ML071370234

IR 05000193-07-201, on 04/24-26/2007, Rhode Island Nuclear Science Center

ML071370234
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	05/22/2007
From:	Michael Case NRC/NRR/ADRA/DPR
To:	Tehan T State of RI, Atomic Energy Comm, Nuclear Science Ctr
Michael Case, NRR, 301-415-1004
References
IR-07-201
Download: ML071370234 (22)

See also: IR 05000193/2007201

Text

May 22, 2007Dr. T. Tehan, DirectorRhode Island Nuclear Science CenterRhode Island Atomic Energy Commission16 Reactor RoadNarragansett, RI 02882-1165SUBJECT: RHODE ISLAND NUCLEAR SCIENCE CENTER - NRC ROUTINE INSPECTIONREPORT NO. 50-193/2007-201Dear Dr. Tehan:

This letter refers to the inspection conducted on April 24-26, 2007, at the Rhode Island NuclearScience Center Research Reactor facility. The inspection included a review of activitiesauthorized for your facility. The enclosed report presents the results of this inspection.This inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions in your license.Within these areas, the inspection consisted of a selected examination of procedures andrepresentative records, observations of activities, and interviews with personnel.Based on the results of this inspection, the NRC has determined that a Severity Level IVviolation of NRC requirements occurred. The violation was evaluated in accordance with theNRC Enforcement Policy included on the NRC's Web site. The violation is cited in the enclosedNotice of Violation (Notice) and the circumstances surrounding it are described in detail in thesubject inspection report. The violation is of concern because it indicates a failure to followwritten operating procedures.You are required to respond to this letter and should follow the instructions specified in theenclosed Notice when preparing your response. The NRC will use your response, in part, todetermine whether further enforcement action is necessary to ensure compliance withregulatory requirements.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, itsenclosure(s), and your response, if you choose to provide one, will be made availableelectronically for public inspection in the NRC Public Document Room or from the NRC'sdocument system (ADAMS), accessible from the NRC Web site athttp://www.nrc.gov/readingrm/adams.html. To the extent possible, your response should notinclude any personal privacy, proprietary, or safeguards information so that it can be madeavailable to the Public without redaction.

T. Tehan-2-Should you have any questions concerning this inspection, please contact Mr. Kevin M. Witt at301-415-4075.Sincerely,/RA by Jennifer M. Golder for Michael Case/Michael J. Case, Division DirectorDivision of Policy and RulemakingOffice of Nuclear Reactor RegulationDocket No. 50-193License No. R-95Enclosures: 1. Notice of Violation2. NRC Inspection Report No. 50-193/2007-201cc w/encl.Please see next page

Rhode Island Atomic Energy CommissionDocket No. 50-193

cc:Governor Donald CarcieriState House Room 115Providence, RI 02903Dr. Stephen Mecca, ChairmanRhode Island Atomic Energy CommissionProvidence CollegeDepartment of Engineering-Physics SystemsRiver AvenueProvidence, RI 02859

Dr. Harry Knickle, Chairman Nuclear and Radiation Safety CommitteeUniversity of Rhode IslandCollege of Engineering112 Crawford HallKingston, RI 02881Dr. Andrew Kadak253 Rumstick RoadBarrington, RI 02806Dr. Bahram NassersharifDean of Engineering University of Rhode Island

102 Bliss HallKingston, RI 20881Dr. Peter GrometDepartment of Geological Sciences Brown UniversityProvidence, RI 02912Dr. Alfred L. Allen425 Laphan Farm RoadPascoag, RI 02859Mr. Jack Ferruolo, Supervising Radiological Health SpecialistOffice of Occupational and Radiological HealthRhode Island Department of Health3 Capitol Cannon, Room 206Providence, RI 02908-5097Test, Research, and TrainingReactor Newsletter University of Florida202 Nuclear Sciences CenterGainesville, FL 32611

T. Tehan-2-May 22, 2007Should you have any questions concerning this inspection, please contact Mr. Kevin M. Witt at

301-415-4075.Sincerely,/RA by Jennifer M. Golder for Michael Case/Michael J. Case, Division DirectorDivision of Policy and Rulemaking

Office of Nuclear Reactor RegulationDocket No. 50-193License No. R-95Enclosures: 1. Notice of Violation

2. NRC Inspection Report No. 50-193/2007-201cc w/encl.Please see next pageDISTRIBUTION

PUBLICPRT r/fRidsNrrDprPrtaRidsNrrDprPrtbRidsNrrDprRidsOeMailCenterRidsOgcMailCenterBDavis (cover letter only)(O5-A4)ACCESSION NO.: ML071370234TEMPLATE #: NRR-106OFFICEPRTBPRTB:LAPRTB:BCDPR:DDNAMEKWittEHyltonJEadsMCase

