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Amend 3 to License SNM-1826 for Rs Holding,Inc,Changing Address,Condition 11 Re Location for Use of Licensed Matl & Condition 18 Re Conduct of Program.Record of 860218 Telcon Encl
	ML20206A267
Person / Time
Site:	07002872
Issue date:	04/17/1986
From:	Adam W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
References
	NUDOCS 8606180065
	Download: ML20206A267 (3)
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Adia-----------------------------3 NRC Form 374A U.S. NUCLE AR CEGULATORY COMMISSION 1

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SUPPLEMENTARY SHEET 070-02872 Amendment No. 03 RS Holding, Inc.

Edison Park

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8499 Darrow Road Twinsburg, OH 44087 In accordance with letter dated January 27, 1986 License Number SNM-1826 is amended as follows:

Item 2 (Address) is changed from 18530 South Miles Parkway, Cleveland, Ohio 44128 to Edison Park, 8499 Darrow Road, Twinsburg, Ohio 44087.

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O Conditions 11. and 18. are amended to'3 read:

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11. Licensed material shall be.used only at Edison Park, 8499'Darrow Road, Twinsburg, Ohio.

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18. Except as specifically provided otherwise in this license, the licensee shall l

conduct its program in accordance with the statements, representations, and procedures contained in the documents including any ~ enclosures, listed below.

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The Nuclear Regulatory Commission's regulations'shall govern unless the statements, representations and procedures in the 1,1censee's application and correspondence are more restrictive than the regulations.5,wyi

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Application dated May 30, r1983;' and W; i [$W '.: /"/,/,

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0606100065 060417 REG 3 LIC70 i

SNM-1826 PDR For the U.S. Nuclear Regulatory Commission APR 171986 riginai Signed

. Date By William J. Adam, Ph.D.

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Prepared by Oak Ridge Associated CONFIRMATORY SURVEY Universities Prepared for OF THE U.S. Nuclear So**m"EisSns REUTER-STOKES FACILITY Region lli Office Supported by CLEVELAND, OHIO Safeguards and Materials Programs Branch; g,g,gggpgy Division of Inspection Programs:

Office of

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?;forcement Radiological Site Assessment Program Manpower Education, Research, and Training Division DRAF.T REPORT APRIL 1986 O

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DRAFT CONFIRMATORY SURVEY A

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REUTER-STOKES FACILITY CLEVELAND, OHIO Prepared by G. L. Murphy Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff E.L. Deming M.R. Dunsmore A.S. Masvidal Prepared for Safeguards and Materials Programs Branch Division of Inspection Programs Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region III Office DRAFT REPORT April 1986 This report is based on work performed under Interagency Agreement DOE No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S.

Nuclear Regulatory Commission and the U.S.

Department of Energy.

Oak Ridge Associated Universities performs complementary work under, contract number DE-ACO$-760R00033 with the U.S. Department of Energy.

This draf t report has not been given full review and patent clearance, and the dissemination of its information is only for of ficial use.

No release to the public shall be made without the approval of' the Office of Information Services, Oak Ridge Associated Universities.

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DRAFT TABLE OF CONTENTS O

te 11 List of Figures iii List of Tables 1

Introduction and Site History 1

Site Description Procedures..............................

1 Results 3

Conclusion..............................

4 13 References.........................

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DRAFT LIST OF FIGURES O

ram Figure 1:

Location of Reuter-Stokes Facility, Warrensville Heights, 6

Ohio......

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Reuter-Stokes, Inc. Partial Floor Plan, Warrensville Heights, 7

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Figure 3:

' Location of Total and Removable Alpha Contamination Survey 8

Points in Room 18 i

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Location of Total and Removable Alpha Contamination Survey 9

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Alpha Survey Results-Room 18 11 l

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REPORT OF ' DIE CONFIRMATORY SURVEY p

REUTER-STOKES FACILITY V

CLEVELAND, OHIO INTRODUCTION & SITE HISTORY From the mid-1960's until 1985, Reuter-Stokes operated a radiation detector assembly facility at 18530 South Miles Parkway, Warrensville Heights, Ohio (Figure 1).

The licensee was authorized by the Nuclear Regulatory Commission (NRC) to possess and use U-235 and Np-237 under SNM-1826, and other sealed sources under byproduct materials licenses 34-18156-01 and 34-18233-01.

The operational activities were terminated in 1985 and the facility was decontaminated. Close-out survey reports were presented to the NRC for review by Nuclear Sources and Services, Houston, Texas; Reuter-Stokes, Twinsburg, Ohio; and Applied Health Physics, Bethel Park, Pennsylvania. I-3 At the request of the NRC, Region III, the Radiological Site Assessment Program (RSAP) of Oak Ridge Associated Universities (0RAU) conducted a confirmatory survey and document review to determine if the facility satisfies the criteria for release for unrestricted use.

SITE DESCRIPTION Unsealed radionuclides were used in two rooms in the northwest corner of the building (Figure 2).

The former chemical laboratory (Room 18) is approximately 5 m x 7 m with a drop-in ceiling, 1 1/2 m below roof line.

The roofline is approximately 4 m above the floor.

The former detector assembly area (Room 19) is approximately 6 m x 7e with similar ceiling and roof dimensions.

Sealed sources were used in two small rooms located near the building loading dock.

PROCEDURES Document Review:

The NRC did not require the preparation of a decommissioning plan for this facility.

ORAU reviewed the close-out survey reports for the f acility prepared by three organizations:

1

DRAFT Nuclear Sources and Services, Houston, Texas.

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Measurements for removable alpha contamination, on the floors ' and lower walls (up to 3 m) indicate that these areas are within the release 2

guidelines of 20 dpm/100 cm for transuranic nuclides (Np-237).

No measurements are given for the drain (s), exhaust ducts, or roof.

The final survey does not report levels of total alpha contamination, survey instrument calibration procedures, nor calibration source certifia.ation documentation.

Reuter-Stokes, Inc., Twinsburg, Ohio.

Total alpha and beta-gamma data were presented for floors and lower walls (up to 3 m).

Although no data is presented for smears, drains, ducts or other structures, the report indicates these areas were ".

at background level".

s The survey methods were described and the instrumentation used in the survey was idectified.

All instrumentation had been calibrated by commercial laboratories.

An Eberline RM-20 ratemeter was used for total alpha contamination surveys.

This instrument is considered suitable for surveying, but, a digital scaler readout would have been more appropriate for contamination level measurements, considering the relatively low guideline value established by the NRC for Np-237.

Applied Health Physics, Inc., Bethel Park, Pennsylvania.

2 The report indicates total alpha contamination ranged from 0 dpm/100 cm to some unspecified maximum value, and the removable alpha contamination 2

ranged f rom 0 to 68.9 dpm/100 cm.

These samples were not analyzed by alpha spectroscopy to determine the radionuclide content.

If the 2

2 68.9 dpm/100 cm was due to Np-237, the 20 dpm/100 cm release criteria would have been exceeded. Exposure rate data is presented in the report, but nn supporting data is presented for total and removable alpha activity.

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DRAFT Applied Health Physics, Inc., also provided a Certificate of Radiological Safety, entitled " Release of Facilities for Unrestricted Use".

This certificate has no validity, because only the NRC has authority to release a facility from licensing restrictions.

Facility Survey:

The f acility had been renovated at the time of the ORAU survey.

The walls were painted, and new floor tile had been applied.

To perform confirmatory measurements, paint was removed, using commercial paint stripper, and floor tile and adhesive were removed using a chisel. Floor tile was removed from three grid blocks in Room 18 and six grid blocks in Room 19.

The locations were selected based on history of use (i.e. near hoods, floor drains, assembly areas, etc.) and elevated readings from the final survey reports. Paint scrapings were removed from three areas in Room 18, which -also had elevated readings from the final survey reports.

No paint scrapings were collected in Room 19.

Tile adhesive was collected from one grid block and residue from one floor drain in Room 18.

No tile adhesive or drain residue samples were collected in Room 19.

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In each grid block, where paint or individual tiles were removed all

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accessible areas were scanned using a portable scaler with alpha scintillation

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detectors.

The rooms were also scanned for elevated gamma radiation levels using a ratemeter with NaI(TI) detectors.

One smear sample was collected in each grid block where direct measurements were recorded, as well as in drains, ducts and other locations. Access to the roof was not possible at the time of the survey due to inclement weather (approximately 15 cm of snow).

RESULTS Room 18 (Figure 3)

Table 1 presents the confirmatory data for Room 18.

Comma exposure rates ranged from 9-10 DR/h, which is within the normal background range for buildings in this area.

The removable alpha contamination ranged from a b

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minimum detectable activity (MDA) of 3 dpm/100 cm2 to 23 + 3 dpm at the 3

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1 DRAFT cp:ning cf th] flur drcin.

Th2 tctc1 cipha c:ntonin;ticn rcng;d froa cn MDA of 18 dpm/100 cm2 to 286 dpm/100 cm,

2 Room 19 (Figure 4)

The alpha contamination survey results for Room 19 is summarized in Table 2.

Gamma exposure rates ranged from 9-10 pR/h.

The removable alpha 2

2 contamination ranged from an MDA of 3 dpm/100 cm to 4 + 1 dpm/100 cm,

2 The total alpha contamination ranged from an MDA of 18 dpm/100 cm to 2

286 dpm/100 cm.

The highest total and removable alpha contamination measurements were from the cold-air return duct, near the east wall.

Rooms 32 and 49 These rooms (sealed sources only) were gamma scanned.

No elevated levels above background (9-10 pR/h) were detected.

Direct contamination measurements and smears were not performed because the history did not indicate the use of unsealed sources.

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Miscellaneous Media Paint scraping, floor adhesive, and drain residue from Room 18 were analyzed by gamma spectroscopy in an intrinsic Ge well detector and the results are summarized in Table 3.

One representative paint sample and one floor adhesive sample contained small concentrations of U-235 (0.5 + 0.1 and 2.2 + 0.4 pCi/g); Np-237 was less than the MDC of 0.10 pCi/g.

Other paint samples were collected at locations 246W and 248W, however the gamma scan results indicated no detectable U-235 or Np-237 activity.

Rust scrapings / residue from the floor drain contained 258 + 2 pCi/g of U-235 and 0.5 + 0.4 pCi/g Np-237.

CONCLUSION Although no individual close out survey report presented sufficient data

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nor documentation for verification purposes, the combination of these 4

DRAFT reports, in total, provides adequate information to assess the effectiveness of the decontamination operation.

The results of our confirmatory sur"ey indicate no removable or fixed contamination in excess of the criteria for release of a facility for unrestricted use.

With the exception of the drain residue in Room 18, all 2,

the most restrictive removable alpha activity is less than 20 dpm/100 cm category for alpha emitters, Np-237.

However, the U-235 to Np-237 ratio in the residue is approximately 500 to 1, which indicates the Np-237 fraction 2

would be considerably less than 1 dpm/100 cm, within the release guidelines 2

for Np-237. All total alpha activity is less than 300 cpm /100 cm,

Based on the documents reviewed and independent measurements it is ORAU's opinion that the Reuter-Stokes, Inc. facility, 18530 South Miles Parkway.

Warrensville Heights, OH, satisfies the NRC guidelines for release of a facility for unrestricted use.

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ALPHA SURVEY RESULTS - ROOM 18 REUTER-STOKES, INC., CLEVELAND, OHIO a

Sample Location Total Alpha Removable Alpha No.

Activity Activity 2

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193F Floor

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<3 215F Floor 27

<3 543C Ceiling Hood Exhaust

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<3 5220 Ceiling Exhaust Duct

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<3 Upper Wall (Not Gridded)

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<3 Upper Wall Main Girder

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<3 Drain 5882 (18" Inside) c

<3 Drain 5882 (Lip) 286 23 + 3b 245W Wall 45

<3 246W Wall 63

<3 248W Wall 81

<3 aRefer to Figure 3.

(~xx_) bErrcr reported at the 95% confidence level based on counting statistics

only, cArea not accessible by alpha scintillation detector.

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1 DRAFT TABLE 2 ALPHA SURVEY RESULTS - ROOM 19 REUTER-STOKES, INC., CLEVELAND, OHIO Sample Locationa Total Alpha Removable Alpha No.

Activity Activity 2

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<3 37F Floor

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<3 42F Floor 61

<3 Heat Duct West 134

<3 Heat Duct East 89

<3 Duct Cold Air Return 286 4+lb Drain Lip (18 6

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bError reported at the 95% confidence level based on counting statistics only.

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RADIONUCLIDE CONCENTRATIONS IN MISCELLANEOUS MEDIA REUTER-STOKES, INC., CLEVELAND, OHIO Sample Locationa Radionuclide Activity (pCi/g)

No.

U-235 Np-237 Paint 5880P Wall 0.5 + 0.lb

<0.10 Adhesive 5881A Floor 2.2 + 0.4

<0.07 Residue 5882 Drain 258.0 7 2.0 0.5 + 0.4 aRefer to Figure 3.

b rror reported at the 95% confidence level based on counting statistics E

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DRAFT REFERENCES 7

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1.

Final Report - Decommissioning Survey Report the Reuter-Stokes Facility, 18530 South Miles Parkway, Warrensville Heights, Ohio, by Nuclear Sources and Services, Inc., dated 01/22/86.

2.

Decontamination Report for 18530 South Miles

Parkway, Warrensville Heights, Ohio, by Reuter-Stokes, Inc., dated 01/27/86.

3.

Radiation Survey Report and Certification for Release for Unrestricted Use of the facilities formerly used by Reuter-Stokes Company, 1850 (sic) South Miles Road, Warrensville Heights, Ohio, by Applied Health Physics, Inc.,

dated 1/20/86.

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Action File Note and Retum Approwel For Clearance Per Convestation As Requested FeH:orrection Propero Reply Circulate Lfor Your Infosmetion See Me com e.,t in,esti t.

.i.n.t.,e Coordination Justify REMARKS d

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PQ ) if DO NOT was this form as a RECORD of approvels, concurrowes, disposess, cleerences, and similar actions FR004:(Name, org. symLof, Agency / Post)

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CPO 1983 0 - 381-529 (317)

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@ reuter-stokes Edison Park,8499 Darrow Rd., Twinsburg Ohio 44087. Telephone (216) 425-3755 February 17, 1986 U.S. Nuclear Regulatory Commission Materials Licensing Section Region III 799 Roosevelt Road l

Glen Ellyn, IL 60137

Reference:

Special Nuclear Material License SNM-1826 Control Number 80601 By-Product Material License 34-18156-01 Control Number 80602 By-Product Material License 34-18233-01 Control Number 80603 Reuter-Stokes letter dated January 27, 1986 Reuter-Stokes Decontamination Report dated January 27, 1986 Centlemen:

In the Reuter-Stokes, Inc. Decontamination Report for 18530 South Miles Parkway, Warrensville Hts., Ohio, 44128, dated January 27, 1986, in Section VIII. 3, we reference a survey conducted by Applied Health Physics for the potential new owner of the facility, ACOR Orthopaedic.

W are submitting a copy of this report as additional supplemental

' iformation for your review. Applied Health Physics, Inc.

hts certified the facility meets the criteria for unrestricted tse.

Sincerely, REUTER-ST0KES, INC.

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Vice President, Operations Radiation Safety Officer GP:hm Enclosure g

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This is to certify that the facilities and/or equipment described below have been surveyed Jj ij by the undersigned using calibrated instrumentation as indicated and at the time of survey, f

were found to comply with accepted radiological safety. standards as noted on the reverse yp li side of this certificate.

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Radiation source:

Uranium-235 and Neptunium-237. Si. 9 d Instrumentation: Ludlum Instrument Co., Model 19 Micro-R Meter, s/n 37379 [:( Ludlum Instrument Co., Model 61 Alpha Meter s/n 36870 f j .[ This survey was performed on Jan. 9:10:11. 1986 ~ h' J q k,

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Y RADIATION SURVEY REPORT and CERTIFICATION FOR RELEASE FOR UNEESTRICTED USE of facilities formerly used by REUTER-STOKES COMPANY 1850 South Miles Road Warrensville Heights, Ohio 44128 This Radiological Survey was performed on Jan. 9, 10, & 11, 1986 APPLIED HEALTH PHYSICS, Inc. Bethel Park, PA 15102 l for ACOR ORTHOPAEDIC 4129 Mayfield Road Cleveland, Ohio 44121 U.S.A. Respe fully ubmitt By: January 20, 1986 Gallaghar, CHP, PE Pres t i

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s. HE LTH PHYSICS 3 O..Ox m. m m e,ex.... m e2 gmeyg ONE PROFESSIONAL SOURCE FOR ALL RADIATION SAFETY SERV' 'ES. I-

HEALTH PHYSICS inc. Phone 412 563 2242 Bethel Park. Pa.15102 2986 Industrial Blvd.

Box 197 The objective of this survey was to confirm that the facility owned by Reuter-Stokes, Inc., an affiliate of The General Electric Company, located at 18530 South Miles Parkway, Warrensville Heights, Ohio, satisfies the current criteria in order to have 1,t released for unrestricted use.

