ML20127N448

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USGS Triga Reactor Annual Rept for Jan-Dec 1992
ML20127N448
Person / Time
Site: U.S. Geological Survey
Issue date: 12/31/1992
From: Timothy Debey
INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
To: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 9301290201
Download: ML20127N448 (18)
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January 21,fl993 Mr. L.J. Callan Director, DRSS, Region IV. "

U.S. Nuclear Regulatory Conunission 611-Ryan Plaza Drive, Suite 400

-Ar1Ington, TX 76011

Dear Mr. Callan:

The attached annual report of the U.S. Geological Survey TRIGA- reactor facility is cubmitted in accordance with license conditions. The ,

facility docket number is 50-274.

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S i nce re ly ,

Reactor Supervisor }

f Enclosure Copy to:

Document Control Desk:(2)

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, 9301290201.921231 t-PDR- ADOCK 05000274 R. PDR-

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- . U.S. GEDIOGICAL SURVEY 1RIGA RFACIOR

-ANNUAL REPORP JANUARY 1,1992 - DECEMBER 31, 1992 NRC LICDISE 10. R-113 - DOCKET NO. 50-274 I. Administrative Chames Dr. Carl Hedge assumed the position of Reactor Administrator in October, 1992. This change ocx:urred because the reactor project was administratively transferred from the Branch of Geochemistry to the Branch of Isotope Geology. Dr. HMge is the chief of the Branch of Isotope "cology.

II. Operatirn Dmerience -

The Geological Survey TRIGA Reactor (GSTR) was in nontal operation for the year 1992. No major facility changes were made dur h3 the year.

A total of 267 irradiation requests were processed durirg the year, with the average request representing 57 samples and 11.3 full-pwer hours of reactor operation. A synopsis of irradiations perfoned during the year is given below, listed by the organization subnitting the samples to the reactor staff:

Oruanization Number of'Samnles-Geologic Division - Geochemistry 11,352 Geologic Division - Isotope Geology 3,301 Geologic Division - Cent. Mineral Res. 1 Geologic Division - Sedimentary Proc. 7 Non-USGS users 589 Tbtal 15,250 A. Thermal power calibrations were perfonmd in February aM August, with minor adjustments required.

B. 7ko new Class I experiments were approved during this period.

The Class I experiments involved the activation of a bromine tracer compouM and routine argon age-dating experiments. No new Class II experiments were approved during the year.

C. During the report period, 208 daily checklists and 12 monthly checklists were completed in compliance 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 150.

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. . E. Fivo-stardard fuel c1cmanta from the Michigan Stato reactor were installed in the coro during the yasr. Four of thcae replaced high-turnup elements ard the fifth replaced a leakiry instnmental element in the G-ring. A total reactivity gain of about S.50 was achiewx1. In Doocmber, all fuel elements woro inspectal ard fourd to be within the tolerances specified in the -

Technical Specifications.

III. Inh 11ation of ihmv Gemrataj Mogavatt Timo Reactor Number of MQDib _liQurg_ Has critical , Pulnes-January 105.129 107 houro 36 minutea 0 February 120.832 -125 hours 47 minutes 0-March 170.323 174 hours0.00201 days <br />0.0483 hours <br />2.876984e-4 weeks <br />6.6207e-5 months <br /> 59 minutes 0 April 131.048 134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br /> 50 minutes O May 136.167 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> 10 minutca 0 June 122.278 128 houra O minutes 0 July 122.100 123 hours0.00142 days <br />0.0342 hours <br />2.03373e-4 weeks <br />4.68015e-5 months <br /> 34 minutes 0-August 121.892 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> 42 minutos O September 80.193 88 houra 38 minutos 0 October 128.114 129 hourn 46 minutea 0 November 92.658 94-hours 48 minutes 0 December 64 dd5 74 hQura 45 minuten D

'Ibtala 1395.280 1452 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.52486e-4 months <br /> 35 minutes 0 IV. DIEhLMal Shutdgwns SctinLlia Dato snuac 491 1/7/92 Scram due to loss of AC per.

492 1/9/92 CSC watchdog scram due to coq uter lockup.