DATE05/17/2007 05/17/200705/21/2007 05 / 22 /2007OFFICIAL RECORD COPY

Enclosure 1NOTICE OF VIOLATIONRhode Island Atomic Energy CommissionDocket No. 50-193Rhode Island Nuclear Science CenterLicense No. R-95During an NRC inspection conducted on April 24-26, 2007, a violation of NRC requirementswas identified. In accordance with the NRC Enforcement Policy, the violation is listed below:Technical Specification 4.8 states, "Experiments shall be reviewed, approved, and properlyinstalled and operational in accordance with written operating procedures." Operating

Procedure 12, "Use of Pneumatic Irradiation Facilities," states, "The authorization is provided by

the Assistant Director before the irradiations begin when he signs the irradiation request form."Contrary to the above, on January 30, 2007, four experimental samples were irradiated in thereactor pneumatic irradiation experimental facility that were not reviewed and approved in

accordance with the written operating procedures.This is a Severity Level IV violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, the Rhode Island Atomic Energy Commission ishereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory

Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 and a copy to the

NRC Inspector of the facility that is the subject of this Notice, within 30 days of the date of the

letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a

"Reply to a Notice of Violation" and should include: (1) the reason for the violation, or, if

contested, the basis for disputing the violation or severity level, (2) the corrective steps that

have been taken and the results achieved, (3) the corrective steps that will be taken to avoid

further violations, and (4) the date when full compliance will be achieved. Your response may

reference or include previous docketed correspondence, if the correspondence adequately

addresses the required response. If an adequate reply is not received within the time specified

in this Notice, an order or a Demand for Information may be issued as to why the license should

not be modified, suspended, or revoked, or why such other action as may be proper should not

be taken. Where good cause is shown, consideration will be given to extending the response

time.If you contest this enforcement action, you should also provide a copy of your response, withthe basis for your denial, to the Director, Office of Enforcement, U.S. Nuclear Regulatory

Commission, Washington, DC 20555-0001.Your response will be made available electronically for public inspection in the NRC PublicDocument Room or from the NRC's document system (ADAMS), accessible from the NRC

Web site at http://www.nrc.gov/reading-rm/adams.html. Therefore, to the extent possible, itshould not include any personal privacy, proprietary, or safeguards information so that it can be

made available to the public without redaction. If personal privacy or proprietary information is

necessary to provide an acceptable response, then please provide a bracketed copy of your

response that identifies the information that should be protected and a redacted copy of your

-2-response that deletes such information. If you request withholding of such material, you mustspecifically identify the portions of your response that you seek to have withheld and provide in

detail the bases for your claim of withholding (e.g., explain why the disclosure of information will

create an unwarranted invasion of personal privacy or provide the information required by

10 CFR 2.390(b) to support a request for withholding confidential commercial or financial

information). If safeguards information is necessary to provide an acceptable response, please

provide the level of protection described in 10 CFR 73.21.In accordance with 10 CFR 19.11, you may be required to post this Notice within two workingdays.Dated this 22 of May 2007/RA by Jennifer M. Golder for Michael Case/Michael J. Case, Division DirectorDivision of Policy and Rulemaking

Office of Nuclear Reactor Regulation

Enclosure 2U. S. NUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONDocket No:50-193

License No:R-95

Report No:50-193/2007-201

Licensee:Rhode Island Atomic Energy Commission

Facility:Rhode Island Nuclear Science Center

Location:Narragansett, Rhode Island

Dates:April 24-26, 2007

Inspector:Kevin M. Witt

Approved by:Michael J. Case, Division DirectorDivision of Policy and Rulemaking

Office of Nuclear Reactor Regulation

EXECUTIVE SUMMARYRhode Island Atomic Energy CommissionRhode Island Nuclear Science Center ReactorInspection Report No. 50-193/2007-201The primary focus of this routine, announced inspection included onsite review of selectedaspects of the licensee's Class I research and test reactor safety programs including:

organizational and staffing, effluent and environmental monitoring, experiments, design

changes, committees, audits and reviews, procedures, radiation protection, and transportation

activities.The licensee's programs were acceptably directed toward the protection of public health andsafety, and in compliance with NRC requirements.Organization and Staffing

!The licensee's organization and staffing and assignment of responsibilities remained incompliance with the requirements specified in Technical Specification Section 6.Effluent and Environmental Monitoring

!Effluent monitoring satisfied license and regulatory requirements and releases werewithin the regulatory limits.Experiments

!The approval and control of experiments generally met Technical Specification andapplicable regulatory requirements. One violation was noted for failure to properly

review and approve experiment samples in accordance with written operating

procedures.Design Changes

!Based on the records reviewed, the inspector determined that the licensee's designchange program was being implemented as required.Committees, Audits, and Reviews

!The Nuclear and Radiation Safety Committee acceptably completed the review,oversight, and audit functions required by Technical Specification Section 6.4.Procedures

!The procedural review, revision, and implementation program satisfied TechnicalSpecification requirements.

