ML15084A006
| ML15084A006 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 08/28/2014 |
| From: | Hathaway C State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| To: | Boyle P G Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15084A006 (7) | |
Text
STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONSRhode Island Atomic Energy Commission16 Reactor RoadNarragansett, RI 02882-1165Telephone # 401-874w2600August 28, 2014Docket No. 50-193Mr. Patrick Boyle, Project ManagerResearch and Test Reactor Licensing BranchDivision of Policy and Rulemaking.U.S. Nuclear Regulatory Commission (NRC)Office of Nuclear Reactor Regulation.Washington, DC 20555
Dear Mr. Boyle:
.This letteir and the enclosures constitute the annual report required by the RINSC Technical Specifications(Section-6.8-4ý).:Enclosure.1 provides reactor operating statistics. Enclosure 2 provides informationef.rtfiiinig to inadvertent -reactor shutdowns or scrams. Enclosure 3 discusses maintenance operationsperformed during th6erelirtiig'period. Enclosure 4 describes changes to the facility carried out under theconditionsof Section'50.59 of Chapter 10 of the Code of Federal Regulations. Lastly, Enclosure 5iuminaiizes thie radiological controls information. If there are any questions regarding this information,please call me at.401-874-2600.Sincerely,Constance HathawayHealth PhysicistEnclosures (5)Copy to:Mr. Craig Bassett, USNRCDr. John J. Breen,' Chairman, NRSCDr. Clinton Chichester, Chairman, RIAEC .Dr..Nancy Breen, RIAECMr. Howard Chun, RIAEC.Dr. Bahram' Nassersharif, RIAECDr. Yana K. Reshetnyak, RIAEC7At~oA~L ENCLOSURE 1Technical SpecificationsSection 6.8.4.aMonth Year Operating Hours Energy (MWH) Energy.(MWD)July 2013 8.03 .__ 7.17 0.30August 2013 15.48 1 1.83 0.49September 2013 .7.50 7.97 0.33October 2013 _9.50 820 0.34November 2013 24.73 34.20 1.43December 2013 21.58 30.23 1.26January 2014 50.87 55.09 2.30February 2014 14.42 ..19.03 0.79March 2014 37.70 50.27 2.09April 20-14 46.68 66.30 .. ...... 2.76May 2014 -34,95 ..49.63 2.06June 2014 34.55 49.30 2.05TOTAL FY2014 305.99 389.22 16.02Total Energy Output since Initial Criticality: 64,708.32 MWhrs or 2696.18 MWdays.
ENCLOSURE 2EMERGENCY SHUTDOWNSAND SCRAMSThe following is a list of the unscheduled shutdowns and inadvertent scrams that occurred during the2013-2014 reporting period. This information is required by Technical Specification 6.8.4.bDate Run No. Logbook Page Cause Description9/05/13 8809 59 149 Instrumentation Period scramdue to badground onNeutron FluxMonitor12/12/13 8826 60 12 Operator Power modeswitch onO. 1MW vs.2MW01/07/14 8829 60 15 Operator Overpowerscram due tolowering range,inadvertently....__shifted 2 ranges01/24/14 8835 21 21 Operator Overpower due.to.loweringrange too__ quickly04/08/14 8858 60 45 Operator Overpower dueto loweringrange,inadvertentlyshifted 2 ranges04/30/14 8867 60 55 Instrumentation Overpowerscram on fluxmonitor signalnoise ENCLOSURE 3Technical Specification 6.8.4.c requires a listing of the major maintenance operations performed in the2013-2014 reporting period including their impact upon the safe operation of the reactor and the reasonsfor the corrective maintenance.In September of 2013, the primary cooling water pipe gaskets in the high power end of the reactor poolwere replaced with like material.. The old gaskets had deteriorated due to normal wear and tear,A major upgrade to the facility's security system began in April of 2014. This project is being sponsoredby the Global Threat Reduction Initiative, GTRI, and will completely replace the existing security system.The new system will continue to have the alarms for pool level, loss of power and fire systems troubleand will include a large increase in the capability of the system and the scope of the protected envelope.Noted improvements in the protection of reactor related equipment will be a steel tool box mounted onthe wall for fuel handling tool storage equipped with tamper detection and high security locks, and asimilar box for the overhead crane pendant with high security locks on both the pendant box and the craneelectrical power breaker handle. An independent remote monitoring system with cameras and radiationdetection at the reactor pool level will also be installed. The plan is for the new system to go live by theend of August. (Note: At issue of this report, the new system actually went live on July 30'b. A finalsummary will be included in the next annual report.)