493 1/10/92 CSC watddog scram due to computer lockup.

494 1/30/92 CSC watddog scram due to computer lockup.

495 2/10/92 CSC watchdog scram due to computer . lockup.

496 2/24/92 CSC watddog scram due to comp 2ter lockup.

497 2/27/92 Manual scram due to building evacuation alarm.

l- 498 3/12/92 CSC watchdog scram due to cotiputar lockup.

l 499 3/25/92 CSC watchdog scram due to. computer lockup.-

l 500 4/21/92 CSC watddog scram due to computer lockmp.

501 4/28/92 CSC watchdog scram due to computer lockup.

502 4/29/92 CSC vatddog scram due to computer lockup.

503 5/15/92 CSC watchdog scram due to ocmputer-lockup.

504 5/19/92 CSC watchdcg scram due to computer lockup.

505 5/19/92 CSC watchdog scram due to commter lockup.

506 6/16/92 CSC watchdog rcram due to computer -lociaap.

507 6/23/92 CSC watchdog ceram duc to computer lockup.

l_

508 6/24/92 CSC watchdog scram due to coquter lockup.

l .509 7/1/92 CSC watchdog ceram due to computer lockup.

510 7/13/92 CSC watchdog scram due to computer lockup.

511 7/14/92 CSC watchdog scram due to compiter lockup.

512 7/16/92 NJP1000 hi power scram due to noine opike.

l 513 7/22/92 CSC watchdog scram due to coqmter lockup.

514 7/28/92 CSC watchdog scram due to computer lockup.-

515 8/20/92 .CSC watchdog caram due to computer lockup.

2

- . 516 8/27/92 Manual scram due to loss of room underpressure.

517 10/20/92 CSC watchdog scram due to caputer lockup.

518 10/20/92 CSC watchdog scram due to canputer lockup.

519 10/21/92 CSC watchdog scram due to computer lockup.

520 10/22/92 CSC watchdog scram due to camputer lockup.

521 11/2/92 CSC watchdog scram due to computer loch p.

522 11/2/92 Scram due to loss of AC p]Wer.

523 11/3/92 CSC watchdog scram due to computer lockup.

524 11/10/92 CSC watchdog scram due to cmputer lockup.

525 11/12/92 CSC watchdog scram due to camputer lockup.

526 11/17/92 CSC watchdog scram due to camputer lockup.

527 11/17/92 CSC watchdog scram due to camputer lockup.

528 11/24/92 NPP hi power scram due to slow square wave response.

529 11/24/92 NPP hi power scram due to slow square wave response.

530 11/24/92 NP hi power scram due to slow square wave response.

531 11/30/92 CSC watchdog scram due to ccrnputer lockup.-

532 11/30/92 CSC watchdog scram due to computer lockup. =

533 12/1/92 Database timeout scram.

534 12/11/92 Database timeout scram.

535 12/14/92 CSC watchdog scram due_to computer lockup.-

536 12/29/92 Manual scram due to building fire alarm.

537 12/29/92 CSC watchdog scram due to computer lockup.

538 12/30/92 CSC watchdog scra- due to computer lockm.

V. Maior Maintenance Operations A leaking instrumented fuel element was detected in June, h is element had been in use since May, 1969. Data from the continuous air monitor and subsequent calculations give an estimated release of 54.6 microcuries of activity to the environment. W e release occurred over a 15 day period and no 10CFR20 limits were exceeded. Other less significant maintenarx:e itens include the replacement of a neutron detector mounting bracket and replacement of the exhaust fan motor, sheave, and belt. Ion exchange resin was replaced three times during the year, in January, June and December.

VI. Summary of 10 CFR 50.59 chames h ere was one 50.59 change approved at the facility during this report period. A new neutron detector mounting bracket design was evaluated by the safety committee and approved for use. Wie mountirg bracket is an improved.

design that greatly simplifies the nethod for adjusting the position of the in-pool neutron detectors. Although three new mounting brackets will eventually be installed, only one was installed during 1992. We safety comntittee evaluation of the change made under the provisions of 10CFR50.59 concluded that the new mounting bracket:

(1) does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report, ,

.(2) does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report, and, (3) does not reduce the margin of safety as defined in the basis for any technical specification.