The bulk of the radionuclides handled were Uranium 235 and Neptunium 237. The processing of these radioactive materials was limited to two rooms located in the northwest area of the facility. Both rooms were controlled access areas. A shower facility located next to the chemistry room and a restricted area used to store sealed sources were also included in this survey. The Guideline used to determine that radioactivity has been reduced to levels currently accepted by the Nuclear Regulatory Commission was Appendix I, Guidelines for Decontamination of Facilities and Equipment prior to Release for Unrestricted Use or Termination of Licenses for By-Product, Source, or Special Nuclear Material. The latter was issued in July of 1982 by the U.S. Nuclear Regulatory Commission. Since the survey areas referred to as the Chemistry Lab and Assembly Rooms had been reconstructed, i.e., adhesive and tile covering the floor and new paint applied to the walls, only a limited alpha radiation survey could be performed. This survey included a smear test to determine if any loose or easily tr'ansferable radioactive contamination existed on the exposed surfaces. CONS U LT ATION SERVICES

PRODU CTS R AOl ATIO N APPLIC ATIO N S

Pg. 2 of 3 In conjunction with this, a fixed alpha survey using Ludlum Model 61, air proportional alpha survey meter, was performed along with an extensive gamma radiation study

to determine if there were any areas of increased gamma exposure rates.

The results are as follows: Alpha surface contamination ranged from a low of 0 dpa/100cm2 in Sample Location A-74425 on the exposed block wall, in the rear of the Chemistry Lab above the ceiling tiles. The highest amount of removable alpha radioactivity was noted around the top exterior surface of an exposed floor dra.in. This drain, (Smear Area A-74610), located in the lower right quadrant of the Chemistry Lab revealed removable alpha activity at 68.9 dpa/100cm2 The pipe interior, (Sample Area A-74570), proved to be 22.5 alpha dpa/100cm2 Both of these areas are within N.R.C. 2 Guideline limits for U-235 and associated decay products, 1000 dpa/100cm, Floor tiles were removed in selected areas within both the Chemistry and Assembly Rooms. No removable radioactivity was detected over background. t All duct work, light fixtures, door handles and vector paths leading into and exiting the two areas showed no increased activity over background. A slight increase in alpha activity (Smear Area A-74586) was detected on the exterior roof at the exit point of the left roof vent which serviced the fume hood once located within the Chemistry Lab, 33.14 dpa/100ced. Again, well within N.R.C. Guideline limits. No removable alpha activity was detected in the adjacent shower area nor the storage area. No fixed alpha surface contamination was detected within the survey area with the A calibrated Ludlum Model 19 Micro-R Mater, s/n 37379 was used to measure gamma radiation. .m.

1 Pg. 3 of 3 l exception of Area A-74610, the top exterior surface of the exposed floor drain located in the lower right quadrant of the Chemistry laboratory, 2 500 alpha dpa/100cm,* Again, within N.R.C. Guideline requirements. Figure 1 is a copy of the floor plan of the building which shows that the gamma radiation levels detected are within normal background levels. Gamma exposure rates ranged from 9 to 13 pR/h. The gamma background outside the facility was 7-9 pR/h. Air particulate concentrations in both the Chemistry Lab and Assembly Room are below those limits stated for unrestricted areas in Part 20, Appendik B _N.R.C. Standards for Protection arainst Radiation, for the radionuclides Np-237 and U-235. Included with this report are the results of gasma survey performed in both the Chemistry Lab and Assembly Room as well as selected spots within the facility. Other data will be furnished upon request. The facility, owned by Reuter-Stokes, Inc., an affiliate of The General Electric Company, located at 18530 South Miles Parkway, Warrensville Heights, Ohio, meets the requirements, in order to be released for unrestricted use. Enclosed is a certificate of Radiological Safety an release for l unrestricted use which was issued by Robert C. Gallagher, CHP, for the above named, facility. 1,

Ludlum Model 61, s/n 16870 1

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u ROOM ORIENTATION DRWG. Ganna Survey of Chenistry Area Roon Flooc(referencea to ricop plan or uuilding: AREA 18). ~ Each tile square floor surface was surveyed for sanna radia-tion with the Ludlun Model 19 Mi cro-R Me.ter ISer. No 373793. This type of survey w.ould show any ganna enitter radionuclid presen t under the tile floop, e i This survey also documents the anbient sanna exposure to per-sonnel in the area. l l 4 I TERmt5 TAT 1 %. E Pil8NE l l 1,Mn KIN 12 3 4 5 E 15115121217A J ff1Jfffif111I1 y ,I f f / ? ! J 4 ? I." ! l l 4l l U11111/1/111111 'l )///1if11/J]//1 illt1111111liff l31 i11i?f11111111 ,1 4i rIJi??t?IJfI? \\ 'l11IIi11111Ii11 gyg $1 //11//11111//1 i 4IIii1iifiIiiiI JJ!1!I1Ii11Ii11 I rI ii!I i! 't I rit Olif111/111filli Hf}}}}}}}}}]/11) 0111111111Illi11

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1 y GAMMA SURVEY OF CHEMISTRY ROOM (Floor) Tila pR Reading Tile pR Reading Tile pR Reading Tile pR Reading Tile pR Readin; Loc ~ tion pR/hr. Location pR/hr. Location pR/hr. Location pR/hr. Location pR/hr. A-1 10 D-1 10 G-1 11 J-1 10 M-1 9 A-2 9 D-2 10 G-2 10 J-2 9 M-2 10 A-3 10 D-3 9 G-3 10 J-3 10 M-3 10 A-4 11 D-4 9 G-4 10 J-4 10 M-4 9 A-5 11 D-5 10 G-5 10 J-5 9 M-5 10 A-6 11 D-6 10 G-6 10 J-6 11 M-6 9 A-7 11 D-7 9 G-7 10 J-7 11 M-7 10 A-8 11 D-8 10 G-8 10 J-8 10 H-8 10 l A-9 11 D-9 10 G-9 10 J-9 10 M-9 11 A-10 10 D-10 9 G-10 10 J-10 10 M-10 10 A-11 10 D-11 10 G-11 9 J-11 10 M-11 10 A-12 10 D-12 10 G-12 9 J-12 10 M-12 10 A-13 10 D-13 10 G-13 10 J-13 11 M-13 9 A-14 11 D-14 10 G-14 10 J-14 11 M-14 9 B-1 9 E-1 9 H-1 9 K-1 10-N-1 10 B-2 10 E-2 10 H-2 10 K-2 10 N-2 9 B-3 10 E-3 10 H-3 9 K-3 10 N-3 9 B-4 10 E-4 10 H-4 9 K-4 9 N-4 10 B-5 11 E-5 10 H-5 9 K-5 11 N-5 10 B-6 10 E-6 10 H-6 10 K-6 10 N-6 10 B-7 10 E-7 10 H-7 10 K-7 10 N-7 9 B-8 11 E-8 9 H-8 11 K-8 10 N-8 10 B-9 10 E-9 11 H-9 10 K-9 9 N-9 10 B-10 9 E-10 11 H-10 11 K-10 10 N-10 10 B-11 10 E-11 9 H-ll 11 K-11 10 N-11 9 B-12 10 E-12 10 H-12 10 K-12 11 N-12 10 B-13 11 E-13 10 H-13 11 K-13 10 N-13 10 B-14 10 E-14 10 H-14 10 K-14 11 N-14 11 l C-1 10 F-1 10 I-l 10 L-1 10 0-1 10 C-2 11 F-2 10 I-2 11 L-2 10 0 -2 10 C-3 9 F-3 11 I-3 10 L-3 11 0-3 9 C-4 10 F-4 10 I-4 10 L-4 10 0-4 10 C-5 10 F-5 10 I-5 10 L-5 10 0 -5 10 C-6 10 F-6 9 I-6 9 L-6 10 0-6 10 C-7 10 F-7 10 I-7 10 L-7 11 0-7 11 C-8 10 F-8 10 I-8 11 L-8 11 0-8 10 C-9 10 F-9 10 1-9 11 L-9 10 0-9 10 C-10 10 F-10 9 I-10 10 L-10 10 0 -10 9 i C-ll 10 F-11 10 I-11 11 L-11 10 0 -11 10 C-12 10 F-12 10 I-12 10 L-12 10 0 -12 11 C-13 11 F-13 11 1-13 10 L-13 10 0 -13 10 C-14 10 F-14 11 1-14 11 L-14 10 0 -14 10 l e J

1 1 Pg. 2 of 2 GAMMA SURVEY OF CHEMISTRY ROOM (Cont.) Tila pR Reading Tile pR Reading Tile ydt Reading Tile pR Reading Tile pR Reading oc" tion uR/hr. Location pR/hr. Location pR/hr. Location pR/hr. Location pR/hr. s P-1 11 S-1 9 P-2 10 S-2 9 P-3 11 S-3 11 P-4 10 S-4 11 P-5 10 S-5 10 P-6 10 S-6 10 P-7 10 S-7 9 P-8 10 S-8 10 P-9 10 S-9 10 P-10 10 3-10 11

P-11 10 S-11 10 P-12 10 S-12 11 P-13 10 S-13 10 P-14 10 S-14 10 Q-1

'10 T-1 9 Q-2 10 T-2 10 Q-3 9 T-3 11 Q-4 10 T-4 11 Q-5 10 T-5 11 Q-6 10 T-6 10 Q-7 10 T-7 10 Q-8 10 T-8 10 Q-9 10 T-9 9 Q-10 10 T-10 10 Q-11 11 T-11 9 Q-12 10 T-12 10 Q-13 10 T-13 11 Q-14 11 T-14 9 R-1 9 U-1 10 R-2 9 U-2 10 R-3 10 U-3 10 l R-4 10 U-4 10

R-5 10 U-5 11 l R-6 10 U-6 11 lR-7 10 U-7 11 R-8 10 U-8 11 R-9 10 U-9 10 R-10 10

.U-10 11 ' R-11 9 U-11 11 ' R-12 10 U-12 11 R-13 10 U-13 11 , 1-14 9 U-14 10 L tteid2 the building gamma background: 7-9 pR/hr. Ambient gamma background in Chemistry Reen 3' high: 10 pR/hr. Ludlum Model 19 Micro R Meter (S/N 37379)used. Calibrated on 12/11/85, Void after 3/11/86. Gridded by boundaries of l' x l' tile squares. I Notot These are actual readings with no background subtracted. Survey Performed By: Nathaniel L. Butden, Jr. Date Performed: 1/10/86 e

( l GAMMA SURVEY OF ASSEMBLY AREA ROOM (Floor) Tilo pR Reading Tile pR Reading Tile pR Reading Tile yR Reading Tile pR Reading Locetion 3R/hr. Location pR/hr. Location pR/hr. Location pR/hr. Location pR/hr. A-1 13 C-1 12 E-1 12 G-1 11 1-1 10 A-2 11 C-2 11 E-2 11 G-2 11 I-2 11 A-3 12 C-3 10 E-3 10 G-3 11 I-3 11 A-4 11 C-4 11 E-4 10 G-4 11 1-4 12 A-5 11 C-5 11 E-5 11 G-5 10 I-5 12 A-6 11 C-6 11 E-6 11 G-6 10 I-6 10 A-7 12 C-7 10 eE-7 11 G-7 11 I-7 10 A-8 11 C-8 11 E-8 A-9 10 C-9 10 3-9 12 G-9 10 I-9 9 G-8 11 I-8 10 A-10 11 C-10 10 1>-10 11 G-10 10 I-10 10 A-ll 10 C-11 10 E-11 10 G-11 10 I-11 11 A-12 9 C-12 10 E-12 10 G-12 11 I-12 12 A-13 10 C-13 10 E-13 10 G-13 10 1-13 12 A-14 10 C-14 10 E-14 11 G-14 9 I-14 9 A-15 9 C-15 10 E-15 11 G-15 10 I-15 10 A-16 9 C-16 10 E-16 11 G-16 10 I-16 11 A-17 9 C-17 10 E-17 10 G-17 10 I-17 10 A-18 11 C-18 10 E-18 10 G-18 10 I-18 10 A-19 10 C-19 10 E-19 10 G-19 9 I-19 12 A-20 12 C-20 10 E-20 10 G-20 9 I-20 10 B-1 12 D-1 11 F-1 13 H-1 11 J-l 12 B-2 12 D-2 12 F-2 11 H-2 12 J-2 11 B-3 11 D-3 10 F-3 11 H-3 11 J-3 12 B-4 11 D-4 12 F-4 11 H-4 11 J-4 11 B-5 10 D-5 11 F-5 11 H-5 11 J-5 11 B-6 11 D-6 11 F-6 12 H-6 11 J-6 11 B-7 12 D-7 11 F-7 11 H-7 10 J-7 11 B-8 10 D-8 10 F-8 11 H-8 11 J-8 10 B-9 11 D-9 9 F-9 10 H-9 11 J-9 10 B-10 12 D-10 11 F-10 11 H-10 11 J-10 10 B-11 10 D-ll 10 F-11 11 H-11 11 J-11 11 B-12 10 D-12 10 F-12 10 H-12 11 J-12 11 B-13 10 D-13 10 F-13 10 H-13 10 J-13 9 B-14~ 10 D-14 10 F-14 10 H-14 10 J-14 10 B-15 9 D-15 9 F-15 10 H-15 10 J-15 10 5-16 9 D-16 10 F-16 10 H-16 10 J-16 11 3-17 10 D-17 9 F-17 10 H-17 9 J-17 10 h18 10 D-18 10 F-18 10 H-18 10 J-18 10 1-19 11 D-19 9 F-19 10 H-19 9 J-19 10 1-20 11 D 10 F-20 10 H-20 11 J-20 11 9 J

' /. .~ Pg. 2 cf 3 CAltfA SURVEY OF ASSEMBLY AREA ROON(Cont.) i i Tilo pR Reading Tile pR Reading Tile pR Reading Tile pR Reading Tile pR Reading lc" tion pR/hr. Location uR/hr. Location pR/hr. Incation pR/hr. Location pR/hr. K-1 11 N-1 12 0-1 11 Q-1 13 S-1 11 i K-2 11 M-2 11 0-2 12 Q-2 11 S-2 10 K-3 12 M-3 10 0-3 11 Q-3 10 S-3 10 K-4 11 M-4 12 0-4 11 Q-4 11 S-4 11 K-5 10 M-5 11 0-5 10 Q-5 12 S-5 11 ,K-6 10 M-6 11 0-6 10 Q-6 10 S-6 11 K-7 11 M-7 11 Q-7 11 Q-7 10 S-7 11 K-8 12 M-8 10 0-8 11 Q-8 10 S -8 10 K-9 11 M-9 11 0-9 11 Q-9 11 S-9 12 <K-10 10 M-10 11 0-10 11 Q-10 10 S-10 10 K-11 10 M-11 10 0-11 10 Q-11 10 S-11 10 ,K-12 9 M-12 11 0 -12 12 Q-12 11 S-12 11 K-13 11 M-13 11 0-13 10 Q-13 10 S-13 11

K-14 10 M-14 11 0-14 10 Q-14 11 S -14 10

,K-15 10 M-15 12 0 -15 11 Q-15 10 s-15 10 ,K-16 11 M-16 11 0-16 10 Q-16 10 S-16 10

K-17 11 M-17 10 0-17 12 Q-17 10 S-17 11

+

K-18 11 M-18 10 0 -18 11 Q-18 11 S-18 10 K-19 11 M-19 11 0 -19 12 Q-19 10 S-19 10 lK-20 11 M-20 12 0-20 10 Q-20 10 S-20 11 l L-1 12 N-1 11 P-1 11 R-1 12 T-1-62Y1f8818 iL-2 1: t N-2 10 P-2 10 R.2 11 T-2 11 lL-3 11 N-3 11 P-3 11 R-3 12 T-3 11; L-4 1.2 N-4 10 P -4 10 R-4 11 T-4 11 i L-5 10 N-5 10 P -5 10 R-5 10 T-5 11

)L-6 11 N-6 11 P-6 11 R-6 10 T-6 11 lL-7 11 N-7 11 P-7 10 R-7 11 T-7 11

L-8 11 N-8 9

P -8 11 R-8 9 T-8 11 L-9 11 N-9 10 P-9 10 R-9 10 T-9 10 t-10 10 N-10 10 P -10 10 R-10 10 T-10 11 i lL-11 10 N-11 10 P-11 10 R-11 11 T-11 12

L-12 10 N-12 10 P -12 10 R-12 10 T-12 11
L-13 10 N-13 10 P-13 11 P-13 10 T-13 11 jL-14 10 N-14 10 P -14 11 R-14 10 T-14 11

!L-15 10 N-15 10 P -15 10 R-15 10 T-15 11 !L-16 9 N-16 11 P -16 11 R-16 10 T-16 10 !L-17 10 N-17 12 P.17 11 R-17 11 T-17 10

L-18 10 N-18 12 P -18 10 R-18 11 T-18 10 lL-19 11 N-19 11 P-19 11 R-19 11 T-19 11: L-20 10 N-20 11 P-20 10 R-20 10 T-20 10 t

, +. ,, _. - -..,,, _, - _ -.,., - - - -.,, _, - -,,,,,. - _,, _. -. - - - -.,,. _ -.... _ _ _ =. - -

1 7 /. Pg. 3 of 3 CAMMA SURVEY OF ASSEMBLY AREA ROOM (Cont.) filo pR Reading Tile pR Reading Tile pR Reading Tile pR Reading Tile pR Reading

tion pR/hr.

