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Introduction As stated in the UFTR Technical Specifications, Section 6.6.1: | Introduction As stated in the UFTR Technical Specifications, Section 6.6.1: | ||
Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the Commission within six (6) months following the end of each prescribed year. The prescribed year ends August 31 for the UFTR. Each annual operating report shall include the following information: | Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the Commission within six (6) months following the end of each prescribed year. The prescribed year ends August 31 for the UFTR. Each annual operating report shall include the following information: | ||
(1) a narrative summary of reactor operating experience including the energy produced by the reactor and the hours the reactor was critical (2) the unscheduled shutdowns including, where applicable, corrective actions taken to preclude recurrence (3) tabulation of major preventative and corrective maintenance operations having safety significance (4) tabulation of major changes in the reactor facility and procedures, and tabulation of new tests of experiments, that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were invol ved (5) A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the facility operators as determined at or before the point of such release or discharge. (The summary shall include to the extent practicable an estimate of individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed, a statement to this effect is sufficient.) | |||
(6) A summarized result of environmental surveys performed outside the facility. | |||
(7) A summary of exposure received by facility personnel and visitors where such exposures are greater than 25% of that allowed. | |||
: 1. Summary of Reactor Operation Experience Facility staff completed a restart plan in September 2015 after an extended maintenance outage starting in late 2008. The UFTR has continued the broad range of research and educational utilization that was performed in the past. | : 1. Summary of Reactor Operation Experience Facility staff completed a restart plan in September 2015 after an extended maintenance outage starting in late 2008. The UFTR has continued the broad range of research and educational utilization that was performed in the past. | ||
The energy generated and operation hours in the reporting year are given as follows: | The energy generated and operation hours in the reporting year are given as follows: | ||
Line 59: | Line 59: | ||
The Argon-41 release concentration is measured every six months during facility operation. Ar | The Argon-41 release concentration is measured every six months during facility operation. Ar | ||
-41 was measured twice for this reporting period and the release values reported below reflect thi s. The Ar-41 release data is shown in Table II and below. | -41 was measured twice for this reporting period and the release values reported below reflect thi s. The Ar-41 release data is shown in Table II and below. | ||
Table II Argon-41 Released 2015-2016 Reactor Energy (kW-hrs) Ar-41 Released | Table II Argon-41 Released 2015-2016 Reactor Energy (kW-hrs) Ar-41 Released | ||
(!Ci) Ar-41 Monthly Average (!Ci/ml) September 333.0 1.4755E+6 4.7175E-10 October 182.9 8.1058E+5 2.5916E-10 November 61.6 6 2.7319E+5 8.7346E-11 December 214.7 9.5123E+5 3.0413E-10 January 0.5591 2.4773E+3 7.9206E-13 February 3.176 1.4074E+4 4.4998E-12 March 861.3 3.8164E+6 1.2202E-9 April 1694 8.7492E+6 2.3785E-9 May 513.8 2.6530E+6 7.2123E-10 June 508.8 2.6271E+6 7.1420E-10 July 252.6 1.3042E+6 3.5456E-10 August 2034 1.0504E+7 2.8556E-9 Release per kW | (!Ci) Ar-41 Monthly Average (!Ci/ml) September 333.0 1.4755E+6 4.7175E-10 October 182.9 8.1058E+5 2.5916E-10 November 61.6 6 2.7319E+5 8.7346E-11 December 214.7 9.5123E+5 3.0413E-10 January 0.5591 2.4773E+3 7.9206E-13 February 3.176 1.4074E+4 4.4998E-12 March 861.3 3.8164E+6 1.2202E-9 April 1694 8.7492E+6 2.3785E-9 May 513.8 2.6530E+6 7.2123E-10 June 508.8 2.6271E+6 7.1420E-10 July 252.6 1.3042E+6 3.5456E-10 August 2034 1.0504E+7 2.8556E-9 Release per kW | ||
-hr of operation (Sep | -hr of operation (Sep | ||
Line 67: | Line 67: | ||
33.18 Ci Yearly average Ar | 33.18 Ci Yearly average Ar | ||
-41 release concentration: | -41 release concentration: | ||
7.81 E-10 µCi/ml | 7.81 E-10 µCi/ml | ||
: 6. Environmental Surveys In addition to periodic radiation surveys using hand-held instruments, environmental monitoring is accomplished using radiation dosimetry badges. Areas monitored are located around the exterior of the reactor building and nearby buildings, including the Nuclear Sciences Building and the Journalism Building. This monitoring is performed by the Radiation Control Office of the Environmental Health and Safety Division at the University of Florida. The environmental dosimetry reports are tabulated and presented in Table III. | : 6. Environmental Surveys In addition to periodic radiation surveys using hand-held instruments, environmental monitoring is accomplished using radiation dosimetry badges. Areas monitored are located around the exterior of the reactor building and nearby buildings, including the Nuclear Sciences Building and the Journalism Building. This monitoring is performed by the Radiation Control Office of the Environmental Health and Safety Division at the University of Florida. The environmental dosimetry reports are tabulated and presented in Table III. | ||