-2-Radiation Protection

!Surveys were being completed and documented as required.

!Postings met regulatory requirements.

!Personnel dosimetry was being worn and recorded doses were within the NRC'sregulatory limits.

!Radiation monitoring equipment was being maintained and calibrated as required.

!The Radiation Protection Program satisfied regulatory requirements.

!The radiation protection training program was being administered as required.Transportation

!No radioactive material shipments had been made under the auspices of the reactorlicense within the past year.

REPORT DETAILSSummary of Plant StatusThe licensee's nuclear science center reactor, licensed to operate at a maximum steady-statethermal power of two megawatts (2 MW), continues to be operated in support of operator

training, surveillance, and utilization involving neutron activation analysis. During the inspection

the reactor was operated at two megawatts for an operator licensing examination. The reactor

was also operated on Tuesday and Thursday at full power to conduct sample irradiations.1.Organization and Staffinga.Inspection Scope (Inspection Procedure [IP] 69006)The inspector reviewed the following to verify compliance with the staffingrequirements in Technical Specification (TS) Sections 6.1, 6.2 and 6.3:*staff qualifications and management responsibilities*staffing requirements for the safe operation of the reactor

• selected portions of the operations logbooks for the past twelve months

• Rhode Island Nuclear Science Center (RINSC) organizational structure andstaffing*Rhode Island Atomic Energy Commission (RIAEC) meeting minutes, datedNovember 6, 2006 and April 5, 2007*RINSC Operating Procedures, Section 1, "General Considerations," originalversion - not revised to date*RINSC Annual Report for July 1, 2005 through June 30, 2006

• TS for the RINSC, Amendment No. 29, dated December 28, 2004b.Observations and FindingsThe organizational structure and functions of the RINSC had not functionally changedsince the last inspection (refer to NRC Inspection Report No. 50-193/2006-204). The

licensee's current operational organization and assignment of responsibilities, as

reported in the latest Annual Report, were consistent with those specified in the TS Sections 6.1, 6.2 and 6.3. All positions were filled with qualified personnel and a

review of the applicable records verified that staffing was as required by TS Section 6.1 and the licensee's procedures. There have been no changes in the staffing since

the last inspection. The inspector noted that the staffing at the facility was acceptable

to support the ongoing activities. During the inspection, the NRC conducted a

licensing examination for one Senior Reactor Operator and one Reactor Operator. A

separate report will be sent to the licensee and the candidates summarizing the results

of the examination.c.ConclusionsThe licensee's organization and staffing and assignment of responsibilities remainedin compliance with the requirements specified in TS Section 6.

-2-2.Effluent and Environmental Monitoringa.Inspection Scope (IP 69004)The inspector reviewed the following to verify compliance with the requirements of 10CFR Part 20 and TS Sections 3.7.2, 4.7, and 6.8.4:*the licensee's environmental monitoring program*counting and analysis records associated with airborne releases

• Completed Stack Monitor Air Particulate Detector Efficiency Check Forms, datedJuly 27 and October 13, 2006*Completed Stack Monitor Channel Test Forms, dated July 27 and October 13, 2006*Completed RINSC Forms NSC-13, "Stack Gas Monitor - Argon-41 CalibrationFactor Calculation Form," dated July 31 and October 17, 2006*Radioassay Report of RINSC Retention Tank Water Prior to Sewer Discharge,RINSC Form NSC-09, dated September 19, 2006*Completed RINSC Forms NSC-3d, "Weekly Gross Radioactivity Record forPrimary Water," dated from January 4, 2006 to present*Quarterly isotopic analyses of primary coolant water samples, dated fromJanuary 4, 2006 to present*Weekly isotopic analyses of secondary coolant water samples, dated fromJanuary 4, 2006 to present*Monthly environmental dosimetry records for January 1, 2006 to present

