ML20134H247

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Trip Rept of 941216 Visit to Cleveland,Oh Re Emergency Planning at Advanced Medical Sys
ML20134H247
Person / Time
Issue date: 12/20/1994
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Axelson W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20127A948 List:
References
FOIA-96-444 NUDOCS 9702110220
Download: ML20134H247 (2)


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l December 20, 1994 MEMORANDUM TO: W. L. Axelson, Director i Division of Radiation Safety and Safeguards i FROM: John A. Grobe, Chief Nuclear Materials Inspection Section 2 i

SUBJECT:

TRIP REPORT - EMERGENCY PLANNING AT ADVANCED MEDICAL SYSTEMS, INC.

I I l On December 16, 1994, Wayne Slawinski and I met with Capt. Tom Root of the  !

I Cleveland Fire Department and Commissioner Robert Staib of the Cleveland  !

Department of Environment to discuss Advanced Medical Systems, Inc. (AMS). l We presented a description of the agency, AMS facilities, licensed activities, NRC emergency planning **ouirements and recent AMS water problems.

following this meeting, I met with officials from Cleveland, Cuyahoga County, Ohio, the Northeast Ohio Regional Sewer District and Arts to discuss weaknesses in the relationship between the city emergency response personnel and AMS as l

discussed in our recent inspection report. In the cover letter for that report, AMS was requested to respond to several emergency planning concerns by the end of December 1994. In addition to our concerns, the city was concerned about the level of offsite emergency planning. A listing of meeting attendees is attached.

The city confirmed that AMS had provided adequate training to the city first responders and that they were comfortable rerpending to an emergency at the facility. The city also indicated that additional training was warranted for its Haz-Mat staff. There was consensus between the city, county and state that a more complete offsite emergency plan may be needed. The state presented the offsite plan for all DOE facilities in Ohio as an example.

I provided a description of the inventory at AMS and suggested that the city and AMS consider completing a hazards assessment and then determine the nature uf any additional planning that they believe may be necessary. I indicated l that AMS had an emergency plan in place that met NRC expectations, but we were l addressing implementation concerns and violations of their plan with AMS. I l also presented the generic planning guidance from our NUREGs for projecting offsite doses from fires involving cobalt metal.

Commissioner Staib established a planning group involving AMS, the fire department, emergency medical service, police department and county representatives to meet in early January 1995 to continue discussing this issue and developing a plan and timeline for final resolution of the matter.

Capt. Root stated his belief that fire pre-plans could be adequately upgraded '

in a short period of time.

  • I f1 9702110220 970129 PDR FOIA ENGLISH96-444 PDR l

W. L. Axelson i Following the meeting on emergency planning, a brief discussion occurred regarding recent water problems at AMS. I provided a description of the Confirmatory Action Letter we issued December 15, 1994, and measurements made December 12-14, 1994, of storm water and waste water.

I believe that as a result of this meeting the city, county and state personnel have a better appreciation of the hazard at AMS, weaknesses in AMS programs, and our oversight of the facility. We will continue our close oversight of AMS and our support to the city answering their questions.

Please contact me with any questions you may have.

cc: H. Miller, DRA R. Lickus, PA0 W. Slawinski -

J. Madera i

i DOCUMENT NAME: B:\TRIPRPT.AMS Ta veceive e copy of ties document indicate in the bea: "C" = Copy wMhout ettechment/enclosu o *E' = Copy with attachment / enclosure

  • N* = ido copy 0FFICE RIII o,M 6 RIII RIII RIII NAME Grobe:dp__4 0
  • JATE 12/ 4 /94 12/ /94 12/ /94 12/ /94 0FFICIAL RECORD COPY
  • December 20, 1994 Northeast Ohio Regional Sewer District ATTN: Mr. Erwin J. Odeal Executive Director '

3826 Euclid Avenue Cleveland, Ohio 44115-2504

SUBJECT:

