ML20132D336

NRC Insp Manual Ti 2800/026, Followup Insp of Formeraly- Licensed Sites Identified as Potentially Contaminated

ML20132D336
Person / Time
Issue date:	02/16/1995
From:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
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ML20132D318	List: IA-96-464, Forwards Description of Expert Sys for Evaluation of Retired Nuclear Matl Licenses ML20132D313 ML20132D332 ML20132D336 ML20132D340
References
FOIA-96-464 2800-026, 2800-26, NUDOCS 9612190327
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i ug l y *g UNITED STATES NUCLEAR REGULATORY COMMISSION E WASHINGTON, D.C. 2066H201 f

%*****/ NRC INSPECTION MANUAL IMDB/NNSS TENPORARY INSTRUCTION 2800/026 FOLLOWUP INSPECTION OF FORNERLY-LICENSED SITES IDENTIFIED AS POTENTIALLY CONTANINATED r

SALP FUNCTIONAL AREA: N/A APPLICABILITY: 2600 and 2800 2800/026-01 OBJECTIVE l

To verify the status of formerly-licensed sites for which there is inadequate

documentation in the docket file to demonstrate that they were properly [

decommissioned.

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i 2800/026-02 BACKGROUND l

l In 1976, the General Accounting Office (GAO) raised concerns about the l decommissioning of sites fonnerly licensed by the Atomic Energy Commission's l (AEC's) regulatory body, which is now the Nuclear Regulatory Commission (NRC).

In its response, NRC agreed to reexamine the files of the tensinated licenses. .

Between 1977 and 1982, Oak Ridge National Laboratory (ORNL) reviewed the docket files for all fuel cycle and materials licenses terminated before 1965 (approximately) to verify that all sites had been properly decommiissioned. This was done under an interagency agreement with the NRC. The files of 16,230 former licensees were reviewed and a total of 12 contaminated sites were identified.

All of the 12 sites had been licensed pursuant to 10 CFR Part 40 and none l

represented a significant risk to public health and safety. NRC took action to i have fonner licensees decontaminate seven of the sites. The Department of Energy  !

(DOE) accepted responsibility for the other five sites under its Fomerly -

Utilized Site Remedial Action Program (FUSRAP).

In 1989, GAO issued a report on NRC decommissioning procedures and criteria.

This report raised additional concerns about the decommissioning of formerly-licensed sites. On August 3, 1989, Chairman Carr testified to the House Subcoastittee on Environment, Energy, and Natural Resources that NRC would review the records of all sites tensinated since 1965. ORNL was contracted again to

. review all docket files retired between 1965 and 1985. This second study

. required the creation of a computerized inventory of the docket files in addition j to screening the files to determine whether all licensed sites had been properly decosumissioned. If documentation were inadequate to verify that a fonnerly-licensed site had been properly decomunissioned, the status of the site was to be verified by inspection.

Issue Date: 02/16/95 2800/026 9612190327 961216 PDR FOIA SAVAGE 96-464 PDR

.. t j

Subsequently, NRC oecided that it was necessary to review the files of all j

• teminated licenses (Pre-1965 and Post-1985) using the sameThis screening criteria would improve j and to document their status in one computer inventory. l information retrieval and pemit comparison of the review findings for all l

The staff intends to verify by inspection the status 1 terminated license files.

of additional sites for which there is inadequate decommissioning documentation also.

i 2800/026-03 INSPECTION REQUIREMENTS j 03.01 When the docket file for a formerly-licensed site or a sealed source license is referred to the region for followup, review the concerns raised by ORNL and verify that there are no errors or misunderstandings j in ORNL's findings. First priority shall be given to sites scoring >300, 4 Check regional then sites scoring $300, and then sealed source files.

j files and institutional memory regarding legitimate concerns raised by i ORNL. If necessary, request the former licensee and/or the current site owner to review its files and institutional memory regarding concerns about the site. If any of the sites are located in Agreement States and there is reason to believe that State files may help, request the L

Agreement State to check its files and institutional memory, and forward any results to the region.

