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| author name = Hathaway C | | author name = Hathaway C | ||
| author affiliation = State of RI, Atomic Energy Comm, Nuclear Science Ctr | | author affiliation = State of RI, Atomic Energy Comm, Nuclear Science Ctr | ||
| addressee name = Boyle P | | addressee name = Boyle P | ||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/DPR | | addressee affiliation = NRC/Document Control Desk, NRC/NRR/DPR | ||
| docket = 05000193 | | docket = 05000193 | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:August 28, 2015 Docket No. 50-193 Mr. Patrick Boyle, Project Manager Research and Test Reactor Licensing Branch Division of Policy and Rulemaking u.s. Nuclear Regulatory Commission (NRC) | ||
Office of Nuclear Reactor Regulation Washington, DC 20555 | |||
== | ==Dear Mr. Boyle:== | ||
This letter and the 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 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 401-874-9451. | |||
Sincerely, | |||
~~~~ | |||
Constance Hathaway Health Physicist 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. Bahram Nassersharif, RIAEC Dr. Yana K. Reshetnyak, RIAEC | |||
ENCLOSURE 1 REACTOR OPERATING STATISTICS Technical Specifications Section 6.8.4.a Month Year Operating Hours Energy (MWH) Energy (MWD) | |||
July 2014 45.73 52.60 2.19 August 2014 48.10 38.55 1.60 September 2014 30.78 40.17 1.67 October 2014 15.68 20.13 0.84 November 2014 26.85 33.08 1.38 December 2014 30.18 38.72 1.61 January 2015 23.70 29.73 1.24 February 2015 33.90 27.57 1.15 March 2015 36.05 39.87 1.66 April 2015 38.43 35.35 1.47 May 2015 30.90 36.53 1.52 June 2015 32.78 42.30 1.76 TOTAL FY2015 393.08 434.60 18.11 Total Energy Output since Initial Criticality: 65,142.92 MWhrs or 2714.29 MWdays. | |||
ENCLOSURE 2 UNSCHEDULED SHUTDOWNS OR SCRAMS The following is a list of the unscheduled shutdowns or scrams that occurred during the 2014-2015 reporting period. This information is required by Technical Specification 6.8.4.b Date Run No. Logbook Page Cause Description 07/09/14 8890 60 78 Instrumentation Scram caused by power loss 08/04/14 8904 60 93/94 Instrumentation Short Period and Operator scram due to interference with wires over bridge during rod adjustment / | |||
Hi-flux scram due to operator error 08/14/14 8911 60 101 Instrumentation Scram due to period spike 11/10/14 8942 60 132/133 Mechanical Overpower scram during swap of cooling loops during operation. Cold water in idle loop caused overpower 11/18/14 8945 60 36 Operator Hi Power scram during startup - | |||
operator error 02/20/15 8975 61 10 Instrumentation Reactor Scram due to noise 02/23/15 8976 61 11 Instrumentation Short period scram due to noise 02/26/15 8979 61 14 Operator Scram due to operator error 03/23/15 8988 61 23 Mechanical Scram due to power surge throughout facility 04/23/15 9006 61 43 Operator Overpower scram due to operator error 08/26/15 9048 61 87/88 Instrumentation Unscheduled shutdown due to power surge and two overpower scrams due to instrulnentation issue during testing | |||
ENCLOSURE 3 MAINTENACE OPERATIONS Technical Specification 6.8.4.c requires a listing of the major maintenance operations performed in the 2014-2015 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance. | |||
As stated in last year's report, a major security system upgrade was made to the facility beginning in April of2014. The system went live as of July 30th, 2014. The system has been tested several times in accordance with quarterly facility testing requirements and is working as expected. | |||
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 2014-2015 reporting period. | |||
There were no facility changes made during this period requiring a 10 CFR 50.59 evaluation. | |||
ENCLOSURES RADIOLOGICAL CONTROLS | |||
: 1. Environmental Surveys outside the Facility - Technical Specification 6.8.4.e Quarterly TLD 1 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 100 mrem per year. | |||
The quarterly doses in units of mrem are shown in the table below. | |||
LOCATION 3 rd QTR2014 4th QTR2014 1st QTR 2015 2 nd QTR2015 Northeast Wall 0 33 0 No report available Demineralizer 116 83 80 No report available Door Heat Exchanger 29 0 35 No report available Door 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 10 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 annual dose rate 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 hours per day, and applying the occupancy factor of 0.01, the annual dose that would be receive by an individual in the demineralizer room would be 2.79 mrem. The dose received at the Heat Exchanger Door would be 0.64 mrem. The annual dose received at the Northeast wall would be 0.33 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 and varying use of the different irradiation facilities. Note that while dose reports for the second quarter of this year (2015) are not available at the time of this writing, these doses are not expected to significantly change the overall annual dose received by the general public. This expectation is based on the history of these dose values and lack of change of factors which could affect dose rates. | |||
: 2. Annual Exposures Exceeding 500mrem - 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 lThermoluminescent Dosimeter; Radiation Detection Co. reads the dosimeters at minimum of 10 mrem. | |||
effluent released from the facility exhaust stacks shall not exceed lE+05 times concentrations specified in 10CFR20, Appendix B, Table II, when averaged over time periods permitted by 10CFR20? | |||
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 lE-8 llCi/cc xlE+5 == lE-3 llCi/cc. Concentrations released during the year were less than 0.02 of that limit. | |||
The total Argon-41 release during the reporting period was 6.083E+1 curies. The calculated effective dose equivalent for their release is 1.3 mrem/year (COMPLY Code). | |||
B. Liquid effluent concentrations released to the sewer are documented on the Sewer Discharge Radioassay 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 3,406,870 ml. The isotopes and their relative activities discharged are given below. | |||
Radioisotope Total Activity Discharged (microcuries) | |||
H3 414 C14 420 Cdl09 11.3 Pb214 2.72 Bi214 5.62 2 Technical Specifications, Section 3.7.2.}} | |||
Latest revision as of 23:37, 10 November 2019
| ML15252A067 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 08/28/2015 |
| From: | Hathaway C State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| To: | Patrick Boyle Document Control Desk, Division of Policy and Rulemaking |
| References | |
| Download: ML15252A067 (7) | |
Text
August 28, 2015 Docket No. 50-193 Mr. Patrick Boyle, Project Manager Research and Test Reactor Licensing Branch Division of Policy and Rulemaking u.s. Nuclear Regulatory Commission (NRC)
Office of Nuclear Reactor Regulation Washington, DC 20555
Dear Mr. Boyle:
This letter and the 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 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 401-874-9451.