NRC INSPECTION - RAD 10 ANALYTICAL SAMPLING AND RADIOLOGICAL SURVEY RESULTS OF THE NORTHEAST OHIO REGIONAL SEWER DISTRICT SOUTHERLY WASTEWATER TREATMENT PLANT AND EASTERLY WASTEWATER TREATMENT PLANT (REPORT NO. 999-90003/94060(DRSS))

Dear Mr. Odeal:

This refers to the special inspection conducted by Mr. Michael Kurth of this office from October 31 through December 5, 1994, of the Southerly Wastewater Treatment Plant (SWTP) and Easterly Wastewater Treatment Plant (EWTP). The inspection was prompted by the positive identification of cobalt-60 in a filter cake (sludge) sample collected by the Northeast Ohio Regional Sewer District (NE0RSD) personnel on September 22, 1994, at the SWTP. The NRC inspector, working with the assistance of the Ohio Department of Health personnel, collected sewer waste water, sludge, and ash samples for radiological analysis and performed surveys of SWTP and EWTP treatment process areas.

The enclosed copy of our inspection report identifies the areas surveyed during the inspection. The inspection consisted of beta / gamma surveys and the collection and radiological analysis of sewer waste water, sludge, and ash samples.

As a result of the inspection, we have no health and safety concerns. Surveys conducted during the inspection did not identify any areas of elevated exposure rates within the SWTP and EWTP treatment process areas. No cobalt-60 concentrations were identified above the minimum detectable levels in the 81 samples collected from the SWTP and the EWTP treatment process areas.

However, trace amounts of iodine-131 ranging from 0.7 to 1.4 picocuries per gram (pci/g) were identified in five samples taken at the SWTP on November 1, 1994. Also, the SWTP incinerator ash samples (3 per day) were identified as containing trace quantities of: beryllium-7 ranging from 12 to 32 pCi/g; thallium-201 ranging from 12 to 75.7 pCi/g; and radium-226 ranging from 3 to 10 pCi/g. The concentrations of iodine-131 and beryllium-7 identified in the SWTP samples were below the 10 CFR Part 20.2003, " Disposal for Release into Sanitary Sewerage" limits.

The State of Ohio regulates the use of accelerator produced radionuclides and naturally occurring radionuclides. Therefore, thallium-201 (accelerafor produced) and radium-226 (naturally occurring) are considered to be regulated by the State of Ohio. A copy of this report will be issued to 'the Ohio Department of Health for their review of these findings.

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. l Mr. Erwin J. Odeal In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of -

this letter and the enclosed inspection report will be placed in the NRC ,

Public Document Room. ~

We will gladly discuss any questions you have concerning this inspection.

Sincerely.

Original Signed By W. G. Snell for Gary L. Shear, Chief Fuel Cycle and Decommissioning Branch

Enclosure:

Inspection Report No. -

999-90003/94060(DRSS) cc w/ enc 1: T. Adams, B. Koh & Associates B. Koh, B. Koh & Associates C. Trepal, Earth Day Coalition

. The Honorable H. K. Metzenbaum, U. S. Senate T. Brady, Board of Health, County of Cuyahoga R. Owen, Ohio Department of Health M. White, Mayor, City of Cleveland bec w/ enc 1: J. Turdici, OED0 J. T. Greeves, NMSS E. W. Brach, NMSS J. H. Austin, NMSS T. C. Johnson, NMSS M. Nalluswami, NMSS C. G. Jones, NMSS R. L. Fonner, OGC W. L. Axelson, RIII PUBLIC (IE07)

DOCUMENT NAME: NE094060 DSS g gg i .. . .. , . , s . . .--.. . . m.s. . . . c . c.,, .. w. .. ....,f.-i c . c , .. . . .a f.- i -

0FFICE RIII C RIII c- RIII 6 NMSS G NAME Kurth d'b Snell wc.s Shear uGS k Austin (A4Sh jusc/ e.

