Text

USGS Triga Reactor Annual Rept for 1994
	ML20078A645
Person / Time
Site:	U.S. Geological Survey
Issue date:	12/31/1994
From:	Timothy Debey; INTERIOR, DEPT. OF
To:	Collins S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	NUDOCS 9501250081
	Download: ML20078A645 (19)
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'O United States Department of the Interior t

GEOll)GICAL SURVEY liOX 25016 M.S. 974 DENVER FEDERAL, CENTER DENVER, COI.ORADO 80225 (N ki PI ) It b i t R 10 January 18, 1995 Mr. Sanuel collins Director, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Dr., Suite 400 Arlington, TX 76011

Dear Mr. Collins:

'Ihe attached annual r@ ort of the U.S. Geological Survey TRIGA reactor facility is subnitted in accortlance with license conditions.

'Ihe facilit? docket number is 50-274. '

Sin rely, 7- Timoth M. DeBay ne -

Reactor Supervisar l

Enclcsure Copy to:

Document Control Desk (2)

Mr. Blair Nicholas l USNRC 611 Ryan Plaza Dr Suite 400 Arlingten TX 76011 0 ' ,.00 00 j ;

9501250001 950118 p'I j i l PDR ADOCK 05000274 PDR l

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s U.S. GIDIOGICAL SURVEY TRIGA REACIOR ANNUAL Ruu<f JANUARY 1,1994 - DECH4BER 31,1994 NRC LICENSE 10. R-113 - DOCKET NO. 50-274 I. Personnel Chames me Reactor Health Physicist resigned in Mart:h and was tenporarily replaced by another staff person. A permanent, full time repla ment for the Reactor Health Physicist was hired in September. Se facility staff continues to be 4 full time employees (re tctor operators and health physicist).

II .- Occratim Experience

'Ihe Geological Survey TRIGA Reactor (GSIR) was in normal operation for the year 1994. No major facility changes were made during the year.

A total of 240 irradiation requests were pr - W during the year, with the average request representing 55 samples and 9 full-power hours of reactor operation. A synopsis of irradiations performed during the year is given below, listed by the organization subnittirg the samples to the reactor staff:

OruanizatiGD Number of Samples Geologic Division - Geochemistry 10,809 Geologic Division - Isotope Geology 1,344 Geologic Division - Cent. Mineral Res. 21 Geologic Division - W 4 m ntary Proc. 8 Non-USGS users 970 Total 13,152 A. Thermal power calibrations were performed in February and August, with minor adjustments required.

B. One new Class I experiment was approved during this period.

'Ihe Class I experiment involved the activation of a rock and mineral sanples. No new Class II experiments were approved during the year.

C. During the report period, 175 daily checklists and 12 monthly checklists were canpleted in cmpliance with technical specifications requirements for surveillance of '

the reactor facility.

D. Tours were provided to individuals and groups during the year for a total visitor count of approximately 205.

E. Six fuel movesnents were performed during 1994 for the purposes of increasing reactivity, performing experiments and the removal of a leaking element.

III. Tabulation of Enerav Generated Megawatt Time Reactor Number of Month Hours Was Critical Pulses January 107.679 109 hours0.00126 days 0.0303 hours 1.802249e-4 weeks 4.14745e-5 months 47 minutes 0 February 117.890 121 hours0.0014 days 0.0336 hours 2.000661e-4 weeks 4.60405e-5 months 41 minutes O Mardi 163.100 166 hours0.00192 days 0.0461 hours 2.744709e-4 weeks 6.3163e-5 months 19 minutes O April 80.479 88 hours0.00102 days 0.0244 hours 1.455026e-4 weeks 3.3484e-5 months 20 minutes 0 l 75.500 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months 19 minutes May 0 June 120.850 122 hours0.00141 days 0.0339 hours 2.017196e-4 weeks 4.6421e-5 months 3 minutes 0 July 54.009 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months 16 minutes 0 August 74.641 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months 36 minutes 0 September 105.413 107 hours0.00124 days 0.0297 hours 1.76918e-4 weeks 4.07135e-5 months 29 minutes 0 October 80.567 81 hours9.375e-4 days 0.0225 hours 1.339286e-4 weeks 3.08205e-5 months 34 minutes 0 November 82.295 83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months 56 minutes 0 l C+M -r 132.250 D3 hours 1 minute D l Totals 1194.673 1228 hours0.0142 days 0.341 hours 0.00203 weeks 4.67254e-4 months 21 minutes 0 IV. Unscheduled Shutdown 1 Serial No. DgLtg Cause 580 1/20 CSC watchdog scram due to cattputer lockup. i 581 1/20 CSC watchdog scram due to cotiputer lockup.

