ML20207A654
| ML20207A654 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 02/26/1999 |
| From: | Hertel N Neely Research Reactor, ATLANTA, GA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9903050155 | |
| Download: ML20207A654 (16) | |
Text
. . . . .
GeorgiaMsBODUna0@ Neely Nuclear Reseats Center f @ QC @@_@ 900 Atlantic Drive Atlanta, Georgia 30332-042S a (404)894-3600 FAX:(404)894-9325 February 26,1999 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Reference:
Annual Report Docket 50-160; License R-97 in April 1998, the U.S. Nuclear Regulatory Commission (USNRC) issued Amendment No.12 to the Georgia Institute cf Technology Research Reactor Facility License No. R-
- 97. This amendment removed from the license the authority to operate the reactor, authorized possession-only, and changed the Technical Specifications to remove the ;
operational requirements of the reactor. TI's new Technical Specifications (TS) no longer require an annual operating report f a be submitted to the USNRC. However, ,
since the facility was under the previone ',S for a portion of calendar year 1998, the '
following annual report is being submitted pursuant to Section 6.7a of the TS in force under Amendment No.11 to the license. The reporting period for the information included is January 1,1998 through December 31,1998 (calendar year 1998).
- 1. OPERATIONS
SUMMARY
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- a. Chanaes in the Facility Desian The heavy water coolant was removed from the reactor during June 1998 and retumed to the Department of Energy. In accordance with the TS issued under Amendment No.12, specifications 2.3,3.2 and those related to footnote (c) in Table 2.1 are no longer in force and activities related to them are no longer being performed.
The decommissioning plan was submitted July 1,1998. No changes in the facility design are allowed until the decommissioning plan is approved.
- b. Performance Characteristics
- ' l During the reporting period, the reactor was not operated at anytime. There is no fuel on hand in the reactor and the heavy water coolant has been removed.
l- A Unit of the University System of Georgia An Equal Education and Employment Opportunity Institution 9903050155 990226 go DR ADOCK 0
- c. L Changes in Ooerating Procedures The new and/or revised procedures approved by the former Nuclear Safeguards Committee, and now the Radiation Safety Committee and the t Technical Safety Review Committee during the calendar year 1998 are, as follow:
9700- Preparation of Procedures ;
'6110 Response to Adverse Weather, Tornadoes, and Hurricane ;
6120. . Response to Bomb Threat 0155 Training Requirements for Unescorted Access to the Radiological Control Zone ,
. 9016 Calibration and Testing of Filter Bank Monitors I' 9037- Tritium Determination in Urine 9038 Bioassay Program >
9040 Liquid Waste Tank Analysis 9041 Storage Pool Water Sampling Analysis >
9053 Calibration Procedure for Basic Portable Neutron Meters 9056 Calibration and Operation of the Ludlum 2000 Scaler l' 9150 Operation and Calibration of Area Radiation Monitors 9155 Determination of Minimum Detectable Concentration 9157 Operation and Calibration of the Gamma Spectroscopy System ;
9170 Calibration and Operation of DMC-100 Electronic Personal Dosimeters !
9251 Procedure for Receiving and Opening Radioactive Packages 9290 Radioactive Waste Management and Disposal 9300. Respiratory Protection 9306 Preparation and Maintenance of Radiation Work -
Permits 9308 Airbome Radioactivity Surveys
! 9312 Sealed Sources Leak Test l- 9501 Control and Accountability of Radioactive Materials
! 9502 Control and Accountability of Radiation Generating L Equipment i 9510 Radioactive Material Shipment L
The following procedures were canceled during the calendar year 1998:
1513 Transfer of Heavy Water to Shipping Drums 3500 . Heavy Water Inventory 4000 Containment Building Pressure Test 4002 Reference Vessel Pressure Test l' 4051 lon Bed D2O Recovery .