• Comply calculations for gaseous effluents for the period July 1, 2005 to June 30,2006, dated October 24, 2006*RINSC Radiation Safety Office SOP 201, "External Monitoring," Revision (Rev.)0, dated March 23, 2000*RINSC Annual Report for July 1, 2005 through June 30, 2006b.Observations and FindingsThe licensee ensures compliance with NRC regulations for environmental monitoringby ensuring that all doses at the site boundary are less than the dose limits specified

in 10 CFR 20.1301. Several Optically Stimulated Luminescence Dosimeter (OSLD)

badges are strategically placed in several locations around the perimeter of the

reactor bay and outside of the building. Records for 2006 indicate radiation exposures

that are below the applicable requirements. The licensee also monitored primary and

secondary coolant radioactivity levels on a weekly basis. No abnormal readings were

discovered. The inspector also reviewed the licensees records for disposal of liquid

radioactive waste. One disposal of 600 gallons of liquid waste was disposed of to the

sanitary sewer system. The inspector verified that the monitoring of the disposal was

conducted in accordance with the applicable requirements.To demonstrate compliance with the annual dose constraints of 10 CFR 20.1101(d),the licensee calculated the amount of Argon-41 produced by experiments and the

operation of the reactor through measurement of gaseous exhaust. The results

indicated that the releases were well within 10 CFR Part 20 Appendix B, Table 2

-3-concentrations, and TS limits. The highest dose calculated that could be received asa result of gaseous emissions from reactor operations was less than 2.0 millirem

(mrem) per year. These doses were well below the limit set in 10 CFR 20.1101(d) of10 mrem per year. The licensee has stated that the levels measured outside of the

facility are within the regulatory requirements.c.ConclusionsEffluent monitoring satisfied license and regulatory requirements and releases werewithin the regulatory limits.3.Experimentsa.Inspection Scope (IP 69005)The inspector reviewed selected aspects of the following in order to verify thatexperiments were being conducted consistent with TS Sections 3.1, 3.8 and 4.8:*potential hazards identification*experimental administrative controls and precautions

• RINSC Operations Log Books No. 54, dated from December 6, 2005 to present

• Nuclear and Radiation Safety Committee (NRSC) meeting minutes datedOctober 30 and December 14, 2006*NRSC Draft meeting minutes dated March 8, 2007

• NRSC Charter, Rev. 0, dated November 14, 2005

• RINSC Operating Procedures, Section 1, "General Considerations," originalversion - not revised to date*RINSC Operating Procedures, Section 8, "Operations at Power and Adjustmentsin Power Level," latest revision dated January 26, 1995*RINSC Operating Procedures, Section 12, "Use of Pneumatic IrradiationFacilities," original version, - not revised to date*RINSC Operating Procedures, Appendix P, "Incore Irradiations," Rev. 0, datedAugust 2, 2006*Form NSC-7a, "Neutron Irradiation Request Form - Short Irradiation," latestrevision dated September 1994*Form NSC-7b, "Pneumatic System Long Irradiation Request Form," latest revisiondated September 1994*Form NSC-8, "Gamma Irradiation Request Form," latest revision dated February

1994*Form NSC-11, "Shift Record Data Sheet," Rev. 2, dated March 28, 2003 -associated with RINSC Operating Procedures, Section 8*Form NSC-18, "RINSC Reactor Operations Data," Rev. 0, dated March 28, 2003 -associated with RINSC Operating Procedures, Section 8*Form NSC-70, "RINSC Irradiation Sample Tracking Summary Form," latestrevision dated September 1994*Completed Forms NSC-7a, "Neutron Irradiation Request Form [1-15 minuteirradiations]," Rev. 0, dated from December 5, 2006 to present

-4-*Completed Form NSC-73, "RINSC Facility Use Request Form - Proposal entitled,'Sterilization of Sediments with Gamma Irradiation'," dated June 15, 2006*RINSC Annual Report for July 1, 2005 through June 30, 2006b.Observations and FindingsOne of the experiments routinely conducted at the RINSC is the irradiation of variousmaterials for the purpose of neutron activation analysis. The most frequently used

experimental facilities are the pneumatic irradiation facility and the in-core devices.

