ML20151E319

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Insp Rept 70-0572/88-01 on 880609-0701.Major Areas Inspected:Confirmatory Survey of Bldgs 7,10 & 11 & Surrounding Outdoor Areas at Monsanto Ag & Results of Decontamination of Floor Area in Bldg 7
ML20151E319
Person / Time
Site: 07000572
Issue date: 07/13/1988
From: Kunoswki M, Shafer W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20151E316 List:
References
70-0572-88-01-0, 70-572-88-1, NUDOCS 8807260017
Download: ML20151E319 (8)


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a U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 070-00572/88001(DRSS)

Docket No. 070-00572 License No. SNM-567 Licensee: Monsanto AG 1515 Nicholas Road Dayton,-OH 45418 Inspection Conducted At:

Monsanto AG 1515 Nicholas Road Dayton, OH 45418 Inspection Conducted:

June 9 through July 1, 1988 M.

A.' Xunow.A N & Y A ski 7-/J-P7 Inspector:

Radiation Specialist Date N..)D 7-/3-N

'J Approved By:

D. Shafe, Chief Emergency Preparedness and Date Radiological Protection Branch Inspection Summary Inspection on June 9 through July 1,1988 (Report No. 070-00572/88001(DRSS))

Areas Inspected:

Special announced inspection limited to performing a confirmatory survey of Buildings 7, 10,-and 11, and surrounding outdoor areas at Monsanto AG in Dayton, OH, and to review the results of the decontamination of a small floor area in Buildi1g 7 that was identified by the confirmatory survey as having residual contamination in excess of NRC guidelines for release of facilities for unrestricted use.

Results:

The survey confirmed the absence of contamination in Buildings 7, 10, and 11, and surrounding outdoor areas except for a small floor area in Building 7.

A review of the results of the subsequent decontamination of this area indicated no apparent contamination in excess of NRC guidelines.

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4 DETAILS 1.

Person Contacted Robert L. Schimmel, Monsanto Research Corporation - Mound 2.

Purpose of Inspection The purpose of this inspection was to perform a confirmatory survey of Buildings 7, 10, and 11, and surrounding outdoor areas (see Attachment 1) to assure there was no contamination present in excess of the limits specified in the NRC draft document "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use on Termination of Licenses for Byproduct, Source or Special Nuclear Material."

Building 7 (see Attachment 2) is an underground bunker formerly used to store containers of low level and TRU waste (transuranic waste, consisting mainly of Am-241).

In 1987, the containers were shipped to a waste processor in Tennessez, where the waste was sorted and repackaged.

The waste was eventually transferred to a U.S. DOE disposal site in Idaho.

According to a licensee representative, Building 11 was used to repackage

' some waste prior to transfer to the waste processor.

Building 10 is physically connected to Building 11 and was surveyed during this inspection to verify that radioactive material had not been spread when waste was being repackaged in Building 11, 3.

Confirmatory Surveys On June 9,1988, an NRC inspector conducted direct radiation survey measurements and wipes for removable contamination in Buildings 7, 10, and 11.

In addition, 3 soil samples (see Attachment 1) were taken outside the bunker and numerous direct beta gamma radiation measurements were taken inside and outside the 3 buildings.

The direct radiation surveys for alpha contamination were conducted with an Eberline Model PRS-1 Scaler-Ratemeter, serial nunber 442, equipped with a zinc-sulfide scintillation detector.

The efficiency of the survey meter and detector for Am-241 was estimated at 15% for stationary measurements.

Direct alpha surveys in Buildings 7, 10, and 11 indicated no contamination in excess of the NRC guidelines for Am-241 (naximum of 300 dpm/100 cm2 fixed contamination) expect for a small section of floor in the southeast corner of Building 7, where contamination ranging from 300-1300 dpm/100 cm2 was found (see Attachment 3).

According to the licensee, this area was later decontaminated (see Section 4).

Direct beta gamma radiatinn measurements were taken inside and outside the buildings with the PRS-1 meter and a thin end-window G-M probe.

