ML20077R887

From kanterella
Jump to navigation Jump to search
Annual Rept on Operation of Wa State Univ Triga Reactor - 900701-910630
ML20077R887
Person / Time
Site: Washington State University
Issue date: 06/30/1991
From: Tripard G
WASHINGTON STATE UNIV., PULLMAN, WA
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9108260198
Download: ML20077R887 (7)


Text

- - - _ _ - _ _ _ _ _ _ _ __

F

- . . \

s l

] Washington State University-BORI nom re, v . i ce.m e- 4 ,

wis o u a i i ,  ;

. on lix':~i. Ol y i i

August 19, 1991 l I

i Ibcumnt Control Desk l U.S. lhtclear Beculatory CormticFion l Washington, DC 20555  :

Fo: Docket flo. 50-27; Pacility Licence Fe-76 6

Dear Sir:

In ac: ordance with the Technical Specifications for Facility Licence R-76 and the provisions of 10 CFR 50 59, Paracenph (6), the attached annual report prepared by l Jerry A. lleiditer, Reactor Supervinor of the WSU facility, in hereby submit.ted.

The report covers the period July 1,1990 to June 30, 1991.

. Sincerely, j-b't,t h f . _^'l. w ncf Gerald E. Tripard Director Enclosure cc: NRC, Region V, Office of Regional Ad:rinistrator J.A. Neidiger  !

American Nuclear Innurera CET: crc  !

9108260}98 910/90 PDR R

ADOCK 050dD027 PDR p g()

g h/

't ANNUAL REPORT ON TIIE OPERATION OF THE VASHINGTON STATE UNIVERSITY TRIGA REACTOR racility License R 76 for the Reporting Period of July 1,1990 to June 30, 1991 f

=)

A. Narrative Summary of the Year's 0.peration

1. Operating Experience '

The Washington State University Reactor has accumulated 356 Hogawatt -i hours on Core 32 A during the reportir5 period. A total of 342 irradiations for a total of 4568 samples were performed. In ,

addition, 4 pulses greater than $1.00 of reactivity addition were  ;

performed during this reporting period. The quarterly operations summaries are shown-in Table 1, section B..

2. There' vere no changes in design, performance characteristics. or procedures that related to reactor safety during the reporting =

period.

3.. All surveillance tests and requirements were performed and compleced within-the prescribed time period. The results of all inspections revealed no abnormalities and were within expectern values. '

B.- EDerny and Cumulative Outnut' The quarterly oporatfors summaries are given in Table I below.- I TABLE I Fiscal Year Summary of Reactor Operations  :

-J.A f 0ND J F.M AMJ ' TOTALS Hours of Operation 101 85- 94 96 375 Megawatt llours 94 84 94 84 356 -

No. of Irradiations 95- 91 92 64 342 No. of Samples Irradiated 1336 1286 1031 915 4568-L No. Pulses >-$1.00 0'- 1 0 3 4- it I' LThe cumulative energy output since criticality of the TRIGA core since 1967' t.

Is 661 Megawatt Days, . The mixed core-of FLIP and Standard fuels installed in 1976 has accumulated 600 Megawatt Days.

[' . , .. .

i i

  • I

. s 2

F C. Emttgtncy Shutdovits and inadvertent Berama I i

There were no SCRAMS and no emergency shutdowns that occurred during the {

reporting period, I i

f D. Halor Haintenanet l t

09/07/90 Repinced the 1 1/2 inch water inlet meter and the 2 inch  !

discharge water meter on the liquid waste collection system, j t

All other major maintenance performed was routine planned mainte.1ance l items a E. Shang_es. .. Tests and Experiment s Performed Under 10 CFR 50,59 Critetig  !

There yore no changes, tests or experiments perforn,ed under 10 CFR 50.59 i criteria during the reporting period. l F. .Eudioactive Effluent Discharces i

1. Radioactive Liquid Releases '

A total of 3,$5 microcurlos was released in 407,946 liters of liquid  !

during the reporting period. This yields  !

concentration of liquid waste of 8.70x10*ganmicrocuries average release per  !

millilitet. The monthly releases are.ltsted in Table 11-below.. ,

TAB LE ' II  !

Radioactive Liquid Releases t

[

t t

Quantity, Concentration, Volume, .i Month .uci uCi/mi Percent MPC I Liters l 5

Jul,(1990) 0.77 4.25x10*8 42,5 18,189.  !

