ML20238F205

Matls Licensing Package for Amend 19 to License SNM-356 for Princeton Univ,Environ Health & Safety.Control:125403

ML20238F205
Person / Time
Site:	07000391
Issue date:	03/09/1998
From:	Elizabeth Ullrich NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
References
125403, NUDOCS 9809030186
Download: ML20238F205 (17)

Text

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I 4 NRC FORM 374

• U.s. NUCLEAR REGULATORY Commission Amendment No.19 MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization'Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations h:retofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or trar,sfer such material to persons authorized to receive it in accordance with the regulations of the apphcable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified bIlow.

Ucensee in accordance with the letter dated January 29,1998,

1. Princeton University 3. Ucense number SNM-356 is amended in Environmental Health and Safety its entirety to read as follows:

2. 262 Alexander Street 4. Expiration date December 31,2005 Princeton, New Jersey 08544 5. Docket No. 070-00391 Reference No.

6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material '

possess at any one time under 'his license i ...

A. Plutonium 239 A.$ Encapsulated as Pu-Be A. 97.6 grams neutron sources .

B. Plutonium 239 B. Plated alpha sources

. B. 0.016 grams

9. Authorized use:

A. and B.- For use in educational. demonstrations',' laboratory experim nts, and instrument calibration.

CONDITIONS

10. Licensed material shall be used only at Princeton University, Main Campus, Princeton, New Jersey and James Forrestal Campus, Plainsboro, New Jersey.

11. A. Licensed material shall be used by, or under the supervision of, individuals designated in writing by the Radiation Safety Committee, Malcolm S. Steinberg, Chairperson.

B. The Radiation Safety Officer for this license is Robert R. Milwicz.

12. Licensed material shall not be used in or on human beings.

13. The licensee shall not use licensed material in field applications where activity is released except a I provided otherwise by specific condition of this license.

9eo9030186 980'309 O I PDR ADOCK 070003 1

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OFFICIAL RECORD COPY ML10 l

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NRC FORM 374A

• W.s. NUCLEAR REGULATORY Commission PAGE 2 of 3 PAGEs License Number SNM-356 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070-00391 Amendment No.19 1

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14. A. Sealed sources and detector cells containing licensed material shall be tested for leakage and/or t contamination at intervals not to exceed six months or at such other intervals as are specified by the certificate of registration referred to in 10 CFR 32.210, not to exceed three years.

B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles shall I be tested for leakage and/or contamination at intervals not to exceed three months. )

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C. In the absence of a certificate from a transferor inchica't'ing that a leak test has been made within six months prior to the transfer, a sealed source or detector cell received from another person shall not be put into use until testedt.

D. Each sealed source fabri$ated by the licensee shall be inspected and tested for construction defects, leakage, and contamination prior to any use or transfer as a sealed s'ource.

Is a ,* , . r-E. Sealed sources and. detector' cells need not be leak tested if: ,

(I) they containfonly hydrogen-3; or J l t , , y (ii) they contain 'o'nly a radioactive gain; or : . ,

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(iii) the half-life of the isotope is 30 days or less; or 4j _

w y (iv) they contain no more t6n 100 m rocuries of be'td nblor gamma emitting material or not more than 10 microcuries,of alpha emitting material; or$

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(v) they are not designed to emit alpha particles, are in storahe, and are not being used. However, when they are removed from storage for use or transfer to another person, and have not been  ;

tested within the required leak test interval, they shall be tested before use or transfer. No l sealed source or detector cell shall be stored for a period of more than 10 years without being j tested for leakage and/or contamination.

i F. The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, '

a report shall be filed with the U.S. Nuclear Regulatory Commission and the source or detector cell I shall be removed immediately from service and decontaminated, repaired, or disposed of in l- accordance with Commission regulations. The report shall be filed within five days of the date the leak test result is known with the U.S. Nuclear Regulatory Commission, Region I, ATTN: Director, Division of Nuclear Materials Safety,475 Allendale Road, King of Prussia, Pennsylvania 19406. The report shall specify the source or detector cell involved, the test results, and corrective action taken.