Samples that have been irradiated at RINSC include materials such as biological

tissues, geological samples, and various other materials. The SRO and HP approves

all routine samples to be irradiated in accordance with the TS limitations for each

sample to be irradiated in the core. No new experiments had been initiated, reviewed,

or approved since the previous inspection at the facility. If any new experiments were

to be initiated, they would be reviewed and approved by the NRSC. The inspector

confirmed that most of the experiments conducted were in accordance with TS limits

and procedural requirements. The inspector also verified that all of the experiment

authorizations were reviewed on an annual basis.While conducting a review of the experiment sample irradiations conducted using thepneumatic irradiation facility, the inspector noted that the review and approval forms

for several experiment samples could not be located. The licensee's procedure for

reviewing and approving experiment samples is documented on form NSC-7a. The

purpose of this particular experiment was to provide a proof of principle. These

irradiations were conducted under the experiment authorization for general

irradiations. A total of four samples of geological material were irradiated in the

reactor on January 30, 2007, at a power level of 2 MW. The licensee noted that the

TS requirements for experiment conditions were met although the inspector could not

find any record indicating that a review and approval was completed before the

samples were irradiated. Some mitigating factors in the safety significance of this

issue include the mass of materials was much lower than what would normally be

used in an experimental sample, and this event was an isolated incident of which the

inspector did not note any other similar instances during this inspection.TS 4.8 states, "Experiments shall be reviewed, approved, and properly installed andoperational in accordance with written operating procedures." RINSC Operating

Procedure 12 §12.1 states, "The authorization is provided by the Assistant Director

before the irradiations begin when he signs the irradiation request form." Contrary to

this requirement, the licensee irradiated four experiment samples without properly

completing the record of experiment review and approval in accordance with the

written operating procedure. The inspector communicated to the licensee the

importance of following the established procedures for review and approval of an

experiment. The licensee was informed that failure to review and approve

experiments in accordance with written operating procedures was an apparent

violation (VIO) of TS 4.8 (VIO 50-193/2007-201-01).The inspector observed the licensee conduct operations for an experiment utilizing thepneumatic irradiation facility on April 24, 2007. All of the procedures required for

loading and extracting the samples were strictly followed and the personnel

-5-conducting the operation did so in a safe and knowledgeable manner. The inspectorverified that all of the checks conducted were in compliance with TS required values

and parameters.c.ConclusionsThe approval and control of experiments generally met TS and applicable regulatoryrequirements. One violation was noted for failure to properly review and approve

experiment samples in accordance with written operating procedures.4.Design Changes a.Inspection Scope (IP 69007)In order to verify that any modifications to the facility were consistent with10 CFR 50.59, the inspector reviewed selected aspects of:*facility configuration documents*proposed facility design changes for the past two years

• NRSC meeting minutes dated October 30 and December 14, 2006

• NRSC Draft meeting minutes dated March 8, 2007

• safety reviews and audits conducted by the committees and noted in therespective committee and subcommittee meetings minutes*NRSC Charter, Rev. 0, dated November 14, 2005

• RINSC Operating Procedures, Section 1, "General Considerations," originalversion - not revised to date*RINSC Annual Report for July 1, 2005 through June 30, 2006b.Observations and FindingsThrough review of applicable records and interviews with licensee personnel, theinspector determined that no significant changes requiring prior NRC approval had

been completed at the facility since the last inspection. The inspector verified that

administrative controls were in place that required the appropriate review and approval

of all changes prior to implementation. The Assistant Director for Reactor Operations

and the Reactor Supervisor normally determine whether change authorizations need

to be reviewed by the NRSC based on the complexity of the project and the relation to

the safety of the reactor. Letters describing facility changes are completed to inform

operations personnel of operating information and to document RINSC activities which

are not recorded in the operating log book. The inspector noted that 10 CFR 50.59

reviews and approvals conducted by the NRSC were focused on safety and met the

applicable TS and procedural requirements.c.Conclusions

Based on the records reviewed, the inspector determined that the licensee's designchange program was being implemented as required.

-6-5.Committees, Audits, and Reviewsa.Inspection Scope (IP 69007)In order to verify that the licensee had established and conducted reviews and auditsas required in TS Section 6.4 the inspector reviewed selected aspects of:*Radiation Safety Records Review Form*NRSC meeting minutes dated October 30 and December 14, 2006

• NRSC draft meeting minutes dated March 8, 2007

• safety reviews and audits conducted by the committees and noted in therespective committee and subcommittee meetings minutes*NRSC Charter, Rev. 0, dated November 14, 2005

