ML20138E531

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Insp Rept 99990003/94-60 on 941031-1205.No Safety or Health Concerns Noted.Major Areas Inspected:Surveys of Northeast Ohio Regional Sewer District Southerly Wastewater Treatment Plant & Easterly Wastewater Treatment Plant Process Areas
ML20138E531
Person / Time
Issue date: 12/16/1994
From: Kurth M, Shear G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20138E446 List:
References
FOIA-96-443 99990003-94-60, NUDOCS 9412280060
Download: ML20138E531 (11)
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U. S. NUCLEAR REGULATORY COMMISSION REGION III Report No.

999-90003/94060(DRSS)

License No. Non-Licensee Organization:

Northeast Ohio Regional Sewer Distr :t (NE0RS0)

Cleveland, Ohio Inspection At:

NE0RSD Southerly Wastewater Treatment Plant 6000 Canal Road Cuyahoga Heights, Ohio 44125 NE0RSD Easterly Wastewater Treatment Plant 14101 Lakeshore Boulevard Cleveland, Ohio 44110 On-site Inspection Conducted: October 31 through November 4, 1994 Inspector:

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Mic'hsel F. 'Kurth I ~Date Radiation Specialist Accompanying Personnel: Frank Talbot, Ohio Department of Health Approved By:

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  1. 24//+

Gary L. Shear, Chief /

Date Fuel Cycle and Decommissioning Branch Inspection Summary On-site inspection on October 31 throuah November 4.1994, and sample analysis through December 5. 1994 (Report No. 999-90003/94060(DRSS))

Areas Inspected 1 This was a special inspection conducted to perform surveys of the Northeast Ohio Regional Sewer District (NE0RSD) Southerly Wastewater Treatment Plant (SWTP) and Easterly Wastewater Treatment Plant (EWTP) treatment process areas.

Sewer waste water, sludge, and ash samples were collected at different treatment process locations at the SWTP and the EWTP for gamma-radiological analysis.

Results:

The NRC inspector did not identify any appreciable exposure rate readings above background of the treatment process areas at the SWTP and the EWTP. The radiological analysis con wcted of the sewer waste water, sludge and ash samples did not identify an.;.oncentrations above the minimum,

detectable activity for gamma emit,' Ng radionuclides, in phrticular, cobalt-60.

However, trace amounts of thallium-201, radium-226, thorium-232, iodine-131, and bery11ium-7 were identified in certain samples.'

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DETAILS 1.

' Persons Contacted Thomas Lenhart, Assistant General Counsel, Northeast Ohio Regional Sewer District (NE0RSD)

  • Michael DaDante, Superintendent, NE0RSD Easterly Wastewater Treatment Plant (EWTP)

Frank Cuffaro, Superintendent, NE0RSD, Southerly Wastewater Treatment Plant (SWTP)

' Tim Tigue, Assistant Superintendent, NE0RSD, SWTP Rich Connelly, Manager, Water Quality and Industrial Survrillance, NE0RSD Frank Talbot, Ohio Department of Health

  • K. Ed Houdeshell, Unit Process Nanager, NE0RSD, EWTP Tim Atkins, Shift Supervisor, NE0RSD, SWTP Jim Yusko, Shift Supervisor, NE0RSD, SWTP George Uhl, NE0RSD John Mayer, NE0RSD
  • Denotes those present during the November 3, 1994, exit meeting conducted at the Easterly Wastewater Treatment Plant.

' Denotes those present during the November 4, 1994, exit meeting conducted at the~ Southerly Wastewater Treatment Plant.

2.

Backaround During an April 1991 aerial monitoring survey conducted in the Cleveland, Ohio area, increased radiation levels were detected at the Northwest Ohio Regional Sewer District (NE0RSD) Southerly Wastewater

-Treatment Plant (SWTP) located in Cuyahopa Heights, Ohio. The material involved with the increased radiation levels was subsequently determined to be cobalt-60. The SWTP services a large section of the Cleveland / Northeast Ohio area. The SWTP treatment includes incineration of sludge, transport of ash in slurry form to settlement / evaporation ponds, and eventual removal of the dried product for use as fill on the SWTP property.

During the performance of surveys in November and December 1993, a NE0RSD contractor identified six areas of elevated radiation exposure levels at the Northeast Ohio Regional Sewer District Easterly Wastewater Treatment Plant (EWTP) located in Bratenahl and Cleveland, Ohio.