03.02 For each site in question, determine whether a site visit If is required to the site is 4

resolve any of the concerns raised by the file review. ,

located in an Agreement State, request the Agreement State to inspect the )

j site, with NRC accompaniment if necessary. For sealed source licensees, '

' a site visit would not be required normally; however, if the site will be inspected because of potential site contamination, an inquiry into the  ;

' disposition of the sealed sources can be conducted as part of the site visit. Infom the Regional State Agreements Officer (RSA0) of any

requests made to an Agreement State.

03.03 Coordinate all site visits with the appropriate radiological control t

program within the State, local authorities, the former licensee (if Explain the possible), and current site owner before the inspection.

specific issues concerning the site status raised by the file review.

03.04 Detemine if documentation missing from the docket file can be obtained Check

' from additional records that may still be available at the site.

the institutional memory of site operations by interviewing key personnel from the former licensee, current site owner (if different), or other -

knowledgeable individuals. For sealed sources, these inq91 ries should be made by telephone or written correspondence if possible.

03.05 If necessary or desirable to verify the status of the site, survey the site for residual contamination or other radioactive material associated with previous AEC/NRC activities. Detemine whether remedial actions are required to remove radioactive materials in excess of NRC limits for 4

unrestricted use. Notify IMDB/ MSS promptly of any site found

' contaminated and obtain NMSS input on plans to proceed.

NOTE: If significant site contamination is identified, the inspector should contact regional management before i leaving the site to discuss the need for barriers,

' Issue Date: 02/16/95 2800/026

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{ postings, and/or administrativa controls to address any l

- inusediate health and safety concerns.

03.06 If the fomer licensee or current site owner will perfom remedial l actions that are expected to be completed within a few months, monitor l the cleanup activities to ensure they meet the intent of 10 CFR Parts 19  !

and 20, and verify that the site is decontaminated to levels suitable for  !

unrestricted use. Coordinate with IMDB/NMSS regarding the transfer of i sites requiring long-term remediation to the Site Decommissioning Management Plan (SDNP) or another long-term program.

03.07 When all regional action on a license file is complete, return the file to the NRC File Center, unless otherwise instructed.

2800/026-04 GUIDANCE 04.01 If an Agreement State cannot support a request to review its files, the region should assist with the review of State files to the extent possible. If there are questions about whether NRC will be allowed to review State files, coordinate with the RSA0 and INNS /NMSS. Obtain copies of official documents for the docket file whenever possible. If official documents are not available, verbal confirmation may be used to l close out specific concerns about contamination if a record of sah

! conversations is placed in the docket file And neither of the following conditions apply. Verbal confirmation shall .n_tt, be used as a basis for clo ing out a concern if -- l

a. The concern raised by ORNL involved the sensitivity of the survey l instruments originally used, or l

l b. lme license authorized possession of a large quantity of unsealed material (>100 kilograms of uranium / thorium or >l curie of long-lived I

byproduct material such as cobalt-60).

04.02 Copies of Agreement State inspection reports should be obtained for the docket files. The region should review' Agreement State inspection l findings and determine whether they resolve the concerns about the  !

license file. If an Agreement State cannot support a request to inspect a site in its jurisdiction, the region should offer to provide assistance with inspecting the site. If there are questions about NRC perfoming an '

inspection in an Agreement State, coordinate with the RSA0 and IMS/ MSS.

The license files involving unaccounted sealed sources are a lower priorit and less amenable to resolution. For active sites, or even license s active at another site, it may be possible 6 detemine the -

disposi ion of the sources. Government licensees in particular may be able to detemine the disposition of sources. For licensees no longer active, it may be very difficult to come to any conclusion. Recognizing the difficulties of tracing the disposition of sealed sources when neither documents nor institutional memory remain, the regions should try I to resolve these without an undue expenditure of effort and should exercise their judgment as to whether particular sources are of concern.

04.03 The inspector should try to arrange mutually agreeable inspection times to ensure that knowledgeable individuals at the site will be available for interview. Non-Agreement States should be invited to accompany the inspector on any site visits.

Issue Date: 02/16/95 2800/026

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, 1 04.04 Obtain copies of official documents for the docket file whenever

- possible. If official documents are not available, verbal confirmation

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may be used to close out specific concerns about contamination if a record of such conversations is placed in the docket file and neither of the conditions listed in 04.01 applies.

04.05 The initial survey should be a scoping survey to determine whether there is any indication that residual contamination or other radioactive material may be present. A sample scoping survey plan is provided in Appendix A, including criteria for determining when remediation is required. Guidance on release criteria is provided in Appendix 8.