location pR/hr. Location pR/hr. Iocation pR/hr. Location pR/hr. U-1-h$((f$,81h U-2 13 U-3 13 U-4 12 U-5 11 0-6 13 U-7 12 U-8 12 'J-9 13 U-10 11 'J-11 11 J-12 11 J-13 11 J-14 11 J-15 10 J-16 11 J-17 11 J-18 11 J-19 10 J-20 11 'ut ide the building gamma background: 7-9 pR/hr. Ambient background in Assembly .oom: 10 pR/hr. at 3' high in center of room. Ludlum Model 19 Micro R Meter (S/N 37379)used. 'clibrcted on 12/11/85 Void after 3/11/86. Gridded by boundaries of l' x l' tile squares. .oto These are actual readings with no background subtracted. urvey Parformed By: Nathaniel L. Burden, Jr. Date Performed: 1/9/86

l ROOM ORIENTATION DRWG. 'l i Gaema Survey of Assenbly Area Roon Floos(metecenced to floop plan of building: AREA 19). i Each tile squace floop seface was seveyed for sanna cada - tion with the LudIun Mode' 9 Mi cro-R uster [Ser. No. 37399 This type of survey would show any ganna enitter radionuolid present under the tale floop.e ( This sevey also docuseents the anbient ganna exposee to pop-sonnel in the area. e..g s DIRE ELEC.58L M II f 4 4 1214 5 5 7 8 919111t GPelllE171gl4 31 l hiffill//III//J///J/11 I Of11111111111111111111 i Cif1111111111111111111 l D111111111111111111111 l Cf11111111111111111111 V11IIif11111111II1Iii1 Qi1ifi111111Ii11111111 l %fi111111Ii11iI1ifi11I 1111111111111111111111 31111liff111111111111I Xf1til1111111111111111 a kliIi11i1 1ifi11fi1 111i hi1ifi11/i111i11i11111 NI t i l z i r i i i 11111111111 Nifi1ifi11fi1iff1ifi1 9111iI11II11i1111i1111 bl1i111111111111111111 R111121111ifi1ifi11/11 l jiIIIIIIIIIJIIIJfII1iI i T1111ifi1ifi1ifi1ifi11 QALIliff 11111111111fIl

~- I 'l .@ reuter-stokes (p% Edison Park 8499 Darrow Road ' op, Tk gS.U-Twinsburg, Ohio 44087 / 216/425-3755 Telexi 985253 0 January 27, 1986 U. S. Nuclear Regulatory Commission Materials Licensing Section Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Reference:

Reuter-Stokes, Inc. Special Nuclear Material License SNM-1826 Control Number 22365 Reuter-Stokes, Inc. By-Product Material License 34-18156-01 11-h E# 8 Control Number 78288 Reuter-Stokes Instruments, Inc. By-Product License 34-18233-01 il - 1.MB Control Number 15513 N.R.C. letter dated May 2, 1985 Gentlemen: 6 We have decontaminated and decommi ssioned our facility located at 18530 South Miles Parkway. Enclosed are copies of the close-out surveys. We request that you review the survey reports and release the facility for unrestricted use. The renewal of our R-S Instruments By-Product License, where we had requested to use a one milicurie Cobalt-60 sealed source at our 19701 South Miles leased facility, came in one month after we had moved the operation to Edison Park. No survey was taken since there was no processing or storage of radioactive material at this location. In addition to the close-out survey report, we are submitting the following information as requested in your letter of May 2, 1985: a) A diagram of the 18530 South Miles Parkway facility is enclosed. The smaller diagram shows the areas where radioactive materials were used and stored, and which are included in the surveys. The ~ larger diagram locates these areas within the entire facility. i r r,n gi / b) 'wo surveys were performed. The first was done by Nuclear ff0 8 g Sources and Services, Inc., P.O. Box 34042, Houston, Texas v T7234. The second survey was performed by Reuter-Stokes g7 Engineering and QA personnel under the supervision of the j adiation Safety Officer. c) ~ lhe Nuclear Sources and Services, Inc. survey was performed on b 3 Ng y -Qctober 10-13, 1985, and is dated January 22, 1986. The Reuter-Stokes survey was performed over the period of October 19, 1985, hEud (ur to December 10, 1985, and on January 23, 1986. The comoined G p urvey report is dated January 27, 1986. NOO [. th. - continued -

F 3 $ reuter-stokes Edison Pak Twinsberg. Ohio 44087 January 27, 1986 Page 2 - continued d) The instrumentation used for the survey measurements is described in the survey report. Certificates of calibration are also part of the survey report. e) Background readings are included in the survey data. We are presently in active negotiations to sell the 18530 South Miles Parkway property and would greatly appreciate a prompt review of the survey report. Sincerely, REUTER-ST0KES, INC. Geor alko Vice President, Operations Radiation Safety Officer GP:cIn enc.

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I ) NUCLEAR SOURCES & SERVICES, INC. AREA CODE 71316414391 HOUSTON, TEXAS 77234 ) P. O. BOX 34042 January 24, 1986 Reuter Stokes ) Edison Park 8499 Darron Rd. Twinsburg, OH 44087 ATTN: Mr. George Palko )

Dear Mr. Palko:

Enclosed is the final report on the decommissioning of the South Miles Road facility. ) I apologize for not completing it sooner. If there are any further questions, please contact me. l Sin er ly ) Charles T. G lagher Technical Services Manager CTG /bc Ref.#86081 i i i h l l ) 1 SHIPPING ADDRESS: 5711 ETHERIDGE / HOUSTON, TEXAS 77087 l

I ~ H NV. I j O, t I C) P .O. Final Report Decommisioning Survey Report The Rueter Stokes Facility Located at 18500 South Miles Road Warrensville Heights, Ohio 44128 C) Conducted by Nuclear Sources & Services. Inc., Houston Texas Januar / 22, 1986 ,O l t l' c f' O' r GD { 1 0 1 4.,,,w..

) D Introduction ] The following report was prepared to document that the facility at 18530 South Miles Rd. Warrensville, Ohio has been decontaminated of any residual radioactive contamination, down below current acceptable release levels recommended by the Nuclear Regulatory Commission. The objective of the decontamination efforts initiated by Reuter-Stokes. Inc. (the facility owner) was not only to meet the requirements prescribed by the NCR, but to assure that any residual contaminates were at least one order of magnitude (1/10) of the release for unrestricted usage levels. History From the mid-1960's to the present, the areas herein refered to as the Chemistry Lab and Assembly Area had been utilized as radioactive material handling areas. The radionuclides predominetly handled were Uranium 235 and Neptuntum 237, used in the manufacture of radiation detection equipment. The ) radionuclides were chemically plated onto foils inside the fume hoods in the Assembly Area. (See Map 1) In 1985 the company aquired a new facility location to accomadate the company. NSSI was contacted in August 1985 to conduct a preliminary study for contamination in order to formulate plans for the decontamination of the premises and a J final comprehensive survey to qualify the facility for unrestricted use. Preliminary Survey Since the radionuclides of interest were alpha emmitters, a -sJ survey utilizing a portable alpha scintillation probe and ratemeter was conducted on August 7, 1985 to locate areas within the facility where surface contamination might reside. In addition a wipe survey was preformed to determine the difference between fixed contamination and removable contamination. The wipe surveys were measured using both an alpha scintillation probe in 3 conjunction with a scaler /ratemeter and a liquid scintillation counter to document that no other radionuclides beside the previously mentioned alpha emmiters were present. 'O i 2 ,D

l l; The results of the preliminary wipe survey were as follows: Alpha Scintillation dpm/100 Liquid Scintillation Counter Location Sample # Removed dpm/100 Sq. Cm. gross cpm /100 So Cm. Map # 3 1 12 30 2 2 36 62 2 3 7 24 2 4 39 66 2 5 27 50 2 U 6 6 22 2 7 12 30 2 8 9 26 2 9 18 38 2 10 104 152 2 11 6 22 2 12 28 52 2 13 7 24 2 14 6 22 2 15 24 46 2 16 19 40 2 17 31 56 2 18 21 42 2 19 197 274 2 20 113 164 3 21 587 790 3 22 15 34 3 23 56 88 3 24 16 36 2 25 89 132 3 26 92 136 3 27 12 30 3 28 6 22 3 29 0 14 3 -'d 30 13 32 3 31 17 24 2 32 50 80 2 dpm = disintergrations per minute cpm = Counts per minute Ludlum Alpha Scintillation Probe 43-1 S/NP495 Ludlum Model 2200 scaler /ratemeter S/N12224 O Packard Tri Carb Liquid Scintillation Counter D 3 0

D 3 3 Decontamination Action Although the prellmanary surveys located only several pieces of equipment that would be above the release levels specified for unrestricted use in. 100 dpm/100 sq.cm. the management at Rueter-

Stokes, Inc.

stated that they wanted the decontamination to be D more conservative then the NRC's limits by a factor of 10 less. This level set by Rueter-Stokes essentially would bring the facility down to natural background levels. On October 9, 1985 the decontamination of the facility was initiated. All items intended for usage at the new facility which exhibited any indication of contamination using an alpha scintillation probe and 3 ratemater, were properly packaged and transported according to Department of Transportation Title 49 Code of Federal Regulations. The next step was to remove and package all the items that were to be removed for disposal to a licensed low levei radioactive waste site. The items included the following: O Items Locations Stand up Hood Chemistry Lab 2-5 Orawer Cabinets Chemistry Lab Desk Chemistry Lab 2-Shelves Bathroom Lab Bench with Sink Chemistry Lab g Glove Box Assembly Area Locker Cabinet Assembly Area Benches under Vented Area Chemistry Lab Balance Table Chemistry Lab Fume Hood Chemistry Lab Fume Hood Bench Chemistry Lab O 26-55 gallon drums containing: Ceiling Tiles. Light Fixture, Tile Floors. Plumbing. Duct work from all Fume Hoods and Vented

Areas, Motors from Air Blowers, Liquid Wastes, Neptumium 237

& Uranium 235 wastes and miscellaneous objects. O O 4 O

c ' ~ i m s + P / Final Survey / ' ] When all removable items were removed, a final contamination survey was performed by griding the floors of interest into 1 meter by I meter squares. The same was done to the walls to a height of approximately 3 meters high (see attachments). Each grid square was surveyed for both fixed and removable contamination. J All wipe surveys were also measured for non alpha emmitting radionclides with the use of a IIquid scintillation counter. The results were as follows: Alpha Counter LSC Location Wipe Sample # Removable dpm/100 Sq. Cm. Removable cpm /100 Sq.Cm. Map # D l 84 4 2 1 54 4 3 3 30 4 4 2 34 4 5 1. 52 4 6 5 30 4 3 7 1 36 4 8 2 54 4 9 0 42 4 10 1 36 4 11 0 26 4 12 1 44 4 9 13 0 54 4 14 0 74 4 15 2 44 4 16 1 52 4 17 0 46 4 18 1 22 4 q 19 1 34 4 20 0 38 4 21 2 46 4 22 0 32 4 23 1 52 4 24 2 70 4 25 2 46 4 m ' 26 0 42 4 27 0 26 4 28 0 38 4 29 0 30 4 30 0 30 4 31 3 38 4 ,a ~ / 5 m y,$ M p.

O. O' Alpha Counter LSC Location g-Wipe Sample # Removable dpm/100 Sq. Cm. Removable cpm /100 Sq.Cm. Map # 32 1 26 4 33 0 30 4 34 0 32 4 1 35 0 40 4 36 0 38 4 O 37 o 4a 4 38 3 46 4 39 5 48 4 40 0 48 4 41 2 32 4 42 ' l 36 4 0 43 2 48 4 44 3 58 4 45 3 56 4 46 0 66 4 47 3 44 4 48 4 48 4

0 49-1 62 4

50 1 74 4 51 0 63 4 52 3 58 4 53 3 66 4 54 2 38 4 0 55 0 48' 4 4 - 56 0 34 4 57 - 2 42 4 58 3 54 4 59 0 58 4 i 60 3 56 4 .O 61 3 64 4 i 62 2 70 4 63 3 54 4-l 64 0 50 4 l -65 2 76 4 66 0 78 4 0 67 0 48 4 69 0 50 4 69 5 74 4 r 70-2 30 4 71-2 56 4 s. 72 2 40 4 n. N 73 4 76 4 6 O ..r.- ...,r. ,,-,...m_-_.- ,..m_.. ,.-_.-_,y .,.-,,._--,-y....,.

~O-1 l 'O Alpha Counter LSC Location

O Wipe Sample #

Removable dom /100 Sq. Cm. Removable dpm/100 Sq.Cm. Map # 74 4 66 4 75 1 56 4 76 1 48 .4 i 77 0 40 4 ~O 78 0 50 4 79 2 70 4 80 4 66 4 81 4 44 4 i 82 4 58 4 83 1 62 4 ?O. 84 2 66 4 85 3 72 4 86 4 66 4 87 1 44 4 88 4 72 4 89 5 54 4 'O 90 2 80 4 91 62 4 92 '4 32 4 93 3 54 4 94 1 60 4 4 95 2 66 4 !O 96 2 40 4 97 2 56 4 98 4 46 4 99 2 70 4 i 100 1 40 4 I 101 3 38 4 102 2 44-4 O 103 2 28 4 104 0 42 4 105 2 30 4 106 3 60 4 f 107 4 40 4 08 7 32 4 'O 109 8 40 4 4 110 6 52 4 til 5 34 4 112 4 56 4 113 5 38 4 fg i!4 2 28 4 t 7 O

r v 'O i 1 Alpha CoLqter LSC Location O Wipe Sampia # Removable dom /100 Sq. Cm. Removable cpm /100 Sq. Cm. Map # 115 3 30' 4 3 116 7 36 4 117 2 36 4 118 3 38 4 'O I19 1 38 4 120 4 56 4 121 3 30 4 122 7 52 5 123 5 54 5 124 4 26 5 'O 125 4 70 5 126 3 42 5 128 5 40 5 .129 4 44 5 130 1 60 5 131 4 58 5 'O 132 0 42 5 133 2 52 5 134 6 42 5 135 5 66 5 136 4 40 5 i 137 4 56 5 138 2 62 5 lO 139 1 48 5 140 2 44 5 L I41 4 48 5 142 2 42 5 143 3 52 5 {O 144 1 42 5 145 2 66 5 146 6 40 5 147 4 46 5 148 6 58 5 149 5 60 5 150 5 52 5 O 151 7 56 5 152 3 48 5 153 0 58 5 i 154 2 42 5 l 155 8 46 5 156 2 54 5 .O 8 .;O

5

O '

4 lO' Alpha Counter L5C Location O Wipe Sample # Removable dom /100 Sq. Cm. Removable cpm /100 54. Cm. Map # 157 5 64 5 i 158 4 42 5 159 3 52 5 160 4 50 5 "O ist 4 32 5 162 2 38 5 163 2 54 5 164 3 88 5 165 2 32 5 166 4 36 5 4 'O 167 2 50 5 168 7 70 5 169 7 50 5 170 4 56 5 171 5 44 5 172 3 30 5 O 173 4 48 5 174 5 54 5 2 175 3 34 5 176 5 44 5 177 3 56 5 i 178 7 52 5 O 179 I 50 5 180 6 58 5 181 4 38 5 182 3 30 5 183 4 20 5 184 3 42 5 O 185 5 26 5 186 3 36 5 187 4 50 5 188 2 40 5 189 5 30 5 190 3 62 5 lg 191 4 32 5 192 6 34 5 193 4 32 5 194 3 42 5 195 4 40 5 196 4 44 5 .O 4 a .O 4

O o. Alpha Counter LSC Location O Wipe Sample # Removable dom /100 Sq. Cm. Removable cpm /100 Sq. Cm. Map # 197 2 40 5 198 1 52 5 199 3 24 5 200 3 42 5 g 203 4 40 5 204 4 38 5 205 4 50 5 206 3 48 5 207 5 34 5 208 3 44 5 209 2 38 5 g 210 3 42 5 211 2 34 5 212 3 24 5 213 3 38 5 214 1 36 5 215 4 22 5 g 216 2 28 5 217 4 20 5 218 3 30 5 219 3 28 5 220 4 20 5 221 6 42 6 q' .222 4 62 6 223 3 36 5 224 4 30 5 225 2 26 5 226 5 42 5 227 3 38 5 O 228 3 54 5 229 0 32 5 230 3 36 5 231 3 38 5 232 2 48 5 233 4 38 6 n v 234 4 32 6 235 6 56 6 236 2 48 6 238 7 48 6 O 10 0

a O, O Alpha Counter LSC Location O Wipe Survey # Removable dpm/100 Sq. Cm. Removable epm /100 Sq. Cm. Map # 239 3 40 6 240 1 38 6 241 3 32 6 242 8 26 6 243 7 46 6 g 244 4 52 6 245 1 46 6 246 4 34 6 247 8 38 6 248 3 22 6 0 249 2 34 6 250 3 46 6 251 1 52 6 252 3 74 6 253 1 44 6 254 4 44 8 O 255 2 54 8 256 5 36 8 257 3 26 8 258 3 54 8 259 I 42 8 260 4 30 8 O 261 5 36 8 262 4 30 8 263 4 34 8 264 4 84 8 265 4 30 8 266 7 40 8 267 0 34 8 0 268 6 52 8 269 3 38 8 270 6 56 8 271 1 30 7 272 6 28 7 273 2 36 7 .n 274 0 36 7 274 3 38 7 276 3 56 7 277 5 52 7 278 4 30 7 279 3 26 7 O 280 2 54 7 11 0

). ~ O 9 Alpha Counter LSC Location Wipe Survey # Removable dom /100 Sq. Cm. Removable cpm /100 Sq. Cm. Map # 281 3 40 7 282 7 42 7 283 2 70 7 284 2 58 7 g - 285 4 44 7 286 3 66 7 287 4 52 7 F88 3 48 7 289 4 56 7 290 2 46 7

3 291 1

44 7 292 3 60 7 293 2 58 7 l 294 4 52 7 l 295 5 42 7 !g 296 3 54 7 297 6 48 7 298 4 38 7 299 4 50 7 300 7 32 7 301 1 56 7 302 4 32 7 0 303 2 30 7 } 304 5 34 7 305 7 58 7 306 4 30 7 307 2 58 7 O dpm disintergrations per minute cpm = Counts per minute Ludlum Alpha Scintillation Probe 43-1 S/N P495 Ludlun. Model 2200 scaler /ratemeter S/N 12224 O Packard Tri Carb Llould Scintillation Counter O 12 O.