Further analysis of two of the six areas concluded that the elevated levels were from greater than average deposits of potassium-40, a naturally occurring radionuclide. Analysis of the other four areas concluded that the elevated levels were from cobalt-60. Proceeding this survey, more extensive surveys were conducted at the EWTP by the NE0RSD contractor and the NRC, resulting in the conduct of limited surface remediation on the EWTP grounds. The surveys and remediation efforts are documented in NRC Inspection Report No. 999-90003/94042(DRSS).

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3.

Samolina Locations and Analytical Results j-On September 22, 1994, the NE0RSD collected a SWTP filter cake (sludge) i sample for radiological analysis. The analysis concluded that the sample contained 151 picocuries per gram (pCi/g) of cobalt-60. This i

prompted the NRC to conduct further sampling at the SWTP and the EWTP.

A.

S=alina Locations On November 1 through 3,1994, sewer waste water, sludge and ash i

samples were collected from different areas within the SWTP and i

the EWTP. Table Nos. I through 3 of this report identify the sampling locations. Samples were collected from each of the six intake points into the SWTP and from each of the three intakes points into the EWTP. Also, samples were collected from different treatment process areas in the SWTP and the EWTP. One sample per l

day was collected at each location.

j B.

Analytical Results Sample analysis was conducted at the Region III laboratory using the gamma spectrometry system. Table Nos. I through 3 of this report identify the samples' locations and analytical results. As illustrated in Table Nos. I through 3, no samples were identified as containing cobalt-60 above the minimum detectable levels.

i However, trace quantities of iodine-131 were identified in five samples collected on November 1,1994. The iodine-131 concentrations ranged from 0.7 to 1.4 pCi/g, concentrations which are below the 10 CFR Part 20.2003, " Disposal for Release into Sanitary Sewerage" limit.

(Iodine-131 limit for disposal into the sanitary sewer is a monthly average concentration no greater than 10 pCi/ml.) Therefore, we have no health and safety concern.

Also, the SWTP furnace ash samples were identified as containing trace quantities of bery111um-7, thallium-201, and radium-226.

The ash samples collected from November 1 through 3,1994, were identified as containing trace quantities of beryllium-7 ranging from 12 to 32 pCi/g, concentrations which are below the 10 CFR 20.2003 limit.

(Beryllium-7 limit for disposal into the sanitary sewer is a monthly average concentration no greater than 6,000 pCi/ml.) Therefore, we have no health and safety concern. These ash samples were also identified as containing trace quantities of thallium-201 ranging from 12 to 75.7 pCi/g, and trace quantities of radium-226 ranging from 3 to 10 pCi/g. Because thallium-201 is an accelerator produced radionuclide and radium-226 is a naturally occurring radionuclide, these types of materials are regulated by the State of Ohio. A copy of this report will be provided to the Ohio Department of Health for their review.

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Survev locations and Results Surveys were conducted using a Ludlum Model 19 Micro R Meter, NRC Tag No. 011021, last calibrated September 13, 1994, and a Ludlum Model 12 with attached pancake probe, NRC Tag No.,047068, last calibrated August 29, 1994. Surveys were performed in each of the areas where sampling was conducted at the SWTP and EWTP on November 1 through 3, 1994. Also, a survey was performed of the EWTP Pre-Aeration Tank area.

The survey exposure rates ranged from 4 to 14 microroentgen per hour (gR/hr) (includes background) on the surface and one meter above the sampling areas and the EWTP Pre-Aeration Tank Area. The background measurements taken at the SWTP and EWTP ranged from 4 to.10 pR/hr. The areas where the survey exposure rates were slightly higher than the background exposure rates were attributed to building brick (small quantities of naturally occurring radionuclides, such a.s thorium-232 and potassium-40 are common materials found in brick).

5.

Exit Meetina At the conclusion of the on-site inspection on November 3 and 4,1994, the inspector met with those individuals identified in Section 1 of this report. A summary of the preliminary results and the forthcoming letter were discussed. The NE0RSD management and employees did not identify any information provided during the inspection as proprietary.