6020 Response to Heavy Water Leakage in Containment Building
- 6030- Response to Irradiated Fuel Element Becoming Unshielded
.7201 Cooling Tower Sampling for Radionuclide Analysis
- 7224 D2O Leak Detection System Surveillance i 7279 Kanne Recorder Calibration 9010 Kanne Chamber Calibration
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i L 9012 Operation and Calibration of Gas Monitor i
'9062 Calibration and Procedure for Victoreen Panoramic l Model 470A 9064. Calibration Procedure for Eberline RO-3A l 9070 ' Calibration of Harshaw Integrating Picoammeter 2000-B I
9074 Calibration Procedure for PIC-6A 9154 Operation and Daily Check of the Gamma Analyses System for Effluent Monitoring -
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- d. Results of Surveillance Tests and insoections
.The surveillance tests and the inspections of the facility required by the Technical _ Specifications were performed. Documentation of each of the
! tests and inspections are available at the site for review.
- e. Changes. Test and Exoeriments Anoroved by the USNRC There were no changes, tests or experiments that required the approval of
- the USNRC pursuant to 10 CFR 50.59(a).
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l f. ; Current Staff. Nuclear Safeauards Comrnittee. Radiation Safety Committee. and Technical Safety Review Committee l
- 1) Current Staff l
Dr. Nolan E. Hertel, Director, Neely Research Center
- Dr. Rodney Ice, Radiation Safety Officer, Office of Radiological Safety
-Mr. Peter Newby, Associate Director of the Neely Nuclear Research Center, Assistant Reactor Supervisor, and Reactor Engineer (Resigned Position, i
! Jdy 1998). I
- Mr. Billy Statham, Reactor Supervisor (part-time), Neely Nuclear Research Center Mr. Dwayne Blaylock, Senior Reactor Operator /Research . Engineer I, Neely ,
Nuclear Research Center l l- . Mr. Johannes Strydom, Research Scientist I, Office of Radiological Safety Mr. Edgar Jawdeh, Research Scient!at I, Office of Radiological Safety !
Mrs. Arlene R. Smith, Administrative Coordinator, Neely Nuclear Research !
Center and Office of Radiological Safety !
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- 2) In aGuon, the NNRC employed the following graduate students on a part- !
time basis during portions of the reporting period- l I
' Alain Rodriguez Mike Valenzano Ken Veinot l Jeremy Sweezy
, Julia Banks
[ Emily Fort i
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Michele Sutton -
- Marie Weber Sofie Weber Duane Nakahata
- 3) The : membership of the L Nuclear Safeguards Committee, which was disbanded pursuant to T.S. Amendment No.12 in April 1998, was:
Mr. Emsley Cobb -Reactor Operation and Reactor Safety Dr. Bemd Kahn -Radiation Protection / Environmental Measurements Dr. Robert Braga -Chemistry
, Dr. Prateen V. Desai -Thermal Hydraulics, Mechanical Systems Dr. Billy R. Livesay -Material Science, Physics Mr. Jack Vickery -Security Dr. Thomas G. Tomabene -Biology and Biochemistry Dr. S.M. Ghiaasiaan -Nuclear Engineering Mr. Len Gucwa - -Reactor Safety Mr. Steve Ewald -Health Physics Dr. Peggy Girard -Biology and Biochemistry Mr. James O'Hara -Health Physics 4)' HThe membership of the Radiation Safety Committee is:
Dr. Robert Braga' -Chemistry Dr.- Bemd Kahn -Radiation Protection / Environmental Measurements Dr. Tomas G. Tomabene -Biology and Biochemistry Mr. Steve Swant -Budget / Planning Dr. Stuart Stock -Materials Science Mr. Jack Vickery -Security (GA Tech Police Dept.)
Dr._ Gary Schuster -Dean, College of Science Dr. Nolan E. Hertel -Director NNRC, Health Physics
' Mr. Lee Zacarias -Environmental Safety Dr. Rodney Ice -Radiation Safety Officer
'5) . The membership of the Technical Safety Review Committee is:
Dr. Nolan E. Hertel -Director NNRC, Health Physics-Dr. Rodney Ice ' -Radiation Safety officer Mr. Bill Miller -Director, Master Planning Project, Facilities Dr. J. Nati Davidson -Associate Dean of Engineering
- Dr. Ward O. Winer-- -Regents Professor & Chair, Mechanical Engineering
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' ! 2. POWER GENERATION l
There was no reactor operation during this reporting period.
