ML20247Q808
| ML20247Q808 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 09/13/1989 |
| From: | Velasquez J UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.) |
| To: | Rouse L NRC |
| References | |
| 25947, UNC-ALO-89-276M, NUDOCS 8909290099 | |
| Download: ML20247Q808 (2) | |
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UnlTOD nDEG2nF c"bMSBanTizn g._ g 6501 America's Parr Ibuquerque, New Mexico 87110 g
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September 13,1989 I
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UNC-ALO-89-276M NMSS MAIL SEcTION
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i DOCKE.T CtD(K k.
g Mr. Leland Rouse N
S usec Chief, Fuel Cycle Safety.Utgrlen SEP161989 )
U.S. Nuclear Regulatory Commission V
Washington, D.C. 20555 m"NEm
,( g DOCKET CLERK
SUBJECT:
Docket No.70-820
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,x License No. SNM-777
Dear Mr. Rouse:
I have reviewed your letter of August 22,1989 regarding the final survey reports for the UNC Recovery Systems operation in Rhode Island and offer the following for your consideration.
Grid Block 138
' Your letter referred to concern regarding the condition of this grid block based on the data presented in Table 14, page 115 of ORAU's report. The data contained therein relative to B-138 is data obtained by ORAU in 1986 (see attached 1). More recent data is available.
As a result of ORAU's findings we were requested by NRC to conduct additional clean-up of B-138. We conducted additional excavation of the area as agreed to by NRC and took additional samples. We provided the results of those analyses to NRC in January, 1987 (see Attachment 2) which indicated that the area was clean to NRC's satisfaction.
Per NRC's instruction we then filled the excavated areas with a minimum of 4 ft. of clean soil. UNC believes that the area has been sufficiently decontaminated and proposes no further remediation.
Outfall Regarding the outfall, we are disappointed that NRC identifies this area as being of concern at this late date. The data presented in the report is well over 5 years old, generated at the time of ORAU's original site verification visit. Since that time we have had many discussions with NRC and ORAU and never has there been a concern raised regarding the outfall until recently. We have been operating on the premise that all areas except those identified by NRC in previous discussions had been satisfactorily remediated.
In fact, NRC's consultant concludes on page twelve of its report that "it is ORAU's opinion DfD4 8909290099 890Md
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' September 13,1989
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'that the unrestricted areas of the UNC site satisfy the NRC guidelines established for.
~ decommissioning".
We make note 'of this because of the diligent and sometimes extreme efforts UNC has undertaken to decommission this site. We believe that we have gone well beyond the mandate'of the ALARA principle in site decommissioning only to have NRC continue to require us to continually chase one more " hot spot".
In discussing this matter with Ms. Mary Horn of your staff recently, she informs us that NRC's concern is focused on sampling points 7 and 9 as depicted on Figure 9 of ORAU's report.
More particularly, NRC would like for us;to remove the residual material contained within the sluice and the material around the sluice joint in the area of sample No. 7. Inasmuch as this represents a limited area and requires nominal effort UNC will L
endeavor to meet NRC's request. I have instructed Mr. Helgeson to arrange for removal of residuals contained in the sluice as well as escavating an area around the sluice joint in the vicinity of sample location No 7. This work is scheduled to be conducted during the week of September 18. We will be in contact with Ms. Horn when we are ready for any verification sampling NRC might deem necessary.
It is our desire to complete all excavation and sampling as soon as possible.
Your assistance in accomplishing this would be appreciated greatly. If NRC could conduct its sampling in late September, I see no reason why the remaining issues cannot be resolved and the license terminated before year's end.
Sincerely,
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Juan R. Velasquez President JRV: dms cc:
Karl Helgeson Bob Greg Paul McLain
I' ATTACHMENT'1'
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s6 Oak Ridge Manpower Education.
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Universities Oak Ridge, Tennessee 37831-0117 Division
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4 October 15, 1986 4
- RECEIVED $y.
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Mr. William Crow C)
U.S.5" LEAR REGU g
Division of Fuel Cycle & Material n,iGSK f p,
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20555 FOLLOWUP SURVEY OF OUTSIDE AREAS AT UNC - WOOD RIVER $ y CT16h *119N C_ '
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Dear Mr. Crow:
On September 26, 1986, I visited the UNC f acilities in Wood Rive 4cnhtdN,
f or the purpose of resurveying those areas where residual radionuclides contamination had been identified by earlier surveys (Figure 1).
Walkover gamma scans were conducted over each of these grid blocks. Additional grid blocks in the area of the lagoon were also scanned. Locations exceeding twice ambient background levels were. identified in grid blocks B-036, D-094, B-024, B-082, B-084, B-085, B-137, B-138, B-139, B-140, B-049, B-050, B-058, and B-059.
These locations, shown on Figures 2 and 3, were small, compared to the grid block area, and maximum levels were less than 10 times the background exposure rate.
At 1 meter above the surf ace, exposure rates are less than 10 pR/h above-background. The sources of the elevated levels in blocks B-024 and D-036 were identified and removed. No actions were conducted on other locations during-my vis it to the site.
Composite soil samples were then obtained f rom the surf ace of grid blocks.