582 2/1 NM1000 data error scram.

583 2/1 NM1000 data error scram.

584 2/1 NM1000 data error scram. ;

585 2/1 NM1000 data error scram.

586 2/8 CSC watchdog scram due to cotiputer lockup.

587 2/11 CSC watchdog scram due to ocmputer lockup.

588 2/23 CSC watchdog scram due to catputer lockup.

589 2/24 CSC watdidog scram due to cartputer lockup. !

590 3/8 CSC watchdog scram due to costputer lockup.

591 3/17 CSC watchdog scram due to camputer lockup.

592 3/23 CSC watchdog scram due to cattputer lockup. >

593 3/31 CSC watchdog scram due to ocmpiter lockup.

594 4/29 CSC watchdog scram due to cattpucer lockup.

595 5/4 CSC watchdog scram due to ocmputer lockup.

596 5/17 NPP 1000 rcram.

597 5/18 CSC watchdog scram due to cattputer lockup.

598 5/26 CSC watchdog scram due to caimputer lockup.

599 6/14 CSC watchdog scram due to computer lockup.

600 6/15 CSC watchdog scram due to cutputer lockup.

601 6/21 CSC watchdog scram due to costputer lockup.

602 6/23 CSC watchdog scram due to cortputer lockup.

603 6/29 CSC watchdog scram due to cattputer lockup.

604 6/29 CSC watchdog scram due to castputer lockup.

605 7/27 CSC watchdog scram due to computer lockup.

606 8/8 CSC watchdog scram due to cartputer lockup.

607 8/8 CSC watchdog scram due to computer lockup.

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I 608 8/10 CSC watchdog scram due to computer lockup. '

609 8/10 CSC watchdog scram due to ocmputer lockup.

610 8/16 CSC watchdog scram due to ocmputer lockup.

611 8/24 CSC watchdog scram due to computer lockup. ;

612 9/19 CSC watchdog scram due to ocmputer lockup. t 613 9/26 CSC watchdog scram due to ocmputer lockup. ;

614 9/28 CSC watchdog scram due to conputer lockup. l 615 9/29 CSC watchdog scram due to conputer lockup.

616 9/30 CSC watchdog scram due to ocmputer lockup.

617 10/12 CSC watchdog scram due to couputer lockup. i 618 10/12 DataM e timeout scram '

619 10/12 DataM= timeout scram 620 10/12 Datab w timeout scram 621 10/13 DataM w timeout scram 622 10/13 Data M m timeout scram 623 10/13 Database timeout scram i 624 10/13 Database timeout scram 625 10/14 DataM= timeout scram 626 10/19 !M1000 data error scram 627 10/19 CSC watchdog scram due to conputer lockup.

628 10/28 CSC watchdog scram due to ccmputer lockup.

629 11/1 CSC watchdog scram due to coup 2ter lockup.

630 11/8 CSC watchdog scram due to corputer lockup.

631 11/9 CSC watchdog scram due to ocmputer lockup.

632 11/22 CSC watchdog scram due to canputer lockup.

633 11/29 CSC watchdog scram due to conputer lockup.

634 11/30 CSC watchdog scram due to ccmputer lockup.

635 12/2 CSC watchdog scram due to canputer lockup. ,

636 12/6 CSC watchdog scram due to cxmputer lockup, 637 12/7 CSC watchdog scram due to ocmputer lockup.

638 12/7 CSC watchdog scram due to ocmputer lockup.

639 12/8 CSC watchdog scram due to cxmputer lockup.

640 12/8 CSC watchdog scram due to computer lockup. I 641 12/14 CSC watchdog scram due to ocuputer lockup. ,

642 12/15 CSC watchdog scram due to conputer lockup. !

643 12/15 CSC watchdog scram due to cxmputer lockup.

t V. Maior Maintenance Operations e

An instnmented fuel element developed a cladding leak on 1/4/94 and was located and removed from the core on 1/5/94. A total release of fission product gases was estimated to be 259 microcuries for this event. '

A separate report detailing the event was sent to the NRC in January, ..

1994. Other less significant activities included the troubleshooting and replacement of several items in the digital control system and replacement of the ion exchange resin in May.