- 3. SHUTDOWNS There was no reactor operation during this reporting period. ;
4.- - UNSCHEDULED MAINTENANCE ON SAFETY RELATED SYSTEMS AND COMPONENTS There were five minor repairs performed on safety-related systems and components. Records of maintenance performed on components are available i at the NNRC offices for inspection. l
- 5. - CHANGES. TESTS AND EXPERIMENTS During 1998, there were no experiments which used the GTRR.
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, -6l R'ADIOACTIVE EFFLUENT RELEASES
- a. Technical Specification 6.7.(6)(a) - Gaseous Effluents -Summation of All Releases Via Stack, i.e., ground level release.
(1) FISSION AND ACTIVATION GASES Tritium Released (gaseous)
None Measurable Argon-41 Released: None (Reactor Shutdown)
(2) 10 DINES RELEASED None released (Reactor Shutdown)
(3) PARTICULATES None released (Reactor Shutdown) l- Minimum Detectable Activity gross beta / gamma = <1.13 E-05 pCi l Minimum Detectab!e Activity 4 j gross alpha = <6.78 E-06 Ci l
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- b. Liquid Effluents .
(1) IQIALGROSS RADIOACTIVITY (p/ gamma)
Total- Average Maximum % Tech Release - . Release Rate
- Conc. Released Specs i'
Cl . ( Ci/cc) ( Ci/cc) 1st QTR. 7.27E-07 . 2.04E-12. 2.45E-08 <1% !
2nd QTR: 9.75E-07 2.74E-12 - 3.31E 1.1%
3rd QTR 1.79E-06 5.03E-12 5.91 E-08 1.97 %
4th QTR 2.08E-06 5.83E-12 1.04E-07 3.47 %
Annual . 5.57E-06 3.91 E-12 1.04E-07 3.47 %
Average release rate values are based on a Georgia Tech campus water - .
discharge rate of 3.566*10" ml/ quarter.
I (2) TOTAL- GROSS RADIOACTIVITY (Alpha) I Total Average Maximum % Tech Release . Release Rate b Conc. Released Specs Ci ( Ci/cc) '(pCl/cc) ist OTR1 5.80E-08 : 1.61 E-13 4.97E-9 <1%
2nd QTR 1.00E ' 2.79E-13 5.19E-09 '<1%
3rd QTR 1.63E-07 . 4.57E 5.35E-09 <1%
4th QTRD 1.21 E 3.39E-13 ' 7.26E-09 <1%
i Annual' . 4.41 E 3.09E-13 7.26E-09 <1%
, La. = Lower than Minimum Detectable Activity.
.b. Average release rate values are based on a Georgia Tech campus water ;
discharge rate of 3.566*10" ml/ quarter.
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(3) FISSION AND ACTIVATION PRODUCTS .
1 Cobalt-60 is the only activation product released via the liquid pathway from the reactor facility. The Co-60 does not result from l reactor operations, but is attributable to material stored in storage I pool that is part of the State of Georgia Radioactive Materials License No.147-1-SNM. No fission products are released via the liquid effluent pathway.
(i) CO6 RELEASE Total Average Maximum % Tech l Release Release Rate b Conc. Rel eased Specs ,
Ci ( Ci/cc) ( Ci/cc) ]
1st OTR <MDA* <MDA* <M DA" <1%
i 2nd QTR <MDA" <MDA* < M DA* <1% i 3rd QTR <MDA* <MDA* <MDA* <1%
4th QTR <MDA* <MDA" < M DA* <1%
Annual <MDA* <M DA" <MDA" <1%
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- a. Lower than Minimum Detectable Activity. MDA for Co : < 1.3E-06 Ci/cc
- b. Average release rate values are based on a Georgia Tech campus water discharge rate of 3.566*10" ml/ quarter.