I G. The licensee is authorized to collect leak test samples for analysis by the licensee. Alternatively, tests for leakage and/or contamination may be performed by persons specifically licenced by the Commission or an Agreement State to perform such services.

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I NRC FORM 374A .

W.s. NUCLEAR REGULATORY Commission PAGE 3 of 3 PAGEs License Number SNM-356 MATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SHEET 070-00391 Amendment No.19

15. Sealed sources or detector cells containing licensed material shall not be opened or sources removed from source holders or detector cells by the licensee.

16. The licensee shall conduct a physical inventory every six months, or at other interval approved by NRC, to account for all sealed sources and/or devices received and possessed under the license.

17. The licensee may transport licensed material in accordance with the provisions of 10 CFR 71," Packaging and Transportation of Radioactive Material.", # 1 "1 .

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18. Except as specifically provided otherwise in this license, the licensee shall conduct its program in accordance with the statements, representations, and procedures contained in the documents, including any enclosures, listed below. The Nuclear Regulatory Commission's regulations shall govern unless the

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statements, representations, and procedures in the licensee's application and correspondence are more restrictive than the regulations. 4 A. Application dated October 26,1995 ', O B. Letter dated December 1,19953 3l -

C. Letters dated January 29,1998 and March 5,;1998 describing the Decom'missioning Plan for Palmer Hall, Room 106 . '

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For the U.S. Nuclear Regulatory Commission

! Originalsigned by Elizabeth Ullrich Data March 4 1998 By l

Elizabeth Ullrich Nuc' ear Materials Safety Branch 2 Division of Nuclear Materials Safety Region i King of Prussia, Pennsylvania 19406 u.

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I March 9,1998 l Docket Nos. 030-00882 License Nos. 29-05185-24 040-05259 SUD-381 i 070-00391 SNM-356

! Control Nos. 125402.

~L 125404

.125403 Garth G.. Walters General Manager

- Occupational Health and Safety -

-l, Princeton University

! 262 Alexander Street Princeton, NJ 08544

Dear Mr. Walters:

This refers to your license amendment requests. Enclosed with this letter is the amended license.

The " Decommissioning Plan" described in your letters dated January 29 and March 5,1998 for the decommissioning of Room 106 of Palmer Hall is approved. We request that you inform us of the decommissioning schedule so that we may perform inspection of decommissioning activities and confirmatory surveys as necessary. Your licenses have been amended to include the Decommissioning Plan.

No amendment of your licenses is required in order for you to dispose of licensed material to an authorized waste broker, as was requested in your letter dated February 3,1998. The regulations in 10 CFR 20.2001(a)(1) allow disposal of licensed material by transfer of waste material to an authorized recipient. The specification of a waste broker in the license s application confirmed that you had procedures in place for waste disposal and was not intended to further restrict transfer of waste. Additional regulations pertaining to waste disposal are  ;

contained in Subpart K of 10 CFR Part 20.'

Your application should have been signed by a management representative, rather than the Radiation Safety Officer or the Assistant Health Physicist, indicating that management has reviewed the application and concurs in the statements and representations contained therein.

Note also that a management representative should sign all future correspondence that requests a change in yourlicense.

OFFICIALRECORDCOPY ML 10 m

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O O G. Walters 2 3

Occupational Health and Safety Please review the enclosed documents carefully and be sure that you understand and fully implement all the conditions incorporated into the amended licenses. If there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region l Office, Licensing Assistance Team, (610) 337-5093 or 5239, so that we can provide appropriate corrections and answers.

Thank you for your cooperation.