VI. Summary of 10 CFR 50.59 chances ;

'Ihere were no 50.59 charges at the facility during this report period.

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VII. Radioactivity Releases A. Listed below are the total amounts of radioactive gaseous effluents released to the environs beyond the effective control of the reactor facility.

License (R-113) 10 CFR 20 Argon-41 Allowable Tritium (HIO) Allowable Month (Curies) (Curies) (mouries) (mCuries)

January 0.625 5.8 0.133 250 February 0.673 5.8 0.162 250 March 0.828 5.8 0.208 250 April 0.345 5.8 0.159 250 May 0.193 5.8 0.155 250 June 0.359 5.8 0.162 250 July O.326 5.8 0.179 250 August 0.505 5.8 0.175 250 September 0.592 5.8 0.191 250 October 0.729 5.8 0.204 250 November 0.449 5.8 '

0.184 250 Os m nhar 0.S4S 5.8 O.209 25Q_

'Ibtal 6.472 70.0 2.121 3000

% of allowable limits: 9.25% .071%

Note: h tritium unaud.4.ations are estimates based on the amount of water lost by evaporation from the reactor multiplied by the concentration of tritium as HIO. Tritium sanple analyses are being performed by Colorado State University.

B. No low level solid waste or solidified resin was shipped for burial in Washington state during the year and no contaminated water was discharged to the sewer systen.

Note: h principal radioactive waste generated at the reactor facility is the demineralizer resin - used resin with small quantities of rinse water was solidified in 55-gallon drums.

VIII. Radiation Monitorim A. Our program to monitor and control radiation exposures included the four major elements below during the operatirg year.

1. Eighteen ganna-sensitive area nonitors are located throughout the Nuclear Science Building. A remote readout panel is located in the reactor health physics office. High alarm set points range frca 2 mR/hr to 50 mR/hr. High level alarms are infrequent and due to sanple movements.

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2.AContinuousAirMonitor(CAM)sanplestheairintherpctor An equilibrium particulate vust- h ation of about 1 x 10- uC1/ml present for two minutes will result in an increase of 500 cpn above background. % ere are two alarm setpoints. A low-level alarm is set at ,

3000 gan and the high level alarm is set at 10000 cpn.

Reactor bay air is sanpled during all reactor operations. S e fixed particulate air filter is changed each week and counted on a HPGe multidiannel analyzer counting systen. S e charcoal filter, fitted behind the air filter, is also changed and counted weekly. In all instances, filter analyses showed that no reactor r uduced isotopes were present on l the filters.

3. Contamination wipe surveys and radiation surveys with portable survey instruments are performed at least once a month. All portable instruments are calibrated with a 3-Curie (initial activity) Cs-137 source traceable to NBS and wipes are counted on a Ganna Products G4020 low level counting system.

Wirty contaminated areas were noted within the facility during ,

rapinewipesurveys. Beta activities ranging from 30 to 1219 pC1/100 on were noted. Soap and water were used to remove this contamination.

S e roof area over the reactor tank is raped off and posted as a radiation area (averaging 2.5 mR/hr) during 1 W operations. l

4. Personnel, X and ganna, beta and neutron dosimeters are assigned I to all permanent m = nts of the Nuclear Science Building. CaSO4:Dy and LiF dosimeters have been used at six outdoor environmental stations.

Reactor facility visitors are issued self-reading dosimeters. Reactor staff pumael are issued alharb neutron badges.

Pamuel monitoring results are categorized below:

Rem Deep Dose Shallow Dose Neutron Dose -

B:ruivalent Ibuivalent Eaulvalent Reactor Staff Whole Body Cumulative Dose for Calendar Year (throuch 11-30-94)

Highest 0.073 0.073 0.000 Hands Cumulative Shallow Dose for Calendar Year Highest 0.106 i

Reactor Experimenters Whole Body Cumulative Dose for Calendar Year Highest 0 0 0 Hands Cumulative Dose for Calervhr Yeg Highest 0.129 Reactor Visitors and Occasional Exper b nters No individual reading was greater than 4 mrem.

i st through November g: Personnel dosimetry results are for January 1 30 . W e results for C+ w 4 r have not yet been received.

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t Envirumuud.al Statiggi - TLD Monitorirn Results Incation BAD Exhaust Stack O.1317 1 West Gate (Rm 149) 0.0399 l Ioading Dock Gate (Rm 151) 0.0989 Fence (by Cooling Tower) 0.0205 Southwest Light Pole 0.0109 Southeast Light Pole 0.0018 i

- Control (background) 0.1247 Note: Above totals have the background subtracted (see Control) .