Inspectors may also use guidance in Inspection Procedure (IP) 83890 and other routine inspection procedures, as appropriate. If radioactive material is found or if the site is too extensive to permit an inspector to reasonably eliminate the possibility of contamination, a detailed site ,

survey should be perfomed. The former licensee or current site owner should be requested to conduct the detailed site survey. whenever possible. If neither party is able or willing to perform a survey, funds are available under FIN A9093, " Radiological Evaluation Assistance for Formerly Licensed Sites," to have the Oak Ridge Institute for Science and i

1 Education (0 RISE) perform scoping surveys, confirmatory surveys (during/after remediation), and sample analyses. ORISE may be requested to evaluate licensee surveys also. Regions should submit requests for ,

technical assistance (RFTAs) in accordance with Manual Chapter (MC) 0312 to obtain services from ORISE. If the site has not been inspected 4

already, regional management should consider the need for a site visit before an RFTA is submitted.

04.06 Inspectors should use guidance in IP 83890, " Closeout Inspection and Survey," and other routine inspection procedures as appropriate to monitor remediation activities. Each region shall notify IM08/NMSS promptly of any site found contaminated and discuss transfer of sites requiring long-term remediation to the SDMP or another remediation program. The following criteria should be used to determine which sites  ;

should be transferred to SDMP for remediation (see NUREG-1444). ,

a. The responsible organization is not financially viable (e.g., unable to pay for decommissioning).

b. There are settling ponds, burial sites, or large amounts of contaminated soil that will be difficult to decommission.

c. There are contaminated structures or other permanent facilities that will be difficult to decommission.

d. There is contamination or potential contamination of the ground water from onsite wastes.

04.07 No guidance.

2800/026-05 REPORTING REQUIREMENTS Each region shall document its findings regarding the specific concerns identified by ORNL for each site in quarterly status reports to IMDB/NMSS.

Regions should provide the infomation shown in the example status report provided in Appendix C. IM08 will track each site referred to the region and Issue Date: 02/16/95 2800/026

I In addition, each region shall send the IM08 l l

verify that it :s closed out.  ;

contact statistics on the number of sites referred to the region for followup,

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number of sites eliminated from concern, number of sites found contaminated, and number of sites pend

ng a determination. These figures should be divided into i This information is l

licenses with scores above 300 and scores below 300. l l

required for the Monthly Information Status Report, however it will only be submitted quarterly. (See Appendix 0 for guidance.)

Inspections and confirmation surveys should be documented in an inspection

' report. All site visits, whether for inspection or for other pcrposes, should be documented including a description of the site and any controls in place.

Status reports and inspection reports shall be forwarded to the contact listed i

in Section 08 of this temporary instruction (TI). Documents demonstrating that a site is suitable for unrestricted use shall be placed in the docket file for i ,

that site and sent to the IMOS contact. 'i f, I I

2800/026-06 COMPLETION SCHEDULE i

The completion schedule for followup inspections of formerly licensed sites will vary depending on the resources available and the number of sites requiring followup action. In general, the initia? inspection of each site requiring a l

j site visit should be completed within 9 months of receiving the docket file.

! 2800/026-07 EXPIRATION l

This temporary instruction shall remain in effect until December 31, 1997.

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l 2800/026-08 CONTACT t Questions regarding this temporary instruction should be addressed to Paul j j

Goldberg, Project Manager for the Review of Tenninated Licenses, at (301) l 415-7842. \

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! 2800/026-09 STATISTICAL DATA REPORTING i Staff hour expenditures or administrative effort should be charged to Regulatory ,

l Information Tracking System (RITS) number 2328M - Review of Terminated Licenses. l 3

Direct inspection effort should be charged to the retired docket number, the item '

of major interest code (i.e., IMAT - Materials Inspections), and the inspection l

procedure element code (i.e., OA - Other Routine Activities, or OR - Other Reactive Activities). Include the temporary instruction number 2800/026X with a

l Complete, or R -

the appropriate status codes P - Partially Complete, C -

Completed By Reference, so staff hour expenditures charged to the TI can be i

accounted for by site.