Sincerely, OriginalsignedbyJohn D. Kinneman John D. Kinneman, Chief Nuclear Materials Safety Branch 2

Division of Nuclear Materials Safety

Enclosures:

1. Amendment No. 59, License No. 29-05185-24

2. Amendment No. 20, License No. SUD-381

3. Amendment No. 19, License No. SNM-356

4. "Information That Should Be Submitted to the NRC for Decommissioning and --

Termination of Licensed Facilities" cc:

Robert Milwicz, Radiation Safety Officer ~

Sue M. Dupre', Assistant Health Physicist

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G. Walters 3 i Occupational Health and Safety l

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I DOCUMENT NAME: G:ONMSDOCWORK\LICLTR\L2905185.24 10877714 To receive e copy of this document,ind6cete in the box: "C' = Copy w/o attach /enci *E' = Copy w/ sttach/enci *N' = No copy OFFICE DNMFSI) lN Df/WS/RJ. , lM l l NAME EUllrid W M man 03/ /98 DATE 03/09/#8 63#098 03/ /98

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OFFICIAL RECORD COPY ML 10 l

D\ R Prm.ceton Un.iversity U

. Environm:ntal Health and Saf;ty March 5,1998 Q-5 Ms. Elizabeth Ullrich Nuclear Materials Safety, Branch B Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 RE: License Numbers: 29-05185-24, SNM-356, SUD-381 Control Number: 125402

Dear Ms. Ullrich:

In your phone call of March 4,1998, you requested additional information regarding the decommissioning plan that Princeton University submitted for work to be performed in Room 106 of Palmer Hall. This letter provides the information you requested concerning the following topics:

Waste Generation: the decommissioning work is expected to generate one to two 55-gallon drums of dry waste, containing no more than 1 Ci total of Cs-137. ,

i Training: the decommissioning work will be performed by a health physicist and a health physics technician supplied by Teledyne Brown Engineering - Environmental Services (TBE-ES). Princeton University has reviewed resumes containing the qualifications of TBE-ES personnel. In addition, we expect that these qualifications and a description of the TBE-ES l training program have been provided to the NRC in documentation submitted by TBE-ES in support of the company's application for NRC license # 29-00055-06 ALARA Program: all aspects of the decommissioning work, including worker doses, doses to ,

members of the general public and effluent releases, will be performed under Princeton l University's current ALARA guidelines. The scope of the work is such that no decommissioning worker or any member of the public is likely to receive a dose exceeding 10% I of the dose limits specified in 10CFR20. l l

Quality Assurance Program: TBE-ES is carrying out the decommissioning project under the oversight of the Princeton University radiation safety staff. Throughout the course of the work, the University will utilize on-site audits and recordkeeping audits to verify that TBE-ES is implementing the decommissioning plan as provided to the NRC. Such audits will include verification that TBE-ES is using appropriate and calibrated instrumentation and is instituting all 262 Alexander Street Telephone 609 258-5294 Princeton, NJ 08544 Facsimile 609 258-1804 /7g tyg g E-Mail chs@ princeton.edu Homepage http://www. princeton.edu/~chs 1

I0 M 0FFICIALRECORDCOPY Mt 10 1%X REr0 MAR - 5 1998

I o" Princeton Upiversity, March 5,1998, Page 2 necessary radiation protection' control measures and will include post-decommissioning measurements to verify that decommissioning has been satisfactorily accomplished.

We appreciate your prompt action regarding this plan. Please contact me at (609) 258-5294 if you have any questions concerning this letter.

Very truly yours,

&fl ,md Sue M. Dupre -

j Assistant Health Physicist SMD/smd Enclosure as per text l

c: Laurel Harvey Robert Milwicz, Radiation Safety Officer Robert Ortego Garth Walters

Joel Antkowiak, Teledyne Brown Engineering i Files 9.5a, Palmer Hall (1) l

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l TELEPHONE CONVERSATION RECORD

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Licensee Name: Princeton University Date: 3/4/98 Time: 9:00 AM License No.: 29-05185-24 Docket No.: 030-00882 Control No.:125402, SUD-381, SNM-356 040-05259,070-00391 125403,125404 Licenseo

Contact:

Sue Dupre, Ass't Telephone No: 609-258-5294 Health Physicist NRC

Contact:

Betsy Ullrich Telephone No: 610-337-5040 i l

Subject:

telephone deficiency - Palmer Hall Room 106 decommissioning Summary: I discussed current decommissioning guidance with Sue Dupre, and informed her of the possibility that a Federal Register Notice might be required. I told her that I do not know if there is a required period of time that activities would be prohibited for response to the Federal Register Notice. She asked to be informed ASAP, because they have tentatively )

set the date of March 16 with Teledyne. This is during spring break, and the area is much quieter and less crowded with most students and faculty gone during that time.