3 I

i e O VII. IMisq$1vity Italmtm A. Listcd belcu are the total amounts of radioactive gaseous ef fluents released to the environs beyond the effective control of the reactor facility.

License (R-113) 10 CFTt 20 AITjon-41 A11cwable Tritium (Irlo) A11cuable liQIlth IGitiM1 __ lGILhsl JuCuries) __(QJr_irg1 Janual'f 0.75 5.8 249.8 0.25 Febntary 1.27 5.8 168.1 0.25 Mirch 1.35 5.8 347.5 0.25 April 1.36 5.8 224.8 0.25 May 0.92 5.8 469.4 0.25 June 0.80 5.8 499.7 0.25 July 0.81 5.8 186.2 0.25 August 0.67 5.8 236.2 0.25 September 0.56 5.8 279.4 0.25 October 0.60 5.8 367.9 0.25 November 0.75 5.8 268,0 0.25 December LIB  !!J 163.5 L2D

'Ibtal 10.29 70.0 3460.5 uCi 3.00

% of allowable 14.7% 0.12%

Noto #1: 'Ihe att3cn activities reported are integrated values obtained from the facility's gaseous stack monitor. Calculated values have bra subotituted for measured values in the few instances when the monitority m/ stem was dcun for maintenance or repair.

Noto #2: The tritium concentrations are estimates based on the amount of water lost by evaporation from the reactor multiplied by the concentration of tritium as 1r10. Tritium cample analyses are being performed by Colorado State University.

B. 340 liters of seepage water was pumped from the reactor tank annulusdugty1992. In November 0.945 microcuries in 170 liters was diluted to 5.9x10~ microcuries per milliliter. I 170litersofwaterwasdilutedto1.68x10~gDecember0.267microcuriesin microcuries per milliliter.

C. Four 55-gallon drum of low level solid waste and solidified resin were shipped for burial in Nevada during the year.

'Ihe total amunt of radioactive waste released frca the reactor facility -

during the year is catimated to be approxim toly 10 mC1.

Note: 'Ihe principal radioactive wasto generated at the reactor facility is the domineralizer resin - used resin with trull quantities of rinse water is solidifled in 55-gallon drums with Portland cement prior shipment.

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

VIII. Radiation Monitorim

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

1. Fifteen area monitors (14 gammas, 1 neutron) located throughout the Nuclear Science Buildirn. 1b provide a background signal, a small check source is attached to the scintillation detector. High alarm set points range from 2 mR/hr to 50 mR/hr. High level alarms have been intrequent and due to instrument mlfunctions.
2. One centinuous Air Monitor (CAM) syling the air in the r? actor bay. An equilibrium concentration of 3.0 x 10 uCi/ml present for two minutes will result in an increase of 400 cpm above background. There are two alarm set points. A low-level alarm is set at 3,000 cpn, and the high level alarm is set at 10,000 cyn.

Reactor bay air is sampled during all reactor operations, The fixed particulate C r filter is changed each day of reactor operation and counted on a Gamma Products G4020 Low level counting system. The charcoal filter, fitted behind the air filter, is changed and counted weekly. In all instances, final sample calculations show less than MPC (10 CFR Part 20, Appendix B, Table 11)  ;

concentrations for all isotopes in question in the reactor bay.

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 Cs-137 source traceable to NBS and wipes are counted on a Gamma Products G4020 1 m Level counting system.-

Fiveareasofcontaminationwerenoteddurjngroutinewipesurveys.

Beta activity rangirg from 86 pCi to 868 pC1/100 cm was noted on a table top. Contamination was removed with soap and water. The roof batch over the reactor bay continues to be roped off and posted as a radiation area (averaging 2.5 mR/hr) during routine 1 MN operations.

4. Personnel, X and gamma, beta and neutron film badges are assigned -

to all permnent ocx:upants of the Nuclear Science Building. CaSO dosimeters-have been used at four outdoor environmental stations.f;Dy Reactor facility visitors are issued L-49 self-reading dosimeters. Reactor. staff personnel are issued albedo neutron badges.