Note: The docket nusber should be listed in the Licensing Tracking System (LTS) with a retired status code 4 to ensure that fee statements a generated and to allow RITS to recognize the retired docket as being valid for staff time expenditures. Staff should not create fictitious docket numbers for capturing staff hour data. Contact M.Jones Moriarty at 301-415-7876,if at 301-415-7807, if assistance with LTS is required, or B.

assistance with RITS is required.

2800/026 Issue Date: 02/16/95

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2800/026-10 ORIGINATING ORGANIZATION INFORMATION

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! 10.01 Oraanizational Resoonsibility; The Operations Branch of the Division of Industrial and Medical Nuclear Safety (IM0B/NMSS) initiated this TI.

10.02 Resource Estimate. The estimated onsite inspection time necessary to interview personnel, check records, and perform an initial scoping survey

!. is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per site. Actual inspections at a specific site may require i substantially more or less time depending on the circumstances. With trip preparation, t, avel, and report preparation, the total time required is estimated to average 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. .

END l

• Appendix A - Sample Scoping Survey Plan Appendix B - Guidance on Release criteria .

Appendix C - Example Site Status I:eport  !

Appendix D - Input for Monthly Information Status Report (MISR) i I

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1 2800/026 Issue Date: 02/16/95

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I APPENDIX A 4

SAMPLE SCOPING SURVEY PLAN i

Licensee

Name i Address i City, State, Zip Code J

j License No.: XXX-000 (Terminated) .- ,

j Docket No.: OX0-00000 (Terminated) 4 Insnection Dates: Month Day, 19yr l ,

Insnector(s): Name(s)

Purpose of Insnection: Describe (e.g., To perform a scoping survey to determine whether any radioactive contaminants exist onsite, and if necessary, determine the general extent

' of residual activity present in building surfaces and grounds, and adjacent offsite areas.)

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Determine radionuclide(s) used at the facility:

. I.

List isotopes.

A. Review file to determine use areas:

Describe areas of use.

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! B. Interview previous or current employees:

Discuss as applicable.

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II. Identify affected and unaffected areas:

j Discuss generally.

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! A. Affected Areas (Areas that have the potential for contamination):

! Define (e.g., labs, machine shops, storage areas, manufacturing i

areas, locker rooms, emission stacks, offsite areas adjacent to

release points where material may have been deposited) l B. Potential Areas (Areas inmediately adjacent to affected areas):

Define (e.g., loading docks, storage areas, hallways, roofs)

C. Unaffected Areas (All remaining areas not identified as affected or potentially affected):

Define (e.g., offices, lobbies, bathrooms, parking lots) 4 i

A-I 2800/02 Issue Date: 02/16/95

III. Determine survey instruments and efficiency (see NUREG/CR-5845, " Manual for

. Conducting Surveys in Support of License Termination"):

A. If only a few nuclides used, determine efficiency for all nuclides:

See Sanple Instrumentation Worksheet.

4 B. If numerous nuclides used --

1 1. Determine efficiency of predominately used radionuclides or

2. Determine efficiency based on nuclide present in analyzed samples.

j See Saapie Instrumentation Worksheet.

j C. List instruments to be used:

1 Complete before inspection.

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! IV. Burial Sites

! A. Determine if facility had onsi'.e burials:

Discuss (e.g., Based on a review of the docket file and discussions

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with the fomer licensee, it was determined that there was no onsite burial.)

l B. If the possibility of subsurface contamination or burials exist, what i additional sampling and surveying will be conducted?

i Describe (e.g., Because it has been determined that onsite burial i did exist, ORISE has been contacted to perform surveys of this site.)

C. Do groundwater monitoring wells exist?

Discuss (e.g. , Because it has been determined that some onsite j burial took place, and onsite groundwater sampling wells exist, j water samples will be collected from these wells. In addition, the i results of the analysis of previous samples from these wells will be obtained.)

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) V. Other A. Photograph site and adjacent areas:

Discuss (e.g., Photos will NOT tee taken.)

VI. Survey A. Areas to be surveyed:

Describe (e.g., survey will include floors, drains, pipes, ducts, cracks, lower 2 meters of walls, ventilation system to extent practicable, areas adjacent to release points, and outside areas adjacent to buildings.)

Guidelines:

Affected areas - 100 percent walkover using 2-eater wide lanes.

potential areas - 50 percent walkover using 2-enter wide lanes.