I asked Sue Dupre to respond in writing to four issues:

1. Provide the total amount of waste expected to be generated, estimate the total activity involved, and the total dose to workers and public from the decommissioning.

She stated that they expect one, maybe two,55-gallon-drums of waste to be generated, containing less than 1 microcurie total Cs-137. The worker and public doses are expected to be less than 10% of allowable limits. '

2. Provide a description of the training program for the decommissioning workers. In this case, a contractor is providing the workers, who may have training for the decommissioning activities under the contractor license; if so, I asked her to provide the license number of the contractor. Princeton does also have a training program in l l

its license commitments. , j

3. Provide an ALARA commitment for the decommissioning activities; again, Princeton i has an ALARA program, and she intends to reference that.

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4. Provide a statement regarding a QA program for the decommissioning activities, or the basis for not needing a QA program. We discussed what kinds of activities might fall under a QA program, and she felt that she could respond to this question.

I also discussed with her that no amendment is required in order for Princeton to change waste brokers. however, an amendment will be issued for the approval of the decommissioning plan.

Action Required /Taken: Milestone 15 for licensing actions. Wait for response. Determine if Federal Register Notice is needed.

Signature: / 7 Date: March 4,1998 Betsy U ri 0FFICIAl.RECORDCOPY ML 10

O O Princ'eton Dniversity Environmental Health and Safety b ,.

February 3,1998 Mr. John Kinneman  !

Nuclear Materials Safety, Branch B Division of Nuclear Materials Safety ]

- U.S. Nuclear Regulatory Commission

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475 Allendale Road j King of Prussia, PA 19406 1 l

RE: License Numbers: SNM-356 Docket Number: 070-00391

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Dear Mr. Kinneman:

I am writing to request an amendment to Princeton University's special nuclear j

materials license #SNM-356 to permit the use of various radioactive waste  ;

disposal brokers. In our most recent license application, dated October 26,1995, we specified in Item 11 of the application that waste disposal services for Princeton University are provided by one broker, Teledyne Brown Engineering. j i

However, we would like to invite other waste disposal brokerage companies to I provide bids for our waste disposal needs and to allow ourselves the flexibility to )

choose between several brokers, depending on the ability to provide service, the quality of the service, and the cost of the service. We are requesting permission to use any reputable NRC- and/or Agreement State-licensed radioactive waste disposal broker with the ability to provide the safe, regulatorily-compliant and competent services we need.

Your prompt consideration of this request is greatly appreciated. If you have any questions concerning this letter, please contact me at (609) 258-5294.

Sincerely, j

Sue M. Dupre Assistant Health Physicist SMD/smd

- C: Laurel Harvey Robert Milwicz, Radiation Safety Officer j Prof. Malcolm Steinberg i

Garth Walters Files 4.A.1, 9.2 y 262 Alexander Street Telephone 609 258-5294 Princeton, NJ 08544 Facsimile 609-258-1804 E. Mail chs@ princeton.edu Homepage http://www. princeton.edu/~ehs

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Princ~cton Univ:rsity Environmental Health and Safety

.- January 29,1998 Mr. John Kinneman Nuclear Materials Safety, Branch B >

Division of Nuclear Materials Safety g70 ' g3T/

U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 RE: License Numbers: 29-05185-24, SNM-356, SUD-381

Dear Mr. Kirmeman:

In a letter dated October 7,1997, I informed you that Princeton University had decided to cease principal activities involving licensed radioactive material in Palmer Hall and that decommissioning work which would require the submission of a decommissioning plan in accordance with 10CFR30.36(g)(1) would be performed in Room 106 of Palmer Hall. With this letter I am submitting to you a copy of the decommissioning plan for NRC review and approval. 'Ihe Princeton University Radiation Safety Committee has given the plan its approval.