ENCLOSURE 4FACILITY CHANGES -1OCFR50.59 REVIEWTechnical Specification 6.8.4.d requires that we provide a listing and description of any 10 CFR 50.59evaluations conducted during the 2013-2014 reporting period. There were no facility changes madeduring this period reqtuiring a 10 CFR 50.59 evaluation.The RINSC is continuing with efforts to upgrade and modernize thereactor control room. These changeswere previously evaluated and approved by the Nuclear and Radiation Safety Committee. The changesinclude new displays for reactor power level, core and experiment status, and area radiation levels. Otherchanges include adding annunciators, alarms, and additional test points.
ENCLOSURE 5RADIOLOGICAL CONTROLS1. Environmental Surveys outside the Facility- Technical Specification 6.8.4.eQuarterly TLD' badges are deployed outside the reactor building in three separate locations. Thegeneral public does not frequent these locations and therefore occupancy factors may be used toapproximate annual dose. The allowable external dose rates must be below 100 mrem per year.The quarterly doses in units of mrem are shown in the table below.LOCATION 3Y QTR 2012 4th QTR 2012 1! QTR 2013 2nd QTR 2013Northeast Wall 0 0 --- 16 .19Demineralizer 48 173 120 96DoorI Heat'Exchanger 17. 36 38 18DoorThese areas are in locations where access is limited. Consequently, the general public will notfrequent these areas, and appropriate occupancy factors can be used to approximate annual dose.Assuming that the maximum time that a member of the general public would be present in one ofthese locations is 10 minutes per day, an occupancy factor of 0.01 can be used to obtain theannual dose that would be received by a member of the general public, in any of these areas.The annual dose rate at the Northeast Wall, Demineralizer and Heat Exchanger Doors isdependent on the operations schedule of the reactor. Ignoring the fact that the dose rate is notpresent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, and applying the occupancy factor of 0.01, the annual dose that wouldbe receive by an individual in the demineralizer room would be 4.37 mrem. The dose received atthe Heat Exchanger Door would be .1.09 mrem. The annual dose received at the Northeast wallwould be 0.35 mrem. The variations from quarter to quarter and from previous reports were duein part to movements of items within the reactor building during the fiscal year and varying use ofthe different irradiation facilities.2. Annual Exposures Exceeding 500mreo -Technical Specification 6.8.4.fThere were no personnel exposures greater than 500 mrem.3. Radioactive Effluents -Technical Specification 6.8.4.gA. Individual gaseous effluent concentrations for each reactor operation are recorded on theMonthly Information Sheets (Form NSC-78). The concentration of radioactive materials. in theeffluent released from the facility exhaust stacks shall not exceed 1E+05 times concentrations'Thermoluminescent Dosimeter; Radiation Detection Co. reads the dosimeters at minimum of 10 mrem.
I -specified in I OCFR20, Appendix B, Table II, when averaged over time periods permitted by1OCFR20.2Gamma spectroscopy of stack gas samples has shown that the principal gaseous effluent isArgon-4 1. The maximum concentration for this principle contaminant permitted under TechnicalSpecifications is 1E-8 j4Ci/cc xlE5 1E-3 jiCi/ce. Concentrations released during the year wereless than 0.2 of that limit.The total Argon-41 release during the reporting period was 54.49 curies, The calculated effectivedose equivalent for their release is 1.2 mrem/year (COMPLY Code).B. Liquid effluent concentrations released to the sewer are documented on the Sewer DischargeRadioassay Report (NSC-09). Each release was approved prior to discharge with its ph being.within the acceptable range and with the sum of the fractions of the respective radioisotopesbeing below the discharge limit of 1. For the reporting period, the total volume of discharge was36,626,856 ml. The isotopes and their relative 'activities discharged are given below.Radioisotope Total Activity Discharged (microcuries)H3 6306.290C14 6711.861Pb214 34.453Na22 0.141Sb122 8.052Co60 0.179Cd109 3.6792 Technical Specifications, Section 3.7.2.