O Personal Protection The NSSI personnel conducting the decontamination actions and decommisioning surveys wore Thermoluminessent Dosimeters (TLD) badges during the the time spent at the facility to document any possible whole body exposure they might have received. These badges were worn in addition to the badges they are issued normally every month for monitoring purposes under NSSI's other licensed activities. The results of TLD badges were as follows:

Teridin, M.C.

SS# 337-50-3036 10 mR Gallagher, C.T. SS# 046-38-0418 10 mR During the removal of items from the contaminated areas where the potential for airborne concentrations of contaminants was possible ? (i.e. ceiling tile

removal, vent duct removal and fume hood dismantling)

The individuals wore duel cartridge, half face respirators. The filtering cartridges are rated for protection from organic vapors, radionuclides, dust and fumes. They were: MSA Comfo 11 Half Face Respirator MSA GMA 11 Filter Cartridge in conjuction with the above mentioned times when respirators were utilized, air sampling was conducted to document either the presence or absence of any airborne contaminants. Both a high volume air sampler and a low volume personnel air sampler was used. The results of that sampling was as follows: Sample # Procedure Monitored Alpha mCt/cc -9 i Removal of Assembly Area Celling (Low Volume) 2.04x10 -12 2 Removal of Hood Stacks (High Volume) 2.97x10 m -11 3 Removal of Vent Ducts (Low Volume) 4.50x10 -12 4 Removal of Standup Hood Ducts (Low Volume) 5.0x10 -11 5 Removal of Chem Lab Celling ( High Volume) 1.9x10 -12 6 Removal of Assembly Area Celling (High Volume) 2.22x10 Upon completion of the decontamination, and arrival back at NSSI headquarters in Houston, Texas, urine samples were submitted by the individuals for analysis by an outside laboratory for Uranium 234 concentration. The results from that urinalysis are seen on attachment #1. 13

MAP #1 E NG INEERING D DE PARTMENT D STO R AG E BATHROOM t 3 STANE UL ! SINK ENTRO HC'E EEICI' D CHEMISTRY LAB EENCH BENCH 3

UE HOCE

~' GLOVE TABLE BOX u D n 0: ASSEMBLY

o AREA f E $$

T A B LE ,/ ~ BENCH FILE TABLE I o

D MAP #2 i 1 E NG INEERING l a DE PARTMENT I -j D STO RAG E i '3 STANC I j UP g ; . SINK ) \\ENTED HCC r EENCH ) CHEMISTRY ~~T i U LAB EENCH, BENCH. 3 CUE I O HOOD -Q f' GLOVE / TA LE BOX \\ / 9 m (9 I (- } l / ASSEMBLY @ b ~'{ Sobs 31 OWN E:RAIN d AREA K l/ I t d TA LE l i 6 l 3 l S BENCH @ 4 TABLE @ O U

D MAP #3 3 J h 8 c PLUMBING ({) @ VENT ROOF u) .c.> % To Glove B c, { In Asses:bl; ( 1 Roorr. EYA o /b fi r'? f e / / / RD (2J) O VENTED FUME s AREA HOOD.

O 3 4 5 6 7 8 9 4 4 4 4 4 4 4 5 6 0 1 2 3 4 7 7 7 7 7 7 7 O 0 1 2 6 7 8 9 0 0 0 9 9 9 9 1 1 1 1 3 9 5 2 1 2 3 4 5 6 7 0 7 0 6 9 1 1 1 2 2 3 3 1 7 5 O 0 4 8 1 8 4 2 2 1 4 3 6 5 8 0 7 5 mo 6 9 1 1 1 2 2 3 3 1 o R 7 3 9 0 5 2 7 4 9 5 9 2 y 6 9 1 3 1 1 2 2 3 3 0 7 5 l 1 1 4 b me 6 2 8 9 6 1 8 3 0 6 0 3 P s 6 9 1 4 1 2 2 3 4 0 8 5 A s O 1 1 M A 7 7 5 1 1 5 8 7 0 9 2 1 0 1 4 6 9 1 1 2 2 3 4 1 8 5 6 8 4 0 1 8 9 0 1 2 0 2 5 6 9 1 6 7 1 1 3 3 4 1 8 5 4 O 1 3 2 1 0 9 1 1 1 1 1 0 1 1 1 1 1 00 8 7 6 5 4 0 3 8 8 8 8 8 0 8 2 1 0 9 8 7 6 6 6 6 5 5 5 5 O T F SA E O 2 3 4 5 6 8 9 2 2 2 2 2 2 5 1 1 1 1 1 1 1 8 9 0 1, 5 6 7 4 4 5 5 4 4 4 1 1 1 1 1 1 1 8 9 0 1 2 3 4 6 6 7 7 7 7 7 O 1 1 1 1 1 1 1 4 7 9 0 5 6 5 6 7 8 5 2 0 4 6 8 9 0 0 1 1 2 2 7 5 3 1 1 1 1 2 2 2 2 2 2 1 1 1 3 6 8 1 4 7 4 7 6 9 6 3 1 b 4 6 8 9 0 0 1 1 2 2 7 5 3 a 1 1 1 1 2 2 2 2 2 2 1 1 1 L O y 2 5 7 2 3 8 3 8 5 0 7 4 2 r t 4 6 8 9 0 0 1 1 2 3 7 5 3 5 s 1 1 1 1 2 2 2 2 2 2 1 1 1

i 8

5 3 m 1 4 6 3 0 9 2 9 4 1 7 5 3 P e A h 4 6 8 9 0 0 1 1 2 3 1 1 1 1 1 1 1 2 2 2 2 2 2 M C 0 3 5 4 9 0 1 0 3 2 9 6 4 4 6 8 9 9 1 1 2 2 3 7 5 3 O 1 1 1 1 1 2 2 2 2 2 1 1 1 5 4 3 2 1 0 9 8 8 8 8 8 8 7 1 1 1 1 1 1 1 3 2 1 0 9 8 7 6 6 6 6 5 5 5 1 1 1 1 1 1 1 O 0 9 8 7 6 5 4 4 3 3 3 3 3 3 1 1 1 1 1 1 1 ~

257 258 263 264 269 270 9 MAP #8 257 263 269 196 195 271 265 259 256 262 268 197 198 266 260 254 O 268 267 262 261 256 255 g 272 2 73 282 283 0 292 293 281 291 301 302 303 294 284 274 Bathroom O 280 290 300 307 304 295 285 275 279 289 299 306 305 296 286 276 298 297 O 288 287 r 278 277 O-C w N MAP #6 g 0 2 O. 2 M M M M ~ w ~ p" e ~ ~ ~ 2 w 0

6 Controls for Environmental Pollution, Inc. -" S O S ' Oft' 0f111 M h. p o oo x S.c i o n....t a e c. New Me =.m

H

?db' OUT OF STAT;z S00 / 54D-21 CO PAGE 1 CEP, Inc. REPORT LAB # B5-10-385 RECEIVED: 10/21/85 11/13/85 15:26:24 REPORT Nuclear Sources & services PREPARED Centrols for Environmental TO P.O. Ear 34042 BY Pollution, Inc. ,/' N Houston, TX 77234 1925 Rosina Street manta Fe, Det 87502 Ct!KTIFICD BY ATTEN Peter M. Tadin ATTEN PHOPEE (505) 982-9841 CONTACT GAIL CLIENT DEBBI SAMLES J COW ANY Nuclear Sources & Services FACILITY WORM ID Einassau TAKEN 10/17/35 g TCANS Federal Emmress TYPE Urine P. O.

4393 INVOICE under seaarate cover SMFLE IDENTIFICATI(M CEP, Inc.

TEST CODES and NMES used on this report 9.1 Gallaaher, C. U234 a Uraniuse-234 QR Tordin, M. C. i O O O O O O O O O O O

Ph b. : Controls for Environmental Pollution, Inc. a. t> ni it> < ter s; > to u i > o no x u. iS 1 o.... ir. f.. N. w M r. +., I out op mTara coo /C43 01 CO i PAGE 2 REPGtT IF ANALYSIS LAB # B5-10-385 l l SMFLE IDDITIFICATI(M DATE C(LLECTED TYPE OF ANALYSIS es/T. V. Gallcgher, C. 10/17/85 Uranium-234 O.00 0.03 1 I j Tordin. M. C. 10/17/85 Urantum-234 O.00 O.03 l l i i t i i i f i l l k i i l I i I l l 1 i l } i i O e e e e e e e e e e

O.* NUCLEAR BOURCEB & BERVICES, INC. O P. O. E,0X 34042 HOUSTON, TEXAS 77234 AREA CODE 71316414391 N-55 OVERPACK PROCEDURES O On receipt inspect the N-55 for any damage. If damaged advise NSSI. (USA 713-641-0391) In order to open: O 1. Removc any wire seals or wires which hold the closures down. 2. Lift off the upper outer shell of the N-55. 3. Remove the lid from the 17H open head drum. Remove the O label packet attached to the lid. 4. Place the radioactive source and shields inside the 17H drum. 5. As sources are placed in the shield measure the radiation ,O level of neutrons and/or gammas: a. At the surface of the N-55. b. At a distance of 1 meter from the N-55. Under no circumstances may the dose rate at the surface exceed 200 O ar/hr for neutrons plus sammas. Under no. circumstances may the dose rate at 1 meter exceed 10 mr/hr. After placing the sources in the drum add sawdust, vermiculite, or ther Packing or bracing so as to keep the radioactive material from O shifting or puncturing the drum. 6. Replace the lid on the inner 55 gallon drum and ti8hten the bolted lock ring. 7. Replace the upper section of the N-55 and close the toggle g closures. 8. Apply security seal wires to hold the toggles closed. 9. Fill out the Restricted Articles certifica'tions and O apply the appropriate labels. All the necessary labels were provided in the packet on top the inner 17H drum. 10. Arrange for a carrier to transport the N-55 container. O coned. a SHIPPING ADDRESS: 5711 ETHERIDGE / HOUSTON, TEXAS 77087

O.* NUCLEAR BOURCES & BERVICES, INC. g P. O. BOX 34342 HOUSTON, TEXAS 77234 AAEA CODE 71316414391 + 0 11. Contact NSSI by telex (No. 160810 NSSI-MUT) and advise when the shipment will be made, the carrier, and the waybill. 12. Ship the container prepaid. Collect shipments will not be accepted. 0 1 l l !O O O O O 'O O SHIPPING ADDRESS: 5711 ETHERIDGE / HOUSTON, TEXAS 77087

.I U.S. NUCLaAR RaCULATORY COMMISSloN tO7J CELTIFICATE CF COMPLIANCE S *. #" II Por Redienstive Meterish Peaknese 1,qe) Certifieste Nunter 1.ebl Rowleien No. 1.fel Peekage identiflesalen No. 1.(d) Pqoss No. 1,(e) Teest No. Pages 9070 7 USA /9070/Bf IF 1 3 . PREAMSLE 2.te) his eartKleste b heued to estlety Sections 173.393e.173.394,173.35, and 173.308 of the Desertment of Transportation Heaardous Meteriale Resuletiens (de CFR 170180 and 14 CFR 133) and Sections 146-19-10e mid 14a-19-100 of the L _ og Transportation Dangerous Cargoes Raoulations let CFR 146-140), es amended. 3.0) he seekselns and contents descrtied in hem 5 below, meets the esfety standards est forth in Subpart C of Title to. Code of Federal Reguietlens, Port 71. *?ackaging of Medicensive Meteriets for Transport and Transportetton of Radioactive Meterial Under

* " ' " ' * " ' ' ~

O 2.(el his eartifieste does not relieve the soneignor from sempilence with any reguirement of the regulations of the UJ. Department of Transporintion or other opplicabie reeudetory agencise, incduding the government of any sountry through or into which the pookage snel be transported.

3. His eartiflamie is leaued on tre basis of a safety enefysis report of the peekage design or application-3.(e)

Prepared by (Neme end addres): 3.th) Title and identificetion of report or application: Nuclear Packaging. Inc. Nuclear Packaging Incorporated 815 S:uth 28th Street application dated April 23, 1982 l ' Tacoma, WA 98409 3.le) Doeket No. 71-9070 O. CONDITIONS 4 This certivic.te i. sondition. opon the fuifiiiin, of the reguir.ments of subpart o of to err vi. es appris=bie, and th. sondriions sp.cefied in leem 5 below.

5. Doesrlption of Pocketing and Authorised Contents, Model Nurfter. Fissile Class. Other Conditions, and References.

(a) Packaging ~ - (1 ) Model No.: N-55 (2) Description A low carbon steel overpack filled with rigid polyurethane foam. The containment vessel is a SS-gallon drum, meeting the requirements of O DOT Specification 17H or 17C. The overpack is a right circular cylinder 48 inches high by 32 inches diameter with a 34-1/2-inch high by 24-inch diameter cavity. The 20-gage galvanized steel shell is filled with 3-pound per cubic foot rigid polyurethane foam. Closure of the upper and lower (lid and body) sections of the overpack is provided by four toggle clamps, and a neoprene gasket at the stepped joint between the O two sections. Four lugs are provided for lifting and tie-down. The j package gross weight is approximately 750 pounds. t* (3) Drawing ,o The packaging is constructed in accordance with Nuclear Packaging, j Incorporated Drawing No. X-60-2000, Rev. C. O O

y..'.

Page 2 - Certificate No. 9070 - Revision No. 7 - Docket No. 71-9070 / ti (b) Contents (1) Type and fom of material (1) Radioactive material including fissile material in the form of dry solids contained in D0T Specification 17H or 17C drums. O Liquids, powders and slurries are not pemitted. ~ (11) Tritium absorbed on metal backing as titanium tritide held within the container assembly shown in Lawrence Livermore Laboratory Drawing No. AAA-77-109723. Rev. C. l O (iii) Dry, solid fonas of plutonium and uranium. (2) Maximum quantity offmaterial per package (1) For the contents described in 5(b)(1)(1) greater than Type A quantity 6 radioactive material. Fissile material contents not to exceed the generally licensed mass limits as'specified in 10 CFR 671.11 and plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements. Internal decay heat not to exceed 3 watts. N (11) For the contents. described th 5(b)(1)(ii) a maximum of'six (6) G1 container assemblies held within a DOT Specification 17H drum. Maximum activity not to exceed 30.000 curies per package. Internal decay heat not to exceed 1.08 watts per package. (iii) For the contents described in 5(b)(1)(111). 200 grams fissile O plus fissile uranium provided the total Pu content does not exceed 200 grams, with a heat generation rate of 5 watts. The radioactive material must be packaged within sealed metal cans or 00T Specification 2R containers (49 CFR 3178.34); and placed within inner containers constructed as specified in Appendix 1.10.4.1 1.10.4.2. and 1.10.4.3 of the application. Prior to each shipment, O a helium leak test must be performed on both the inner and outer containnynt assemblies capable of detecting a leak no greater than 10' ats cc/sec at standard temperature and pressure. Following the gas leak testing.,all inner container welds must be leak tested using a liquid penetrant method in accordance,with O Article 6. Section V. ASME Code. No package with a detectable leak shall be delivered to a carrier for transport. (3) Fissile Class II Minimum transport index to For the contents described in O be shown on label 5(b)(1)(iii): g Five(5) O v;.