Aug, 0.26 1.43x10 8 14,3 18',189 l Sep. 0,53 5,08x10'9 5.1 104.147 Oct, NO RELEASE Nov. 0,04 .3.85x10*9 3,9 9775 ,

Dec. 0. 34 -- -9,03x10*9 9.0 37,533 .,

Jan,(1991) NO RELEASE ,

Feb, 0.25 6,82x10*9 6.8 36,848  !

May, 0,88 8 08x10*9 8.1 109,319 I Apr. 0.24 6,58x10*9 6.6 36,919 May.-  ;.0.11 5.91x10*9 5.9- 18,495 Jun. 0.13 6,90x10'9: 6,9 18,532 1 Based on-a release limit of 1.00x10*7 uC1/ml for unkomm mixture found in L Technical Speci fications 6,10, paragraph 5, page 36.

n

}

--- N

. , . - - . . . _ - . . . _ . , . . . , ____.._.-._-_-._..-..,,.-_;.. _--..u-,._.._. . - _ . . _ _ . . _ _ . , . . _ . . . . . . . . _ . ,

s 3

2. Radioactivo Cascous Release During the reporting period, no significant quantity of any gaseous or particulate material with a half life greater that eight days was released.

During the reporting period, at no time did the release exceed 20% of MPC for Argon.41.

A total of 3.99 Curies of Argon 41 was released in 6.70x10 13 cc of air,whighyeildsanaveragemonthlyconcentrationofArgon41of 5.96x10' uC1/cc. The monthly releases are summartred in Tabic ITI

~below.

TAllLE III ,

Hon'My Argon 41 Releases Concentration Before Percent HPC I Quantity Month Dilution, uC1/cc After Dilution mC1 l

Jul.(1990) 6.73x10 8 0.67 382 Aug. 4.19x10 8 0.42 238 Sep. 1.12x10*7 1.12 614 Oct. 7.69x10*8 0.77 436 Nov. 4.06x10 8 0.41 223 <

Dec. 5.05x10 8 0.51 268 J an.'(1991) 4.35x10 8 0.44 247 Feb. 6.71x10*0 0.67 344 Har, 5.98x10 8 0.60 339 Apr. 5.01x10 8 0.50- 275 May 7.10x10 8 0.71 403 Jun. 3,99x10 8 0.40 219 r

- 1 Based on 10 CFR 20 limit of 4.0x10~0 uCi/cc (Table II, Col. 1), and

- dilutiog faenor of 4.0x10*3 (S. A.R 6.4.2g for an af ter dilut ion limit of-1.0x10" uci/cc. (20% of limit is 2.0c10' uC1/cc).

3 . --. ' Radioactive Solid Waste Disposal"
No solid waste _ generated by-the Nuclear _ Radiation Center reactor was shipped off sito during the reporting period, l.

~

. _ . - - _ _ , _ _ . . _ . . _ _ , . . _ _ - . _ - - _ _ - _ _ . . . . - , .. . _ _ . - _ . - - . . - _ _ _ _ , . _ . - , ~ -

4 d

C. - Insonnel and Visitor Radiation. Exposures The average quarterly exposures of Nuclear Radiation Center reactor staff and experimenters who routinely utilize the W.S.U. reactor are given in Table IV below. The maxiinum quarterly exposure of one individual, who is a reactor staff rneinber and who routinely prepares irradiated saroples for shipinent and calibrates radiation survey meters, was 30 millitem. - whole body _

A total of 1920 non Nuclent Radiation Center staff or routine f acility user individuals visited the Center during the reporting period, out of which 912 enter postad Radiation Areas.- As determined by digital pocket dosimeter and An exposure recorded the average individual exposure was

<0.1 millirem wi th a snaximurn exposure of 2 inillf rem.

A total of 30 group tours, consisting of.456 individuals, visited the Center during the reporting period. As determitied by digital pocket dosimeter and an exposure ret.orded,-the average grour exposure was <0.1 millirem with a maximum of 0.1 millirem TABLE IV Average Quarterly Reactor and Experimenter Staff Exposure (in millirern)

Jul Aug Sep Oct-Nov Dec Jan reb Mar Apr Hay Jun I 7.5 12.5 11.4 4.2 I June's film bad;e results not available from the vendor at the time this report was prepared.

11.- Reactor Eacility Radiation and Contamination Levels The g utine aren radiation surveys of the buildinc in non reactor vital areas had an average doso level of 0.02 mR/llr., while routinely. accessible

- reactor vital areas had an average dose level of 0.22 mR/Hr. The highest averago dose level in a routinely.ancessible reactor vital area was 1.17 mR/llr., which occurred in Room 201, North pool Room. The lowest average dove in a routinely. accessible reactor vital area was- 0.02 mR/llr. , which occurred--in Room 201A, the Reactor-Shop area. The average dose in-the

' Reactor Control Room was 0.04 mR/llr. The avorage dose in the radiochemistry sample hoods was 0.05 mR/llr. The highest average on site dose IcVel was 82 mR/llr. which occurred in Room 2A, Cave Room, which is a L locked storage area where radioactive material and radioactive sources are stored.

