ML11234A032
| ML11234A032 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/28/2011 |
| From: | Guarino S State of RI, Atomic Energy Comm |
| To: | William Kennedy Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11234A032 (7) | |
Text
STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS OF RHODE ISLAND ATOMIC ENERGY COMMISSION Rhode Island Nuclear Science Center 16 Reactor Road Narragansett, RI 02882-1165 July 28,2011 Docket No. 50-193 Mr. William Kennedy, Project Manager Non-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects -III/VN U. S. Nuclear Regulatory Commission (NRC)Washington, DC 20555
Dear Mr. Kennedy:
This letter and enclosures constitute the annual report required by the RINSC Technical Specifications (Section 6.8.4). Enclosure 1 provides reactor operating statistics.
Enclosure 2 provides information pertaining to inadvertent reactor shutdowns or scrams. Enclosure 3 discusses maintenance operations performed during the reporting period. Enclosure 4 describes changes to the facility carried out under the conditions of Section 50.59 of Chapter 10 of the Code of Federal Regulations.
Lastly, Enclosure 5 summarizes the radiological controls information.
If there are any questions regarding this information, please call me at 401-789-9391.
Sincerely, Mtpn 1 Guarino Health Physicist Enclosures (5)Copy to: Mr. Jack Donohue, USNRC Region I Dr. John J. Breen, Chairman NRSC Dr. Stephen Mecca, Chairman RIAEC Dr. Anthony C. Nunes, RIAEC Dr. Peter Gromet, RIAEC Dr. Andrew Kadak, RIAEC Dr. Bahram Nassersharif, RIAEC uc)0 ENCLOSURE I Technical Specifications Section 6.8.4.a Total Energy Output since Initial Criticality:
63,880.5 MWH, 2661.68 MWD Month July August September October November December January February March April May June FY'11 Totals Year 2010 2010 2010 2010 2010 2010 2011 2011 2011 2011 2011 2011 Reactor Operating (Hours)23.78 29.55 20.83 19.08 27.4 20.32 25.78 19.6 29.07 42.98 71.68 66.8 396.87 Energy Generated (MWH)24.57 35.55 24.71 17.67 31.63 29.93 31.44 25.43 34.4 55.67 124.17 107.43 542.6 Energy Generated (MWDays)1.02 1.48 1.03 0.73 1.32 1.25 1.31 1.06 1.43 2.32 5.18 4.48 22.61 ENCLOSURE 2 EMERGENCY SHUTDOWNS AND SCRAMS The following is a listing of the emergency shutdowns and inadvertent scrams that occurred during the 2009-2010 reporting period. This information is required by Technical Specification 6.8.4.b.Date 7/1/10 7/2/10 7/13/10 7/23/10 8/3/10 8/11/10 8/12/10 8/30/10 8/31/10 10/26/10 11/4/10 11/8/10 11/10/10 11/21/10 11/22/10 11/23/10 12/3/10 12/14/10 12/16/10 1/4/11 1/7/11 1/10/11 1/28/11 2/2/11 2/10/11 3/15/11 3/29/11 4/5/11 4/15/11 4/19/11 4/27/11 4/28/11 4/28/11 6/1/11 6/16/11 Run No.8501 8502 8504 8508 8510 8513 8514 8520 8521 8536 8539 8540 8542 8546 8547 8548 8550 8552 8553 8556 8558 8559 8564 8566 8568 8577 8581 8584 8589 8590 8593 8595 8595 8609 8617 Logbook 57 57 57 57 57 57 57 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 58 Page 143 144 146 150 152 155 156 5 6 22 25 26 28 32 33 34 36 38 39 43 45 46 51 53 56 64 69 72 77 78 81 83 83 97 105 Description Loss of Power to Magnet Amps Scram for Tour Scram for Experiment Scram for Tour Scram for Tour Rods dropped for inspection Rods dropped for inspection Rods dropped for inspection Rods dropped for inspection Scram for Tour Equipment malfunction Scram for Tour Scram for Tour Scram for Tour Scram for Experiment Operator error -Wrong Power Range Rods dropped for inspection Scram for Tour Scram for Tour Equipment malfunction High Neutron Flux High Neutron Flux -Low Power Loss of Power to Magnet Amps High Neutron Flux -Low Power Loss of Power to Magnet Amps Loss of Power to Magnet Amps Loss of Power to Magnet Amps Loss of Power to Magnet Amps Scram for Tour Scram for Tour Scram for Experiment High Neutron Flux -Low Power Scram for Experiment Loss of AC Power Equipment malfunction Deliberate/Inadvertent Inadvertent Deliberate Deliberate Deliberate Deliberate Deliberate Deliberate Deliberate Deliberate Deliberate Inadvertent Deliberate Deliberate Deliberate Deliberate Inadvertent Deliberate Deliberate Deliberate Inadvertent Inadvertent Inadvertent Inadvertent Inadvertent Inadvertent Inadvertent Inadvertent Inadvertent Deliberate Deliberate Deliberate Inadvertent Deliberate Inadvertent Inadvertent Table includes planned scrams, ("deliberate"), and unplanned scams, ("inadvertent").
The Scrams involving "Loss of Power to Magnet Amps" during Run Numbers 8564, 8568, 8577 8581, and 8584 were attributed to an electrical fluctuation caused by Rabbit System #2. When the system timer completes the predetermined countdown it causes valves to open and close to change the direction of airflow in the pipes and return the sample to the Send/Receive station. These scrams coincided with the sudden change in airflow and the return of the samples. It was found that the sudden electrical fluctuation would cause the reactor magnet current amplifiers to trip, and thereby remove the current to the reactor safety system and cause a shutdown.
This problem was resolved with modifications to the recently upgraded Rabbit System Controls.