IX. Enviiumm.ntal Monitorim Pursuant to GSTR su siures, on and off-site soil and water sanples are collected and analyzed on a biennial basis. Envisum=ntal soil and water sanples were collected in 1994. 'Ihe attached map gives the locatiors of the soil sanples taken on the Denver Federal Center. Subsequent lists are attached that give the locations of offsite soil sanples, and water sanples that were collected at various nearby locations. 'Ibe analyses ,

results for the sanples are in the final attachment. All sanple activity !

u.imd_ cations are of the same relative magnitude as those of previous sanples.

'Ibere have been no uncontrolled radioactivity releases frm the reactor to the present date. 'Ihus, the data on file from past years to the present are considered to be background infonnation.

OFFSITE SOIL SAMPLf4 Sample Number Location OS-1 Glennon Heights School, West Virginia and Pierson streets. About 10 feet east of north entrance gate.

05-2 Divinney Elementary School, South Welch Circle and South Wright streets. About 30 feet north of incenerator inside of fenced area.

OS-3 West Florida and South Kindall streets, at northwest corner near base of street light.

OS-4 Ninth and Quitman streets at base of street light.

OS-5 Sloans Lake, 50 feet north of Recreation Center building.

OS-6 Jefferson County Park at 33rd and Fenton, on softball diamond, 3rd base line at edge of grass.

OS-7 Jefferson Avenue Methodist Church, 44th and Kipling streets, under sign in front of building.

OS-8 Carl G. Morse Park, 20th and Allison streets, on softball diamond, at home plate.

OS-9 Moffat Water Treatment Plant on 20th Avenue, west side of entrance gate.

OS-10 Lakewood Country Club at 10th and Pierce streets, approximately 20 feet inside.of ncrth gate. ;

OS-11 Washington Heights School at West 1st Avenue and Lamar streets, at baseball field, first base.

05-12 Alameda Park at Harlan and Jefferson Place, north baseball field, in back of baseball field backstop.

OS-13 East side of Kipling across from gate 1 of the Federal Center, between east side of street and the athletic field.

ALL WATER SAMPLES (1 liter volume)

W-1 At pedestrian bridge crossing the stream at 3rd and Center Avenue on Federal Center.

W-2 At the " duck pond", east side of Federal Center, on the west side of the pond.

W-3 Ward Reservoir No.1, at the north end, at the boat ramp.

W-4 Sloans Lake, south side.

W-5 Clear Creek at the Youngfield Street bridge.

W-6 Kendrick Reservoir, at the east side. i 1

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Sample 05-1 Nuclide Cone. ( pCi/g)* t i .96 y Cs-134 -0 01 0 05 Cs-137 0 07 0.05 111-232 0 31 0.19 Co-60 -0 01 0.04 Ra-226 0.72 0.10 l'c.5 9 0 08 0. I S N I .1-54 0 02 0.05 Zr 45 -0.06 0.10 mg K-40.'g 16 1.2 l U-238 2.5 2.5 l Sample 05-2 Nuclide Conc. (pCi gf 21.96 l

t's-13 4 -0019 0.O N Cs-137 0 085 0.046 Th-232 0 84 0.16 Co-(0 0.027 0 037 Ra-220 0 37 0 074 Fe49 0 15 0.17 Mn-54 0.010 0 039 Zr-95 0.056 0 085 mg K-40.'g i4 0.93 U-238 l.3 2.2 Sample 05-3 Nuclide Conc. 'pCi/g F *l.96 Cs-134 0.023 0 036 Csd37 0 12 0.041 Th 212 0 ~7 0 14 Co-(>0 -0.0049 0.034 Ra-226 0.61 0.072 Fe-50 -0034 0.069 Mn-54 -0.0063 0.030 Zr 45 0 071 0.14 mg K-40'g 15 0.84 U-238 0.94 1.9 f 1

All concentration, are exprewed in pCi g, escept that of K40, which is expressed m mg K40/g 1