Sincerely,
~~~~
Constance Hathaway Health Physicist 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. Bahram Nassersharif, RIAEC Dr. Yana K. Reshetnyak, RIAEC
ENCLOSURE 1 REACTOR OPERATING STATISTICS Technical Specifications Section 6.8.4.a Month Year Operating Hours Energy (MWH) Energy (MWD)
July 2014 45.73 52.60 2.19 August 2014 48.10 38.55 1.60 September 2014 30.78 40.17 1.67 October 2014 15.68 20.13 0.84 November 2014 26.85 33.08 1.38 December 2014 30.18 38.72 1.61 January 2015 23.70 29.73 1.24 February 2015 33.90 27.57 1.15 March 2015 36.05 39.87 1.66 April 2015 38.43 35.35 1.47 May 2015 30.90 36.53 1.52 June 2015 32.78 42.30 1.76 TOTAL FY2015 393.08 434.60 18.11 Total Energy Output since Initial Criticality: 65,142.92 MWhrs or 2714.29 MWdays.
ENCLOSURE 2 UNSCHEDULED SHUTDOWNS OR SCRAMS The following is a list of the unscheduled shutdowns or scrams that occurred during the 2014-2015 reporting period. This information is required by Technical Specification 6.8.4.b Date Run No. Logbook Page Cause Description 07/09/14 8890 60 78 Instrumentation Scram caused by power loss 08/04/14 8904 60 93/94 Instrumentation Short Period and Operator scram due to interference with wires over bridge during rod adjustment /
Hi-flux scram due to operator error 08/14/14 8911 60 101 Instrumentation Scram due to period spike 11/10/14 8942 60 132/133 Mechanical Overpower scram during swap of cooling loops during operation. Cold water in idle loop caused overpower 11/18/14 8945 60 36 Operator Hi Power scram during startup -
operator error 02/20/15 8975 61 10 Instrumentation Reactor Scram due to noise 02/23/15 8976 61 11 Instrumentation Short period scram due to noise 02/26/15 8979 61 14 Operator Scram due to operator error 03/23/15 8988 61 23 Mechanical Scram due to power surge throughout facility 04/23/15 9006 61 43 Operator Overpower scram due to operator error 08/26/15 9048 61 87/88 Instrumentation Unscheduled shutdown due to power surge and two overpower scrams due to instrulnentation issue during testing
ENCLOSURE 3 MAINTENACE OPERATIONS Technical Specification 6.8.4.c requires a listing of the major maintenance operations performed in the 2014-2015 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance.
As stated in last year's report, a major security system upgrade was made to the facility beginning in April of2014. The system went live as of July 30th, 2014. The system has been tested several times in accordance with quarterly facility testing requirements and is working as expected.
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 2014-2015 reporting period.
There were no facility changes made during this period requiring a 10 CFR 50.59 evaluation.
ENCLOSURES RADIOLOGICAL CONTROLS
- 1. Environmental Surveys outside the Facility - Technical Specification 6.8.4.e Quarterly TLD 1 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 100 mrem per year.
The quarterly doses in units of mrem are shown in the table below.
LOCATION 3 rd QTR2014 4th QTR2014 1st QTR 2015 2 nd QTR2015 Northeast Wall 0 33 0 No report available Demineralizer 116 83 80 No report available Door Heat Exchanger 29 0 35 No report available Door 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 10 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 annual dose rate 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 0.01, the annual dose that would be receive by an individual in the demineralizer room would be 2.79 mrem. The dose received at the Heat Exchanger Door would be 0.64 mrem. The annual dose received at the Northeast wall would be 0.33 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 and varying use of the different irradiation facilities. Note that while dose reports for the second quarter of this year (2015) are not available at the time of this writing, these doses are not expected to significantly change the overall annual dose received by the general public. This expectation is based on the history of these dose values and lack of change of factors which could affect dose rates.
- 2. Annual Exposures Exceeding 500mrem - 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 lThermoluminescent Dosimeter; Radiation Detection Co. reads the dosimeters at minimum of 10 mrem.
effluent released from the facility exhaust stacks shall not exceed lE+05 times concentrations specified in 10CFR20, Appendix B, Table II, when averaged over time periods permitted by 10CFR20?
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 lE-8 llCi/cc xlE+5 == lE-3 llCi/cc. Concentrations released during the year were less than 0.02 of that limit.
The total Argon-41 release during the reporting period was 6.083E+1 curies. The calculated effective dose equivalent for their release is 1.3 mrem/year (COMPLY Code).
B. Liquid effluent concentrations released to the sewer are documented on the Sewer Discharge Radioassay 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 3,406,870 ml. The isotopes and their relative activities discharged are given below.
Radioisotope Total Activity Discharged (microcuries)
H3 414 C14 420 Cdl09 11.3 Pb214 2.72 Bi214 5.62 2 Technical Specifications, Section 3.7.2.