ENCLOSURE 3 Technical Specification 6.8.4.c requires a listing of the major maintenance operations performed in the 2010-2011 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance.
Secondary Cooling System #1 is in the process of being re-piped so the pipes will go through a cinderblock wall at the rear of the building rather than through an opening in the exterior doors. This will increase security in the Vital Area as well as allow use of the exterior doors by approved personnel.
The cooling tower will also be relocated approximately 10 feet for better positioning and drainage.Several facility doors have been replaced with heavy-duty fire-rated commercial doors. Some of these doors allow access to Vital Areas and have been equipped with security alarms in accordance with the Security Plan. These new doors provide better safety, security, and ease of use.The Rabbit System project that underwent a 10 CFR 50.59 evaluation in FY10 has been completed.
The blower that provides the air pressure for sample transport has been replaced with a larger capacity blower to accommodate the new system. Additional security measures have been added to protect the use of the system and the storage of radioactive material.The exterior window located adjacent to the Rabbit System has been upgraded to a high-security impact resistant window to increase security surrounding reactor related systems.
ENCLOSURE 4 FACILITY CHANGES -10CFR50.59 REVIEW Technical Specification 6.8.4.d requires that we provide a listing and description of any 10 CFR 50.59 evaluations conducted during the 2010-2011 reporting period.A malfunction in the test generator card of the facility neutron flux monitor has caused an error in one channel in the calibration check. This malfunction has also caused the "Non-Op" light to illuminate.
The equipment has been inspected and no required safety channels have been affected by the malfunction.
Procedures have been updated to reflect the changes while new equipment is being fabricated to replace the damaged components.
The secondary cooling system and confinement air handling instrumentation and controls were upgraded to contain a new digital interface.
The system allows for manual control through traditional push buttons or automatic control through a digital touch-screen display. Additional sensors were added to the systems to monitor various flow rates, temperatures, and pressures.
The system allows for better control of the system, more information for the operator, and replaces aging equipment.
ENCLOSURE 5 RADIOLOGICAL CONTROLS 1. Environmental Surveys outside the Facility -Technical Specification 6.8.4.e Quarterly OSL' badges are deployed outside the reactor building in three separate locations.
The general public does not frequent these locations and therefore occupancy factors may be used to approximate annual dose. The allowable external dose rates must be below 50 mrem per year. The quarterly doses in units of mrem are shown in the table below.LOCATION 3R QTR 2010 4TQTR 2010 1s 'QTR 2011 2ND QTR 2011Z Northeast Wall 16 19 2 M*Demineralizer 45 M M M Door Heat Exchanger 3 9 23 121 Door*M is below the minimum measurable dose of the badges. In this case, 1 mrem. For purposes of calculating annual dose M will be assumed to be 0.These areas are in locations where access is limited. Consequently, the general public will not frequent 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 of these locations is 15 minutes per day, an occupancy factor of 0.01 can be used to obtain the annual dose that would be received by a member of the general public, in any of these areas.The dose rate in the Northeast Wall area is due to storage of RAM, and is present regardless of reactor operation.
Applying the occupancy factor, the annual dose to an individual in this area would be 0.37 mrem over the course of last year. The annual dose rate at the Demineralizer and Heat Exchanger Doors is dependent on the operations schedule of the reactor. Ignoring the fact that the dose rate is not present 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 would be received by an individual at the Demineralizer Door would be 0.45 mrem. Likewise the dose received at the Heat Exchanger Door would be 1.56 mrem. The variations from quarter to quarter and from previous reports were due in part to movements of items within the reactor building during the fiscal year.2. Annual Exposures Exceeding 500 mrem -Technical Specification 6.8.4.f There were no personnel exposures greater than 500 mrem.3. Radioactive Effluents
-Technical Specification 6.8.4.g A. Individual gaseous effluent concentrations for each reactor operation are recorded on the Monthly Information Sheets (Form NSC-78). The concentration of radioactive materials in the effluent released from the facility exhaust stacks shall not exceed 1E+05 times concentrations specified in 1OCFR20, Appendix B, Table H, when averaged over time periods permitted by IOCFR20.3 Gamma spectroscopy of stack gas samples has shown that the principal gaseous effluent is Argon-41. The maximum concentration for this principal contaminant permitted under that Technical Specification is 1E-8 times I E5 or 1E-3 pCi/cc. Concentrations released during the year were less than 0.02 of that limit.The total Argon-41 release during the reporting period was 75.63 curies. The calculated effective dose equivalent for this release is 1.6 mrem/year (COMPLY Code).1 Optically Stimulated Luminescence 2 Landauer reads the OSL dosimeters to I mrem.3 Technical Specifications, Section 3.7.2.
ENCLOSURE 5 RADIOLOGICAL CONTROLS B. Liquid effluent concentrations released to the sewer are documented on the Sewer Disposal Record (Form NSC-52) and/or the Liquid Release Record (Form NSC-17). During the reporting period, one discharge was made to the sewer. On June 6, 2011, 50 gallons of water from the RINSC Retention Tank were discharged to the sewer. The discharge contained 5.020 JlCi of Tritium, 2.460 jiCi of Sodium-24, 0.189 gtCi of Antimony-122, 0.026 jiCi of Antimony-124, and 0.024 jiCi of Tellurium-132.
The concentrations discharged were, Tritium 2.65E-05 jiCi/ml, Sodium-24 1.3E-05 pgCi/ml, Antimony-122 1.OOE-06 gCi/mi,, Antimony-124 1.39E-07 liCi/ml, and Tellurium-132 1.27E-07 gCi/ml. Using the sum of the fractions rule, the discharge was 0.032 (3.2%) of the discharge limit.