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Sample OS-4 Nuclide Cone. (pCi/gF :1.06 Cs-134 0 015 0.042 Cs-137 0 062 0 046 Th-232 0.75 0.16 Co-60 -0017 0.037 Ra-226 0.77 l 0088 Fe-59 -o087 l 0.083 Mn-54 0.016 l 0.042 Zr 05 0 039 l 0.16 mg K-40.g 16 l 0.97 U-238 3.* l 2.2 Sample 05-5 Nuclide Cone. pCL g)* 1.96 Cs.I34 -0.0074 0.036 Cs-l 37 0.16 0.041 Th-232 1.1 0 15 Co-60 0.020 0.03i Ra-226 0.64 0.075 Fe-59 0.062 0. I 4

\ln-54 -0.017 0.031 Zr-95 0.13 0.15 mg K-40.'g 14 0.79 U-238 2.0 1.9 l Sample 05-6

. Nuclide Con . t pCi gf l t 1.96 Cs-134 -0.016 0.038 Cs-137 0 071 0.044 Th-232 1.1 0.16 Co-no 0.0086 0.038 Ra-226 0 53 0 076 Fe-59 -0 051 0.077 Nln-54 -0019 0 034 Zr 95 -o0047 0.001 mg K-40 g 20 2.0 U-238 0 44 2.0

All concentrations are espiessed in pCi g, except that of K-40. whah is espressed in mg K 40Jg ;

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Sample OS 7 Nuclide Conc. (pCi/g)' I,96 Cs-134 -0.0037 0.036 Cs-13 7 0.38 0.046 Th 232 1.6 0.15 Co-60 0 0085 0.03I Ra-226 1.1 0.079 l re-59 -00096 0.066 Mn-54 0 021 0.036 ;

Zr45 -0018 0.084 l mg K-4Tg 14 0.72 l Lf-238 0.17 1.8 l Sample OS-8 Nuclide Conc. ( pCi 'g >* *l.96 Cs134 0.030 0.04i Cs- 37 0 000 0.045 l Th- 232 032 0. I $

Co-60 -0.0011 0.035 Ra-226 0.60 0.082 Fe-59 -0016 0.082 Mn-54 -0012 0.035 Zraf -o 036 0.086 mg K-40'g 17 0.96 U-23 3 2.5 2.0 Sample USA Nuclide Conc. pCi/g)* *l 96 C3-i'4 0.025 0.041 Cs-137 0.18 0.048 Th-232 0.~7 0.16 Co 60 81020 0 037 j.

Ra-225 02 0.089 l

Fe-50 4 017 0.080 l

Mn-54 0 010 0.039 l Zr-95 0.088 0.17 l mg K-40'g 14 0.91 U-238 1.2 2.2

All concentrations are espressed in pG'g except that of K-40. which is expres. sed in mg K-40<g

Sample 0510 Nuclide Conc. i pCi/g)* i t .96 Cs-134 0.0082 0.045 Cs-137 0 20 0.053 Th-232 0.90 0.18 Co-60 -0034 0.040 Ra-226 0.73 0.094 Fe-59 0.0046 0.23 Nln-54 -0.034 0.038 Zr-95 -0.00072 0.099 mg K-40 g 16 1.0 l U-238 - 1. 4 2.3 l Sample 05-11 Nuclide Conc. (pCi g>* *l.06 Cs-134 0.024 0.042 Cs.I 37 0.29 0.05:

Th 232 1.2 0. I 7 Co-60 0.0022 0.040 Ra-226 0 83 0.085 Fe-50 -0033 0.079 NIn-(4 0 0062 0.040 Zr 05 -0027 0 090 l mg K-40!g 17 0,92 IJ-238 0 19 2.1 i Sample 05-12 Nuclide Conc. . pCUg >* l i t .06 l C3-13 4 -0ya8 0.046 Cs-137 0 35 0.063 !

l Th-232 1.0 0.19 l 4

Co-60 0 078 0.044 ,

1 Ra-226 0 80 0.098 Fe-59 -o070 0 086 N!n-54 0 012 0 051 Zr 05 0.14 0.21 mg K-40:g 15 1.0 U-238 2.7 2.5 l 1

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All concentrations are espressed in pCiJg. except that of K 40, which is espicssed in mg K-40 g I

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Sample OS-13 Nuclide Cone. l pC!/gf 21 %

Cs-l 34 0.017 0.029 Cs-137 0 17 0.033 Th 232 1.1 0,11 Co-60 -0.00h 1 0.026 ila-226 0.79 0 060 F e-50 -0u073 0.052 N!n-54 0 020 0.029

e. /_r 05 0 00fd 0 12 nig K-40'g 16 0 61 U-238 1.~ 1.4 Sample ON-1 Nuclide Cone. i pCi'gf il .96 Cs-l34 -0uo12 0,017 Cs. I 37 0 11 0 020 l

0h-232 0.87 0.069

('o-60 -00012 0.016 l

Ra-226 .) 67 0 037 Fe-59 0.00090 0.05I Nln-54 0 016 0 017 Zr 95 0.026 0.052 mg K-40/g 15 0.41 U-238 I6 0.92 Sample ON-2 l .

