response to a previously identified Inspector Follow-up Item (IFI) in NRC Inspection Report N /2011-202, dated October 6, 201 The inspectors also reviewed the licensees actions taken in response to a previously identified Non-Cited Violation (NCV) in NRC inspection Report N /2011-204, dated January 12, 201 Observations and Findings

IFI 50-139/2011-202-01 (Open) - Follow-up on the licensees actions to investigate and analyze the reactor building crack The inspectors observed that the licensee had formally investigated the cracks in the reactor building by hiring a contractor, AECO The letter from AECOM, dated March 14, 2012, and entitled Letter Report Assessing Concrete Cracks in Reactor Building Foundation Walls, covered the observations made and samples taken on the individual crack The AECOM concluded that the cracks dont appear to be structural (i.e. from overload or settlement), but caused from shrinkage from stresses such as creep and thermal stresse The main recommendation was to repair the roof, which had been completed prior to the April 2012 inspectio Therefore, this issue is considered a closed ite NCV 50-139/2011-204-01 (Open) - Follow-up on the licensees corrective actions to implement access control to High Radiation Areas commensurate with provisions of 10 CFR 20.1601(a).

The inspectors reviewed NRSC meeting minutes and procedures, toured the facility, and interviewed licensee managemen It was determined that the

- 9 -

licensee had sufficiently implemented their corrective actions which include staff retraining on high radiation controls and procedures, the development of a procedure for operations of the Dry Irradiation Facility (DIF) in which the NRSC would formally review and approve, and the addition of a remote alarm system for the DIF gat This issue is considered a closed ite Conclusion

One IFI identified during a previous inspection was reviewed during this inspection and is considered close One NCV identified during a previous special inspection was reviewed, discussed, and close.

Exit Interview

The inspection scope and results were summarized on April 12, 2012 with members of licensee management and staf The inspectors described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license 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 Senior Reactor Operator M.J. Davis

Assistant Director for Reactor Operations S. Guarino

Health Physics B. MacGregor Facility Engineer and Senior Reactor Operator Z. Richards Reactor Operator Trainee T. Tehan

Director, Rhode Island Nuclear Science Center

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

50-139/2012-201-01 IFI

Follow-up on the licensees actions to implement a

formal 10 CFR 50.59 review process

Closed

50-139/2011-202-01 IFI

Investigation and Analysis of Reactor Building

Cracks

50-139/2011-204-01 NCV

The licensee failed to implement access control to

High Radiation Areas commensurate with

Provisions of 10 CFR 20.1601(a)

- 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 B&W Babcock and Wilcox DOT

Department of Transportation 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