ML22208A130
| ML22208A130 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/27/2022 |
| From: | Goodwin C State of RI, Atomic Energy Comm |
| To: | Patrick Boyle Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML22208A130 (11) | |
Text
STATE OF RHODE ISLAND Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882-1165 Telephone# 401-874-2600 July 27, 2022 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 401-874-9437.
Sincerely, Dr. Cameron Goodwin Director, RINSC Enclosures (5)
Copy to:
Mr. Craig Bassett, 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
Enclosure 1 Reactor Operating Statistics Technical Specification Section 6.7.1.1 Operating MWH of Month Year Hours Operation July 2021 19.83 22.39 August 2021 21.38 21.09 September 2021 30.62 42.47 October 2021 26.87 22.94 November 2021 25.15 19.95 I I I December 2021 36.95 47.79 January 2022 28.03 27.66 I February 2022 41.18 41.05 I March 2022 80.70 89.17 April 2022 43.98 16.36 May 2022 42.83 49.68 June 2022 41.92 47.17 447.72 MWH or Total FY2022 439.44 18.66 MWD Total Energy Output Since Initial Criticality 68,751.40 MWH or 2864.64 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 2021-2022 reporting period:
Log book 67 Run# 9789 - Blade#4 dropped during approach to criticality Run# 9791 - Scram due to instrument noise Run# 9794 - Scram due to instrument noise Run# 9800 - Scram due to short period/ instrument noise Log Book 66 Run# 9690 - >1OOKW scram via power selector switch contacts.
Run# 9696 - Scram due to loss of A/C Power. Second scram due to incorrect range selected. Operator error Run# 9700 - Scram due to instrument noise.
Run# 9707 - Reactor scram due to incorrect range selected. Operator error.
Run# 9713 - Scram due to improper centering of magnet.
Run# 9729 - Scram due to instrument noise, Second scram due to instrument trouble.
Run# 9736 - Scram due to operator error, manual rundown initiated.
Run# 9752 - Scram due to operator error, manual rundown initiated.
Run# 9754 - Scram due to spurious short period.
Run# 9757 - Scram due to short period runback.
Run# 9778 - Scram due to spurious noise signal. Second scram due to signal noise.
Run# 9780 - Scram due to signal noise, no indications.
Run# 9782 - Scram due to power interruption.
Run# 9783 - Scram due to instrument noise.
Run# 9785 - Scram due to improper magnet centering on Blade#3.
ENCLOSURE 3 MAINTENANCE OPERATIONS Technical Specification 6.7.1.3 requires a listing of the major maintenance operations performed in the 2021-2022 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance.
No major maintenance items conducted.
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 2021-2022 reporting period.
No 10 CFR 50.59 evaluation was performed in this reporting period.
ENCLOSURE 5 RADIOLOGICAL CONTROLS
- 1. Environmental Surveys outside the Facility - Technical Specification 6.7.1.6 Quarterly TLD 1 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 2022 reports are not available yet due to the vendor's reports delay affected by COVID-19.
2 nd QTR 3 rd QTR 4th QTR 1 st QTR 2nd QTR LOCATION 2021 2021 2021 2022 2022 Northeast Wall 6 9 42 11 No data Demineralizer Door 21 29 83 64 No data Heat ExchanQer Door 52 23 55 74 No data 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 0.0252, the annual dose that would be receive by an individual in the demineralizer room would be 4.925 mrem. The dose received at the Heat Exchanger Door would be 5.1 mrem. The annual dose received at the Northeast wall would be 1.7 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 Two facility member exposures were greater than 500 mrems of extremity shallow dose due to handling of experiment samples.
1Thermoluminescent Dosimeter; Mirian 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, janitor's closets.
- 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 1 E+05 times concentrations specified in 10CFR20, Appendix 8, 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 3.20E-5 µCi/cc and 0.032 of the limit.
The total Argon-41 release during the reporting period was 77.74 curies. The calculated effective dose equivalent for this release is 1.6 mrem/year (COMPLY Code). The Comply Code report is attached.
- 8. Liquid effluent concentrations released to the environment are documented on the Sewer Discharge Report (NSC-52). 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 1.077E7 ml. The isotopes and their relative activities discharged are given below.
Radioisotope Total Activity Discharged (microcuries)
H-3 11512.03 C-14 184.26 Mn-54 40.43 Sb-124 0.81 1-124 1.35 Pb-214 50.41 8i-214 73.76 K-40 7.25 3
Technical Specifications, Section 3.7.2.1
COMPLY: Vl.7. 7/18/2022 8:06 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 - Vl.7.
Prepared by:
RI Atomic Energy Commission RI Nuclear Science Center 16 Reactor Road, Narragansett, RI 02882 Sangho Nam 401-874-9439 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington, DC 20460
COMPLY: Vl.7. 7/18/2022 8:06 2022 Ar-41 Release SCREENING LEVEL 4 DATA ENTERED:
Release Rate Nuclide (curies/YEAR)
AR-41 7.774E+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 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: Vl.7. 7/18/2022 8:06 WINDROSE DATA, FILE: 2016 windrose data 2m.dat Source of wind rose data: 2016 Windrose data Dates of coverage: 1954-1994 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 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: Vl.7. 7/18/2022 8:06 Windrose wind frequency is unusually LOW.
RESULTS:
Effective dose equivalent: 1.6 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**********