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DATE 12/d/94 12/u,/94 12/ic. /94 12/fo /74 j, 0FFICIAL RECORD COPY 4

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Mr. Erwin J. Odeal In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC Public Document Room.

We will gladly discuss any questions you have concerning this inspection.

Sincerely, Original Signed By W. G. Snell for -

Gary L. Shear, Chief Fuel Cycle and Decommissioning Branch

Enclosure:

Inspection Report No. ,

999-90003/94060(DRSS) ,

cc w/ enc 1: T. Adams, B. Koh & Associates B. Koh, B. Koh & Associates C. Trepal, Earth Day Coalition The Honorable H. K. Metzenbaum, U. S. Senate T. Brady, Board of Health,- County of Cuyahoga R. Owen, Ohio Department of Health M. White, Mayor, City of Cleveland b

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i U. S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 999-90003/94060(DRSS)

License No. Non-Licensee Organization: Northeast Ohio Regional Sewer District (NE0RSD)

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 l Inspector: .

/2 Michiel F. 'Kurth

/ Date

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Radiation Specialist Accompanying Personnel: Frank Talbot, Ohio Department of Health Approved By: (Mb R 3/

Gary L. Shear, Chief /

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Date Fuel Cycle and Decommissioning Branch Inspection Summary On-site inspection on October 31 throuah November 4.1994. and sample analysis l throuah December 5. 1994 (Report No. 999-90003/94060f0RSS)) '

Areas Insoected: This was a special inspection conducted to perform surveys of the Northeast Ohio Regional Sewer District (NE0hSD) 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, i Results: The NRC inspector did not identify any appreciable exposure rate readings above background of the treatment process areas at the SWTP and the l EWTP. The radiological analysis conducted of the sewer waste water, sludge and ash samples did not identify any concentrations above the minimum, 1 detectable activity for gamma emitting radionuclides, in particular, l i cobalt-60. However, trace amounts of thallium-201, radium-226, thorium-232, J iodine-131, and beryllium-7 were identified in certain samples.' j xh

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. l DETAILS l

1. Persons Contacted .

I 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 Treatmen,t Plant (SWTP)

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

  • K. Ed Houdeshell, Unit Process Manager, NE0RSD, EWTP Tim Atkins, Shift Supervisor, NE0RSD, SWTP Jim Yusko, Shift Supervisor, NE0RSD, SWTP Georgs 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 Jewer District (NE0RSD) Southerly Wastewater Treatment Plant (SWTP) located in Cuyahoga Heights, Ohio. The material involved with the increased radiation levels was suosequently 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 levelswerefrom(jreaterthanaveragedepositsofpotassium-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 NE0R$D 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. Samolino Locations and Analytical Results .

On September 22, 1994, the NE0RSD collected a SWTP filter cake (sludge)  !

sample for radiological analysis. The analysis concluded that the.

sample contained 151 picocuries per gram (pci/g) of cobalt-60. This  ;

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

the EWTP. Table Nos. I through 3 of this report identify the  !

sampling locations. Samples were collected from each of the six .I 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  !

day was col'lected at each location. i 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. ,

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 irt to 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 bery111um-7 ranging from 12 to 32 pCi/g, concentrations which are below the 10 CFR 20.2003 limit. (Bery111um-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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4. Survey 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-Aerat' ion Tank area.

The survey exposure rates ranged from 4 to 14 microroentgen per hour (pR/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 '
slig;.tly higher than the background exposure rates were attributed j to built.'ing brick (small quantities of naturally occurring i radionuclides, such as thorium-232 and potassium-40 are common ,

materials found in brick).