• RINSC Operating Procedures, Section 1, "General Considerations," originalversion - not revised to date*RINSC Annual Report for July 1, 2005 through June 30, 2006b.Observations and FindingsThe licensee has established the NRSC to review operations to assure that the facilityis operated in a manner consistent with public safety and within the terms of the facility

license as required by TS 6.4.1. A charter is established in licensee procedures forthe NRSC and the inspector verified that the NRSC is following all aspects of the

charter. The NRSC had meetings more frequently than required and a quorum was

always present as required. Review of the minutes indicated the NRSC provided

guidance, direction and oversight, and ensured suitable use of the reactor. The

minutes provided an acceptable record of appropriate review functions and safety

oversight of reactor operations.The inspector noted that the NRSC charter had been revised to change the votingeligibility of several committee members. The change removed the voting privileges

from all of the RINSC staff on the NRSC, including the Director, Assistant Director,

and Radiation Safety Officer. TS 6.4.4 states, "A quorum of the NRSC shall consist of

not less than four (4) members and shall include the Radiation Safety Officer or

designee, the Director or the Assistant Director for Operations and the Chairman or

designee." The inspector noted that if all of the RINSC staff members did not have

voting privileges, it is possible for the chairman or designee to be the only voting

member during a committee meeting. ANSI/ANS-15.1-1990, "The Development of

Technical Specifications for Research Reactors," states, "there shall be a minimum of

three persons for review." The inspector communicated to the licensee the need for a

reliable and effective oversight committee with at least three voting members. The

licensee committed to fix the NRSC written charter before the next inspection to

require three NRSC voting members to be present for a NRSC meeting quorum. This

issue will be considered by the NRC as an Inspection Follow-up Item (IFI) and will be

reviewed during the next inspection at the facility (IFI 50-193/2007-201-02).Audits required by TS Sections 6.2.4 and 6.2.5 were performed by NRSC membersand met the applicable requirements. The audits appeared to be acceptable. The

-7-inspector noted that the safety reviews and audits, and the associated findings, wereacceptably detailed and that the RINSC staff were supportive of the audits. During

review of the audits, the inspector noted that the licensee immediately corrected any

minor issues. The audits did not identify any issues related to the safe operation of

the RINSC.c.Conclusions

The NRSC acceptably completed the review, oversight, and audit functions requiredby TS Section 6.4.6.Proceduresa.Inspection Scope (IP 69008)To verify that facility procedures were being reviewed, revised, and implemented asrequired by TS Section 6.5, the inspector reviewed selected aspects of:*NRSC meeting minutes dated October 30 and December 14, 2006*NRSC draft meeting minutes dated March 8, 2007

• NRSC Charter, Rev. 0, dated November 14, 2005

• RINSC Operating Procedures, Section 1, "General Considerations," originalversion - not revised to date*RINSC Operating Procedures, Appendix Y, "Facility Access for Visitors," latestrevision dated August 2, 2006*RINSC Radiation Safety Office SOP 100, "Standard Operating Procedures," Rev.0, dated March 23, 2000*RINSC Annual Report for July 1, 2005 through June 30, 2006b.Observations and FindingsProcedures had been formulated for the safe, routine operation of the reactor. Records showed that procedures for potential malfunctions (e.g., radioactive releases

and contaminations, and abnormal events) had also been developed and were

available to be implemented as required. The inspector noted that procedural

changes were being reviewed and approved by the NRSC as required by TS.

Training of personnel on procedures and changes was acceptable. Through

observation of various activities at the facility, including reactor operation and sample

handling, the inspector determined that licensee personnel conducted activities in

accordance with applicable procedures. The inspector observed the completion of a

reactor start-up, routine operation, and shut-down. It was noted that the required

checks, verifications, and actions were completed in accordance with the applicable

procedure.c.ConclusionsThe procedural review, revision, and implementation program satisfied TSrequirements.

-8-7.Radiation Protection Programa.Inspection Scope (IP 69012)The inspector reviewed the following to verify compliance with 10 CFR Parts 19 and20, and the requirements outlined in TS Table 3.2 and Sections 3.7, 4.2, and 4.7:*radiological signs and posting in various areas of the facility*facility and equipment during tours

• organization and staffing

• radiation protection training records

• instrument calibration records

• RINSC Radiation Safety Office SOP 101, "Radiation Safety Training," Rev. 0,dated March 23, 2000*RINSC Radiation Safety Office SOP 110, "Radiation Protection Audits," Rev. 0,dated March 23, 2000*RINSC Radiation Safety Office SOP 201, "External Monitoring," Rev. 0, datedMarch 23, 2000*RINSC Radiation Safety Office SOP 202, "Bioassay," Rev. 0, dated March 23, 2000*RINSC Radiation Safety Office SOP 203, "Determining TEDE and TODE," Rev.0, dated March 23, 2000*RINSC Radiation Safety Office SOP 204, "Skin Exposures," Rev. 1, datedApril 29, 2002*RINSC Radiation Safety Office SOP 220, "Pocket Dosimeter Calibration," Rev. 0,dated March 28, 2003*RINSC Radiation Safety Office SOP 300, "Routine Surveys," Rev. 1, datedFebruary 10, 2004*RINSC Radiation Safety Office SOP 801, "Instrument Calibration," Rev. 0, datedNovember 6, 2000*RINSC Radiation Safety Office SOP 802, "Pocket Dosimeter Calibration," Rev. 0,dated November 6, 2000*facility weekly, monthly, quarterly, and other periodic contamination and arearadiation surveys from 2006 to present*Quarterly dosimetry records for staff and researchers for January 1, 2006 topresent*Survey Program Summary Data for January 1, 2006 to present