The decommissioning work in Room 106 is being performed in two phases. The first phase involved the completion of work that did not require the submission of a decommissioning plan. For example, the characterization survey had found that casework and other readily removable components in the room contained fixed low levels of contamination. Removal and disposal of these components involved procedures normally applied during cleanup and renovation oflaboratories and did not otherwise meet the conditions of 10CFR30.36(g)(1). Consequently, a decommissioning plan was not required for the first phase of the work. The first phase has been completed. The second phase involves the jackhammering of contaminated areas of the floor, which is a procedure not routinely applied during cleanup or maintenance operations, and consequently, a decommissioning plan must be submitted.

As the plan explains, the project involves very limited decommissioning work with few radiation protection issues. We hope to schedule Teledyne Brown Engineering - Environmental Services to perform the decommissioning work in mid-March and would appreciate your prompt review of this plan.

Please contact me at (609) 258-5294 if you have any questions concerning this letter and the enclosed plan.  !

Sue M. Dupre i Assistant Health Physicist 1 SMD/smd i

Enclosure as per text j c: Laurel Harvey l Robert Milwicz, Radiation Safety Officer j Robert Ortego  ;

Garth Walters  !

Joel Antkowiak, Teledyne Brown Engineering l Files 9.Sa, Palmer Hall (1) 125403 '

l 262 Alexander Street Telephone 609 258-5294 ~

l Princeton, NJ 08544 Facsimile 609 258-1804 E Mail chs@ princeton.edu http://www princeton.edu/~ehs 0FFmEMDCOW < H mepage i ML 10 l

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Decommissioning Plan Site Location:

Room 106, Palmer Hall, at Princeton University, Washington Road, Princeton, NJ Site Description and Conditions:

Room 106 was formerly a nuclear chemistry laboratory located in Palmer Hall. Palmer Hall is being converted to a campus student center, and all principal activities involving licensed radioactive materials have ceased. Teledyne Brown Engineering - Environmental Services (TBE-ES) was contracted to conduct a characterization survey within Room 106.

A diagram of Room 106 is attached as Appendix A. Room 106 is located in the partially-below-grade basement floor of Palmer Hall and is bounded by a little-used storage area and restroom on two sides, by a hallway, and by an exterior wall. Room dimensions are approximately 16 feet by 22 feet. Prior to any decommissioning activities, the room contained two fume hoods, two lab benches with sinks and an angle iron vault sunk into an 8 foot deep concrete pit in the floor. TBE-ES's characterization survey indicated the presence of relatively minor fixed contamination of the bench tops, the fume hoods, the angle iron frame of the vault, the floor and the vault pit at levels sufficient to require removal before the room could be released for unrestricted use. The contaminant has been identified as Cs-137.

Since the submission of a decommissioning plan was not required for the simple routine removal and disposal of the contaminated bench tops, the frame of the vault, and the fume hoods and associated ductwork, TBE-ES proceeded to prepare Room 106 for renovation by taking out and disposing of these easily removable contaminated components. With the completion of this first phase of the renovation work, contamination of the room is now confined to portions of the floor and to the floor and front wall of the vault pit. Appendix B is a diagram of Room 106 showing the location and levels of contamination currently present. This decommissioning plan is being submitted to cover the non-routine activities involved in decontaminating the floor and the vault pit.

Planned Decommissioning Activities:

TBE-ES will perform the remaining decommissioning work. The work performed by TBE-ES will be performed by a Health Physics Supervisor with extensive decommissioning experience and by an experienced Senior Radiological Technician.

The contamination is fixed in the concrete of the floor, and its removal will require removal of the contaminated concrete. TBE-ES plans to jackhammer the contaminated concrete to an initial depth of 1 to 2 inches, remove the debris, resurvey, and continue the process again as needed. Debris and waste generated during this process will be disposed of as radioactive waste. TBE-ES expects to complete the work, including the final survey, within two i

working days.

