ML20196L735
| ML20196L735 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/13/2020 |
| From: | Martin P State of RI, Atomic Energy Comm |
| To: | Patrick Boyle Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML20196L735 (11) | |
Text
STATE OF RHODE ISLAND Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882-1165 Telephone # 401-874-2600 July 13, 2020 Docket No. 50-193 Document Control Desk U.S. Nuclear Regulatory Commission (NRC) 11555 Rockville Pike Rockville, Maryland 20852 Attn: Mr. Patrick Boyle, Project Manager
Dear Mr. Boyle:
This letter and the enclosures constitute the annual report required by the RINSC Technical Specifications (Section 6.7.1). Enclosure 1 provides reactor operating statistics. Enclosure 2 provides information pertaining to unscheduled 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 401-874-9442.
Sincerely, Paul W Martin Jr Reactor Supervisor Enclosures (5)
Copy to:
Mr. Michael Takacs , USNRC Dr. John J. Breen, Chairman, NRSC Dr. Clinton Chichester, Chairman, RIAEC Dr. Nancy Breen, RIAEC Mr. Howard Chun, RIAEC Dr. Yana K. Reshetnyak, RIAEC Dr. Nitin Padture, RIAEC
Enclosure 1 Reactor Operating Statistics Technical Specification Section 6.7.1.1 Operating MWH of Month Year Hours Operation July 2019 16.68 13.05 August 2019 17.53 8.32 September 2019 5.33 5.83 October 2019 10.18 9.45 November 2019 47.57 70.97 December 2019 24.82 19.63 January 2020 19.50 22.59 February 2020 29.32 24.32 March 2020 7.73 4.40 April 2020 21.07 18.80 May 2020 6.45 5.84 June 2020 44.73 65.58 268.78 MWH or Total FY2020 250.91 12.2 MWD Total Energy Output Since Initial Criticality 68,109.55 MWH or 2837.90 MWD
ENCLOSURE 2 UNSCHEDULED SHUTDOWNS OR SCRAMS Technical Specification Section 6.7.1.2 Page 1 of 1 The following is a list of the unscheduled shutdowns or scrams that occurred during the 2019-2020 reporting period:
Date Run Log Page Cause Description No. book 7/1/19 9551 65 43 WR ch 1 Range Momentary loss of range selector for WR selector channel 1 7/16/19 9554 65 46 Watchdog Scram Momentary circuit communication loss caused watchdog protection to activate 8/20/19 9561 65 53 WR ch 1 Range Momentary loss of range selector for WR selector channel 1 10/2419 9567 65 62 Short period Moved PuBe source too quickly causing scram Neutron Flux Monitor channel to see rapid change in flux/power 11/7/19 9572 65 67 Watchdog Scram Momentary circuit communication loss caused watchdog protection to activate 6/4/20 9619 65 123 Watchdog Scram Momentary circuit communication loss caused watchdog protection to activate
ENCLOSURE 3 MAINTENANCE OPERATIONS Technical Specification 6.7.1.3 requires a listing of the major maintenance operations performed in the 2018-2019 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance.
No major maintenance has been performed in this reporting period.
ENCLOSURE 4 FACILITY CHANGES - 10CFR50.59 REVIEW Technical Specification 6.7.1.4 requires that we provide a listing and description of any 10 CFR 50.59 evaluations conducted during the 2018-2019 reporting period.
No 10 CFR 50.59 evaluations were performed in this reporting period.
ENCLOSURE 5 RADIOLOGICAL CONTROLS
- 1. Environmental Surveys outside the Facility - Technical Specification 6.7.1.6 Quarterly TLD1 badges are deployed outside the reactor building in three separate locations. The quarterly doses in units of mrem are shown in the table below. The second quarter of year 2020 reports are not available yet due to the delay on completion of the vendors reports affected by the COVID-19 pandemic.
LOCATION 3rd QTR 4th QTR 1st QTR 2nd QTR 2019 2019 2020 2020 Northeast Wall 2 6 6 No data Demineralizer Door 11 37 25 No data Heat Exchanger 16 19 31 No data Door The general public does not frequent these locations and therefore occupancy factors may be used to approximate annual dose. The allowable annual external dose for whole body must be below 100 mrem per year. Assuming that the maximum time that a member of the general public would be present in one of these locations is 10 minutes per day, an occupancy factor of 0.025 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 annual dose at the Northeast Wall, 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 0.025 2, the annual dose that would be received by an individual in the demineralizer room would be 1.83 mrem. The dose received at the Heat Exchanger Door would be 1.65 mrem.
The annual dose received at the Northeast wall would be 0.35 mrem. The variations from quarter to quarter and from previous reports are also due in part to movements of items within the reactor building during the fiscal year and varying use of the different irradiation facilities.