(ii) TRITIUM Total Averago Maximum Release Relesse Rate
- Conc. Released %10CFR20" Ci (pCi/cc) ( Ci/cc) 1st OTR 2.86E-04 8.01 E-10 9.'2E-06 <1%
2nd QTR 1.15E-03 3.22E-09 3.72E-05 <1%
3rd QTR 3.24E-02 9.07E-08 1.17E-03 11.7 %
4th QTR 6.48E-04 1.82E-09 1.32E-05 <1%
Annual 3.44E-02 2.41 E-08 1.17E-03 11.7 %
Average release rate values are based on a Georgia Tech campus water discharge rate of 3.566*10" ml/ quarter.
As percent of Tech Specs, the listed values would be a factor of 10 less.
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.(4)_ TOTAL VOLUME OF LIQUID WASTE RELEASED
.1** QTR ... 5.64E+07 ml 2"d QTR ... 3.79E+07 ml 3'd QTR ... 1.14E+08 ml 4*OTR ... 5.68E+07 mi ANNUAL ... 2.65E+8 ml
_(5)- GEQRGIA TECH VOLUME OF DILUTION WATER USED 18' OTR ... 3.566E+11 ml 2" QTR ... 3.566E+11 ml I
3rd QTR ,.. 3.566E+11 ml 4*QTR ... 3.566E+11 ml ANNUAL ... 1.426E+12 mi i
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- 7. ENVIRONMENTAL MONITORING: (Tech. Spec. 6.7.a(7))
- a. Twenty-five sites are monitored for environmental radiation. The )
parameter monitored for Georgia Tech Research Reactor (GTRR) operations is that of direct radiation from the facility and from emitted i gaseous effluents (predominantly Ar-41). The location of the sites relative !
to the reactor is shown in Figure 1, " Environmental Monitoring Stations".
The sites are predominantly around the reactor perimeter lence or down- l wind from the reactor. An updated wind rose is given in Figure 2. '
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- b. Total assays = 25 sites X 4. quarters = 100 assays. The results are reported in the Environmental Radiation Surveillance table (attached).
The letter M was used to designate any reading which was less than the minimum detectable limit. ,
- c. Monitors are Landauer "X9" aluminum oxide thermoluminescent dosimeters (TLD). The dosimeters meet ANSI standards. None of the ;
twenty-five monitored sites show levels significantly above background. '
The reactor was not operated during1998.
I Thermoluminescent dosimeter (TLD #9) is located on the perimeter fence near the Georgia Tech Short-Term Radioactive Waste storage and i preparation facility licensed by the State of Georgia.
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l Landauer reports that 14 dosimeter locations out of 25, averaged over the year, have radiation levels greater than local background and 11 dosimeters had radiation levels less than local background.
- d. The highest, lowest and annual average levels of radiation for the sampling point (TLD #1) with the highest average radiation exposure with respect to the site, are Highest Annual Average Level -
234.8 mrem /yr Lowest Annual Average Level -
(- 12.8) mrem /yr Average Annual Leven -
111.0 mrem /yr
- e. The gross dose rate readings for all TLDs from all stations varied between 15 and 50 mrem per quarter. The control TLD station varied between 30 and 40 m7m per quarter. This range of variation produced some net dose rate readings soss reading minus control or background reading) that are negative. The l negative readings are replaced by the letter M in the attached Table.
l Statistically, no conclusions can be made about the environmental dose l attributed to the GTRR operation.
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- 8. OCCUPATIONAL PERSONNEL RADIATION EXPOSURE 1998:
Radiation workers of Georgia Institute of Technology are monitored through the use of film badges which are provided by a NVLAP certified vendor and have a lower limit of detection of 510 mrem. A monthly radiation dosimetry report is issued for the personnel of the Neely Nuclear Research Center, a summary shown in Table 1.
- a. Summary of exposure for persons under 18 years of age greater than mrem -
None
- b. Summary of occupational exposures greater than 500 mrem -
None
- c. Person-Rem for the Neely Nuclear Research Center - R-97.
Person-Rem = Sum of occupational workers = 0.961 rem The highest, lowest and average levels of personnel exposure due to reactor and hot cell operations:
Average annuallevel- 46 mrem Highest annuallevel- 110 mrem Lowest annual level- < 10 mrem.
- d. Category of exposure -
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4 i NNRC Radiation Workers Table 1.
