ML20056C310

Forwards Renewed License SNM-1373 & Ser.License Renewed for Term of 5 Yrs

ML20056C310
Person / Time
Site:	07001374
Issue date:	05/11/1993
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Adam Wilson IDAHO STATE UNIV., POCATELLO, ID
References
NUDOCS 9305140247
Download: ML20056C310 (2)

Text

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p r.V 1 1 1093 Docket 70-1374 License SNM-1373 Dr. Albert E. Wilson Professor of Engineering College of Engineerir.g Idaho State University P.O. Box 8060 Pocatello, ID 83209

SUBJECT:

RENEWAL OF LICENSE SNM-1373 License SNM-1373 was renewed on September 10, 1992 for a term of 5 years. The renewed license and Safety Evaluation Report (SER) were transmitted to Idaho State University by letter dated September 10, 1992. A copy of that letter, the license, and the SER are enclosed.

If you have any questions regarding the license, please contact Mr. Tom Wenck at 301-504-2404.

Sincerely, O*inhal signedk Charles W. Emeigh, Acting Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS

Enclosures:

As stated DISTRIBUTION:

Docket No. 70-1374

PDP, NRC File-Center. _ Region IV NMSS r/f FCSS r/f FCLB r/f FCLSI r/f JGreeves ETenEyck LTUenck-A:\\ RENEWAL] *See previous concurrence 0FC FCLB N

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DATE 5/10/93 5/10/93 5/// /93 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY I6M, ~

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I LICENSE CONDITION FOR LEAK TESTING SEALED PLUTONIUM SOURCES-AUGl'ST 1987 A.

Each plutonium source shall be tested for leakage at intervals not_to exceed 6 months.

In the absence of a certificate from a transferer indicating that e test has been made within 6 months prior to the transfer, the sealed source i

shall 'ot be put into use until tested.

l B.

The test shall be capable of detecting the presence of 0.005 microcurie of alpha contamination on the test sample. The test sample shall be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is perwanently or semipermarently mounted or stored.

Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Coenission.

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If the test reveals the presence of 0.005 microcurie or more of removable l

alpha contamination, the licensee shall imediately. withdraw the sealed j

source from use and shall'cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Conmission's regulations. Within 5 days after determining that ary source has leaked, the licensee shall file a report 1

with the Division of Industrial and Medical Nuclear Safety, U.S. Nuclear P.egulatory Comission, Washington,- DC 20555, describing the source, test i

results, extent of contamination, apparent or suspected cause of source failure, and cor'vetive action taken. A copy of the repert shall be sent i

to the Administrater of the nearest NRC Regional Office listed in Appendix D i

of Title 10, Code of Federal Regulations Part 20.

l D.

The periodic leak test required by this conditien does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another 1

person unless they have been leak tested within 6 months prior to the date l

cf use'or trsnsfer.

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September 10, 1992 i

i Docket No. 70-1374-License No. SNM-1373 i

Idaho State University I

ATTN: Dr. V. Charyulu, Dean r

College of Engineering ISU Box 8060 Pocatello, Idaho 83209 i

l Gentlemen:

f Enclosed is Special Nuclear Material License No. SNM-1373, as renewed.

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license is renewed for a 5-year term, expiring Cetober 31, 1997.

We are also enclosing a copy of the safety evaluation report prepared in support of The license renewal.

If you have any questions regarding this licensing action, please contact-Amar Datta (301) 504-2536.

FOR THE NUCLEAR REGULATORY COMMISSION

/S/

John W. N. Hickey, Chi <:f Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS f

Enclosures:

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License No. SNM-1373 2.

Safety Evaluation Report Distribution w/encls.