• RINSC Visitor Dosimetry Logbook

• calibration records for the Area Radiation Monitors, the Continuous Air Monitor(CAM), and the Water Monitor from 2004 to present*RINSC Survey Instrument Calibration Reports, dated from January 1, 2006 topresent*Completed RINSC Forms NSC-12, "Reactor Main Floor Particulate Air MonitorPanel Meter Channel Test," dated July 28 and October 17, 2006*Completed Main Floor Air Particulate Monitor Detector Calibration Forms, datedJuly 27 and October 17, 2006*RINSC Radiation Protection Special Audit, dated January 29-31, 2007

• Rhode Island Nuclear Science Center Radiation Safety Guide (RSG), Rev. 0

-9-b.Observations and Findings(1)SurveysThe inspector reviewed weekly radiation and contamination surveys of the reactorbuilding, which were conducted by radiation safety personnel. The results were

documented on the appropriate forms, evaluated as required, and corrective

actions taken when readings or results exceeded set action levels. The number

and location of survey points was adequate to characterize the radiological

conditions. Surveys by the radiation safety personnel were conducted in

accordance with the appropriate procedure and logged on the appropriate forms.

The licensee has a tracking program for ensuring the surveys are completed in

the appropriate time frame. The inspector verified that the Radiation Safety

Officer (RSO) reviews all of the survey records. No abnormal readings were

discovered.(2)Postings and NoticesThe inspector reviewed the postings required by 10 CFR Part 19 at the entrancesto various controlled areas including the Reactor Bay, and radioactive material

storage areas. The postings were acceptable and indicated the radiation and

contamination hazards present. The facility's radioactive material storage areas

were found to be properly posted. No unmarked radioactive material was found

in the facility.(3)DosimetryThe licensee used a National Voluntary Laboratory Accreditation Program-accredited vendor to process personnel dosimetry. Through direct observation,

the inspector determined that dosimetry was used in an acceptable manner by

facility personnel. For visitors to the facility, a direct read pocket dosimeter is

issued to individuals for general tours. Records indicate that no abnormalreadings were obtained.An examination of the records for the inspection period showed that all exposureswere well within NRC limits and within licensee action levels. All of the staff and

researchers associated with the facility wear OSLD badges and minimal doses

were recorded for 2006 through present. The licensee investigates any dosimetry

readings that indicate a monthly exposure above typical levels for a reactor staff

member. The as low as reasonably achievable (ALARA) goal specified in the

RSG is to keep deep dose exposures to less than 500 mrem per year and the

licensee consistently meets this goal.(4)Radiation Monitoring EquipmentThe calibration of portable survey meters and friskers was completed by radiationsafety personnel at the calibration lab while fixed radiation detectors, the CAM

and stack monitor were calibrated at the detector location. The calibration

records of portable survey meters, friskers, fixed radiation detectors, and air

-10-monitoring equipment in use at the facility were reviewed. Calibration frequencymet the requirements established in the applicable procedures while records were

being maintained as required. These systems had been calibrated semi-annually

as required by procedure. The daily set point verifications for the monitoring

equipment were completed as required. CAM filters were changed and analyzed

monthly as required. No activity above the lower limit of detection was detected

on the air filters. The inspector reviewed the licensee's tracking system for

ensuring the instrument calibrations are completed on time and found it to be

useful.During the inspection, the inspector visited the calibration range located in thebasement of the laboratory building. The radiation safety personnel described the

equipment in the facility for the inspector. The calibration records reviewed were

thorough and were completed using the appropriate techniques and according to

procedure. The inspector observed that proper precautions are always used to

maintain doses ALARA.(5)Radiation Protection ProgramThe licensee's RSG provides the licensee's policy on the safe use of radioactivematerials around the reactor facility. The ALARA program provides guidance for