,/@' N-5.s JUL 22 582 uiDepcriment am s m so.* s. g Washmpon. D C. 20500 assearchand _Lm_ CMIFIN & N N O specie:Prograne Administranen Type B Fissile P=dir=*tive Material Package Design certificate Ntaber IEA/9070/B( )F Revision 0 1his establishes that the packaging design described herein, Wen loaded with the authorized redirw tive contents, has been certified by the National Ocupetent Authority of the United States, as meeting the regulatory requirements for Type B packaging fbr fissile radioactive materials as prescribed in IAEA 1/ Regulations and in accordance with g SS 49 CFR 173.393b and 173.394(b7X(3) of the USA 2f Regulations for the transport of radioactive satorials I. Package 'Identificaticn - 2 del It). N-55 II. Packaging Descripticm - Packaging authorized by this certificate g consists or a low carecm steel overpack with an inner 55-gallon drun (Dor) Specificaticm 17H or 17C) containment vessel with the void between the two filled with regid polyurethane foam. Closure of the typer and lower sections of the overpack is provided by four toggle clanps with a neoprene gasket fitted at the stepped joint.' Overall dimensicns are 48 inches (1,219 man) high by 32 inches (813 sm) in diameter with a gross weight of awroximately 750 pounds (341 kg). III. Authorized Radioactive contents - 1he authorized contents consist of fissile and non-rissile reirwtive materials as titanitun tritide, dry solid forms of uranium and plutonitzn, or other dry solid radioactive materials, all as further limited by U.S..Aaclear Regulatory ocanission certificate of Ocep

m. m0 A) f r twile czmtents t is au w zed O

as Fissile Class II with a mininnan assigned transport index of 5.0. IV. General conditions - a. Each user of this certificata nust have in his possession a O m f this certincata. b. Each user of this certificate, other than Ntaclear Sources and Services, Inc., It>uston, TX 77034 shall register his identity in writing to the Office of Hazardous Materials Regulation, Materials Transportation Bitreau, U.S. Department of Transportation, Nashingtcm, O D. C. 20590. c. This certificate does not relieve any consignor or carrier fran oc.rpliance with any regirement of the Government of any country thorugh or $nto which the package is to be transported. O

v. Marking and Imbeling - The package nust bear the marking USA /9070/B( )r as well as the othar sarking and lahalm prescribed by the USA Regulations.

~Expiraticn $hte.This certificate, unless renewed, eetpires on May 31, 1987. L VI. t O

C7." certificata nuber USA /9070/B( )F, Revision 0 Page 2 1his certificate is issued in accordance with the requirements of the IAEA and USA Regulations and in response to the May 20, 1982 petition by Muclear Saurons and Services, Inc., and in consideration of the associated irifnmatim provided in U.S. Mr*1mr Regulatory nwminalen certifirsta of Oampliance No. 9070 (Appendix A). O Certified by: O Nd /5 /982 + Richart! R. Rawl [] p GE) Otief, Radioactive Materials Branch v O Office of Hazardous Materials Regulation Materials Transportation Bureau 1/ " Safety Series No. 6, Regulatims for the Safe Transport of Radioactive P Eterials,1967 Edition" published by the International Atanic Enertjy k Agency (IAEA), Vienna, Austria. 2/ Title 49, code of nederal Regulations, Parts 100-199, USA. O ,0 1-1 10 l 1 l 'O

O l

NUPAC N-55 USA DOT " TYPE B" OVERPACK for g n 55 GAL. DRUMS .J U -. _ -.Q 1

550 Lbs. Payload

))

Type B, Large Source

( & Fissile Material ' ~ '

Light Weight b

Rugged Construction ( e

76 N-55's Per Truck e

i-

(, ~ DESIGNED SPECIFICALLY FOR THE TRANSPORT OF " TYPE B", LARGE SOURCE AND FISSILE MATERIALS IN 55 GAL. DRUMS. l HIGHEST TRANSPORTATION EFFICIENCY Can move more drums of Type B Payload than.any other overpack. I 78 DRUMS per standard 40 ft. van. Or 84 DRUMS per 45 foot hicube van. CONSTRUCTION g INTERNAL SKIN - smoo'h, one-piece molded fiberglass shell. High strength, impact & corrouion resistant. Easily decontaminated. EXTERNAL SHELL - welded h.3avy gauge steel. USE D Low parting plane allows access to top one third of drum for easy loading or removal. Tiedown and lifting lugs are provided for convenient handling. Adjustable toggle clamps provide rapid opening and closing. 1 D hh Heavy gauge outer steel shell . '.... ' [ Impact limitor & thermal insulation 21 0 @tjp / .:.w Structurallifting lug & tie downs 8 r ....s[ 4 heavy duty adjustable togglue clamps n 48 35% One piece molded fiberglass shell 27 l STd.17H ...::i:i: Steel Drum U . :::,:s.. . " '. : ;/.: NRC Certificate of compliance No. 9070 g q = 32 = 1

O reuter stakes o O REUTER-STOKES, INC. Edison Park O Twinsburg, ohio 44087 DECONTAMINATION REPORT FOR O lesso South Miles Parkway Warrensville Hts., Ohio 44128 January 27, 1986 O O O O O t By Geo ge Palko Radiation Safety 0 Orricer O

o O reuter-stokes a I Reuter-Stokes, Inc. January 27, 1986 Page 2 I. PURPOSE O Reuter-Stokes, Inc., an affiliate of the General Electric Company, has decontaminated the facility located at 18530 South Miles Parkway, Warrensville Hts., Ohio, in order to have it released for unrestricted use. The decontamination was contracted out to Nuclear Sources and Services, Inc. of O Houston, Texas, and the actual decontamination was perform-on October 9 through October 13, 1985. This report is a supplement to the NS & SI report to show that the property has been surveyed by Reuter-Stokes, and that Reuter-Stokes can certify that no detectable radiation levels exist above essential background counts. II. HISTORICAL INFORMATION Reuter-Stokes acquired the property in 1963, and has con-ducted business at that location until mid-1985. Special Nuclear Material and By-Product Material have been licensed

g for the location by the Nuclear Regulatory Commission.

The bulk of the radioactive material processed was in the form of enriched uranium oxide. The processing was limited to two rooms located in the northwest part of the facility. The electroplating was performed in one laboratory room and the assembly of the plated parts was performed in an adjacent O Both rooms were controlled access areas, restricted room. to only those people who actually performed the work. Other radioactive material was in the form of sealed sources used to test the products that Reuter-Stokes fabricates. Use and storage of these sealed sources was also confined to essentially one area that was also restricted. ) III. SURVEY METHOD Guidance listed in Nureg CRC 2082, Section 3, and " Guide-lines for Decontamination of Facilities and Equipment for Unrestricted Usa or Termination of Licenses for By-Product, n Source or Special Nuclear Materials", was used in planning v the survey. The latter is an NRC document issued in 1982, i and is marked Appendix A of the report. i The goal of the decontamination effort was to get the alpha levels down to background in the two rooms where uranium $) was processed and handled, and any adjacent areas that may have been contaminated. The goal has been achieved as ev-idenced by the supporting survey data. For Controlled Access Areas 1 and 2, the grid numbers in this report are that same as those in the NS & SI report. O crid d:.agrams and locations are presented in Attachments 1 through 6. An alpha survey meter and a beta / gamma survey O

m (v) reuter-stokes J Reuter-Stokes, Inc. January 27, 1986 Page 3 '3 meter were used as the primary survey instruments. Additional smears were taken where appropriate along with air samples. The alpha and the beta / gamma surveys were stationary measure ments taken at five different points on each grid. Wall grids were measured in a clockwise direction starting with a position one in the upper left hand corner and position 5 in the center of the grid. The readings were then averaged over the 5 positions. Each grid was approximately one square meter in area. For Controlled Access Areas 3, 4 and 5, the sealed source storage area and the nuclear test lab where sealed sources were used to test products, the beta / gamma survey meter was used for measurements. The grid structure and data are pre-sented in Attachments 7 through 10. One stationary read-ing of one minute was taken for each grid. All readings showed essentially background, the lower limit of the in-strument used, a Victoreen Model 491. Wipes were taken in- ,J side the Cobalt-60 storage pipe, about 1 to 2 feet in, and outside on the pipe that was projecting from the floor, to verify that the 6 curie source did not leak. Counting the wipes showed no readings above background. Counting was done according to procedure RS-SOP-880.3. Sealed sources 3 used or stored in these areas were wipe tested on a periodic basis, as applicable, according to the conditions of our By-Product material license. In addition, measurements were taken with an environmental radiation monitor, Reuter-Stokes Model RSS-lli, to check for any residual activity above background. Data is available ,J that shows all measured areas were at background levels, approximately 10 ur/hr. Eighty-two readings were taken in various parts of the facility. IV. DETECTION EQUIPMENT O

1. Eberline Model RM-20 Alpha Survey Meter with AC-3 alpha probe, calibrated on 6-20-85, with next calibration due 12-20-85, serial number 951.

2. Victoreen Model 491 Beta / Gamma Survey Meter with a 491-30 probe, calibrated on 9-13-85, with next calibration due g

on 3-13-86, serial number B076. v

3. Router-Stokes Gas Flow Proportional Counter System des-cribed in RS-SOP-880.3, calibrated prior to use accord-ing to the procedure, and submitted as Attachment 7.

O g

(] reuterestokes O Reuter-Stokes, Inc. January 27, 1986 Page 4 0 4. Industrial Hygiene High Volume Air Sampler with a Whatman 41 filter paper having 25um particle retention.

5. Reuter-Stokes Model RSS-lll, Serial no. Z-4795, calib-ration on file.

O Calibration certificates for the Eberline and Victoreen survey meters are in Appendix B. V. ALPHA MEASUREMENTS () Five readings were taken in each grid using the Eberline survey meter. Locations that showed alpha activity above background levels were smeared and the smears counted ac-cording to RS-SOP-880.3 to determine if the activity was removable. If so, the grid area was decontaminated by scrubbing with detergent and rinsing with water. It was n then surveyed again. In a few cases the face of the cement block was partially removed in order to remove contaminated areas. Finally, when the surveys showed background, or close to background levels, the two rooms were painted with standard O mmer ial type paint, tiled with new asphalt tile, and a new ceiling installed. A survey after the remodelling shows background levels. Data is presented showing contamination levels before clean-ing, after cleaning and after painting. O All of the superstructure, including heating ducts, plumb-ing and conduit, in the plating laboratory was decontamin-ated with detergent and water. All subsequent readings showed background levels. O ne lighting fixture in the assembly area showed readings significantly higher than background, approximately 2,000 dpm, in a six inch square area. The fixture was removed and will be disposed of as low level waste. All other fix-tures and the superstructure in this area showed background levels. O VI. BETA / GAMMA MEASUREMENTS ) Five readings were taken in each grid using the Victoreen beta / gamma survey meter, with the probe shield in the off O position. Random measurements were also taken with the probe shield in place to make sure there were no higher energy gammas present. O

O reuter-stokes o N r/ Reuter-Stokes, Inc. January 27, 1986 Page 5 It was established that the background level was in the () G order of 0.05mr/hr to 0.06mr/hr by measuring areas in the facility outside the laboratory area. This is essentially the lower limit the equipment can read. VII. Air samples were taken in the two rooms to confirm that no () airborne radioactivity.was present. The filters were count-ed for alpha contamination in the same manner as the smears described in V. above. A filter sample taken in an area where no radioactive material was processed was used as the background control. Data shows no airborne radioactivity present. e VIII. In total, three independent surveys have been taken to verify that the Reuter-Stokes' facility at 18530 South Miles Parkway, Cleveland, Ohio, 44128, has been decontam-inated to background levels and therefore is qualified to g b's released for unrestricted use. The three surveys are: 9s 1. Nuclear Sources and Services Report of January 22, 1986. 2. Reuter-Stokes Report of January 27, 1986. 3. Applied Health Physics Survey taken on January 9 O through January 11, 1986. This report is available from the~ potential purchaser of the facility, ACOR orthopaedic, 4129 Mayfield Road, Cleveland, Ohio 44121. iO - l lo l L g s l O l ,,. ~.. ~ m

O reuterestokes e v Reuter-Stokes, Inc. January 27, 1986 Page 6 VIII. ALPHA MEASUREMENT DATA 9 The data in this table represents the average of the meas-urements taken in each grid after the rooms were painted and remodelled. Individual grid data and the calculation for the standard deviation are available if requested. Data is in dpm (disintegrations per minute). Grid No. dpm Grid No. dpm 1 0 41 0 2 0 42 0 3 0 43 0 4 0 44 0 5 0 45 0 6 0 46 0 7 0 47 0 8 0 48 0 9 0 49 0 10 0 50 0 ,J 11 0 51 0 12 0 52 0 13 0 53 0 14 0 54 0 15 0 55 0 16 0 56 0 d 17 0 57 0 18 0 58 0 19 0 59 0 20 0 60 0 21 0 61 0 22 0 62 0 ,J 23 0 63 0 24 0 64 0 25 0 65 0 26 0 66 0 27 0 67 0 28 0 68 0 ,J 29 0 69 0 30 0 70 0 31 0 71 0 32 0 72 0 33 0 73 0 34 0 74 0 ,J 35 0 75 0 36 0 76 0 37 0 77 0 38 0 78 0 39 0 79 0 40 0 80 0 D

O reuter-stakes o Reuter-Stokes, Inc. January 27, 1986 Page 7 Grid No. dpm Grid No. dpm O' 81 0 131 0 82 0 132 0 83 0 133 0 84 0 134 0 85 0 135 0 () 86 0 136 0 87 0 137 0 88 0 138 0 89 0 139 0 90 0 140 0 91 0 141 0 92 0 142 0 () 93 0 143 0 94 0 144 0 95 0 145 0 96 0 146 0 97 0 147 0 98 0 148 0 0 99 0 149 0 100 0 150 0 101 0 151 0 102 0 152 0 103 0 153 0 104 0 154 0 O. 303 o 133 o 106 0 156 0 107 0 157 0 108 0 158 0 109 0 159 0 110 0 160 0 () 111 0 161 0 112 0 162 0 113 0 163 0 114 0 164 0 115 0 165 0 115 0 166 0 () 117 0 157 0 118 0 168 0 119 0 169 0 120 0 170 0 121 0 171 O 122 0 172 0 5) 123 0 173 0 124 0 174 0 125 0 175 0 126 0 176 0 127 0 177 0 128 0 178 0 O 129 0 179 0 130 0 180 0 b-

O reater-stokes O Reuter-Stokes, Inc. January 27, 1986 Page 8 Grid No. dpm Grid No. dpm O 181 0 231 0 182 0 232 0 183 0 233 0 184 0 234 0 185 0 235 0 O 186 0 236 0 187 0 237 0 188 0 238 0 189 0 239 0 190 0 240 0 191 0 241 0 192 0 242 0 0 193 0 243 0 194 0 244 0 195 0 245 0 196 0 246 0 197 0 247 0 198 0 248 0 O 199 0 249 0 200 0 250 0 251 0 252 0 203 0 253 0 204 0 254 0 0 205 0 255 0 206 0 256 0 207 0 257 0 208 0 258 0 209 0 259 0 210 0 260 0 0 211 0 261 0 212 0 262 0 213 0 263 0 214 0 264 0 215 0 265 0 216 0 266 0 0 217 0 267 0 218 0 268 0 219 0 269 0 l 220 0 270 0 221 0 271 0 222 0 0 223 0 224 0 225 0 226 0 227 0 228 0 O 229 0 230 0 0

1 1 .{) REUTER-STOKES, INC. Page 9 January 18. 1986 GRI DATA PRI R T A ITI NAL E NTAMINATI N AN REM ELLING O AVERAGE EVENTS PER MIN DPM GRID NO PER GRID PER GRID c) 5 0.6 13 6 1.5 32 7 0.6 13 ) 8 0.8 17 27 0.4 8 29 0.4 8 0 30 0.6 13 31 0.8 17 32 1 21 0 33 0.6 13 34 0.6 13 39 0.8 17 ) 41 0.4 8 42 1.8 38 52 0.6 13 61 1.6 4 62 4.6 98 63 4.4 93 !O 64 4.4 93 65 4 85 87 1.6 34 .O 88 4.4 93 0

O REUTER-STOKES, INC. Page 10 AVERAGE EVENTS PER MIN DPM C) onzo no pga agro pga caro 89 3.8 81 90 6.2 131 91 3.2 68 93 0.4 8 103 0.6 13 104 0.6 13 113 2.2 47 114 9.4 199 115 6.2 131 116 8.6 182 124 0.6 13 0 166 1 21 193 1.6 34 194 0.8 17 O 195 0.6 13 203 0.6 13 204 0.8 17 O 207 0.8 17 215 1.6 34 O 0.6 13 217 219 0.4 8 224 0.6 13 227 1.2 25 O 244 0.8 17 O

REUTER-STOKES, INC. Page 11 AVERAGE EVENTS PER MIN DPM ]) GRID NO PER GRID PER GRID 245 1.4 30 246 2.6 55 ) 248 1.4 30 251 0.8 17 252 0.8 17 3 271 0.8 17 D D e e e 0 e

43 REUTER-STOKES, INC. page 12 GRID DATA AFTER ADDITIONAL DECONTAMINATION ) AVERAGE EVENTS PER MIN DPM t GRID NO PER GRID PER GRID O 5 O O i 6 0 0 7 0 0 0 8 0.4 8 27 0.4 8 29 0.4 8 $) 30 0.6 13 31 0.8 17 32 1 21 .O 33 0.6 13 34 0.6 13 39 0.8 17 O 41 0.4 8 42 1.8 38 52 0.6 13 f.O 61 1.8 38 62 4 85 l 63 4.4 93

O 64 4.6 98 65 1.6 34 87 2.6 55

.,0 88 6.2 131 i O

() REUTER-STOKES, INc. Page 13 AVERAGE EVENTS PER MIN DPM GRID NO PER GRID PER GRID 89 3 64 90 8 170 0 91 2.6 ss 93 0.4 8 103 0.6 13 O lo4 o.6 13 113 1.4 30 114 8 170 O ils s lo6 116 8.6 182 117 2.6 ss

O 124 0.6 13 166 1

21 193 1.6 34 I() 194 0.8 17 l 19s 0.6 13 203 0.6 13 O 204 0.8 17 207 0.8 17 21s 1.6 34 0 217 o.6 13 219 0.4 8 224 0.6 13 0 227 1.2 2s O L.