Personnel monitoring results are categorized below:

Rem Deep shallow Neutron Reactor Staff hhole Body Cumulative Dose for Calendar Year (thru 12-14-92)

Highest 0.165 0.165 0.000 1 I'

liands Cumulative Shallow Dose for Calendar Year Highest 0.000 0.200 0.000 5

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_g

- ,s

. .- Reactor Experimenters bhole Body Cumulative Dose for Calerdar Year Highest 0.000- 0.000 0.000 lbnds Cumulative Dose for Calendar Yter

-Highest 0.000- O.250 0.000

- Reactor Visitors and Occasional Dacringnteg} g No irdividual reading was greater than 6 mrem.

Dwironmental Stat 19De Ecm Exhaust Stack 0.2790 West 0.0116 Southwest 0.0000 Southeast 0.0000 Note: 'Ihc "WPSI'" badge is estimted for a one charrJe period.' A correction from our badge supplier wi.ll be forthoanting.

IX. Cnvironmental Monitorim Pursuant to reactor procedures, soil and water samples are collected every second year. Environmental soil and water samples were collected in 1992.

Results are attached

'Ihere have been no uncontrolled radioactivity releaw.s from the reactor to the present date. 'Ihus, the data on file from past years to the present are considered to be backgrourri information.

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/ NWRoWMhWAL NATER $/\/NPLES BARRINGER LABORATORIES,INC t6000 W 61H AVC , fiUITE 300 GOLDEN. CO B0401 (303)277 1607 F AX (303) 27716D9

!!ill Sm.4th Page: 1 U.S. GEOII)GICAL SURVEY Copyt 1 of 2 Mail Stop 424 Bldg. 15, Rm. 150 Denver Federal Conter Denver, CO 80225 Attn Bill Smith Rocolved 2-Sep-92 12:00 Project: PO #: 151010-92 Statunt Final dght 121896E -

Sample Typet Water Gross Alpha Error Grosa Beta Error Total Total i Samplo DCi/l 2g _ __.nQl/l 2a W-1 3.8 12.4 2.0 il.9 W-2 4.0 t2.8 5.0 i2.0 W-3 1.4 il.9 2.7 il.8 W-4 7.5 3.3 12 i2 W-5 2.3 d2.5 22 d3 W-7 1.1 12.2 3.5 il.9 Meeting The Analytical Challenges OfA Cha ning World

Radionuclide Concentrations in USGS SoilSamples O

X e

W V

l j

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e. Sainplc OS 1  ;

Nuclide Coac. (pCPg)' i1 W Cs.134 0.02 0.028-Ca 137 0.13 0.032 Th 232 1.2 0.1I Co40 41.0032 0.025 lla 226 0.87 0.060 I?c.59 4).019 0.056 Mn.54 4).(K134 0.025 Zr-95 41.015 0.063 I nig K 40/g 18.8 0.64 U.238 7.4 0.49 -

i Sample OS.2 Nuclide Conc. (PCUg)' i 1.W Cs 134 0.(KX)71 0.0S0 -

Cs137 0.038 0.082 Th 232 - 1.8 0.27 Co40 0.024 0.082 Ita.226 1.1 0.15 l'c.59 0.096 0.14 Mn 54 0.11 0.081 Zr.95 4).15 0.17 mg K 40/g 32.4 1.5 U 238 3.4 1.4 ,

P-N-Sampic OS-3 Nuclide Conc, (pCilg )' i1.%

Cs 134 -0.0013 0.017 t

Cs.137 0.28 0.021 Th 232 1.1 0.067 Co-60 OIX46 0.016 lla.226 0.70 0.035 l'c 59 - 011062 0.087 Mn 54 0.032 0.017 Zr 95 41.036 0.038 mg K-40/g 18- 0.40 U 238 5.7 0.30

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

e'

    • Sainple OS-4 Nuclide Conc. (pri'g)'
  • 1.9fus Ps.134 0.015 0.019 Cs.137 0.15 0.022

'llr232 .