1 Nuclide Cone. : pCPgf 1.96 l Cs.134 000071 0 030 l l

Cs-137 0.12 0.036 Th-232 0 S6 0.12 Co-60 -00021 0.027 Ra-226 0 70 0.064 Fe-50 -0061 0 053 Nln-54 0.0074 0 029 Zr 05 -0 00041 0 06n mg K-40.'g I5 0.70 i U-238 0.73 1.6

All wncentr.itnun are esprewed in pCi/g, except : hat of K 40. which is espressed in mg K-40 g.

Sample ON-3 Nuclide Cone. t pCi g F 21.96 Cs-134 0 014 0.011 Cs-137 0 053 0.012 Th-232 1.1 0.045 Co-60 -0.00017 0.0095 Ra-226 0.71 0,023 Fe-59 -0.0093 0.020 Nfn-54 -0.010 0 0097 Zr-95 -0.026 0025 mg K-40/g 13 0.23 U-238 1.1 0 55 5 ample ON-4 Nuclide Conc. ipCi g)* 21.96 Cs-134 0 0054 0 044 l Cs-137 0.084 0.04' l Th 232 1.0 0.18 Co-60 -0020 0 039 Ra-226 0.62 0.090 Fe-59 0.034 0. I 3 Nln-54 -00019 0.037 Zr 05 0.046 0.13 mg K-40/g 12 0.00 U-238 1.6 2.3 Sampic ON-5 Nuclide Conc. IpCiig F : ' .06 Cs-134 0 036 0 17 Cs-137 0.14 5043 Th-32 0.77 0 14 Co-60 0 033 0.035 Ra-226 0 56 0 072 Fe.59 0.0098 0.12

.Nin-5 4 -0 0066 0.032 Zr 05 0 062 0 l1 mg K-40/g 14 0 84 U-238 1.8 1.8

All concentrations are espressal m pCrg, cuert that of K.40. which is espressed in mg K 40'g l

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Sample ON-6 Nuclide Cone. (pCi/gf *l.96 ,I Cs-134 0.020 0.028 j Cs-137 0.11 0.034 Th-232 0 86 0.11 Co-60 -0.017 0.026 Ra-226 0.53 0.059 Fe-59 0.018 0.093 ,

Mn 54 0.024 0.028 l

Zr OS -0.0096 0.064 ;

mg K-40/g 15 0 67 ;

U-238 1.3 1.5 t

Sampie UN-7 Nuclide Conc. (pCilg)* *l.96 Cs-134 -0.023 0.037 ,

Cs-137 0.087 0.042 Th 232 0.90 0.15 Co-60 -0.013 0.036 ,

Ra-226 0.54 0.076 0 074 0.13 !

Fe-59 Mn54 -0 0046 0.035 [

Zr 05 0 013 0.12 mg K-40*g 19 0.97 7 U-238 l 1.2 2.0 i

I i

Sampie O.%8 j Nuclide l Canc. (pCUg)* *l.96 C:,-l34 0 0l6 0.(24 0 Cs-137 0.13 0.046 i Th-232 0.89 0 16 !-

Co-60 -0.032 0.036 Ra-226 0.62 0.081 Fe-59 0.040 0.13 Mn-54 0 023 0 039 Zr 95 0.073 0.13 mg K-40/g 15 0.95 U-238 -0.92 2.0 r

All wncentrations are espressed in pCi'g. escept that of K 40. whwh is espressed in mg K-40lg