Unaffected areas - 25 percent walkover using 2-eeter wide lanes.

2800/026 A-2 Issue Dati: 02/16/95

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l. Ij i B. Locations for collection of wipes:

1- Describe (e.g., Wipes will be collected at each ;ocation of l i elevated measurements or randomly, if no elevated measurecents are J

found.)

j C. Collection of residue samples:

Describe (e.g., Samples will be collected of all residues found with elevated readings, including surfaces under paint. If samples are potentially contaminated with hazardous biological or chemical

- materials, the regional office will be contacted for any special instructions on sampling and shipping before collecting the sample.)

I j D. Collection of soil / sediment samples: l Describe (e.g., Soil / sediment samples will be collected from outside areas whtre unsealed licensed material was stored, from .

areas that were formerly settling ponds, at stors and/or sanitary drain outfalls, and in or at the edge of streams or lakes.)

E. Documentation:

See Survey Plan by Location. l Describe (e.g., All surv6y results and locations of elevated i i

readings will be documented with enough detail to be able to relocate any point. Reference will be made to predominant l landmarks.)

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! VII. Identification of Contamination:

A. Provide sufficient information for laboratory personnel to  ;

identify / track samples and wipes that were collected:

Describe (e.g., Each sample and wipe will be uniquely identified.)

B. Conduct laboratory analysis:

l. Determine the radiological characteristics of the contamination:

q Discuss (e.g., Samples will be evaluated to detemine exposure i f

rate, and whether they are an alpha, beta, or gamma emitter.) l i

j 2. Detennine whether contamination is removable or fixed:

i Discuss (e.g. , Wipes will be counted to determine whether contamination is fixed or removable.)

l 3. Determine levels of contamination in samples:

Discuss (e.g., Samples will be counted and results reported to the inspector for evaluation.)

1 1 VIII. Evaluate survey and laboratory results:

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1. Identify survey data and laboratory sample analysis that exceed the

maximum guideline criteria

j Discuss. If activity is identified that exceeds the maximum release guidelines, remediation is required.

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See Saaple Instrumentation Worksheet.

Issue Date: 02/16/95 A-3 2800/026

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2. Identify samples that exceed the average (over one square meter),

but are less than the caxitum guideline criteria:

Discuss.

If activity is identified that' exceeds the average l release guideline, but is less that the maximum release

guideline, the NURE6/CR-5849 area weighted formula will be us i to determine the contamination level averaged over one square i

meter. If the area weighted average exceeds the average release guideline, remediation is required.

see Sanple Instrumentation Wortsheet.

APPROVED SY: Date r 4

' Branch Ch1ef 4

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s A-4 Issue Date: 02/16/95 2800/026 4

SURVEY PLAN BY LOCATION LOCATION 1 Area:?????

Size: Affectef/

m Potential / Unaffected Use: Describe (e.g., U-235 and natural uranius. Uranium tetrafluoride-magnesium blend was pressed into briquettes using a 3,000 ton ,

Farquhar press.) \

Potential for Contamination: Discuss. Modify Itens 1-4 as necessary. 1

1. 50 percent surface scan of floor (If items stored in the building cover more than 50 percent of the floor surface, than all available floor  ;

surface area will be scanned.)

2. 100. percent surface sc.an of cracks in floor, support beams (up to 2m high), and drains

3. 50 percent inlets / openings to ventilation system ducts

4. collect samples of positive areas 2 to 3 times background OTHER LOCATIONS ONSITE I Repeat above (Location 1) as necessary.

Issue Date: 02/16/95 A -

2800/026

. I SAMPI 5: INSTRUMENTATION WORKSHEET Inspector:

Date:

Inspection Location:

Inspection Date:

Isotopes of Interest:

Instrument - Type: Probe:

Serial f: Serial #:

I NRC f: NRC #:

cm, Calibration Date: Size (5):

• • • • • • • .n n n a a n;a a a a n;***n .n .n a a .n n n n:.n n ****************

l Check Source: Isotope: ~

Serial No.: I

' NRC Tag No.:

Half Life (T,): years x 365 - days Date: Activity (A,): yCi x 2.2x10' - dpm l

Current Date minus Source Date (t): years or days Current Check Source Activity: A - A, x exp[-0.693t/T,]