Annual Deep Dose # Radiation workers
< 10 mrem 8 10 mrem - 49 mrem 3 50 mrem - 99 mrem 3 I 100 mrem - 149 mrem 7 I 150 mrem - 199 mrem 0
> 200 mrem 0 Total Workers 21/961 mrem total
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, - Should there be any questions concerning this report, please let us know.
Sin re ,-
N -
Nolan E. Hertel-
- Director, Neely Nuclear Research Center -
NEH/ars Cc: 1. Dr. Jean-Lou Chameau
- 2. Dr. Narl Davidson -
- 3. Dr. Charles Liotta-
-4. Members- Technical Safety Review Committee
- 5. Members- Radiation >2afety Committee 1 6.- Director, Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission
_. Washington, D.C. 20555
- 7. Craig Bassett l
- U.S. Nuclear Regulatory Commission i
Region ll
!- 61 Forsyth Street, S.W.
Suite 23T85' l- Atlanta, GA 30303 ,
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C4LM WINDS 3.09% WIND SPEED (20T5) ms ~#
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Figure to Annimi Surface Wind Rose for Atlanta.
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NEELY NUCLEAR RESEARCH CENTER ENVIRONMENTAL RADIATION SURVEILLANCE *
, , 1998
-A B C D E F
, Jan.1-~ Apr.1 - July 1 - Oct.1 - 1998 Total Comments s - Mar. 31 June 30 - ' Sept. 30 Dec. 31 Landauer
'l - -58.7 -2.8 -1.8 - 3.2 50.9 in Stack .l 2 7.4 -22.7 -8.3 4.9 -l 8.7 inner Ring 3 8.3 ~ 1.8
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4' 9 -15 0.2 3.8 -2 inner Ring 5 -2.6 -1.8 : -9.1 1.9- -11.6 Inner Ring l
6 '10.5 5.9 7.4 3 26.8 Inner Ring {
7- ' 4.9
. -3.7 - 2.6 0.6 4.4 Inner Ring I 8 15.3 0.9 4.1 0.8 21.1 Inner Ring 9' 4.8 - -1.4 0 2.6 6 Rad. Waste Barn 10 7.9 3.1 1.5 2.4 14.9 Inner Ring i 11 8.8 -16.5 -3.4 -3 -7.3 - Inner Rmg '
l 12 9.1- -4.8 2.1 4.8 11.2 Inner Ring )
. 13 12.5 -7.8 3.3 7.6 15.6 Inner Ring
-14 9 -4.1 5.8 5.5 16.2 Inner Ring 15- 14.3 1-10 7.4 18 29.7 Inner Ring 16" ' -2.9 -6.8- 0.1 2.1 -1.7 - Outer Ring
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- - 1.6 - -6.3 -7.9- Outer Ring 26 1.9 - -3.8 -2.1 - 2.2 -6.2 Outer Ring 4.6 0.1 3.6 - 1.8 6.5 Outer Ring 28 ~3.6 -1.9 ~-4.2 -2.3 - -4.8 Outer Ring
. 29 - ~Ab -7 -3.3 -
7.7 -l8 Outer Ring 30 0.4 -5.8 -1.5 -4.6 -11.5 Outer Ring J
31 1.8 - 4.5 - 5.5 3.1 ' -2.3 Outer Ring
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32- ' l .9 - 7 -2.4 - 1.3 5.2 Outer Ring 33 - 2.2 7 2 - 1.3 9.9 Outer Ring j Workload MW-HRS 0 0 0 0 0
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- Sum of natural radiation, direct radiation from facility and' gaseous radioactive effluents monitored with Al2O3TLD's less control
. j badge kept at GT Police Department Badges processed by Landauer. The Lower Limit of Detection is 0.1 mrem. All negative readings are indicated by M. Absent - Ab ( TLD was lost ). .
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- The locations 17 - 24 (8 sites)'were deleted on 1/1/98 due to construction on location. TLD locations 31 33 (3 sites) were added sites to accommodate for new construction. The total number of sites monitored are therefcre down 5 from previous reported years of J 30; i.e.: we currently have 25 sites.
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