-O REUTER-STOKES, INC. Page 14 AVERAGE EVENTS PER NIN-DPM

0 GRID NO PER GRID PER GRID 244 0.8 17 245 1.4 30 246 2.6 55 248 1.4 30 251 0.8 17

.O 252 0.8 17 I. 271 0.8 17 O .O ,0 [ l O O t !O O

REUTER-STOKES, INC. Page 15 GRID DATA AFTER DECONTAMINATION ON 12/9/85 AND 12/lo/85 SURFACES OF SOME CONCRETE BLOCKS REMOVED 0 AVERAGE EVENTS PER MIN DPM GRID NO PER GRID PER GRID O 5 o o 6 o o 7 o o O 8 o.4 8 27 0.4 8 29 o.4 8 0 3o o.s 13 31 o.8 17 32 1 21 0 33 o.s 13 34 o.s 13 39 o.8 17 0 41 o.4 -8 42 1.8 38 52 o.s 13 .O si o o l s2 o o s3 o o O s4 o o t s5 o o i 87 o o O 88 o.4 8 O i l

I) REUTER-STOKES, INC. Page 16 AVERAGE EVENTS PER MIN DPM GRID NO PER GRID PER GRID O 89 0 0 90 0 0 O-91 o o 93 0.4 8 103 0.6 13 0 104 0.6 13 113 0 0 114 0.8 17 lO 115 o o 116 0 0 117 0 0 'O 124 0.6 13 166 0 0 193 1.6 34 I) 194 0.8 17 195 0.6 13 203 0.6 13 I) 204 0.8 17 l 207 0.8 17 215 1.6 34 5) 217 0.6 13 219 0.4 8 224 0.6 13 I) 227 1.2 25 .O

3 REUTER-STOKES, INC. Page 17 AVERAGE EVENTS PER MIN DPM -) ^ GRID NO PER GRID PER GRID 244 0.8 17 I 245 1.4 30 g 246 2.6 55 248 1.4 30 251 0.8 17 3 252 0.8 17 O O O o o 50 O

r-([ Pa ge 18 Table: 3 () 3 eta-Gamma' Survey I ns t r ume nt a t i on: Victoreen 491 Sur.'ey Meter Date: 10/85 to 12.95 ~ Patty Kraft Helisca Pattercen ()- Grid Pocition Ccid O t d. No. 1 2 '3 4 5 A.3 De.. () 1 0.050 0/070 0.050 0 055 0.040 0.053 0.0098 2-0.060 0.080 0.050 0.030 0.090 0.062 0.0214 3 0.040 0.070 0.045 0.060 0.090 0.061 0.0180 4 0.030 0.035 0.055 0.050 0.080 0.050 0.0176 5 0.050-0.060 0.040 0.060 0.060 0.054 0.0080 6-0.080 0.060 0.060 0.070 0.040 0.062 0.0133 C). 7 0.100 0.050 0.065 0.070 0.075 0.072 0.0163 8 0.045 '0;080 0.060 0.050 0.050 0.057 0.0125 9 0.035 -0.050 0.060-0.060 0.650 0.171 0.2397 10 0.-035 0.060 0.075 0.040 0.065 0.055 0.0152 11 0.075 0.065 0.040 0.055 0.055 0.058 0.0117 12 0.070 0.'065 0.090 0.050 0.065 0.068 0.0129 C) 13 0.045 0.045 0.060 0.'050 0.045 0.049 0.0058 14 0.040 0.070 0.035 0.070 0.045 ~0.052 0.0150 15 0.060 0.040 0.060 0-030 3.060-0.050-0.0126 16 0.075 -0.040 0.080-0.040 0.060 0.059 0.0169 17 0.045 0.045 0.055. 0.040 0.075' O.052 0.0125 '18 0.070 0.045 0.035 0.065 0.070 0.057 0.0144 (3-19-0.060 0.050 0.060 0.040 0.045 0 051 0.0080 20 0.055 0.080 0.095 0.045 0.070 0.069 'O.0177 '21 0.035-0.065 0.055 0.045 0.095 0.059 0.0206 22 0.045 0.050 0.075 0.040 0.040 0.050 0.0130 23 0.050~ 0.070 0.025-0.065 0.055 0.~053 0.0157 24 0.050 0.040' O.050 0.065-0.050 0.051 0.0080 () 25 0.050 0.055 0.040 0.040 0.045 0.046 0.0058 26 0.040 0.060 0.080 0.040 0.040 0.052 0.0160 27 0.045 0.080 0.050 0.050 0.050 0.055 0.0126 28 0.060 0 040 0.060 0.030 0.050 0.048 0.0117 29 0.050 0.045 0.045 0.055-0.030 0.045 0.0084 30 .0.030 0.050 0.060 0.030 0.G50 0.044 0.0120 ()- 31 0.040 0.060 0.040 0.055 0.050 0.049 0.0080 132 0.080 0.045 0.075 0.035 0.050 0.057 0.0175 33 0.060 10.-060 0.030 0.040 0.060 0.050 0.0126 34 0.045 0.060 0.750 0;045 0.045 0.189 0.2806 35; 0.045 0.060 0.070 0.070 0.050 0.059 0.0102 ~3 6 0.060 0.040 0.035 0.060 0.070 0.053 0.0133 () 37 0.050 0.350 0.050 0.030 0.070 0.110 0.1207 ^:A3b~_\\2_ ~ ~ c1

r-- i Daie 19 f-Table: 3 l 3 eta-Gamma Survey _ 491' Our vey 'Me te r I ns t r ume nt a t i on: Victoceen Date: 10/85 to-12/35 Patty Kraft Melissa Pattarcon ) Grid Positions Grid Otd. No. 1 2 3 4 5 A v g. Dev. ] 38 0.055 0.060 0.075 0.045 0.075 0.062 0.0117 39 0.045 0.060 0.050 0.070 0.065 0 58 0.0093 40 0.055-0.050 0.070 0.055 0.045 0.055 0.0084 41 0.030 0.060 0.055 0.060 0.040 0.049 0.0120 42 0.055 .0.050 0.050 0.040 0.045-0.048 0.0051 '43 0.050 0.060 0.050 0.050 0.050 -0.052 0.0040 44 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ) '45 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 46 0.050 0.050 0.050 0.070 0.050 0.054 0.0080 47 0.050 0.050 0.050 0.050 0.050 0.050 -0.0000 48 0.050. 0.050 0.070 0 060 0.050 .0.056 0.0080 49 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 50 0.050 0.050 0.050 0.050 '0.050 0.050 0.0000 51 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 52 0.050 0.050 0.'050 0.050 1.050 0.050 0.0000 53 0.050 0.050 0.050 0.050 0.050-0.050 0.0000 54 0.060 0.050 0.050 0.'050 0.060 0.054 0.0049 55 0.050-0.050 0.050 0.060 0.050 0.-052 0.0040 56 0.050 0.050 0;050 0.050 0.005 0.041 0.0180 ) 57 0.060 0.050 0.050 0.050 0.050 0.052 0.0040 58 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 59 0.050 0.050 0.050 0.060 0.050 20.052-0.0040 60 0.050 0.050 0.070 0.060 0.-050 0.056 0.0080 61 0.050 0.050-0.050 0.050 0.050 0.050 0.0000 62 0.-050 0.050 0.050 0.050 0.050 0.050 0.0000 63 0.050 0.050 0.050 0.050 0.060 0.052 0.0040 64 0.050-0.050 0.050 0.060 0.050 0.052 0.0040 65-0.-050 0.-050 0.050 0.050 0.050 0.050 0.0000 66 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 67 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 68 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 g. 69 0.050 0.050 0.060 0.050 0.050 0.052 0.0040 f. 70 0.080 0.060 0.040 0.050 0.050 .0.056 0.0136 71 0.050 0.040 0.060 0.060 0.060 0.054 0.0080 72 0.-070 0.040 0.030 0.030 0.030 0.040 0.0155 73 0.040 0.040 0.040 0.040 0.040 0.040-ERR 74 0.080 0.040 0.050 0.040 0.050 0.052 0.0147 1 c

F a le 20 Table: 3 ) Seta-Gamma Survey I ns t r ume n t a t i o n: Victoreen 491 Surrey Meter Date: 10/85 to 12/3s Patty Kraft Helissa Patterson 3 Crid Posttions Cetd Std.

- o.

1 2 3 4 5 Av3 D e i. D 75 0.040 0.050 0.070 0.040 0.070 0.054 0.0136 76 0.030 0.040 0.040 0.030 0.050 0.038 0.0075 77 0.050 0.050 0.060 0.070 0.050 0.056 0.0080 78 0.050 0.050 0.050 0.050 0.050 0.050 C.0000 79 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 80 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 () 81 0.080 0.050 0.050 0.050 0.050 0.056 0.0120 32 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 83 0.050 0.050 0.090 0.050 0.050 0.058 0.0160 84 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 85 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 36 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 9 87 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 88 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 39 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 90 0.050 0.050 0.050 0.050 1.050 0.050 0.0000 91 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 92 0.050 0.050 0.050 0.060 0.050 0.052 0.0040 () 93 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 94 0.060 0.050 0.050 0.050 0.050 0.052 0.0040 95 0.050 0.050 0.060 0.050 0.050 0.052 0.0040 96 0.050 0.050 0.050 0.050 0.080 0.056 0.0120 97 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 98 0.060 0.050 0.050 0.050 0.050 0.052 0.0040 3 99 0.050 0.060 0.050 0.050 0.050 0.052 0.0040 100 0.050 0.050 0.050 0.050 1.060 0.052 0.0040 101 0.060 0.050 0.050 0.050 0.050 0.052 0.0040 102 0.050 0.050 0.050 0.060 0.050 0.052 0.0040 103 0.050 0.060 0.050 0.050 c 050 0.052 0.0040 104 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 0 105 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 106 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 107 0.050 0.050 0.050 0.060 0.050 0.052 0.0040 108 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 109 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 110 0.050 0.050 0.060 0.050 9.050 0.052 0.0040 3 111 0.050 0.050 0.050 0.080 0.050 0.056 0.0120 /% b

E XQ ~ Pa ge 21 Ta bl e: 3 C)' 3 eta-Gamma Survey I ns t r ume nt a t i o n: Victoreen 491 Surre; Meter Date: 10/85 to 12.'35 Patty Kraft Helissa Patterson h Grid Positions Grid Std. No. 1 2 3 4 5 Av3 D e *c () 112 0.050 0.060 0.050 0.050 0.050 .0.052 0.0040 113 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 114 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 '115 0.050 0.060 0.050 0.050 0.050 0.052 0.0040 116 0.060 0.050 0.050 0.050 0.080 0.058 0.0117 117 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ^{) ' 118 0.050 0.050 0.020 0.050 0.050 0.044 0.0120 119 0.050 0.070 0.050 0.050 0.050 0.054 0.0080 120. 0.050 0.050 0.050 0.050 ' O.050 0.050 0.0000 121 0.050. 0.050 0.050 0.050 0.050 0.050 0.0000 122 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 123 0.050 0.050 .0.050 0.050-0.070 0.054 0.0080 m 124 -0.050 0.050 0.050 0.050 1.050 0.050 0.0000-125 0.050 0.050 0.050 0.050 0.050-0.050 0.0000 126 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 1 27 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 128 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 129 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 m 130 0.050 0.050 0.050 0.050 0.050. 0.050 0.0000' 131-0.050 0.050 0.050 0.050 0.050 0.050 0.0000 132 0.'050 0.050. 0.050 0.050 0.050 0.050 0.0000 133 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ~134 0.050 0.050 0.050 0.050 0.-050 0.050 0.0000 135 0.050+ 0.050 0.050-0.050 0.050 0.050 0.0000 () '136 0.'050 0.050 0.070 0.050 0.050 0.054 0.0080 137 0.050-0.050 0.050 0.050 0.050 0.050 0.0000 138 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 139 0.050 0.050 0.050 0.'050 0.050 0.050 0.0000 140 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 141 0.050 0.050 0.050 0.060 0.050 0.052 0.0040 c'i 142 0.050 0.050 0.060 0.050 0.050 0.052 0.0040 143 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 144 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 145 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 146 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 147 0.050 0.050 0.050 '0.050 0.050 0.050 0.0000 148 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 j)

/ Page21 Table: 3 J 3 eta-Gamma Survey I ns t r ume nt a ti on: Victoreen 491 Survey Meter Date: 10/85 to 12/85 Patty Kraft Melissa Patterson Grid Positions Grid O t d. No. 1 2 3 4 5 A z g. De 149 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 150 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 151 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 152 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 153 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 154 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 0 155 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 156 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 157 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 158 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 159 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 160 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 0 161 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 162 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 163 0.050 0.050 0.050 0.050 1.050. 0.050 0.0000 164 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 165 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 166 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 3 167 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 168 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 169 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 170 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 171 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 172 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ') 173 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 174 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 175 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 176 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 177 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 178 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 179 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 130 0.050 0.050 0.050 0.050 050 0.050 0.0000 181 0.050 0.050 0.050 0.050 0 050 0.050 0.0000 182 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 183 0.050 0.050 0.050 0.050 3.050 0.050 0.0000 184 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 3 185 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 x lN

[h - Pate 23 Table: 3 3 Seta-Gamma Survey. . I ns t r ume n t a t i on: Victoreen 491 Survey Meter Date: -10/85 to 12/85 Patty Kraft Melissa Patterson Q Grid Positions Grid Std. No. 1 2 3 4 5~ A " g. De.. 7) 186 0.050 0.050 0.050-0.050 0.050 0.050 0.0000 187 0.080 0.060 0.050 0.050 0.050 0.058 0.0117 ~ 188 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 189 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 190 0.050 0.060 0.060 0.050 0.050 0.054 .0.0049 191 0.050 0.050 0.050 0.050 0.060 0.052-0.0040 [] 192 0.050 0.050. 0.050 0.050 0.050 0.050 0.0000 193 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 194 0.070 0.050 0.050 0.050 0.050 0.054-0.0080 195. 0.050 0.050 0.070 0.060 0.050 0.056 0.0080 196 . fL 0 5 0 0.050 0.050 0.050 0.050 0.050 0.0000 197 0.050 0.050 'O.050 0.050 0.050 0.050 0.0000 m 198 0.050-0.050 0.050 0.050 0.050 0.050 0.0000 199 0.050. 0.050 0.050 0.050 0.050 0.050 0.0000 200 0.050 0J050 0.050 0.050 0.050 0.050 0.0000 203 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 204 0.050 0.050-0.050 0.050 0.050 0.050 0.0000 205 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 206 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 q~) .207 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 208 0.050 0.050 0.050 0.050 '0.050 0.050 0.0000 209 0.050 0.050 0.050 0.050 0.-050 0.050 0.0000 210 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 211 '0. 050 0.050 0.050 0.050 0.050 0.050 0.0000 212 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ';) 213 0.050 0.050 0.050 0.050-0.050 0.050 0.0000 214 0.050 0.050-0.050 0.050 0.050. 0.050 0.0000 '215 0.050 0.050 0.060~ 0.060 0.050 0.054 0.0049 '216 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 -217 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 Ji 218 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 219 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 220 0.050 0.050 .0.050 0.060 0.050 0.052 0.0040 l .221 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 222 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 223-0.050 0.050 0.050 0.050 0.050 0.050 0.0000 vs 224 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ..J ?- D.