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TABLE NO.1 ANALYTICAL RESULTS FROM EASTERLY AND SOUTHERLY SAMPLING SAMPLES COLLECTED NOVEMBER 1, 1994 LOCATION SAM DAY RESULT i 2cr PLE (pCi/g)

Sou. Lagoon A 1

11/1 Co-60

<'MDA Sou. Gravity Thickener Primary 2

11/1 Co-60

<MDA Sludge I-131 0.8 i 0.2 Sou. Gravity Thickened Excess 3

11/1 Co-60

<MDA Activated Sludge Sou. Gravity Belt Excess 4

11/1 Co-60

<MDA Activated Sludge Sou. Thermal Conditioning 5

11/1 Co-60

<MDA Thickened Sludge Tank No. 1 I-131 0.7 1 0.3 Sou. Thermal Conditioning 6

11/1 Co-60

<MDA -

Thickened Sludge Tank No. 4 Sou. Thermal Conditioning 7

11/1 Co-60

<MDA Influent I-131 1.3 0.3 Sou. Vacuum Filter Cake East 8

11/1 Co-60

<MDA Belt Sou. Vacuum Filter Cake West 9

11/1 Co-60

<MDA

)

Belt I-131 1.4 0.3 Sou. Furnace No. 1 Ash 10 11/1 Co-60

<MDA Be-7 13.8 4.0 T1-201 75.7 15.0 Ra-226 10.0 i 3.0 Sou. Furnace No. 2 Ash 11 11/1 Co-60

<MDA Be-7 12.0 4.0 T1-201 64.0 17.0 Ra-226 6.0 i 2.0 Sou. Furnace No. 4 Ash 12 11/1 Co-60

<MDA

'e-7 14.0 4.0

.1-201 58.0 15.0 Ra-226 10.0 2.0 Sou. Big Creek Interceptor 13 11/1 Co-60

<MDA Sou. Southwest Interceptor 14 11/1 Co-60

<MDA Sou. Southerly Interceptor 15 11/1 Co-60

<MDA Sou. Mill Creek Interceptor 16 11/1 Co-60

<MDA'

LOCATION SAM DAY RESULT

'2a PLE (pCi/g) i Sou. Cuyahoga Interceptor 17 11/1 Co-60

<MDA Sou. Sludge Degrit No. 2 18 11/1 Co-60

<MDA Sou. Sludge Degrit No. 3 19 11/1 Co-60

<MDA Sou. Easterly Sludge Line 20 11/1 Co-60

<MDA I-131 1.0 i 0.3 Sou. Initial Grit 21 11/1 Co-60

<MDA East. Grit Classifier 22 11/1 Co-60

<MDA East. Easterly Inlet 23 11/1 Co-60

<MDA East. Collinwood Inlet 24 11/1 Co-60

<MDA East. Heights Inlet 25 11/1 Co-60

<MDA East. Southerly Pumps 26 11/1 Co-60

<MDA East. Pump Building-Waste 27 11/1 Co-60

<MDA Activated Sludge

  • The reported uncertainty refers only to counting statistics.

'The calculated Minimum Detectable Activity (MDA) for cobalt-60 ranged from 0.1 to 0.6 picocuries per gram for all samples collected.

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TABLE NO. 2 ANALYTICAL RESULTS FROM SOUTHERLY AND EASTERLY SAMPLING SAMPLES COLLECTED NOVEMBER 2, 1994 LOCATION SAM DAY RESULT

'2a PLE (pci/g)

Sou. Lagoon A 1

11/2 Co-60

<'MDA Sou. Gravity Thickener Primary 3

11/2 Co-60

<MDA Sludge Sou. Gravity Thickened Excess 2

11/2 Co-60

<MDA Activated Sludge Sou. Gravity Belt Excess NA Shut Down for Maintenance Activated Sludge on this day 1

Sou. Thermal Conditioning 4

11/2 Co-60

<MDA Thickened Sludge Tank No. I 1

Sou. Thermal Conditioning 5

11/2 Co-60

<MDA Thickened Sludge Tank No. 2 Sou. Thermal Conditioning 6

11/2 Co-60

<MDA Thickened Sludge Tank No. 4 Sou. Thermal Conditioning 7

11/2 Co-60

<MDA Influent Sou. Vacuum Filter Cake East 8

11/2 Co-60

<MDA Bel t Sou. Vacuum Filter Cake West 9

11/2 Co-60

<MDA Belt Sou. Furnace No. 1 Ash 10 11/2 Co-60

<MDA Be-7 18.0 t 5.0 Sou. Furnace No. 2 Ash 11 11/2 Co-60

<MDA Be-7 20.0 4.0 Ra-226 10.0 2.0 Sou. Furnace No. 4 Ash 12 11/2 Co-60

<MDA Be-7 22.0 4.0 Ra-226 10.0 2.0 Sou. Big Creek Interceptor 20 11/2 Co-60

<MDA Sou. Southwest Interceptor 22 11/2 Co-60

<MDA Sou. Southerly Interceptor 21 11/2 Co-60

<MDA Sou. Mill Creek Interceptor 23 11/2 Co-60

<MDA

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LOCATION SAM DAY RESULT i 2c7