1 y rv,e-w~p-- q ,._w_wy-_,y-qq. ,y,. ,y_..p _,_,,,,._,,p7_.i,__,yAyyw_,..,_,..,p.py.,,_,..g.,9 ,,._e a,,p 9,,,pp.g.99,#,p9, -p a,y g,,,9 ,. gc ,--gw,y33pesq.w.,W y 9,99 1i e1

5 Routigebuildingsurveysforremovablecontaminatigninnonreactorvital areas had an average level of 1.8x10 6 uCi/

leyc1inthereactorvitalareasaas1,2x10*gD0cm,whigotheaverage uC1/100 m. The h average value in the reactor vital areas was 47.2x10'5 uC1/100cm{ chest which was found on the platform where experittenters stand to insert and withdraw

. their sarnples froin the Thglowsstaveragevalueinthereactor vitalareaswas1,1x10'geactor. uCi/100 cro which was in Room 201B, the Reactor Control Room floor. The average level radiochemistrysamplehoodswas3.2x10*gfremovablecontaminationinthe 2 uC1/100 cm .

1 A non reactor vital area is an area in the building where radioactive materints are used or stored but which is not a part of the Licensed reactor facility, 1._ Environmental Monitorine Progtg The environmental monitoring program uses thermoluminescent dosistoters-(TLD's) at locations both near and at distances around the reactor building facility. The quarterly exposures in the vicinity of the Nucionr Radiation Center are listed in Table V below. The average ambient gamma radiation levels for thia area (80 mile radius) is 65 mrem /yr, (178 uR/ day)'as-reported in the 27th Annual Report of the Environmental Radiation Program, Washington State Department of Social and Health Services.

The values observed indicate there is no significant effect on the environment radiation levels due to reactor operation, TABLE V Environmental Radiation Levels in the Vicinity of the Nuclear Radiation Center 1 (Exposure in uR/ day)

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr+May Jun 2 Median 190. 119 199 - 169 I

For samp]ing stations located 50 meters or greater from the Nuclear Radiation Center, 2 'Apr May Jun TLD data not available from TLD vendor- at the time this report was prepared.

_a _. . _ _ . __

t 6

Quarterly exposures at readily accessible locations at the reactor facility are listed in Table VI below. No significant. effect on the environmental radiation levels by reactor operation was noted.  !

TABLE VI Environmental- Radiation Levela Adjgeent to the Nuclear Radiation Conter (Exposure in uR/ day)

- i Location Jul Aug.Sep Oct.Nov.Dec Jan.Feb. Mar Apr.May.Jun2 Median s

S. Bldg. Entrance 220 190 234 -

216 E. Loading Dock- 187 179 -224 - 197 Pool Rm _ Vent Stack 176 83 179 -

146  ;

Building-W. Roof '198: -179 194 -

190 Rod.fStorage Shed 297 238 284 - - 271 Building N. Side 231 179 493 -

301 Beam Room W._ Door 242 179 194 -

205 i Building W. Sido- 242 214 224 .

228 Pool-Room W. Roof $27 429 582 .

513 i Pool Doom E. Roof 308 226 299 -

278 1

For sampling statiors located less'that 50 maters of the Nuclear Radiation Center.  ;

2

. Apr May Jun TLD data not_ available from TLD vendor at -tho timo this report-was prepared.

Technical Specifications ALARA offluent releases in 3.12(2) specify annual radiation exposures at the closest off site extended occupancy shall not, on nu' annual basis, exceed the average local of f site b u.kground radiation

- level by more than 20%. For the-1st three quartors of too reporting period. the average total .back 6 round radiation level for: sampling points

, 400 meters or greater from the facility was 163 uR/ day, while the average total ~ radiation level at the closest extended occupied area 380 meters away was 172 uR/ day. This yleids a ratio of.5.50%, indienting no significant exposuro level'above natural background.

(

i l'

i'7*h re-m p+ W '+> +M y e"-y" gp up-ryWWp -grq> g ayo"e1 GT *F"""-Y **t'9*F" "'***T'f)W9MY' * - 3 ' M  % **M-?*- '"' * * * * -F W" "N'* '+r-'-'4-:--?r-'ea e ayme s

  • er e awe'<TiFeigwe'W --' --- m a-im#2rs