Pass 24 Table: 3 3 ~ .3 eta-Gamma Survey I ns t r ume nt a ti on: Victoreen 491 Survey Meter Date: 10785 to 12/85 Patty Kraft Helissa-Patterson Grid Positions Grid Std. No. 1 2 3 4 5 Av5 Dev. ] 225 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 226 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 227 0.050 0.050 0.050 0.050. 0.080 0.056 0.0120 '228 0.050 0.'050 0.050 0.050 0.050 0.050 0.0000 1229 0.050 0.050 0.050 0.050~ 0.050 0.050 0.0000 230 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 3 231 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 232' O.-050 0.050 0.050 0.050 0.050 0.050 0.0000 233 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 234 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 235 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 236 0.050 0.050 0.050 0.050 0.050 0;050 0.0000 7' 238 0.050 .0.050 0.050' O.060 0.060 0.054 0.0049 -239 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 240 0.050= 0.050 0.050 0.050 0.060 0.052' O.0040 241 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 L 242' O.050 0.050 0.050 0.050 0.050 0.050 0.0000 243 0.050-0.050 0.050 0.050 0.050 0.050 0.0000

)

244 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 245 0.050 0.050 0.050 0.-050 0.050 0.050 0.0000 246 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ~247 0.050 0.050 0.050 0.050 0.050 0.050' O.0000 ~ 0.060 0.052 0.0040 l 248 0.050 0.050 0.050 _0.050 249 0.050-0.050 0.050 0.050 0.070 0.054 -0.0080 in '250 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ~' 251 0'050 0.050 0.050 0.050 0.050 0.050 0.0000 l 252 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 L 253 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 254 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 255 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 () -256 0.050 0.050 0.050 0.050 0-050 0.050 0.0000- -257 0.050 0.050 0.060 0.050 0.050 0.052 .0.0040 -258 0.050 0.060 0.050 0.050 0.050 0.052 0.0040 259 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 260 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 261 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 262 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 ()

) Pase24 Table: 3 ) 3 eta-Gamma Survey I ns t r ume nt a t i on: Victoreen 491 Curtey Meter Date: 10 35 to 12 85 Patty Kraft Helissa Patterson ) Grid Pouitions Grid S t d. No. 1 2 3 4 5 A. ;. De-g 263 0.050 0.060 0.050 0.050 0.050 0.052 0.0040 264 0.050 0.050 0.050 0.050 0.060 0.052 0.0040 265 0.050 0.050 0.050 0.050 0.060 0.052 0.0040 266 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 267 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 268 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 269 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 3 270 0.050 0.050 0.050 0.050 0.050 0.050 0.0000 271 0.050 0.050 0.050 0.050 0.060 0.052 0.0040 D D D b D

F t l l 5.- Pa ge 16 [J-Table: 4 = P.andom Camma 6ur'.sy of Controlled Access Areas - Inst rument: Victoreen '491 Our'/ey Meter ,.. Datesi10 35 t~o-12 35 [) Patty Kraft . Holisca Patterson i -31ock Po:ition 3 eta + Camma --Number-Sumber Gamma Only I 0.04 0.05 4 2. 7 2 0.05' -0.05 7' 3 0.07 0.05 .10-3 0.08 0.05 ] 24 4-0.07 0.05 30-2- 0.05 0.05-39~ 2 0.06 0.05 g l 40 1 0.06 0.05 l 41 3 0.06 0.05 49 ^5 0.05 0.05 [ 64~ 2 0.05 0.05-l]; 66: 2 0.05 0.05 -105 5 0.05 0.05 109 ~3 0.05 0.05 l 112 2 0.06 0.05 i 113 2 0.05 0.05 ') 1 1. 3.. 3 0.05 0.05 114 3

0. 05 0.05

117.-

-5 0.05 0.05 122 5-0.05 0.05 123 2 0.05 0.05 123' 5 0.07-0.05 '[) 134 3 0.05 -0.05 135 2 0.05 0.05 157 2 0.05 0.05 170 2 0.05 0.05 I '174 3" 0.05 0.05 ? 136 4. 0.05 0.05 q 213: 5 0.05 0.05-i -217 1 0.05 0.05 224 5 0.05-0.05 J226 2 0.05 0.05 227 5 0.08 0.05 246 -L4 0.05 0.05 3 4 r e-V v. <w v. y.--r--- ,,r--v-- 3 .y. -.,-., -.,y. -s,,,w -m.,y<-cy.,-mww-,..r,-... -, y- ,--y .. + +,,

I } 3I Page 27 ) Table: 'l ~ Random Gamma Survey of Controlled Access Areas I ns t rume nt: Vi c toree n '4 91 Survey Heter Date:!10/35 to 12/85 3' Patty Kraft-Molissa Patterson - Block Position 3 eta + Gamma Number Number Gamma Only 3 248 1 0.05 0.05 265 3 0.05 0.05 i

')

gamma and samma survey Note 1: All of the beta + - msasurments,above are in -milliroet ge n/ hour. Note 2: All of the measurements were less than L ' or e' qual to the_ numbers given Gamma surveys taken recm Table Note 3: Seta + m -/' w V 4 l 0 nsJ t 9 O

. -. - ~_. O:f Page 28 t Tablei 2 (( Alpha Wipe Test Results . I ns t rume ntat i on: Reuter-Stokes Flow Counter Date: 10/85 to 12/85 Patty-Kraft-George Palko Helissa Patterson Ch-Grid Position A c t i */i t y Uncertainty No. No. ( dpm) i d pm) m 1 2 2.22 11.10 e'. 1 5 6.66 13.32 5 1 0.00 11.10 6 1 4.44 13.32-6 2 2.22 13.32 6-4 0.00 11.10 7 1 4.44 13.32 c3' 7' 3 2.22 11.10 8 2 4.44 13.32 8 5-2.22 11.10 19 1 4.44 11.10 19-4 8.88 15.54 27 1 4.44 11.10 19 27 4 4.44 11.-.10 29 2 6.66 13.32 =29^ 4 2.22. 11.10 30 2 2.22 11.10' -30 3 2.22 ,11.10 31 1. 6.66 13.'32 e) 31 4 4.~ 4 4 11.-10 32 1 4.44 11.10 32 5 6.66 13.32 33 1 4.44 11.10 34 '2 2.22 11.10 39 1 4.44 11.10 g) 39 5 6.66 13.32 41' 2 4.44 13.32 42 1 8.88 15.54 42 4 6.66 13.32 42 5 4.44 13.32 52 1 2.22 13.32 )" 52. 2 2.22 11.10 61 2 2.22 13.32 61 3 2.22 13.32 62 1 2.22 13.32 N M \\M T p6 A q.u sw w = D_ O i 4 i mI r g p py p y w. -r4a-a--ya w .-v~9-e 9 -we,9-----m y-w- --ym-w-insyr,,y-+y.y.,,-m-

D-Page 29 Table; 2 3 Alpha Wipe Test Results I ns t r ume n t a t i o n: Reuter-Stokes Flow Counter Date: 10/85 to 12/85 Patty Kraft George Falko Helissa Patterson D Grid Position Activity Uncertainty No. No. ( dpm) ( dpm) 62 2 2.22 13.32 g 62 3' 2.22 13.32 62 4 0.00 11.10 62 5 2.22 13.32 63 1 2.22 13.32 63 2 2.22 13.32 63 3 4.44 13.32 63 4 4.44 13.32 63 5 6.66 15.54 64

1 4.44 13.32 64 2

2.22 13.32 64 3 2.22 13.32 64 4 4.44 13.32 0 64 5 4.44 13.32 65 1 2.22 13.32 65 2 2.22 13.32 65 3 0.00 13.32 65 4 0.00 13.32 65 5 0.00 13.32 ) 87 1 2.22 11.10 87 2 0.00 11.10 87 3 6.66 15.54 88 1 0.00 11.10 88 2 2.22 11.10 88 3 4.44 13.32 88 4 2.22 11.10 88 5 2.22 11.10 89 1 8.88 15.54 89 2 4.44 11.10 89 3 4.44 11.10 89 4 4.44 11.10 $) 89 5 6.66 13.32 90 1 4.44 11.10 90 2 6.66 13.32 90 3 15.54 17.76 0 O

i. L Page 30 i Table: 2 j

ilpha Wipe Test Results

= I ns t r ume nt ati on: Reuter-Stokes Flow Counter - Dat e: 10/85 to 12/85 Patty Kraft George Palko Melissa Patterson Grid-Position Ac t i vi t y Uncertainty ~ No. No. ( d pm) ( d pm) i 90 4 4.44 11.10 ) 90 5' 6.66 13.32 91 1 2.22 15.54 91 2 2.22 13.32 91 4 2.22 15.54 91 5 2.22 13.32 -92 4 2.22 13.32 ) 96 3 2.22 13.32 103 3 2.22 13.32 104 1 0.00 13.32 113 2 0.00 11.10 114 1 2.22 11.10 114 2 4.44 11.10 114 3 4.44 11.10 ~ 114 4 2.22 11.10 116 5-6.66 13.32 .115 1 2.22 11.10 '115 2 2.22 13.32 115 3 0.00 13.32 2): 116 1 2.22 13.32 116 1 .2.22 13.32 116 2 6.66 15.54 116 3 4.44 15.54 116 4 2.22 13.32 116 5 2.22 13.32 h 117 1 0.00 13.32 117 2 0.00 13.32 117 3 2.22 13.32 l 117' 4 2.22 13.32 117 5 2.22 13.32 ~ 124 2 2.22 13.32 )_ 133 3 4.44 13.32 166 4 2.22 13.32 [ 166 5 2.22 11.10 180 1 11.10 17.76 L ']. p i I

1 D Page 31 Table: 2 9 Alpha 'dipe Test Results I ns t r ume nt a t i on: Reuter-Stokes Flow Counter Date: 10/85 to 12/85 Patty Kraft George Palko Melissa Patterson S Grid Position A c t t '/t t y Uncertainty No. No. i dpm) ( d pm) 193 3 2.22 13.32 g 193 5 6.66 15.54 194 2 4.44 13.32 195 4 4.44 13.32 199 3 2.22 13.32 203 3 2.22 13.32 204 3 0.00 11.10 3 207 5 6.66 15.54 215 3 '4.44 13.32 215 5 11.10 17.76 217 2 6.66 15.54 219 3 2.22 13.32 224 3 2.22 13.32 ) 227 2 5.66 15.54 227 5 2.22 13.32 244 3 2.22 13.32 245 3 0.00 11.10 245 4 0.00 13.32 246 1 2.22 11.10 ) 246 2 2.22 13.32 246 4 0.00 11.10 248 1 0.00 13.32 248 5 2.22 11.10 251 1 2.22 11.10 252 1 0.00 13.32 ) 262 2 0.00 13.32 262 4 4.44 15.54 O e O

O AffEND/K A emuuuuuuuuumnumusummum8 DEC 3 01932 O... ANNEX A GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT O PRIGR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION.OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL O t ~ O \\ .O ( I O .i U. S. Nuclear Regulatory Co=11ssion Division of Fuel Cycle and Material Safety O washington, D.C. 20555 t ~ O July 1982 O L I-1.17 .O

r { The instructions in this guide, in conjunction.with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in O... decentamination and survey of surfaces or premises and equipment prior p .to abandonment or release for unrestricted use. The limits in Table 1 do notipply to premises, equipment, or scrap containing induced radio-activity ~for which the radiological considerations pertinent to their r use may be different. The release of such facilities or items from . regulatory' contro'l is considered on a case-by-case basis. O 1. The licenseeshall make a reasonable effort to eliminate residual ~ contamination. 2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination O levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering. g 3. The radioactivity on the interiiir surfaces of pipes, drain lines, g or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contam-ination at these Tocations is likely to be representative of contamination on the interior of the pipes, drain lines, or ,f ductwork. Surfaces of premises, equipment, or scrap which are Lo A likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits. m 4. Upen request, the Comission may authorize a licensee to relinquish .O possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified, i This may include, but would not be limited to, s'pecial circumstances such as razing of buildings, transfer of premises to another organization l< continuing work with radioactive materials, or conversion of facilities to a.long-tenn storage or standby status. Such requests must: O a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degrea of residual surface contamination. 'O b. Provide a detailed health a'nd safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public. p- !Oq s I-1.18 O-i . - + ~ ~w--,,-..e>. -,--r h, e -e-w ,-m x

)

(( 5. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that ()... contamination is within the limits specified in Table 1. A copy of the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, Washington, D.C. 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abar.donment. The survey report shall: a. Identify the premises. b. Show that reason'able effort has been made to eliminate f residual contamination. ) c. Describe the scope of the survey and general procedures followed. d. State the fkndings of the servey in units specified in g the instruction. O Following review of the report, the NRC will consider visiting the facilities to confirm the survey. g 'O( f O I-1.19 .O

O U O O O O U U U U U (* O O uw.. ACCEPTABLE SURFACE C0tiTAttitlAT10tl LEVELS NUCLIDE5 AVERAGEbcf MAXIMUMbdf REMOVADLEbef 8 / U-nat, U-235, U-230, and 2 2 2 ass:ciated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm Transuranics, Ra-226 Ra-220, 2 300 dpm/100 cm,2 20 dpm/100 cm2 Th-230. Th-228, Pa-231, 100 dpm/100 cm Ac-227, 1-125, 1-129 Th'-na t, Th-232, Sr-90, 200 dpm/100 cm Ra-223, Ra-224 U-232, 1-126, 1000 dpm/100 cm2 3000 dpm/100 cm2 2 1-131, 1-133 Onta-ganrra emitters (nuclides with decay modes other than 2 2 1000 dpm Sy/100 cm2 alpha emission or spontaneous 5000 dpm sy/100 cm 15,000 dpm Sy/100 cm fissinn) except Sr-90 and others noted above. a!!bere surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently. b s used in this table, dpm (disintegrations per minute) means the rate of emiss*3n by radioactive material as determined by correcting the A cour.ts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation, cHeasurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the' average should be derived for each such object. dThe maximum contamination level applies to an area of not more than 100 cm2 eThe amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft abscrbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. Ilhen removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. ITh3 average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of tstal absorber. i ( b ~

APPENDIX B 3 %M&&NANUSUdSS&dSSSUSUUfb&f85&NUSUd&d&&NdWA l .m... c ~ e. 3 I IE, Thermo L Eberline Electmn CO A AC A ATION CERTIFICATION OF CALIBRATION g A 0-E'O 7 - Ib 4 instrument 8/ Serial No. Type of Source m 3 ^' 7461 W M CP A g.nc; Range Calibration Point Reading '] k X1K 9 400K cpm 400K cpm l/ 00/' cpm k X100 9 40K cpm 40K cpm 1/pg cpm X10 9 4K cpm 4K cpm 4f( cpm g X1 9 400 cpm 400 cpm y0 0 cpm '3 k X1K 9100K cpm 100K cpm i 10% /g ggepm X100 0 10K cpm 10K cpm 10% /gg cpm CE:: 3 X10 9 1K cpm 1K cpm 10% /g cpm g X1 9 100 cpm 100 cpm l')% /gg cpm X 00 20 W CPP 2 l.1-A 5 $ 3 calibration sources used have calibration traceable to the National Bureau of Standa ds. 3 Date Signature P.O. Y'73 '? g 07070VM50V070'0V&M&#070Vfff090Vf&&& O

l 0 2 8 e x a n w n M N -u 77 R e

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4274 CAUBRATION CERTIFICATE APPENDIX B O

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~ ~ ~ ~ " ' 2986 Industnal Blvd. Box 197. Bethel Park. Pa.15102. Phone 412 563 2242 O INSTRUMENT SERVICE AND Call 8 RATION RECORD [" Oa&- SNeS Ync hebdci, Ck gg I h P be 49 -% /C l -2 b mci [ CALIBRATION O I,o a n Condition of Ec%i$ ment //as Received: Pu-239 2 uCi O o SALE O REPAIR - (O-Mini-Pulse MP-1 *** Pu-239 .024 uCi Porchase Order No. 4'7ff9/] [ Contact Name: y/), /11//Wl5M SrY-90 .008 uCi 1CALE SOURCE METER RESPONSE SCALE SOURCE METE R RESPONSE SCALE SOURCE METE R REsponegg mR/hr. mR/hr. mR/hr. ll 7d Y'h b 5 9,I )9,.2 19.6 O /D h*E f,) hk lCO Wo 1b d6 67 O CHECK SOURCE READING PROBE EFFICIENCES // / O End Window - On contact O Alpha p(Side Window - On Contact liC t.t O Beta O ocArrrNrroN: This Record Must Accompany Survey Meter. This is Not a Shipping Record. Frcquency of Recalibration May Vary Depending on Local, State or Federal Requirements. N / b0 Ma'ntenance-O I l f i Is.i ~ l&i nf, lt Vit)EG t& %( git [J M I L / ( PILLIl:0 ADDRESS Calibration s50.00/ Cal. s fo,CO Dosimeter Check 1-4/550.00 l Labor $50.00/ Hour

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I n ,1 PHONE: ((-)//M.M . O.....,-..........h. k, M9 D,s Jd 71 Mi85 OM t=dicen NOTE: In accordance dith NRC Re ulation Title 10-CFR-34.'Calibrat n sources traceable to the ' if te expires in months and this instrument National Bureau of Standa ds. This cegj/ g/ This record ould be maintained in your sh uld be ecalib ated on or before 2 fi es for uture nspection by the U.S. Nuclear Regulatory Commission. .O 6 AHP-RIS 201 m 7-er

