ML20212B232

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Discusses Abandoned Mine Land Program Project 13 Reclamation Plan Review.Data for Two Waste Piles Indicate That Any U Which Exists in Equilibrium W/Radium That Is Present. Reclamation Plan of Partially Filling Pits Adequate
ML20212B232
Person / Time
Issue date: 02/19/1987
From: Hawkins E, Konwinski G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
REF-WM-50 NUDOCS 8703030503
Download: ML20212B232 (4)


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DISTRIBUTION DocketFi[eWM-050 aPDR/DCS

  • DBangart, RIV WM-050/GRK/87/02/14/0 GKonwfriski WDEO.(2)

JHaes, P.CPD, WY LLW Branch, WMLU FEB 191987 URF0 r/f

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Docket File WM-050 RECElVEC' 040WM050100E o

MEMORANDUM FOR:

Do ket File No.'WM-050

'87.FE8 26 A9 :44 I

i FROM:

Gary R. Konwinski, Project Manager

. Licensing Branch 1 a c rE G; < dj;

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Uranium Recovery Field Office, Region IV

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SUBJECT:

ABANDONED MINE LANG PROGRAM PROJECT 13, RECLAMATION PLAN REVIEW l

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i By letter dated October 23, 1986, AVE Engineering Planning and Surveying P.C. (AVI) submitted two documents relating to Abandoned Mine Land Program Project 13, for URF0 review.

The documents were prepared for the Wyoming Department of Environmental Quality (WDEQ) and discuss the, areas of material characterization, hydrology and overall reclamation woik of j

Project 13.

l The NRC became involved in the review process of this site'due to the i

presence of a heap leach site within the project boundary.

Because of I

this, the NRC was asked to determine the jurisdicticO of the heap leach i

site.

In order to accomplish this objective, the'NRC. staff reviewed the

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original submittals as well as additional radiological,-data summaries (delivered to our office on January 29,1987) supplied by AVI.

The NRC review had two objectives.

First, the laboratory data was reviewed by the staff to determine if byproduct materials exist at the site.

Secondly, should byproduct materials exist, they would be quantified to determine if they represent an exempt quantity or a significant amount.

To characterize the radiological makeup of the project site, 238 individual holes were drilled with a combined depth of 19,750 feet.

From these holes, 3,950 soil samples.were obtained.

A review of the analytical test results indicates:that among other constituents, the soil was sampled for uranium-238 and radium-226.

It is this data that URF0 reviewed to determine if equilibrium conditions existed over the site.

Radiological samples from 61 locations were reviewed for uranium and radium concentrations. The data was keyed to specific waste piles, ore piles and an abandoned heap leach pad.

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DATE :87/02/17 e703030503 870219 PDR WASTE WM-50 PDR

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1 WM-050/GRK/87/02/14/0 2-FEB 191967 Two waste piles exist at the site.

They are both located in the northwest corner of the project area. These piles probably consist of a combination of overburden'and low grade ore.

The radiological data for these locations is shown below:

Drill' Hole Depth of U-238 Ra-226 U/Ra Number-Sample (ft) pCi/l pCi/l Ratio 108 10 9.68 2

4.8/1 208 10 52.4 12.5 4.2/1 208 20 86.25 24.9 3.5/1 208 45 47.53 17.1-2.8/1 208 120 168.44 5.7 29.5/1 The data for the two waste piles indicate that any uranium which exists is in equilibrium with the radium that is present.

Due to this, it appears that no uranium depletion has taken place and, therefore, no byproduct' materials exist in these two waste piles.

A large ore pile in thz west-central portion of the project area was the site of intense investigation.

Numerous-holes were drilled in this pile at various depths. The radiological' data is shown below:

Drill Hole Depth of U-238 Ra-226 U/Ra Number Sample (ft) pCi/l pCi/l Ratio 302 25.0 19.29 7.10 2.7/1 303 65.0 11.98 1.60 7.5/1 306 15.0 21.96 7.20 3.1/1 307 65.0 149.96 20.40 7.4/1 320 5.0 7.04 16.00

.44/1 320 10.0 125.65 34.00 3.7/1 320 15.0 64.92 30.30 320 20.0 54.23 30.20 21.4/1 320 35.0 18.29 21.70