keeping doses as low as reasonably achievable and is consistent with the

guidance in 10 CFR Part 20. The inspector verified that the radiation protection

program was being reviewed annually as required by 10 CFR 20.1101(c). No

safety related issues were identified in the review of the program. The NRSC

reviews radiation protection documents during the NRSC meetings, and the RSO

has provided an additional audit of the overall implementation of the Radiation

Protection Program.The RSG requires that all personnel who work with radioactive materials receivetraining in radiation protection, policies, procedures, requirements, at the facilities

prior to having unescorted access at the facility. The radiation safety personnel is

responsible for conducting the training and all of the training is typically conducted

with the RSO. A test is administered at the end of the training to verify that the

individuals understood the material presented. The training covered the topicsrequired to be taught in 10 CFR Part 19 and the review of training materials and

tests indicated that the staff was instructed on the appropriate subjects.(6)Facility TourThe inspector toured the reactor facility, the radiation detector calibration roomand accompanying facilities. Control of radioactive material and control of access

to radiation and high radiation areas were observed to be acceptable. The

postings and signs for these areas were appropriate. Licensee personnel

followed the indicated precautions for access to controlled areas.

-11-c.ConclusionsThe inspector determined that: (1) surveys were being completed and documented asrequired, (2) postings met regulatory requirements (3) personnel dosimetry was being

worn and recorded doses were within the NRC's regulatory limits, (4) radiation

monitoring equipment was being maintained and calibrated as required, (5) the

radiation protection program satisfied regulatory requirements, and 6) the radiation

protection training program was being administered as required.8.Transportation Activitiesa.Inspection Scope (IP 86740)To verify compliance with regulatory and procedural requirements for transferring orshipping licensed radioactive material, the inspector reviewed the following:selected records of various types of radioactive material shipmentsRINSC Radiation Safety Office SOP 501, "Radioactive Waste Packaging," Rev. 0,dated November 6, 2000RINSC Radiation Safety Office SOP 512, "BioPAL Wastes," Rev. 1, datedMarch 26, 2004b.Observations and FindingsThrough records review and discussions with licensee personnel, the inspectordetermined that the licensee had not shipped any radioactive material since the

previous inspection in this area.c.ConclusionsNo radioactive material shipments had been made under the auspices of the reactorlicense during the past year.9.Exit InterviewThe inspector presented the inspection results to licensee management at theconclusion of the inspection on April 26, 2007. The inspector described the areas

inspected and discussed in detail the inspection observations. No dissenting

comments were received from the licensee. The licensee acknowledged the findings

presented and did not identify as proprietary any of the material provided to or

reviewed by the inspector during the inspection.

PARTIAL LIST OF PERSONS CONTACTEDLicensee PersonnelH. Bicehouse, Radiation Safety Officer and Assistant Director for Reactor SafetyJ. Davis, Reactor Supervisor

M. Damato, Health Physics Technician and Reactor Operator Trainee

D. Johnson, Health Physicist

B. MacGregor, Reactor Operator and Facility Engineer

M. Middleton, Assistant Director for Reactor Operations

T. Tehan, Director, Rhode Island Nuclear Science CenterINSPECTION PROCEDURES USEDIP 69004Class 1 Research and Test Reactor Effluent and Environmental MonitoringIP 69005Class 1 Research and Test Reactor Experiments

IP 69006Class 1 Research and Test Reactors Organization, Operations, and MaintenanceActivitiesIP 69007Class 1 Research and Test Reactor Review and Audit and Design ChangeFunctionsIP 69008Class 1 Research and Test Reactor Procedures

IP 69012Class 1 Research and Test Reactors Radiation Protection

IP 86740Transportation ActivitiesITEMS OPENED, CLOSED, AND DISCUSSEDOpened50-193/2007-201-01VIOFailure to review and approve experiments in accordance withwritten operating procedures 50-193/2007-201-02IFIFollow-up to verify the licensee changes the NRSC writtencharter to require three outside voting members to be present

for a NRSC meeting quorum

Closed NoneLIST OF ACRONYMS USEDADAMSAgencywide Documents Access and Management System ALARAAs Low As Reasonably Achievable

CAMContinuous Air Monitor

CFRCode of Federal Regulations

IFIInspection Follow-up Item

IPInspection Procedure

mremmillirem

MWMegawatt

NRCNuclear Regulatory Commission

NRSCNuclear and Radiation Safety Committee

-2-Rev.RevisionRIAECRhode Island Atomic Energy Commission

RINSCRhode Island Nuclear Science Center

RSGRadiation Safety Guide

RSORadiation Safety Officer

TS Technical Specifications

VIOViolation