0.95 0.074 Co4d) 0.(K128 0.018 11a.226 0.66 0.039 1 c.59 0.0025 0.086 Mn.54 0.013 0.019 ,

Zr-95 0.0056 0.NI eng K.40/g 15 0.42 U.238 5.9 0.33

_ . _ , ..-...-. . . . , _ . . _ .. .--. .._. . - .. . - . .._- . _ . .._-. . _ _ . - _ _ _ _ . _, -j Sarnple 0S.5 I Nuclide Conc. (pCi'g)' i 1.9(=r Cs 134 0.CXX)67 0.031 Cs.137 0.17 . ').034 Tli232 2.2 0.11 Co40 0.(X)95 0.032 ita 226 1.1 0.058 1 c.59 0.020 0.I6 Mn.54 0.0025 0.032 Zr 95 -0.(X157 0.066 ing K 40/g 33 0.60 U 238 4.9 0.57 Sainple OS.6 Nuclide Conc. (pC1'g)'

  • 1.9(=1 Cs.134 -0.024 0.071' Cs.137 0.026 0.080 Th-232 1.8 0.026 Co40 0.024 0.078 lla.226 1.0 0.14 1 c.59 0.073 0.14 Mn 54 0.059 0.071 Zr 95 - 41.092 0.16 rug K-40/g 38- 1.5

- U 238 3.8 1.4 t-g sp'kv r e- .3,y mer --nysp ,.-g- n e w-w-- apetp.+-yy--er gey, 9w--tp3,mq w mt- m -gg.am,*nMwN--Mg--1 g,-gtv---++yU- -

_>wrg +f FWe W* dT F 7 yv - wrNW Tr

Sample OS.7 Nuetide C4me. (pCi'g)*

  • 1.9(=1 Cs134 0.023 0.0(4 Cs-137 0.54 0,083 Th.232 2.0 0.26 Co44) 4).025 _ _ _

0.053 lla.226 1.2 0.13 l'c.59 41.026 0.11 Mn-54 41.(K)87 0.055 Zr 93 0.20 0.22 mg K40/g 18 1.2 U 238 9.8 1.2 Sampic OS.8  !

Nuclide Conc. (pCirg)' 11.96:

r Cs 134 0.00M) 0.016 Cs 137 0.080 0.017 Th 232 1.0 0.062 Co44) -0.014 0.014 11a-226 ON4 0.031 1'c 59 0.0091 0.056 Mn 54 41.0053 0.014 Zr 95 0.0l!I 0.053 mg K 40!g 16 0.35

)

U.238 60 0.28 Sample OS-9 Nuelide Cenc. (pCUg)*

  • 1.9(xi

+

Cs 134 0.025 0.048 C#137 0.0028 0.052

'Ih 232 2.1 0.18 Co-60 0.026 0.053 11a 226 0.70 0.085 Fe 59 0.080 0.23 Mn 54 0J040 0.048 Zr 95 41.049 ' O.11 mg K-40/g 37 1.0- >

- U 238- .

4.1 0.89

.f

Sample 0S.10 Nutlide Gme. (pCi's)'

  • 1.W Ca.134 0.0028 0.029 Cs.137 0.51 0.036

'th-232 1.9 0.10 Co40 0.034 0.011 Ita 226 1.1 0.053 l'c-59 41K47 0.053 Mn 54 0.0034 0.029 Zr 95 -0.031 0.062 ing K-40/g 37 0.58 U 238 5.7 0.54 Sample OS Il Nuclide Gme. (pCilg)* 11.%

C#134 0.0017 0.019 Cs.137 0.090 0.021

'th 232 1.1 0.073-Co44 0.015 0.017 11a.226 0.88 0.040 17e -5 9 0.014 0.099 Mn 54 -0.0070 0.016 Zr-95 0.025 0.087 ti.g K-40/g 15 0.40 U 238 6.0 0.34

- _ _ .. _ ... . _ a _ . . _ . . - _ . _ . _ _ _ . . _ , _ . . _ . _ _ . _ _ . -

. Sampic OS-12 Nuclide Cone. (pCi'g)' 11.% i Cs 134 0.0071 0.013 Cs-'s37 0.069 0.013