  • 1 l S. Exit Meetina 3 l 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 e 1 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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l l TABLE NO. 1 ANALYTICAL RESULTS FRDM EASTERLY AND SOUTHERLY SAMPLING SAMPLES COLLECTED NOVEMBER 1, 1994 LOCATION SAM DAY RESULT * *2a PLE (pci/g) i Sou. Lagoon A 1 11/1 Co-60 <'MDA Sou. Gravity Thickener Primary 2 11/1 Co-60 <MDA Sludge I-131 0.8

  • 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 1-131 0.7 i 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 S 11/1 Co-60 <MDA Belt I-131 1.4 0.3 Sou. furnace No. I Ash 10 11/1 Co-60 <MDA Be-7 13.8 i 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 Tl-201 64.0 1 17.0 Ra-226 6.0 i 2.0 Sou. Furnace No. 4 Ash 12 11/1 Co-60 <MDA Be-7 14.0 1 4.0 T1-201 58.0 : 15.0 Ra-226 10.0 i 2.0 Sou. Big Creek Interceptor 13 11/1 Co-60 <MDA Sou. Southwest Interceptor 14 11/1 Co-60 <MDA t Sou. Southerly Interceptor 15 11/1 Co-60 (MDA l

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

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LOCATION SAM DAY  !!ESULT '2a PLE (pCi/g) e Sou. Cuyahoga Interceptor 17 11/1 Co-60 <MDA Sou. Sludge Degrit No. 2 18 11/1 Co-60 <MDA 1

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 0.3 Sou. Initial Grit 21 11/1 Co-60 <MDA East. Grit Classifier 22 11/1 Co-60 <MDA t 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 l 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 i *2a PLE (pCi/g) e 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

  • Sou. Thermal Conditioning 4 11/2 Co-60 <MDA Thickened Sludge Tank No. I Sou. Thermal Conditioning 5 11/2 Co-60 <MDA Thickened Sludge Tank No. 2 Sou. Thermal Conditioning 6 11/2 ro-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 Belt Sou. Vacuum Filter Cake West 9 11/2 Co-60 <MDA Belt Sou. Furnace No. 1 Ash 10 11/2 Co-60 <MDk Be-7 18.0 i 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 1 4.0 Ra-226 10.0 2.0 Sou. Big Creek Interceptor 20 11/2 00-60 <MDA Sou. Southwest Interceptor 22 11/2 Co-60 <MDA Sou. Southerly Interceptor 21 11/2 C0-60 <MDA .

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

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t i l LOCATION SAM DAY RESULT * ~2cr  :

PLE (pci/g)  !

i 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 t Sou. Sludge Degrit No. 4 18 11/2 Co-60 <MDA Sou. Easterly Sludge Line 19 11/2 Co-60 <MDA l Sou. Initial Crit 25 11/2 Co-60 <MDA  :

East. Grit Classifier 28 11/2 Co-60 <MDA East. Easterly Inlet l 13 11'/2 ' Co-60 <MDA i l

East. Collinwood Inlet 15 11/2 Co-60 <MDA i 1

East. Heights Inlet 14 11/2 Co-60 <MDA l Easterly-Southerly Pumps 26 11/2 Co-60 <MDA East. Pump Building-Waste 27 11/2 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. 3 ANALYTICAL RESULTS FROM EASTERLY AND SOUTHERLY SAMPLING SAMPLES COLLECTED NOVEMBER 3, 1994 i

i LOCATION SAM DAY RESULT * ~2a i PLE (pci/g)~ i Sou. Lagoon A 1 11/3 Co-60 <'MDA Sou. Gravity Thickener Primary 3 11/3 Co-60 <MDA i Sludge '

Sou. Gravity Thickened Excess 2 11/3 Co-60 <MDA  !

Activated Sludge i 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 l

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 i'

Be-7 32.0 i 5.0 T1-201 12.0 5.0 Ra-226 3.0 1.0 i l

Sou. Furnace No. 2 Ash 11 11/3 Co-60 <MDA l Be-7 32.0 5.0 I a-2 bi1b Sou. Furnace No. 4 Ash 12 11/3 Co-60 <MDA  !

Be-7 32.0 1 5.0 1 T1-201 12.0 i 5.0 Ra-226 3.0 1.0  ;

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 i. 2a PLE (pCi/g)

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 l

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

'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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