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- x exp[-0.693 x / ] = pCi or dpm I

Meter Reading with check Source (M): pCi (x 2.2x10' - cpm)

J cpm Efficiency (E): N/A = / -

(x 100 -  %) l 1

^

. Background (B): pCi (x 2.2x10' - cpm) Date:

cpm Location:

Background (B): gCi (x 2.2x10' - cpa) Date:

cpm Locatic'i:

Background (B): pCi (x 2.2x10' - cpm) Date: _

cpm Location: ,

2800/026 A-6 Issue Date: 02/16/95

I SAMPI F INSTRUMENTATION WORKSHEET. continued Inspector:

Date:

Maximum Release Criteria for Isotope of Interest (X): dps/100 car (See Appendix 8 and the guidance in NUREG/CR-5849.)

Instrument Reading That Equals Maximum Release Criteria: ((X/100) x S x E} + 8 f

- (( /100) x x }+ = cpm Averaae Release Criteria for Isotope of Interest (X): dps/100 cm 2 Instrument Reading That Equals Average Ralease Criteria: ((X/100) x 5 x E} + B

= (( /100) x x }+ - cpm l

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +.***************

Meter Source Checks Check Source: Isotope: Serial No.:

NRC Tag No.:

Date Time E er Readina Location Issue Date: 02/16/95 A-7 2800/026

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APPENDIX B Guidance on Release Criteria and NUREG-1444, As stated in the SDMP Action Plan (57 FR 13389, April 16,1992) the guidance for determining whether sites are suitable for unrestricted use consists of the following documents:

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1. Options 1 and 2 of the Branch Technical Position, " Disposal or Onsite Storage of Thorium or Uranium Wastes from Past Operations" (46 FR 52061, j .

October 23,1981).

2. " Guidelines for Decontamination of Facilities and Equipment Prior to Release ,

for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," Policy and Guidance Directive FC 83-23, Division t

of Industrial and Medical Nuclear Safety, November 4,1983. (Editorial revision issued August 1987 )

3. " Termination of Operating Licenses for NJclear Reactors," Regulatory Guide 1.86, June 1974, Table 1, for surface contamination of reactor facility structures. Also Cobalt-60, Cesium-137, and Europium-152 that may exist in .'

concrete, components, structures, and soil should be removed such that the 1 exposure rate is less than 5 micro-roentgen per hour above natural ,

l background at 1 meter, with an overall dose objective of 10 millirem per Miller, Chief, year (cf. Lette- to Stanford University from James R.

Standardization and Special Projects Branch, Division of Licensing, Office l

of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, April 21, 1982, Docket No. 50-141).

4. The Environmental Protection Agency's (EPA's) " Interim Primary Drinking Water Standards," 40 CFR Part 141. In accordance with FC 83-23, the maximum ,

contaminant levels for radionuclides in public drinking water, as established by EPA, should be used as reference standards for protection of ,

groundwater and surface water resources.

5. EPA's " Radiation Dose Guidelines for Protection Against Transuranium Elements Present in the Environment as a Result of Unplanned Contamination,"

This document provides guidelines for (42 FR 60956, November 30, 1977).

acceptable levels of transuranium elements in soil.

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8-1 2800/026 Issue Date: 02/16/95 l

l NRC uses the guidelines listed in the following tables as acceptable levels to

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release sites for unrestricted use. Acceptable levels for other radionuclides will be determined on a case-by-case basis.

Table 1. Acceptable Soil Contamination Levels Radionuclide* Maximum Soil Concentration (pCi/gs)

Hydrogen-3 6 (no limit, see Table 2) 6 8 Cobalt-60 b 5 Strontium-Cesium-137l0 --

15 Plutonium-238g239" --

• [

Americium-241 Radium-226* 5 Radium-228* 5 d )

Natural Thoriumd 10 Natural Uranium 10 d 35 Depleted Uraniumd Enriched Uranium 30 l

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Table 2. Acceptable Groundwater Contamination Levels" Radionuclide* Maximum Groundwater Concentration (pCi/ liter)

Hydrogen-3 20,000 ,

l Cobalt-60 100 '

Strontium-90 8 '

Cesium-137 200 Gross alpha incl. Ra-226 15 5

l'a-226/228 4

• If only one radionuclide is present, then the anaisua concentration is the value listed in the table. usuever, if more than one radionuclide is present, determine for oed radionuctide the ratio The between sus of the sensured concentration (in soil or growiduster) and the concentration 1isted in the tabte.

the retles any not onceed one (i.e., uilty).