'th 232 1.3 0.051 i Co40 -0.0(00 0.012 Ita 226 0.67 0.024 1 c-59 4.012 0.024 Mn 54 -0.0045 0.011 Zr 95 0.025 OB44 ing K-40/g 21 0.30 -

l U 238 5.9 0.23

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

4

. i

". Sainple 0513 l

Nutlide Gme. (pC#g)' 11.9(=r Cs134 0.034 0.052 Cs137 0.12 0.056 Th 232 2.1 0.18 Cv4/1 0.019 0.055 ita 226 0.79 0.092 I?c-59 41.019 . 0.0&H Mn.51 -0.011 0.(M4  !

Zr.95 0.13 0.23 rng K-40!g 37 1.0 U-238 4.7 0.92 m_....-...m._- . _ . , _ . _ . - - . _ . - _ . ,

_4_.. . . ~ . _ - . . . . . .

i Sainplc ON.1 Nutlide Ome. (pCi/g)* 11.9(=r Cs-134 41.025 0.029 Cs 137 0.27 0.035 Th 232 1.6 0.11 Co44) 0.011 0.032 l Ita.226 0.097 0.056 l'c 59 0.N7 - 0.082 Mn 54 0.0075 0.029 Zr 95 4).059 0.063 rug K-40/g 33- 0.f4)

U.238 4.0 0.55 '

Sainple ON.2 [

Nuclide Cone. (pCUg)' i1.9(=r Cs 134 0.020 - 0.021 Cs 137 0.079 0.024-1h-232 1.1 0.081 Co44) 0.0091 0.019 ita 226 0.78 0.043 Fe 59 0.031 0.061 b

Mn 54 0.0040 0.020 Zr '95 0.031 0 060 rug K 40/g 18 - -1.1 U 238 6.4 0.36

, . . ~ _ . _ . _ . , . _ _ _ _ , , _ . _ _ _ . _ - _ _ _ _ . _ . _ ~ _ . c._.._.. _2...-.

Sample ON 3 Nuclide Cone. (PC i'g)* 11.W Cs.134 41.012 0.035 C5-137 1.1 0.066 Th.212 1.1 0.15 Codo 0.022 0.033 Ita.226 0.68 0.076 I:c.59 41.017 0.072 Mn.54 4).I069 0.034 Zr.95 0.(K49 0.16 mg K-40/g 15 0.81 U.238 7.0 OM

_w. .

Sample ON-4 Nuditic Conc. (pCi'g)* 11.W Ca 134 0.0020 0.032 C$.137 0.041 0.037 Th.232 1.7 0.12 Code 4).0010 0.035 lla 226 0.96 0.062 l'e-59 4).027 0.06i Mn.54 0.(X)31 0.034 Zr.95 4).(42 0.071 ing K-40!g 33 0.66 U 238 4.8 0.61 Sample ON 5 Nuclide Conc. (pCUg)' i t .W Cs.134 4).022 0.054 Cs-137 0.0M 0.062 Th 232 1.1 0.21 Co40 -0.0018 0.048 ita-226 0.77 0.I1 1:c.59 -0.058 0.11 Mn 54 4).021 0.049 Zr-95 0.024 0.24 1 mg K-40/g 15 1.2 U 238 6.5 0.94 M

. _ ~ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ . _ _ . . _ . _ _ _ _ _ . _ _ . - _ . . . .__

o' Sampic ON 6 l

Nuclide Cone. (pC#g)*

  • 1.9(=, l Ca 134 0.020 0.054 '

O 137 0.30 0.065 i i

Th 232 1.1 0.2 I .

Co40 0.044 0.047 ,

Ra-226 0.69 0.10 Fe 59 0.11 0.28 Mn-54 0 G41 0.053 h 95 0.N1 0.11 mg K 40/g 18 1.2 U 238 7.2 0.89 -

Sampic ON 7  ;

Nuclide Gine. (pCi'g)* i 1.9(=,

G 134 0.0080 0.031 0 137 0.10 0.033 Th 232 1.7 0.11 G340 0.022 0.034 ,

Ra.226 0.87 0.055 Fe 59 -0.04 0.056 Mn.54 -0.0055 0.027 .