Except for slightly elevated readings at the surface of the floor in the previously mentioned contaminated area in the bunker, no readings above normal background were obierved.

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'dipes to quantify removable contamination were taken in the 3 buildings and in filter housings of a ventilation system attached to Building 11.

Analysis of those wipes by Region III Laboratory indicated no removable alpha-or beta-emitting radioactive material in excess.of NRC guidelines except for two wipes taken of the contaminated floor area in the. bunker (see Attachment 3). Both wipes Indicated removable alpha contamination of 25 dpm/100 cm2; the~ limit in the guidelines for Am-241 is 20 dpm/100 cm2 The results of the analysis are listed in Attachment 4.

Three soil samples were taken near the bunker.

The samples were analyzed by the Region III Laboratory for gamma emitters including Am-241.

Results of a 12-hour count indicated only naturally-occurring radioactive material in normal concentrations, except for slightly elevated levels of Cs-137.

The levels of Cs-137 are consistent with those found in soil as a result of fallout from nuclear weapons testings.

4.

Licensee Followup According to enclosures to a letter submitted by the licensee, dated June 27, 1988, a layer of the floor in the southeast corner of the bur.ker was' removed in a successful effort to remove the contamination identified by the NRC inspector.

The area was resurveyed by the licensee and contamination levels were found to be below the limits specified in the NRC guidelines.

5.

Conclusions Based on the NRC survey and licensee followup described herein, buildings 7, 10, and 11, and the immediate outdoor areas are judged suitable for unrestricted use.

Attachments:

1.

Map of Monsanto Research Corporation indicating relative location of Buildings 7, 10, and 11 2.

Drawing of Building 7, the storage bunker 3.

Drawing of Building 7, showing the approximate location of the contaminated floor area and the relative positions of the two wipes taken in that area.

4.

Results of the Analyses of the wipes taken to quantify removable contamination 3

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r ATTACHMENT 4 ANALYSIS RESULTS OF SMEARS Alpha Beta Smear No.

(dpm/100cm2)

(dpm/100cm2) 1 2.0 2.9 2

2.0 2.9 3

25.0 7.9 4

3.2 6.3 5

2.0 2.9 6

10.5 8.2 7

2. 0 2.9 8

3.0 3.0 9

2. 0 2.9 10 6.9 8.5 11 6.3 3.1 12 3.2 8.8 13 2.0 2.9 14 3.0 3.0 15 3.0 3.0 16 2.3 6.6 17 2.0 2.9 18 2.0 6.6 19 2.0 2.9 20 2.0 6.6 21 2.0 2.9 22 2.0 2.9 23 2.0 6.6 24 10.5 8.2 25 2.0 2.9 26 3.2 13.6 27 2.0 2.9 28 2.0 2.9 29 2.0 6.6 30
3. 2 8.8 31 2.0 6.6 32 6.3 3.1 33 2.0 2.9 34 2.0 2.9 35 2.0 2.9 36 2.0 2.9 37 24.9 15.2 38 6.9 8.5 39 2.0 10.2 40
2. 0 2.9

ATTACHMENT 4-c ANALYSIS OF RESULTS OF SMEARS Alpha Beta

< Smear No.

(dpm/100cm2)

(dpm/100cm2) 41 2.0 10.2 42 2.0 6.6 43 2.0 10.2 44 2.0 2.9 45 3.0

. 3. 0 46 3.2 8.8 47 2.0 10.2 48 2.0 10.2 49

2. 0 2.9 50 2.0 2.9 51 2.0 2.9 52 2.0 6.6 53 2.0 10.2 54 2.0 10.2

-55 2.0 2.9 56 3.0 3.0

'57 2.0 2.9 58 2.0 2.9 59 2.0 6.6 60 2.0 2.9 61 6.8 9.6 62 2.0 6.6 1

63 2.0 2.9 64 2.0 6.6 65 2.0 2.9 66 2.0 6.6 67 2.0 2.9 68 2.0 6.6 69 2.0 2.9 70 3.0 3.0 Smears No. 1-40 were taken in Building 7 Smears No. 41-70 were taker,in Buildings 10 and 11 2