.84/1 322 5.0 115.43 91.70 1.2/1 324 5.0 39.88 23.00 1.7/1 325 5.0 39.88 23.00 1.7/1 326 5.0 39.88 23.00 1.7/1 329 5.0 32.5 19.30 1.6/1 332 40.0 16.25 8.00 2.1/1 334 50.0 16.99 6.70 2.5/1 334 60.0 50.17 12.60 3.9/1 334 70.0 39.54 9.30 4.3/1 3

338 50.0 170.06 18.30 9.3/1 338 100.0 32.43 16.20 2/1 1

345 10.0 9.21 2.70 3.4/1 i

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DATE :87/02/17

g WM-050/GRK/87/02/14/0 FEB 191987 345 40.0 184.48 7.00 26/1 348 45.0

.87.61 48.10 1.8/1 348 50.0 99.45 4.60 21.6/1 350 60.0 74.13

-30.40 2.4/1 The data for the large ore pile indicate that of the 25 radiological samples, two are about 50 percent depleted in uranium. This depletion probably represents a combination of acid formation through the dissolution of gypsum crystals and precipitation depletion.

Because of the minimal number of sampled areas which show depletion as well as the low degree of depletion, byproduct material is not thought to be present.

The project site also contains an asphalt heap leach pad.

It appears that the heap leach pad was constructed but never utilized for leaching activities. The radiological data collected for the heap leach pad is.

listed below:

Drill Hole Depth of U-238 Ra-226 U/Ra Number Sample (ft) pCi/1 pCi/1-Ratio a

401 10.0 70.81 24.50 2.9/1 401 50.0 39.80 7.60 5.2/1 406 20.0 60.04-8.60 6.9/1 406 45.0 20.99 7.10 2.9/1 412 70.0 31.41 7.90 3.9/1 422 2.0 260 128.00-2.0/1 431 2.0 65.0

, 30.00 2.2/1 432 2.0 142 53.00 2.7/1 j

433 2.0 148 57.~00 2.6/1 434 2.0 189 68.00 2.8/1 435 2.0 136 55.00 2.5/1 435 4.0 360 183.00 2.6/1 i

436 2.0 135 31.00 4.4/1 437 2.0 148 62.00 2.4/1 438 2.0 118 47.00 2.5/1 438 4.0 71 19.00 3.7/1 As can be seen from the above data, all of the residual heap leach materials that were sampled have their uranium and radium concentrations in an equilibrium range.

Based upon this data, it, appears that no byproduct materials exist on the heap leach pad.

The other remaining piles at the site are located along the eastern i

boundary of the area. These piles appear to be low grade ore stockpiles.

Their radiological data is presented below:

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DATE :87/02/17

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i WM-050/GRK/87/02/14/0 FEB 191987 Drill Hole Depth of U-238 Ra-226 U/Ra Number Sample (ft) pCi/l pCi/l Ratio 502 65.0 66.4 39.20 1.7/1 506 10.0 29.6 7.40 4.0/1 512 40.0 16.00 16.00 1/1 512 90.0 10.10 10.10 1/1 512 100.0 21.3 7.50 2.8/1 516 40.0 17.7 8.40 2.1/1 517 10.0 41.1 23.20 1.1/1 519 10.0 29.7 26.70 1.1/1 622 20.0 60.46 17.90 3.4/1 622 40.0 66.14 20.70 3.2/1 624 30.0 66.41 17.00 3.9/1 603 25.0 31.8 8.10 3.7/1 The data for the easterly waste piles indicate that'three of the sample locations show about a 35 percent uranium depletion.

It is thought that this depletion is due to acid formation by way of dissolution of gypsum crystals and does not represent uranium processing.

The staff, in their review of the materials proposed for reclamation at the ALM Project 13 site, did not identify any materials that indicate that uranium recovery took place.

It appears that as presented in the AVI Technical Reports, a heap leach pad was constructed at the site, but never utilized for uranium processing.

Similarly, the waste / ore piles located at the site do not represent byproduct materials. 'These piles contain a combination of overburden and low grade ore.

Based upon these findings, the staff would conclude that the proposed reclamation plan of partially filling pits and stabilizing in place the waste piles represants an adequate reclamation plan for the site.

Isl Gary R. Koawinski, Project Manager Licensing Branch 1 Uranium Recovery Field Office Region IV IsI Approved by:

Edward F. Hawkins, Chief Licensing Branch 1 Uranium Recovery Field Office, Region IV Case Closed:

040WM050100E

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