- 2. Annual Exposures Exceeding 500 mrem for facility members, 100 mrem for non-staff members or 10 mrem for members of the general public - Technical Specification 6.7.1.7 1
Thermoluminescent Dosimeter; Mirion Technology reads the dosimeters at minimum of 1 mrem.
2 Occupancy factor of 0.025 was used, from NCRP 147 for Outdoors, unattended parking lots, attics, stairways, unattended elevators, janitors closets.
There were no personnel exposures greater than Technical Specification 6.7.1.7 requirements.
- 3. Radioactive Effluents - Technical Specification 6.7.1.5 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 10CFR20, Appendix B, Table 2, when averaged over time periods permitted by 10CFR20.3 Gamma spectroscopy of stack gas samples has shown that the principal gaseous effluent is Argon-41. The maximum concentration for this principle contaminant permitted under Technical Specifications is 1E-8 µCi/cc x1E+5 = 1E-3 µCi/cc.
Average concentrations released during the year were 4.62E-5 µCi/cc and 0.0462 of the limit.
The total Argon-41 release during the reporting period was 59.49 curies. The calculated effective dose equivalent for this release is 1.2 mrem/year (COMPLY Code). The Comply Code report is attached.
B. Liquid effluent concentrations released to the environment are documented on the Sewer Discharge 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 radioisotopes per month being below the discharge limit of 1. For the reporting period, the total volume of discharge was 1.1E7 ml. The isotopes and their relative activities discharged are given below.
Radioisotope Total Activity Discharged (microcuries)
H-3 4223.2 C-14 500 Sb-124 0.1812 I-124 0.3007 Pb-214 7.726 Bi-214 8.579 K-40 0.009562 Na-24 6.486 3
Technical Specifications, Section 3.7.2.1
2020 Ar41 Release COMPLY: V1.7. 7/10/2020 1:41 40 CFR Part 61 National Emission Standards for Hazardous Air Pollutants REPORT ON COMPLIANCE WITH THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS FROM THE COMPLY CODE V1.7.
Prepared by:
RI Atomic Energy Commission RI Nuclear Science Center 16 Reactor Road, Narragansett, RI 02882 Sangho Nam 4018742600 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460 Page 1
2020 Ar41 Release COMPLY: V1.7. 7/10/2020 1:41 2020 AR41 release
SCREENING LEVEL 4
DATA ENTERED:
Release Rate Nuclide (curies/YEAR)
AR41 5.949E+01 Release height 35 meters.
Building height 18 meters.
The source and receptor are not on the same building.
Building width 18 meters.
Building length 20 meters.
STACK DISTANCES, FILE: Stack data 100.dat Distance DIR (meters)
N 100.0 NNE 100.0 NE 100.0 ENE 100.0 E 100.0 ESE 100.0 SE 100.0 Page 2
2020 Ar41 Release SSE 100.0 S 100.0 SSW 100.0 SW 100.0 WSW 100.0 W 100.0 WNW 100.0 NW 100.0 NNW 100.0 COMPLY: V1.7. 7/10/2020 1:41 WINDROSE DATA, FILE: 2016 windrose data 2m.dat Source of wind rose data: 2016 Windrose data Dates of coverage: 19541994 Wind rose location: Narragansett, RI Distance to facility: 155 m Percent calm: 0.05 Wind Speed FROM Frequency (meters/s)
N 0.062 2.00 NNE 0.058 2.00 NE 0.044 2.00 ENE 0.013 2.00 E 0.012 2.00 ESE 0.013 2.00 SE 0.058 2.00 SSE 0.049 2.00 S 0.058 2.00 SSW 0.084 2.00 SW 0.105 2.00 WSW 0.064 2.00 W 0.068 2.00 WNW 0.095 2.00 NW 0.104 2.00 NNW 0.068 2.00 Distance from the SOURCE to the FARM producing VEGETABLES is 100 meters.
Distance from the SOURCE to the FARM producing Page 3
2020 Ar41 Release MILK is 100 meters.
Distance from the SOURCE to the FARM producing MEAT is 100 meters.
NOTES:
The receptor exposed to the highest concentration is located 100. meters from the source in the NE sector.
He gets his VEGETABLES from a farm located 100. meters from the source in the NE sector.
He gets his MEAT from a farm located 100. meters from the source in the NE sector.
He gets his MILK from a farm located 100. meters from the source in the NE sector.
Input parameters outside the "normal" range:
COMPLY: V1.7. 7/10/2020 1:41 Windrose wind frequency is unusually LOW.
RESULTS:
Effective dose equivalent: 1.2 mrem/yr.
- Comply at level 4.
This facility is in COMPLIANCE.
It may or may not be EXEMPT from reporting to the EPA.
You may contact your regional EPA office for more information.
- END OF COMPLIANCE REPORT **********
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