The environmental dosimetry badges closest to the reactor cell radioactive materials storage areas are at locations 1, 2, 5, and 7. | The environmental dosimetry badges closest to the reactor cell radioactive materials storage areas are at locations 1, 2, 5, and 7. | ||
Table III Total Effective Dose Equivalent (TEDE) at Monitored Locations Area No. Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug 1 11 14 16 8 49 2 0 0 2 2 4 3 0 0 0 0 0 4 0 0 0 4 4 5 6 5 16 5 32 6 0 0 0 0 0 7 0 1 4 2 7 8 0 0 0 0 0 9 0 0 0 0 0 10 0 0 0 0 0 11 0 0 0 0 0 12 0 0 0 0 0 13 0 0 0 0 0 Reactor Cell 0 0 13 11 24 | Table III Total Effective Dose Equivalent (TEDE) at Monitored Locations Area No. Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug 1 11 14 16 8 49 2 0 0 2 2 4 3 0 0 0 0 0 4 0 0 0 4 4 5 6 5 16 5 32 6 0 0 0 0 0 7 0 1 4 2 7 8 0 0 0 0 0 9 0 0 0 0 0 10 0 0 0 0 0 11 0 0 0 0 0 12 0 0 0 0 0 13 0 0 0 0 0 Reactor Cell 0 0 13 11 24 | ||
: 7. Radiation Exposures There were no exposures received to facility personnel or visitors where such exposures were greater than 25% of the permissible limit. Facility personnel dosimetry reports are tabulated and presented in Table IV. | : 7. Radiation Exposures There were no exposures received to facility personnel or visitors where such exposures were greater than 25% of the permissible limit. Facility personnel dosimetry reports are tabulated and presented in Table IV. | ||
Table IV Total Effective Dose Equivalent (TEDE) for the UFTR Staff Individual Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug Artunduaga | Table IV Total Effective Dose Equivalent (TEDE) for the UFTR Staff Individual Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug Artunduaga | ||
- 0 0 0 0 Berglund 0 0 0 0 0 Cronin 0 0 0 0 0 Eggers 2 0 0 0 2 Ekdahl 0 0 0 0 0 Jordan 0 0 0 0 0 Newman 0 0 0 0 0 O'Bryan 0 0 - - 0 Shea 0 0 0 0 0 Smola - - 0 0 0}} | - 0 0 0 0 Berglund 0 0 0 0 0 Cronin 0 0 0 0 0 Eggers 2 0 0 0 2 Ekdahl 0 0 0 0 0 Jordan 0 0 0 0 0 Newman 0 0 0 0 0 O'Bryan 0 0 - - 0 Shea 0 0 0 0 0 Smola - - 0 0 0}} |
Revision as of 21:14, 26 April 2019
ML17059D637 | |
Person / Time | |
---|---|
Site: | 05000083 |
Issue date: | 02/28/2017 |
From: | Shea B Univ of Florida |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML17059D637 (7) | |
Text
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College of Engineering UFTR Nuclear Facilities 340 Weil Hall PO Box 116134 Gainesville, FL 3261 352-294-2100 February 28, 2017 U.S. Nuclear Regulatory Commission 2015-2016 Annual Report Attention: Document Control Desk Washington, DC 20555 University of Florida Training Reactor (UFTR)
Facility License R
-56, Docket No. 50
-83 Please find enclosed the 2015
-2016 annual report for the UFTR. This report is being submitted as required by our Technical Specifications, Section 6.6.1.
I declare under penalty of perjury that the foregoing is true and correct to my knowledge.
Executed on February 28, 2017.
Brian Shea Reactor Manager, University of Florida Training Reactor Email: bshea@ufl.edu Phone: 352
-294-2104 Enclosure cc: Duane Hardesty, USNRC Reactor Safety Review Subcommittee
University of Florida Training Reactor Annual Progress Report September 1, 2015
- August 31, 2016 Submitted by Brian Shea Reactor Manager University of Florida Gainesville, FL February 2017
Introduction As stated in the UFTR Technical Specifications, Section 6.6.1:
Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the Commission within six (6) months following the end of each prescribed year. The prescribed year ends August 31 for the UFTR. Each annual operating report shall include the following information:
(1) a narrative summary of reactor operating experience including the energy produced by the reactor and the hours the reactor was critical (2) the unscheduled shutdowns including, where applicable, corrective actions taken to preclude recurrence (3) tabulation of major preventative and corrective maintenance operations having safety significance (4) tabulation of major changes in the reactor facility and procedures, and tabulation of new tests of experiments, that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were invol ved (5) A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the facility operators as determined at or before the point of such release or discharge. (The summary shall include to the extent practicable an estimate of individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed, a statement to this effect is sufficient.)
(6) A summarized result of environmental surveys performed outside the facility.
(7) A summary of exposure received by facility personnel and visitors where such exposures are greater than 25% of that allowed.
- 1. Summary of Reactor Operation Experience Facility staff completed a restart plan in September 2015 after an extended maintenance outage starting in late 2008. The UFTR has continued the broad range of research and educational utilization that was performed in the past.
The energy generated and operation hours in the reporting year are given as follows:
Energy generated:
6661.13 kW-hrs Reactor runtime:
188.0 hrs.