Sampling was perf ormed by obtaining approximately equal quantities of soil f rom the grid center and f our locations, midway between the grid center and the grid corners. The 5 samples were mixed and about 1 kg was removed f or laboratory analysis.
For grids which were only partially soil covered, the composite was prepared f rom 5 samples spaced throughout the soil area.
Several grids were predominantly asphalt surf aces and composites included residual soil deposits which had accumulated on the asphalt surf ace.
There were no attempts to selectively sample areas of elevated surf ace gamma radiation.
The results of soil analysis, presented in Table 1, indicate residual U-235, U-238 and Cs-137 in some of the grid blocks. Concentrations of other radionuclides are sdthin the ranges f or background soil f rom this region.
Two samples were also obtained f rom " hot-spots" in excavated areas of grid blocks B-138 and B-139. These samples contained 8612 and 7812 pCi/g of Cs-137. No other radionuclides were noted at elevated concentrations.
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Mr. William Crow 2
October 15, 1986
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On the basis of these results, there appear to be areas of U-235 surf ace 1
l' soil contamination, indicative of total uranium concentrations in excess of the Branch Technical Position levels.
Isotopic uranium to determine 234/235 rates will be perf ormed on selected samples and results provided later.
Ques tions should be ref erred to me at FTS 626-3305.
Sincerely, N
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[ James D. Berger, Manager Radiological Site Ass essment Program JDB/sjf Enclos ure cc:
J. Roth, NRC, Region I l
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' - ATTACHMENT 2 e-s lc ! '.
Division of Umted Nuclear Corporation ' One Narragansett Trail Telepnone 401/364 7701' l>+.
.g A UMC RESOURCES Company Wood ReverJunction RhodeIsland 02894
.NISRI:
87-003 j
January'28,.1987 i
W.
T.
Crow, Acting Chief Uranium Fuel Licensing Branch.
Division'of Fuel Cycle and Material Safety, NMSS United States Nuclear Regulatory Commission P
Washington, D.C.
20555 i
Gentlemen:
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1 This letter is to present the proposed agenda for our planned meeting
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1 in Silver Springs on. February 4, 1987, and to provide you with the p
analytical results of soil samples taken from areas of additional i
j decontamination since our meeting on September 6, 1985..These areas-
' f' are'from: grid blocks and-specific locations within grid blocks which d
were identified as being of concern to you during that meeting, and as are indicated on the attached map from'that meeting.
Pages 1
's through 4 include.results obtained after initial decontamination i
i following that meeting, and page 5 has results from secondary j
U decontamination which was done based on the initial results.
i 4-It is UNC's belief that the areas that.had been in question now meet l
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the,NRC's decontamination guidelines for the soil at the UNC Recovery j
Systems site.
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If there are any questions regarding this matter, please contact me i.
or Karl Helgeson.
l Very truly yours, I
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U.
R.-J. Gregg, Plant Manager l
UNC Recovery Systems i
cc:
-K.
Helgeson R. Messenheimer J. Velasquez N. Kaufman (w/o attachments) i
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ATTACHMENT: NISRI:
87-003 Pg.
3 DATED:
JANUARV 28 1987 aric
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ll Grid Block I.D.
Type of Analysis B-085 Gross Alpha 8.7 1
1.5 pCi/
0.06 pCi/gm U-234 1.13 gm U-235 0.05 1 0.01 PCi/gm Cs-137 0.56 0.01 pCi/gm Nitrates (as N) 2 PPM /gm i'
L B-126-A Gross Alpha 38.4 2.7 pCi/gm l
U-234 26.9 0.8 pCi/gm j
U-235 1.0 0.2 pCi/gm Cs-137 N/A pCi/gm Nitrates (as N) 10 PPM /gm B-126-B Gross Alpha 29.3 1.7 pCi/gm U-234 21.5 0.3 pCi/gm c.
U-235-O.7 i 0.2 pCi/gm Cs-137 S N/A pCi/gm
-Nitrates (as N) 13 PPM /gm 1
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B-130
~ Gros's Alpha 5.9 1.0 pCi/
pCi/gm
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.U-234 5.1
! 0.2 gm i
U-235 0.2 1 0.1 pCi/gm Cs-137 N/A pCi/gm l
Nitrates (as N) to PPM /gm v
B-134 Gross Alpha 23.7 2.4 pCi/gm U-234 21.8 0.8 PCi/gm l
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0.8 1 0.3 PCi/gm Cs-137-N/A i
pCi/gm l
Nitrates (as N) 5 PPM /gm B-135 Gross Alpha 75.6 i 2.4 pCi/gm U-234 21.3 1 0.5 PCi/gm U-235 0.8 0.2 PCi/gm Cs-137 N/A i
pCi/gm Nitrates (as N) 3 PPM /gm B-138-A Gross Alpha 13.5 1.7 pCi/gm U-234 11.7
! 0.2 pCi/gm U-235 0.5 0.3 PCi/gm Cs-137 1.12 i 0.02 PCi/gm Nitrates (as N) 12 PPM /gm B-138-B Gross Alpha 9.3 1.7 pCi/gm U-234 7.9 1 0.5 pCi/gm U-235 0.3 0.1 pCi/gm Cs-137 4.24 0.04 pCi/gm Nitrates (as N) 20 PPM /gm s-
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