Order Establishing Criteria and schedale for Decosusissioning the 5theg, PA Site (Safety Light Corporetten), 57 Fa 6134, February 20, 1992.

• U.S. Emironenntet Protection Agency, Meetth and Environenntal Protection Standards for Uranium and Thorium Mitt Tellirgs, 40 CFR Port 192, $@ parts 8 and E, July 1, 1991.

Branch Technical Position, Disposet or Onsite Storage of Thortun or Uranlue Westes f rom Past operations, 44 FE 52061, October 23, 1961.

• The vetues for Pu-238/239 and An-241 provided in the Order are eestantietty higher then the values Consult currently boire ,- . , -" in NUREG-1500, uorking Draf t Repstatory Guide on Release Criterie.

Inaspeess and LtDPAsess if values are regaired.

B-2 Issue Date: 02/16/95 2800/026

e Table 3. Acceptable Surface Contamination levels Nuclides' Average' "

• Maximum' ' k Removable' 3 "

2 J-nat, U-235, U-238, and associated 5000 dpm alpha /100 cm 15,000 dpm alpha /100 cm2 1000 dpm alpha /100 cm*

tcay products 2

Transuranics, Ra-226, Ra-228, Th-228, 100 dpm/100 cm 300 dpm/100 cm2 20 dpm/100 cm2 Th-230, Pa-231, Ac-227, I-125, I-129 2

Th-nat, Th-232, Sr-90, Ra-223, Ra-224, 1000 dpm/100 cm 3000 dpm/100 cm2 200 dpm/100 cm2 U-232, I-126, I-131, I-133 Bata-gasma emitters (nuclides with decay 5000 dpm beta-gamma / a 15 000 dpm beta-gamma /

e 1000 dpm beta-gamma /

100 cm 2 2 modes other than alpha emission or 100 cm 100 cm spantaneous fission) except Sr-90 and oth2rs noted above t

f Wre surface contentnetten by both etpha- and beta-genne-emitting nuelldes existe, the limite estabilshed for alpha and beta-gessne-Y-

emitting nuclidae should apply 1 %- l 8 thle table. @ m (dtsintegratione per minute) means the rete of eelssion by radioactive meteriet es determined by correcting the

• [ e rved by en appropriate detector for background, efficiency, and geometric f actore associstsd with the Instrtseentation. -

h steceurements of everage contesinent should not be overaged over more then 1 square meter. For objects of tese surface area, the everage  !

ehould be dortved for each M oct.

I The maximse concentration tevet applies to en area not more then 100 square centimeters.

j The emotet of removebte radioactive meteriet per 100 co' of surface aree should be determined by wiptne het area with dry filter or sof t applying moderate pressure, and esseselns the enount of redloective meteriet on the wipe with notrtseent of known removebte contaminetton on objects of tese surf ace area le determined, the pertinent levete shou be proportionetty and the

, c y entire surface eres should be wiped.

the evere9* *"d xlaun redletion levels associated with surf ace centaminetton resulting from bete-genene emittore should not exceed k

.$ ... m , ., 1 cm and . ered/hr et 1 cm, respectively, measured through not more then 7 mittigrams per aquere centimeter of totet etwort.r

- I APPENDIX C.

Example Site Status Report i Docket no. License no.

1 Licensee Name:

Site Name:

Site Address:

1 City: State: Zip: l l

l Regional

Contact:

Phone:

Status Summary:

Issue Date: 02/16/95 C-1 2800/026

. - - . . = .

I

.s APPENDIX E INPUT FOR MONTHLY INFORMATION STATUS REPORT (MISR) i STATUS OF SITES IDENTIFIED BY ORNL i

Total Sites Eliminated Sites Pending Sites Contaminated

> 300 5-300 i

Total 1

l 4

STATUS OF LICENSES WITH SEALED SOURCES NOT AC:0VNTED FOR Total Eliminated Pending j l

j > 300 5-300 Total i

1 Issue Date: 02/16/95 0-1 2800/026

_ _