ML20210J649
| ML20210J649 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 06/30/1997 |
| From: | Tripard G WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9708180218 | |
| Download: ML20210J649 (8) | |
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Washington StateUniversity
- Nuclear Radiation Center P O Box 641300 Pullman, WA 991041300 509-335-8641 FAX $09 335 4433 August 8,1997 i Document Control Desk U.S. Nuclear Regulatory Commission
. Washington,DC 20555 Re: Docket No. 50-27; Facility License R 76
Dear Sir:
'In accordance with the Technical Specifications for Facility License R-76 and the arovisions of 10 CFR 50.59, (6), the attached Annual Report prepared by Jerry A. Neid ger, Reactor
- Supervisor of the U facility, is hereby submitted. The report covers the period July 1,19% to June 30,1997.-
-Sincerely N@ Gerald E.Tripard Director
.GET/pw Enclosure cc: J.A. Neidiger Office of Nuclear Reactor Regulation /
American NuclearInsurers
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.9708190218 PDR 970630 -*
ADOCK 05000027 R pon
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{ WasliingtonStateUniversity f Lule-u 8taliatum Cenlei P O (los 641300 Pullman WA 99164-1300
$09 335%41 i Ax 509 335 4433 August 8,1997 l Non Power Reactors and Decommissioning Project Directorate
- Division of Reactor Program Management Office of Nuclear Reactor Regulation One White Flint Nonh 11555 Rockville Pike Rockville, MD 20852 2738 Re
- Docket No. 50 27; Facility License R 76 Dear Sir.-
In accordance with the Technical Specifications for Facility License R-76 and the provisions of 10 CFR 50.59, paragraph (6), the attached Annual Report prepared by Jerry A. Neidiger, Reactor Supervisor of the WSU facility,is hereby submitted. The report covers the period July 1,1996 to June 30,1997.
Sincerely, _
Gerald E. Tripard Ditretor GET/pw Enclosure cc: J.A. Neidiger American Nuclear Insurers U.S. NRC, Document Control Desk
ANNUAL, REPORT ON Tile OPERATION OF Tile WASillNGTON STATE UNIVERSITY TRIGA REACTOR Facility License R 76 for the Reponing Period of July 1,1996 to June 30,1997 A. Narrative Summary of the Year's Oncration
- 1. Operating Experience The Washington State University Reactor has accumulated 310 Megawatt hours on Core 33 X during the reporting period. A total of 175 irradiations for a total of 4284 samples were performed. In addition,11 pulses greater than $1.00 of reactivity addition were perfomied during this reporting period. The quarterly operations summaries are shown in Table I, Section B.
l 2. There were no changes in design, perfonnance characteristics, or procedures that related to reactor safety during the reporting period.
- 3. All surveillance tests and requirements were perfonned and completed within the prescribed time period. He results of all inspections revealed no abnonnalities.
11 . Encrev and Cumulative Outnut The quarterly operations summaries are given in Table I below.
TABLEI Fiscal Year Summary of Reactor Operations JAS 0-N D J F-M A-M-J TOTALS Hours of Operation 90 97 72 107 366 Megawatt Hours 68 79 71 92 310 No. of Irradiations 64 42 38 31 175 No. of Samples Irradiated 1407 959 1019 899 4284 No. Pulses > $1.00 1 6 3 1 11 The cumulative energy output since criticality of the TRIGA core since 1%7 is 772 Megawatt Days. De mixed core of Ft.lP and Standard fuels installed in 1976 has accumulated 506 Megawatt Days.
C. Emereenev Shutdowns and Inndvertent Scrams There were no emergency shutdowns that occurred during the reponing period. The dates and causes of the 6 inadvertent SCRAMS are listed in Table 11 below.
TAllLlill inadvertent SCR AMS DA*lli CAUSE 07/16S6 Malfunction of Fuel Temperature Channel #2 'thennalcouple Transmitter.
08/28N6 Pulse Rod SCRAM - Loss of Pulse Rod air pressure.
09/18N6 Period / Loss llV - No indication probable power spike.
02/18S 7 Reactor bridge Area Radiation Monitor- Activated sample temoved from reactor pool.
03/26S 7 Log N spike . Period SCRAM while at 100% power.