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Decommissioning Pl:n 2

. . Princeton University (Palmer 106)

TBE-ES will be required to notify the University Radiation Safety Officer (RSO) in the Environmental Health & Safety Office if any significant deviation from the proposed plan of work described in this Plan becomes necessary. The RSO will review the proposed deviation, and work will not proceed until the RSO has approved the deviation. l Radiation Protection Methods:

This final phase of the decommissioning of Room 106 presents few and easily-controlled radiation protection problems due to the low levels of contamination present. In order to avoid the spread of dust and debris generated from decontamination of the floor and vault pit, TBE-ES will seal the room, including a". openings such as spaces around doors, with duct tape and plastic. To locally control the spread of dust and debris, a HEPA vacuum hose will r':m+ve debris and dust at the point where the jackhammer meets the floor. Personal protective clothing worn by TBE-ES employees will include Tyvek suits and respirators.

Normal contamination control measures will be taken, including careful surveys of TBE-ES personnel before they leave the room. The hallway outside '.he room will be surveyed after the decontamination is completed to ensure that dust and debris were not spread outside the room. Contamin.ited filters and protective clothing will be disposed of as radioactive waste.

Radiatim anonitoring is not required for this project due to the relatively minor levels of contamination presert.

During the decontamination, Room 106 will be kept locked at all times, and access to the room will be limited to TBE-ES personnel and Princeton University Health Physics staff.  ;

All personnel who enter Room 106 will wear protective clothing appropriate to the ongoing l activities. No one excep' TBE-ES staff will be allowed in Room 106 while jackhammenng and othe. Just-generating activities are occurring.

Planned Final Radiation Survey

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TBE-ES will conduct the final radiation survey using measurement and sampling techniques based in part on the guidance provided in the draft document NUREG/CR-5849, " Manual for Conducting Radiological Surveys in Support of License Termination." TBE-ES will use Eberline Model PAC-4G-3 gas flow proportional detectors with thin mylar windows (0.85 '

mg/cm 2) to perform direct measurements for alpha, beta and gamma radiation (although the contaminant found during the preliminary characterization survey has been identified as Cs-137, a variety of radioisotopes was used in the room during its past.). TBE-ES expects to survey over 95% of the surfaces in the room with the Eberline meters. Smear samples will be taken at the rate of one sample per m2 and will be counted on a Packard Model Tri-Carb 1900 liquid scintillation counter or on an equivalent counter. The final survey will also include the exterior hallway, ten feet to either ride of the door to Room 105.

The following table, excerpted from the Nuclear Regulatory Commission's publication

" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear l Material," describes the release limits for any remaining contamination. Efforts will be

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Decommissioning Plan V U 3 Princeton University (P:Imer 106) made to reduce contamination levels to as far below these release limits as reasonably achievable.

Acceptable Surface Contamination Levels Nuclides Average Maximum Removable Some p-y emitters, 5000 dpm/109 cm' 15,000 dpm/100cm2 1000 dpm/100 cm2 including Cs-137 i

Decommissioning Cost Estimate:

TBE-ES's cost estimate for the decommissioning work in Room 106, which included the characterization survey, the removal and disposal of the easily removable contaminated components, the decontamination of the floor and vault pit, the disposal of all wastes generated during the project and the final survey, is $72,119. The University maintains a letter of credit in the amount of 2.25 million dollars for the decommissioning funding plan associated with its broad byproduct materials license. Adequate funds exist to ensure  ;

completion of the decommissioning of Room 106.

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W prWNE Appsndix A BROWN ENGINEERING Environmental Services Room 106: Main View (Original layout prior to 12/15/97)

Room dimensions are approximately 16 ft x 22 ft.

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W TELEDYNE Appendix B BROWN ENGINEERING MmW Sees 1 Room 106: Main View (Room layout after 12/15/97 showing floor contamination levels)

Count rates shown were measured by TBE-ES using Eberline PAC 4G survey meters. No contamination was found outside of crosshatched areas.

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Detecprefficiencyisapproximately65%forCs-137;Detectoractiveareais 50 cm l

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