- _ . . , . . , , _ _ , , , ,_y.. , , _ - _ _

Sample ON-9 Nuclide Conc. I pCi/g)* *1.96 Cs-134 0.017 0.039 Cs-137 0.22 0.048 Th-232 0.84 0.15 Co-60 0.013 0.039 Ra-226 0.67 0.083 Fe-59 0 082 0.14 Mn <4 -0.0058 0.034 Zr of -0053 0.086 mg K-40'g 15 0.90 U-238 0.072 2.1 Sample O.%10 Nuclide Conc. q pCi/g)* 1.96 Cs-134 -0.0039 0.034 C.,- l 3 7 0.19 0.043 Th-232 1.0 0.15 Co-60 -0.032 0 033 Ra-226 0 61 0 075 Fe-59 0 031 0 14 M n-5 4 -0.0065 0.033 ZrA5 -0.0097 0.081 mg K 10'g 15 0.82 U-238 -0.0078 1.9 Sample ON-11 Nuclide Conc. (pCi/g)* il .96 Cs- 124 0 0078 0 045 Cs-137 0.40 0.063 Th 232 1.2 0.19

('a-60 0.019 0.042 Ra-226 0.75 0.096 Fe-59 0 098 0.16 Nln-f 4 0 0012 0 043 Zr of -0.062 0 10 mg K-40 g 16 1.0 U-238 0 066 2.3

Til wneentranons are espressed in pCi'g. cscert that of K-40. whkh k expressed m mg K-40.'g.

r Sample ON-12 Nuclide Conc. (pCi/g)* *l.96 Cs-134 -0.013 0 035 Cs-137 0.14 0.041 Tlw232 0.83 0.014 Co-60 0.013 0.035 Ra-226 0.60 0.073 Fe-50 0.033 0. I 4 Nln-54 -0023 0.031 ,

Zr-95 -0 020 0.081 mg K-40.'g 17 0.88 U-23 8 2.8 1.9

{

Sample ON-13 Nuclide Conc. (pCi/g)* 11.96 Cs-l 3 4 -0.011 0.040 Cs-137 0 25 0.052 Th 232 0 86 0.16 Co-60 0.0076 0.043 Ra-226 0.61 0.084 Fe-59 0.15 0.15 Mn-54 0.033 0.039 Zr 05 -0.011 0.090 mg K-40'g 18 1.0 U-238 0.43 2.0 Sample ON-14 Nuelide Conc. (pCi.'g)* *l.96 Cs-134 0 010 0.041 Cs-137 0.29 0 054 Th-212 0.75 0.16 Co-60 -00092 0.038 Ra 226 0.65 0.085 Fe-59 0 061 0.16 Mn-54 -00067 0.037 Zr 95 0 086 0.14 mg K-40 g 16 1.0 U-238 1.6 2.1

All concentrations are espressed in pCig. escept that of K 40. whkh is espressed in mg K-40>g

r BARRINGER LABORATORIES INC 15000 # STH AVE., SUITE 300 GOLDEN, CO 80401 (303) 2'7 1687 FAX (303) 2771689 page:

Job:

"*n a 942724E Status: Final UNITED STATES GEOLOGICAL SURVEY Analyte: Gross Alpha Project:

Fraction: Total Date Analyzed: 09/16-09/19 Methed: 900.0 LLD: 2 Units: pCi/1 Date Lab Id Sampled Matrix Sample Id Concentration + 2a LLD 942724-1 5-Aug-94 Water Water Samples W-1 1. Stl .10 Au 2 942724-2 5-Aug-94 Water Water Samples W-2 1014 2 942724-3 5-Aug-94 Water Wa*.er Samples W-3 0.911.7 C, 2 942724-4 5-Aug-94 Water Water Samples W-4 8.5 3.4 2 942724-5 5-Aug-94 Water Water Samples W-5 1414 ,

2 942724-6 5-Aug-94 Water Water Samples W-6 0.0 1.9 - N 2 Analyte: Gross Beta Project:

Fraction: Total Date Analyzed: 09/16-09/20 Method: 900.0 LLD: 4 Units: pCi/l Date Lab Id Samoled Matrix Sample Id Concentration + 2a LLD 942724-1 5-Aug-94 Water Water Samples W-1 2.2 1. 6 4 - * '- 4 942724-2 5-Aug-94 Water Water Samples W-2 6.8t2.4 4 942724-3 5-Aug-94 Water Water Samples W-3 4.0 1.8 4 942724-4 5-Aug-94 Water Water Samples W-4 8.1 2.2 4 942724-5 5-Aug-94 Water Water Samples W-5 19 3 4 942724-6 5-Aug-94 Water Water Samples W-6 3.5 1.8 'M 4 l

l l

i

. r\ i!ai, a! C'ullenen O' \ Changine '.t ar!<l j

ML20078A645

Text

Dear Mr. Collins:

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