04/16S7 No apparent signal.
D. Maior Maintenance All major maintenance performed was routine planned maintenance items.
E. Changes. Tests and Exneriments Performed Under 10 CFR 50.59 Crlierta There was one item performed and documented under 10 CFR 50.59 criteria during the reporting period.
05/14S7 Approval to install new Continous Air Monitoring System.
F. Radioactive Effluent Discharnes
- 1. Radioactive Liquid Releases A total of 0.304 microcuries was released in 1,496,702 liters of liquid during the reporting period. The releases are listed in Table Ill.
TAllLE111 Radioactive Liquid Releases Quantity Tank Release Tank Release WSU Sewer Total Dilute Sewer Cone W" Date uCi Cone, uCi/mi Vol, Liters Vol. Liters Vol, Liters uCi/ml MPC 12/09/96 0.I60 8.28 x I 0-' I 8,69I 480.000 498,691 3.21 x 10 l.60 OlA)9/97 0.070 3.66x 10 ' 19.031 480.000 499.031 1.40x 10- O.70 03/27/97 0.074 3.91 x 10-' I8980 480.000 498,980 1.49x 10 O.74
"'Ilased on a release limit of 4.0x10' uCi/ml for unknown mixture,10 CFR 20 Table 3.
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- 2. Radioactive Gaseous Release During the reporting perial, no significant quantity of any gaseous or paniculate nuiterial with a half life greater than eight days was released.
During the reporting period, at no tithe did the Argon-41 release exceed 20% of the Effluent Release Linut.
A total of 2.84 Curies of Argon-41 was released in 5.86x10"cc of air which yields an average monthly concentration of Argon-41 of 4.85x10' uCi/cc. 'lte monthly releases are sununarized in Table IV.
TABLEIV Monthly Argon 41 Releases Cone.Ilefore % Release Limit'" % DAC l .imit"' Quantity
- Month Dilution, uti/ml Before Dilution Before Dilution mci Sil. (1996) 3.58x 10' l.43 <0.01 179 i Aug. 6.04x 10
- 2.42 0.01 302 Sep. 3.84x10* 1.54 0.01 186 Oct. 5.79x10' 2.32 0.01 289 Nov. 4.64x 10* 1,86 0.01
_ 232 Dec. 3.44x 10 ' l.38 <0,01 172 Jan.(1997) 4.48x10* 1,79 0.01 224 Feb. 5.13x 10' 2.05 0.01 232 Mar. 4.37x10 ' l.75 0.01
, 218 Apr. 5.38x10* -2.15 0.01 260 May 5.26x10' 2.10 0.01 263 Jun. 5.85x10' 2.34 0.01 283
"' Based on 10 CFR 20 limit of 10x10' uCi/cc forAr (Table
, o.2 C l 1).. and a dilution factor of 4.0x104 (S.A.R. 6.4.2) for a befo.e dilution limit of 2.5x10 uCi/ce. (20% of limit of 5.0x10' uCi/ce.)
"' Based on 10 CFR 20 DAC limit of 3.0x 10' uCi/ml for Ar (Table 1, Col. 3) and a dilution factor of 4.0x10' for a before dilution limit of 7.5x10' uCi/ml.
- 3. Radioactive Solid Waste Disposal During the arporting period,34 cubic feet of non<ompacted solid waste for a total of 0.32 millicuries and one (1) 55 gallon drum of compacted, dewatered ion 3
exchanger spent tesin containing 0.24 millicuries of Activity was transferred to (Fe Campus Radiation Safety Office for packaging and disposal.
G. l'ersonnel and Visitor Radiation ihoosures The average quanerly exposures of Nuclear Radiation Center reactor staff and experimenters who routinely utilize the WSU reactor are given in Table V. The maximum quarterly exposure of a reactor staff member was $0 millirem, whole body.
A total of 2240 non Nuclear Radiation Center staff or routine facility user individuals visited the Center during the reporting period, out of which 1.100 enter Restricted Areas.
As detennined by digital pocket dosimeter, the average individual exposure was <l.0 millirem.
A total of 36 group tours, consisting of 423 individuals, visited the Center during the reporting period. As detennined by digital pocket dosimeter, the average group exposure was <l.0 millirem.