~

PLE (pCi/g) e Sou. Cuyahoga Interceptor 24 11/2 Co-60

<MDA Sou. Sludge Degrit No. I 16 11/2 Co-60

<MDA Sou Sludge Degrit No. 2 17 11/2 Co-60

<MDA Sou. Sludge Degrit No. 4 18 11/2 Co-60

<MDA t

Sou. Easterly Sludge Line 19 11/2 Co-60

<MDA Sou. Initial Grit 25 11/2 Co-60

<MDA East. Grit Classifier 28 11/2 Co-60

<MDA East. Easterly Inlet 13 11/2 Co-60

<MDA l

f East. Collinwood Inlet 15 11/2 Co-60

<MDA East. Heights Inlet 14 11/2 Co-60

<MDA Easterly-Southerly Pumps 26 11/2 Co-60

<MDA s

East. Pump Building-Waste 27 11/2 Co-60

<MDA l

Activated Sludge "The reported uncertainty refers only to c'ounting statistics.

'The calculated Minimum Detectable Activity (MDA) for cobalt-60 ranged from 0.1 to 0.6 picocuries per gram for all samples collected.

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i TABLE NO. 3 ANALYTICAL RESULTS FROM EASTERLY AND SOUTHERLY SAMPLING SAMPLES COLLECTED NOVEMBER 3. 1994 LOCATION SAM DAY RESULT i '2ar PLE (pCi/g) i Sou. Lagoon A 1

11/3 Co-60

<:'MDA Sou. Gravity Thickener Primary 3

11/3 Co-60

<MDA Sludge Sou. Gravity Thickened Excess 2

11/3 Co-60

<MDA Activated Sludge Sou. Gravity Belt Excess NA Shut Down for Maintenance Activated Sludge on this day Sou. Thermal Conditioning 4

11/3 Co-60

<MDA Thickened Sludge Tank No. 1 Sou. Thermal Conditioning 6

11/3 Co-60

<MDA Thickened Sludge-Tank No. 2 Sou. Thermal Conditioning 5

11/3 Co-60

<MDA Thickened Sludge Tank No. 4 Sou. Thermal Conditioning 7

11/3 Co-60

<MDA Influent Sou. Vacuum Filter Cake East 8

11/3 Co-60

<MDA Belt Sou. Vacuum Filter Cake West 9

11/3 Co-60

<MDA Belt Sou. Furnace No. 1 Ash 10 11/3 Co-60

<MDA Be-7 32.0 5.0 T1-201 12.0 5.0 Ra-226 3.0 i 1.0 Sou. Furnace No. 2 Ash 11 11/3 Co-60

<MDA Be-7 32.0 5.0 T1-201 12.0 5.0 4

Ra-226 3.0 1.0 Sou. Furnace No. 4 Ash 12 11/3 Co-60

<MDA Be-7 32.0 5.0 T1-201 12.0 5.0 Ra-226 3.0 1.0 4

Sou. Big Creek Interceptor 16 11/3 Co-60

<MDA Sou. Southwest Interceptor 17 11/3 Co-60

<MDA

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LOCATION SAM DAY RESULT

'2a PLE (pCi/g) e Sou. Southerly Interceptor 18 11/3 Co-60

<MDA Sou. Mill Creek Interceptor 19 11/3 Co-60

<MDA Sou. Cuyahoga Interceptor 20 11/3 Co-60

<MDA Sou. Sludge Degrit No. I 13 11/3 Co-60

<MDA Sou. Sludge Degrit No. 4 14 11/3 Co-60

<MDA Sou. Easterly Sludge Line NA 11/3 Sample Not Obtainable -

Difficulty Getting Electric Switch To Work Sou. Initial Grit 15 11/3 Co-60

<MDA East. Grit Classifier 26 11/3 Co-60

<MDA East. Easterly Inlet 24 11/3 Co-60

<MDA

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East. Collinwood Inlet 25 11/3 Co-60

<MDA East. Heights Inlet 23 11/3 Co-60

<MDA East. Southerly Pumps 21 11/3 Co-60

<MDA East. Pump Building-Waste 22 11/3 Co-60

<MDA Activated Sludge

'The reported uncertainty refers only to counting statistics.

'The calculated Minimum Detectable Activity (MDA) for cobalt-60 ranged from j

0.1 to 0.6 picocuries per gram for all samples collected.

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