Zr 95 -0.037 0.064 mg K-40/g 43 0.65 U 238 4.2 0.54  !

Sample ON 8 Nuclide Conc. (pCirg)* i1.9fri ,

0 134 -0.010 0.069' O 137 0.26 0.086 Th 232 1.5 0.26 Co40 0.N1 0.081

+

Ra 226 1.0 0.14 Fe 59 0.077 0.14 Mn-54 -0.020 0.066 Zr-95 0.20 030- .

mg K-40/g 34 1.5 U 238:- 33 1.4 ,

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

,a..

$ I

' ' Sainple ON 9 l

Nurlide Cone. (pri'g)' i 1.9(=r 04134 4).011 0.036 Cs. 5.37 0.52 0.n47

'Ih 232 1.9 0.14 Cudd) 0.015 0.039 ita 226 1.0 0.072 I?c.59 41.042 0.070 j Mn54 4).022 0.034 1  ;

Zr.95 41.065 0 081 '1 ing K 40/r 34 0.77 .I

^\

U 238 4.4 0.70 mran-e:ssummms=. -e==amran--nsmmasarun:cowra n - ra.u nze msn.ur Sampic ON.10 Nuclide Conc. (pCi/g)' i1.9far C#134 0.039 0.074 Cs137 0.42 0.088

'lh.232 2.1 0.26 Coddl 41.12 0.075 Ita.226 1.1 0.13 l'c 59 0.45 0.36 - ,

M n-54 4).15 ON4 Zr.95 41.031 0.15 ing K 40/g 37 1,4 U 238 5.4 1.3

--._a=..__ _ . . , . . . .. , , _ _ _ . , . . , , . . _ . _ m__m, Sainple ON.ll Nuclide Cone. (pCi'g)* 11.9(= >

Cs 134 0.0iH 0.025 Cs 137 0.5 I . 0.031

'lh 232 2.0 0.087 Co44) 4).013 0.026 Ita 226 1.1 0.047 l'c 59 4).013 0.015 Mn 54 0.018 0.024 Zr 95 0.052 0.0M2 ing K 40!g 37 0.48 U 238 48 0.45

. _ - - - __. _. . - . _ _ _ .- _ _ _ . _ . , . _ . , _ _ _ _, . _ . , a .

o .

' . , - q s? ._ _

.- sa,upic ON.i2 Nuclide Conc. (pCi'g)'

21.W Cs 134 0.023 0.039 0.56 Cs 137 0.053

'Ih 232 1.1 0.15 ,

Co44) 0.011 0.036 11a226 0.78 0.079 12c.59 0.031 0.00 t I

Mn54 0.024 0.041 h.95 0.021 0.17 mg K40'g 18 07.5 U-238 6.7 0.66

. ,. ,,, . - ~n mava- -

~.

.-~.-.--nu-~--.-.n=.c~....-...,m.e=,r_ -;

Sample ON 13 i Nuclide Conc. (pCi'g)* . i 1.W Cs 134 0.013 0.040 Cs-137 1.2 0.076

'th 232 1.2 0.17 Q>44) 0.026 0.037 Ita 226 0.78 0.087 17c 59 0.019 0.082 Mn 54 -011079 01139 Zr.95 0.0020 0.19 aug K 40!g 17- 0.93 U 238 8.1 0.74 Sample ON 14 Nuclide Conc. (pCi'g)' i1 W C4134 0.0050 - 0.045 Cs 137 Ifl 0.072 Th 232 1.1 0.18 Co-N) 0.016 0.043 11a 226 0.83 0.092 l'c.59 0.19 0.25-Mn 54 -0.0098 0.038 Zr-95 OJX)75 0.20 mg K 40/g 21 1.0 U-238 7.2 .- 0.77 m conc <nis.iava we cyacuca in pag empi uud vi A.4u, wr.nti a capicacaliriiigTmy.

, . . = . , . - - ., . . . . . . . - . . . . _, - - . . - . ... . . . - ,,_

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