TABLE V Average Quanctly Reactor and Experimenter Staff Exposure (in millirems)
Jul Aug Sep Oct Nov Dec - Jan Feb-Mar Apr-May Jun"'
<10 <10 <10 <10
'" June's film badge results not available from the vendor at the time this report was prepared.
Note: 10 millirem minimum exposun: reponed by vendor, 11 . Reactor Facilliv Radiation and Contamination Levels The routine area radiation surveys of the building had an average dose level of 0.02 mR/llr., while routinely accessible reactor areas had an average dose level of 0.03 mR/llr.
The highest average dose level in a reactor area was 0.3 mR/lir., which occuired in Room 201, Reactor Pool Room. The lowest average dose in a reactor area was 0.02 mR/llr.,
which occurred in Room 201 A, the Reactor Shop area. The average dose in the Reactor Control Room was 0.02 mR/llr. The average dose in the radiochemisuy sample hoods was 0.06 mR/llr. The highest average on site dose level was 10 mR/llr. which occurred in Room 2A, Cave Room, which is a locked storage area where radioactive material and radioactive sources are stored, Routine building 2
surveys for removable contamination had an average level of 2.5x 10' aCi/100 cm , while the average level in reactor areas was 5.6x10* pCi/100 cm'. The highest average value in a reactor area was 4.2x 10' pCi/100 cm' which was found on the platform where experimenters stand to insert and withdraw their samples from the reactor.
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The lowest average value in a reactor uma was E 2x 10' pCi/100 cm' which was in Room 201 A, the Reactor Control Room Floor. The average level of removable contamination in the radiochemistry sample hoods was 5,7x10' Ci/100 cm'.
NOTE: A reactor area is an area in the building which is adjacent to and through which I
access can be obtained to the Nactor pool or pool wall.
- 1. Environmental Monitorino Program The environmental monitoring program uses thermoluminescent dosimeters (TLD's) at locations both near and at distances around the reactor building facility. The quarterly i
exposures in the vicinity of the Nuclear Radiation Center are listed in Table VI. The average ambient gamma radiation levels for this area (80 mile radius) is 243 uRem/ day as -
reported in the 30th Annual Report of the Environmental Radiation Program, Washington State Department of llealth, Environmental Health Program, Table A 12, page 131.
The values observed indicate there is no significant effect on the environment radiation levels due to reactor operation.
TABLE VI Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center *
(Exposure in uR/ day) i Jul-Aug Sep Oct-Nov-Dec Jan-Feb-Mar Apr-May-Jun"' Median 186- 108 179 129 151
"'For sampling stations Incated 25 meters or greater from the Nuclear Radiation Center, f
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Quarterly exposures at locations at the reactor facility are listed in Table Vll. No significant effect on the environmental radiation levels by reactor operation was noted.
TABLE Vil Environmental Radiation Levels Adjacent to the Nuclear Radiation Centef" (Exposure in uR/ day)
Location J-A S O-N-D J F-M A-M-f" Median i
E. Loading Dock 221 196 181 188 197 l Rad. Storage Shed 209 188 169 200 192 l Rx Rm E. Sect. Gate . 122 188 193 188 173 Cooling Tower Fence 233 196 145 176 188 i Liquid Waste Tank 209 188 169 165 183 Building Roof West 163 143 145 141 148 l Building W. Side 233 214 205 200 213 Pool Room Exh. Vent 163 107 108 106 121 Pool Room W. Vent 407 259 253 282 300 Pool Room E. Vent 291 214 181 212 225 Building Roof East 151 143 108 118 130 S. Bldg. Entrance 244 268 205 212 232
'"For sampling stations located less than 25 meters from the Nuclear Radiation Center.
Technical Specifications ALARA effluent releases in 3.12(2) specify annual radiation exposures at the closest off-site extended occupancy shall not, on an annual basis, exceed the average local off-site background radiation level by r. ore than 20% For the reporting period,' the average total background radiation level for umpling points 400 meters or greater from the facility was 151 uR/ day, while the average total radiation level at the closest extended occupied area 930 meters away was 158 uR/ day. This yields a ratio of 5%, indicating no significant exposure level above natural background.
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