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ATTACHMENT 9 O REUTER-ST0KES, INC. 1/23/86 EDISON PARK Twinsburg, OH 44087 O BETA-GAMMA SURVEY OF 18530 South Miles Parkway Cleveland, Ohio, 44128 O-A8N SEALED SOURCE STORAGE ROOM Tested with Victoreen Model 491/ (Sealed sources only) Lower limit of instrument is 0.02/ 0.03 mr/hr Background is 0.20/,0.03 mr/hrReadings in mr/hr O WEsr WALL ' c. I c '). C1 Icd l k 0,0% a 02 00% 0 { 3 U cf C6 c7 c f3 I
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ATTACHMENT 10 Egi O REUTER-STOKES,'INC. 1/23/86 EDISON PARK Twinsburg, OH 44087 O Survey Data for Controlled Access Areas 3, 4, and 5. 18530 South Miles Parkway, Cleveland, OH 44128 Victoreen Model 491' Beta / Gamma Survey Meter B076 Background approximately 0.02/0.03 mr/hr O GRID mr/hr GRID mr/hr GRID mr/hr A1 0.02 B1 0.02 C1 0.02 A2 0.03 82 0.03 C2 0.02 O A3 0.02 83 0.01 C3 0.02 A4 0.02 B4 0.02 C4 0.02 A5 0.02 B5 0.02 C5 A6 0.02 86 0.02 C6 0.02 O 'A7 0.02 87 0.03 C7 0.02 A8 0.02 88 0.03 C8 0.02 A9 0.01 B9 0.03 C9 0.03 A10 0.02 B10 0.03 C10 0.02 O All 0.02 Bil 0.03 C11 0.02 A12 0.02 B12 0.02 C12 0.02 'A13 0.02 B13 0.03 C13 0.02 A14 0.02 814 0.03 C14 0.03 O A15 0.01 B15 0.01 CIS 0.02 A16 0.02 B16 0.03 C16 0.02 A17 0.01 B17 0.02 C17 0.03 A18 0.02 B18 0.03 C18 0.02 O A19 0.02 819 0.03 C19 0.03 A20 0.03 B20 0.02 C20 0.02 A21 0.02 B21 0.02 B21 0.02 A22 0.02 B22 0.02 C22 0.02 O A23 0.01 r:23 0.02 C23 0.02 A24 0.02 B24 0.02 C24 0.02 A25 0.03 B25 0.02 C25 0.02 A26 0.03 826 0.03 C26 0.03 O A27 0.01 B27 0.02 C27 0.02 o
. ATTACHMENT 10 Page'2
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I O' GRID mr/hr GRID mr/hr GRID mr/hr 'A28 0.02 B28 0.01 C28 0.03 -A29- -0.03 .' B29 0.02 C29 0.03-A3.. 0.01 830 0.02 C30 -0.03 A31' O.04 B31 0.02 C31 0.03 A32 0.02 B32 0.02 C32 0.02 A33 0.03 833 0.02 C33 0.02 A34 0.02 B34 0.03 C34 0.02 g ' B35 0.02 C35 0.03 'B36 0.02 C36 0.03 B37 -0.02 C37 0.03 ~g B38 0.01 C38 0.02 g-839 0.02 C39 0.02 B40 0.02 C40 0.02 B41 0.02 C41 0.02 B42 0.02 C42 0.02 'O - C43 -0.01 C44 0.02 C45 0.02-C46 0.03 O l I iO i t .O i-i t 0~ ...-., =. _ -. _ __ ~ _,._.._ _,.
ATTACHMENT 11 retiteD M W CAA 1 Radiochem Lab #18 ) CAA 2 Radioactive Mat'l Assembly #19 l CAA 4,5 Co-60 Test Area #32 18530 South Miles Parkway CAA 3 Am-241 Storage Area #49 Cleveland, OH 44128 S N 3 E 13 /4-32 36 /S a 27 48 9 x // /4 /4 x24 39 f f a 24 SS- /2 x /3 0 15 24-44 40 10
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o reuterhStokeS N O. Due 2-s-7s FAGE 1 OF 10 REVISION A 5/23/83 O PROCEDURE NUMBER RS-SOP-830.2 PROCEDURE FOR WIPE TESTING ALPHA EMITTERS O t o O O ' 7f ir: s (/c4it:ti) '/ -Q '! /./
~~f PREPARED BY v~~
~~O Asst. Radiation sifety Orficer / / Q,,,,,_ REVIEWED BY e rqgineering MInager U APPROVED BY~~
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George Pale 6-O Radiation safety Of ficer Vice President - Operations FORM No.1001 ,3 r
reuterhSt0NES O "~ DATE 2-8-78 i PROCEDUF.E NUMBER RS-SOP-880.2 PAGE 2 OF 10 PROCEDURE FOR WIPE TESTING ALPHA EMITTERS REVISION A5/23/8[ l REVISION RECORD O PAGES DATE OF REVISED DESCRIPTION REVISION O Original 2/8/78 REVISION A g Per Engineering Change Notice Number 005693 5/23/83' g O O 'O O O O 'oam aa 10a$
reutergstokes oJrE NO 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 3 OF 10 PROCEDURE FOR WIFE TESTING ALPHA EMITTERS REVISION A 5/23/33 g 1.0 SCOPE This procedure definiates the method in which radioactive sources are to be wiped, a how the wipes are tested, how test results are documented, and the radiation safety procedures to be used. The Reuter-Stokes Radiation Safety Of ficer (RSO) has the responsibility to see that all sources designated in our several NRC licenses are wiped according to the specified frequency. This procedure also applies to the wiping of work areas, floors, hoods, and air samples from the radioactive materials plating laboratory. The alpha emitting materials used in the J plating laboratory are U-235, U-234, and U-233, as described in the referenced SNM license. O 2.0 REFERENCED DOCUMENTS 2.1 Reuter-Stokes, Inc., Special Nuclear Material License SNM 1826. 2.2 Reuter-Stokes, Inc., By-Product Material License No. 34-18156-01. O 2.3 Reuter-Stokes instruments, Inc., By-Product Material License No. 34-13233-01. O 2.4 10 CFR 19 Notices, instructions and Reports to Workers; Inspections. 2.5 10 CFR 20 Standards for Protection Against Radiation. O 2.6 10 CFR 30 Rules of General Applicability to Licensing By-Product Mat-erial. 2.7 10 CFR 70 Special Nuclear Material. g FORM No.1001
o reuter StokCS NO. DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 4 OF 10 PROCEDURE FOR WlEE TESTING ALPHA EMITTERS REVISION A 5/23/83 mo 3.0 SAFETY Only specifically authorized personnel, designated by the RSO, shall perform wipe testing and wiping. These persons shall be monitored with an appropriate film badge and/or dosimeter. All unauthorized personnel shall be kept out of the test and plating labs during wipe testing. Disposable gloves are to be worn by the u persons actually performing the wipes. Sources must not come in contact with the hands,or other portions of the body. t O 4.0 EQUIPMENT AND TOOLS NECESSARY FOR WIPING AND TESTING 4.1 2n geometry flow counter assembly. 4.2 Tank of P-10 gas (Ar-CH4) with regulator and bubbler. 4.3 Ortec Model PC 109 Preamplifier or equivalent. 4.4 Ortec 410 Multimode Amplifier or equivalent. O 4.5 (Two) Ortec Model 431 Timer Scalers or equivalent. 4.6 Ortec Model 115 Power Supply. O 4.7 Power Designs Power Supply Model 2K20 or equivalent. 4.8 Lead Shielding Bricks. O 4.9 Disposable Gloves. 4.10 Forceps. lO 4.11 Deionized water in 100 ml beaker. 1 FORM No.1001 l
^ NO ITUIS DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 5 OF 10 PROCEDURE FOR WIPE TESTING ALPHA EMITTERS REVISION A 5/23/83 g 4.12 Air Sampler - Union Industrial Equipment Model 600. O 4.13 Air Sampler - Mine Safety Appliances Model 5, Part No. 4661l8. 4.14 Two-three square feet of aluminum foil. O'~ 4.15 Q-tips. 4.16 1" filter paper disks. t O 4.17 Am-241 Standard Alpha Source New England Nuclear Model 300. 4.18 Aluminum Trays for flow counter. 'O 4.19 Filter paper - Whatman No. 41 - 11 cm or ecuivalent. 4.20 Masking tape. O 4.21 Leak Test Kit - RAD Services No. RSLTK-01. (This will replace Q-tips, deionized water, aluminum foil and razor blade.) 5.0 RECORD REQUIREMENTS 'O Those radioactive sources designated as ones which must be wiped, will be wiped during the first week of each quarter. At the same time, samples from the plating lab will also be taken. Wipes of workbenches, floors and exhaust hoods shall be O taken. Two air samples are to be taken quarterly and during periods of peak activity. The air sampler should be oriented such that samples can be taken with respect t the worker's breathing zone during actual plating. The Union Industrial .O "O
reuter[ Stokes NO. DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 6 OF 10 PROCEDURE FOR WIPE TESTING ALPHA EMITTERS REVISION A 5/23/83 g air sampler is a stationary unit which should be positioned in the immediate D vicinity of the plating bath. The Mine Safety Appliance air sampler is a portable unit which should be clipped to the tapel or collar for continuous monitoring while working with the SNM. Permanent records are to be kept of all wipes taken and g test results in such a manner as to provide quick access to legible data. 6.0 WIPING OF SOURCES AND LAB AREAS i 6.1 Lay out the aluminum foil, forceps, masking tape, filter paper cut in ') approximately 1" disks and Q-tips. Put on rubber / plastic disposable gloves. Label the Q-tips or filter paper disks with a piece of masking tape and label the filter paper disks for each source to be wiped. Moisten the Q-tips 7 ~ lightly in the celonized water. (Note: Filter paper disks are preferred, but they must be used if alpha emitting material is suspected or possible). 6.2 Carefully, but firmly, wipe the dampened filter paper disks or tip of the g cotton Q-tip over the top, bottom, and sides of the sealed source, or sur-faces of the mounting or storage device on which radioisotope contamination might be expected to accumulate. Since the surfaces of 3 some sealed sources, especially those containing beta emitters, may be mace of a thin foil, special care must be taken to avoid puncturing, erroding or otherwise damaging this surface during leak testing. 3 O FORM No.1001 q .)
reute h b g ATE 2-8-78 PROCEDURE NUMBER RS-50P-880.2 PAGE 7 OF 10 PROCEDURP.FOR WIPE TESTING ALPHA EMITTERS REVISION A 5/23/83 O 6.3 Place the labeled wipes on the aluminum foil until all of the sources, and the lab have been wiped. The lab wipes are to include two wipes from the O work area inside the fume hood, two wipes from an outside work area, two wipes from the floor adjacent to the fume hood, and two wipes from the inside of the fume hood in the vicinity of the exhaust filter. O 6.4 Using the forceps, put the wipes (Q-tip or filter paper disks) onto the aluminum tray and push the tray into the flow counter. Each wipe must be placed onto a new tray before running the test. Test method, calibration, O and calculations are described in the following section. If the source is found to be clean, no counting rate higher than background, the wipe can be disposed of into a normal trash container. If any contamination is evident, O the wipe must be discarded into the special 15/55 gallon steel drum designa-ted for disposal of radioactive materials. O 6.5 At least one air sample must be taken in the plating lab. Place a fresh I filter into the UNICO air sampler and run it for 15-20 minutes. Remove l l the filter carefully, and with a razor blade cut the filter into four pieces. O Count at least two pieces by placing each individually on its own aluminum tray and pushing it into the flow counter. If contaminated, follow the procedure in 6.4, for contaminated wipes. O l l !O 1 i PoRM No.1001 0 L
Mhb NO. O DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 3 OF 10 PROCEDURE FOR WIPE. TESTING ALPHA EMITTERS REVISION A 5/23/83. f
~~g 7.0 SET-UP AND CALIBRATION OF THE COUNTING SYSTEM 7.1 Hook up the flow counter, P-10 gas, and the electronics according to the O~~
diagram in Figure 1. Make sure that the bubbler is connected to the exit gas post of flow counter. 1 7.2 The flow counter must be purged by flowing the gas at a fast bubble rate .O' for a minimum of 100 seconds. The Reuter-Stokes preamp should be connected to the flow counter with a short shielded cable. t ,0 7.3 The Ortec 410 multimode amplifier should be set with a gain of 9 x 2.75 with 2 ps shaping, input attenuator of 10. The Ortec 431 scaler threshold j should be set at approximately 300 my with the sensitivity set at B.P. 0.1 4 0 to 1.1 volts. 7.4 Turn the bias supply to the flow counter to 1100 VDC. After the proper 'O purge, take three 100-second counts to determine background and electronic noise level. Change the 300 MV scaler threshold so that the count rate is less than one count per second. Once this setting is made, it is not to be changed for the duration of the testing. 7.5 Carefully remove the alpha standard Am-241 source from its wooden box with the forceps, and place it on an aluminum tray. Handle the edges of O the plastic container holding the source. Do not handle by touching the l l source with hands or forceps. Push the tray into the flow counter. l 0 PORM No.1001 O l
reutergtokes DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 9 OF 10 PROCEDURE FOR WIPE. TESTING ALPHA EMITTERS REVISION A 5/23/83 i O 7.6 Walt at least 100 seconds for the gas to stabilize again, and take three 100-second counts. Averaging should give a count of 145 cps 1 10 cps. This count rate on the standard is used to calculate the count rate for a reportable contamination. O 7.7 The following data is to be used for calculating the level of contamination of wipes and air monitors, and for calculating the count rate equivalent to a reportable contamination of 0.005 p:1 from an alpha emitting i O source. 1.67 x 10' dpm or 2.78 x 10 dps Am = t alpha standard 2 2 2 x m2 dps O 7.51 x 10 ' curies = 3,7 x 0,, dps/ curie * ^* * ' ' 5**"d*'d 3.7 x 10 " dps = 1 curie O 5.0 x 10~ ' curies = reportable contamination cps (standard) - Background, 5 x 10 curies x cps 7.51 x 10 ' curtes l
~~O x cps = (cps (standard) - Background x 5 x 10 curies) 7.5 x 10 'curtes l~~
l x cps is the number of counts which constitute a reportable contamination O level. The cps from the standard, and the background will vary slightly with each claibration. i l 'O O ponm u ions
O reuter N Stokes NO. DATE 2-8-78 PROCEDURE NUMBER RS-SOP-880.2 PAGE 10 OF 10 PROCEDURE FOR. WIRE. TESTING ALPHA EMITTERS REVISION A 5/23/83 mv 7.8 The calculation for the total amount of contamination on each wipe is a O ratio of counts obtained from a wipe to the counts obtained from the standard Am '1 alpha source. 2 O cps (alpha std), 7.51 x 10 curies Example: cps (wipe) x curies I x curies = cps (wipe) x 7.51 x 10' curies O cps (alpha std) 'O O l l l !O 1 l 10 l lo PoRM No.1001
q sA E80% UNITED STATES / NUCLEAR REGULATORY COMMissl0N y ei{.S REGION 111 l rss noosevetr moao 84 .f oLEN ELLYN, ILUNolS 60137 9 MAY 2 1985 Reuter-Stokes, Inc. ATIN: George Palko 'g Vice President, Operations 18530 South Miles Parkway Cleveland, OH 44128 Gentlemen: O Enclosed.fs Amendment No. 01 renewing your NRC License Nuriber SNM-1826 in accordance with your request. Please note that License Condition 11. authorizes you to use special nuclear materials at your present facility on South Miles Parkway and at your new t facility in Edison Park. Please be advised that we cannot authorize you to O release your present facilities for unrestricted use until we have received and reviewed a copy of the results of your close-out survey. The survey should consist of exposure rate measurements to show that all sources of radioactive material have been removed, and contamination checks of areas where radioactive materials were us d or stored. Average radiation levels associated with surface contamination and removable contamination should not exceed those specified in O the enclosed decontamination guide. Please submit the following information with your close-out survey: a. A diagram of your facility on South Miles Parkway with survey and wipe test results keyed to specific locations. O b. The name of the person / organization perfoming the survey. c. The date the survey was perfomed. d. The instrumentation used for exposure rate measurements and for analysis of the wipes. The method of calibration and the date of the last calibration, g e. Background readings. When submitting the results of the close-out survey, please state in your documentation, "This'is Additional Information, Not A New Request". O Please review the enclosed document carefully and be sure that you understand in accordance with the conditions of your NRC license,gg radioactive materials all conditions. You must conduct your program involvi representations made in your license application, and NRC regulations. In particular, note that you must: O 1. Operate in accordance with NRC regu]ations 10 CFR Part 19, " Notices, Instructions and Reports to Workepst Inspections," 10 CFR Part 20, " Standards for Protection Against Radiation," and other applicable regulati9ns. O lALA c n % C Q -- O vv%yowagg
O MAY 2 1985 Reuter-Stokes, Inc. 2 0 2. Possess radioactive material only in the quantity and form indicated in your Itcense. 3. Use radioactive material only for the purpose (s) indicated in your O: license. 4. Notify NRC in writing of any change in mailing address. 5. Request and obtain appropriate amendment if you plan to change ownership of your organization, change locations of radioactive material, or make O any other changes in your facility or program which are contrary to your Ifcense conditions or representations made in your ifcense application and any supplemental correspondence with NRC. Any amendment request should be accompanied by the appropriate fee specified in 10 CFR Part 170 t 6. Submit a complete renewal application with proper fee or termination O request at least 30 days before the expiration date on your license. You will receive a reminder notice approximately 90 days before the expiration date. Possession of radioactive material after your ifcense expires is a violation of NRC regulations. 7. Request termination of your license if you plan to permanently discontinue O activities involving radioactive material prior to your expiration date. You will be periodically inspected by NRC. Failure to conduct your program in accordance with NRC regulations, license conditions and representations in your license appifcation will result in enforcement action against you in accordance with the General Policy and Procedures for NRC Enforcement Actions,10 CFR O Part 2, Appendix C. If you have any questions or require clarification of any of the above stated information, contact us at (312) 790-5625. Sincerely, O c5 MaterlaWficensing Section O Enclosure (s):
1. Amendment No. 01

2. 10 CFR Parts 2, 19, 20, 70, 71 and 170

3. Decontamination Guidelines O
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