- 2. Unscheduled Shutdowns On 8/19/16, the dump valve de
-energized with the reactor operating at 100 kW steady state causing a full trip. There were no indications of why the dump valve lost power. The reactor key switch was inspected and sprayed with contact cleaner to remove any carbon buildup that may have been a contributing factor to the loss of power to the dump valve.
- 3. Safety Significant Major Maintenance Operations MLP 15 8/26/15 to 9/9/15, South Area Radiation Monitor detector repair.
MLP 15 8/26/15 to 1/25/16, Radiation Monitor System Battery Power Supply repairs.
MLP 15 9/1/15 to 9/23/15, Stack Monitor detector repairs.
MLP 16 3/30/16 to 5/5/16, Linear Channel repairs to increase signal to noise ratio on ranges below 1 Watt.
MLP 16 4/12/16 to 4/18/16, Wide Range Drawer A7 card (Period) potentiometer replacements.
MLP 16 4/25/16 to 5/6/16, Safety Channel 2 potentiometer replacement for Cal Switch.
MLP 16 4/28/16 to 5/23/16, Auto Flux Controller repairs to reduce hunting.
MLP 16 5/2/16 to 6/9/16, Source alarm repair.
MLP 16 7/12/16 to 7/13/16, Current sensor installation for blade drop time measurements MLP 1 6 8/3/16 to 8/17/16, Fire alarm system replacement.
- 4. Major Changes in Reactor Facility, Procedures and Experiments LAR #27 - 11/17/15, Removal of License Condition 2.C.(3).
- 5. Radioactive Effluents Liquid Releases:
The UFTR is equipped with a wastewater holdup tank.
The wastewater radioactivity is measured prior to release.
The wastewater release data is shown in Table I.
Table I Wastewater Released Date Water Released (Gallons)
Gross Activity Released (!Ci/ml) May 2, 2016 936.2 4.1 8E-10 Argon-41 Releases:
The Argon-41 release concentration is measured every six months during facility operation. Ar
-41 was measured twice for this reporting period and the release values reported below reflect thi s. The Ar-41 release data is shown in Table II and below.
Table II Argon-41 Released 2015-2016 Reactor Energy (kW-hrs) Ar-41 Released
(!Ci) Ar-41 Monthly Average (!Ci/ml) September 333.0 1.4755E+6 4.7175E-10 October 182.9 8.1058E+5 2.5916E-10 November 61.6 6 2.7319E+5 8.7346E-11 December 214.7 9.5123E+5 3.0413E-10 January 0.5591 2.4773E+3 7.9206E-13 February 3.176 1.4074E+4 4.4998E-12 March 861.3 3.8164E+6 1.2202E-9 April 1694 8.7492E+6 2.3785E-9 May 513.8 2.6530E+6 7.2123E-10 June 508.8 2.6271E+6 7.1420E-10 July 252.6 1.3042E+6 3.5456E-10 August 2034 1.0504E+7 2.8556E-9 Release per kW
-hr of operation (Sep
-Mar): 4430.93 µCi/ml Release per kW
-hr of operation (Apr
-Aug): 5163.60 µCi/ml Total Ar-41 release for the reporting year:
33.18 Ci Yearly average Ar
-41 release concentration:
7.81 E-10 µCi/ml
- 6. Environmental Surveys In addition to periodic radiation surveys using hand-held instruments, environmental monitoring is accomplished using radiation dosimetry badges. Areas monitored are located around the exterior of the reactor building and nearby buildings, including the Nuclear Sciences Building and the Journalism Building. This monitoring is performed by the Radiation Control Office of the Environmental Health and Safety Division at the University of Florida. The environmental dosimetry reports are tabulated and presented in Table III.
The environmental dosimetry badges closest to the reactor cell radioactive materials storage areas are at locations 1, 2, 5, and 7.
Table III Total Effective Dose Equivalent (TEDE) at Monitored Locations Area No. Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug 1 11 14 16 8 49 2 0 0 2 2 4 3 0 0 0 0 0 4 0 0 0 4 4 5 6 5 16 5 32 6 0 0 0 0 0 7 0 1 4 2 7 8 0 0 0 0 0 9 0 0 0 0 0 10 0 0 0 0 0 11 0 0 0 0 0 12 0 0 0 0 0 13 0 0 0 0 0 Reactor Cell 0 0 13 11 24
- 7. Radiation Exposures There were no exposures received to facility personnel or visitors where such exposures were greater than 25% of the permissible limit. Facility personnel dosimetry reports are tabulated and presented in Table IV.
Table IV Total Effective Dose Equivalent (TEDE) for the UFTR Staff Individual Quarterly TEDE (mrem) Annual TEDE (mrem) Sep - Nov Dec - Feb Mar-May Jun-Aug Artunduaga
- 0 0 0 0 Berglund 0 0 0 0 0 Cronin 0 0 0 0 0 Eggers 2 0 0 0 2 Ekdahl 0 0 0 0 0 Jordan 0 0 0 0 0 Newman 0 0 0 0 0 O'Bryan 0 0 - - 0 Shea 0 0 0 0 0 Smola - - 0 0 0