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Docket No. 70-1374 PDR NRC File Center NMSS R/F IMUF R/F IMSB R/F VLTharpe Region IV-ADatta SG(2)

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pp.eg U.S. NUCLE AR R ECULATORY COMMIS$60N

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g, Pursuant to the Atomic Energy Act of 1954. as amended, the Err.rgy Reorganization Act of 1974 (Public Laiw 93-438). aM Title 10.

g ll Code of Federal Regulations. Chapter I. Pans 30. 31. 32. 33. 34,35, 39,40 aM 70, and in reliance on statements and representations heretofor l

~l made by the licensee, a liceme is hereby issaed authonzing the licensee to receive, acquire, possess, aM transfer byproduct, source, ard special I 1

nuclear matenal designated below; to use such matenal for the purpose (s) and at the place (s) designated below; to deliver or transfer such rr aterial I i

k to persons authorned to receive it in accordance uith the regulations of the applicable Part(s). This license shall be deemed to contain the corditions I y specified in section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations aM orders of the Nuclear

j Regulatory Commasion now or hereafter m effect and to any conditions specified below.

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Idaho State University

3. License number SNM-1373, As renewed i

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4. Expiration date October 31, 1997 g

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g S. Docket or 70-1374 I

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,g i 6 Byproduct source.and/or

7. Chermcal and/or physical B. Maximum amount that hcensee 1

j I-special nuclear matenal form may possess at any one time 1

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Uranium enriched in A.

Clad uranium-A.

1511 grams U-235 t

I the U-235 isotope aluminum fuel plates t

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Uranium enriched in B.

Uranium-aluminum B.

I gram U-235

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Plutonium C.

Encapsulated Pu-Be C.

20 grams Pu t

neutron sources K-I-

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Authorized use:

The materials specified above shall be used in accordance with the

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statements, representations, and conditions specified in the application dated t

g March 13, 1991, and supplements dated June 8. July 1, and July 13, 1992.

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10. Authorized place of use: The materials specified in Conditions 6. A and B above

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shall be used in the Lillibridge Engineering Laboratory at Idaho State University.

l,i The materials specified in Condition 6.C above shall be used in the Lillibridge g

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Engineering Laboratory when the suberitical assembly is in operation and shall be t ;

g stored in a neutron howitzer in a vault in the Physical Science Building basement at t [

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11. The Reactor Safety Committee shall review all new activities and procedures and any I

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12. The Radiation Safety Officer shall be responsible for ensuring periodical performance ;t L

I of instrument calibrations, radiation surveys, and leak tests and reviewing radiation I

exposure records.

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13. The licensee shall comply with the attached " License Condition For Leak Testing

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Sealed Plutonium Sources," August 1987.

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14. Release of equipment or materials for unrestricted use or from contaminated to clean f i

areas onsite shall be in accordance with the attached " Guidelines for Decontamination !g i

of Facilities and Equipment Prior to Rel tsi for Unrestricted Use or Termination of 1

Licenses for Byproduct, Sourc

$ c, ; g Materials," August 1987.

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15. The licensee shall calibrat ach use, unless the instrubph has been c radiation detecti distruments used in connection I

with this license prio g

the 6 months precedin h use.

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16. The licensee shall iciii' emergency procedures; conduet"Eri

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systems; on a per cscheftu,}

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FOR THE NUCLEAR REGULATORY COMMISSION l

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!)g Date:

September 10. 1992 By:

John W. N. Hickey l

Division of Industrial and g

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License Condition for Leak Testing...

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Guidelines for Decontamination...

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t GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT 3

PRIOR TO RELEASE FOR UNRESTRICTED USE i

OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, l

OR SPECIAL NUCLEAR MATERIAL i

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U.S. Nuclear Regulatory Commission

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Division of Industrial and l

Medical Nuclear Safety i

Washington, DC 20555 August 1987

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The instructions in this guide, in conjunction with Table 1 specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior to I

abandonment or release for unrestricted use. The Ifmits in Table 1 do not

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apply to premises, equipment, or scrap containing induced radioactivity for l

which the radiological considerations pertinent to their use may be different.

L The release of such facilities or items from regulatory control is considered on a case-by-case basis.

1.

The licensee shall 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 levels, as detemined 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.

3.

The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are 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.

i 4.

Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such as razing -

of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-tern storage or standby status. Such requests must:.

a.

Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

b.

ProvWe s-detailed health and 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.

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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 Industrial and Medical Nuclear Safety, U. S. Nuclear Regulatory Commission, Washington, DC 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 abandonment.

The survey report shall:

a.

Identify the premises.

b.

Show that reasonable effort has been made to eliminate residual contamination.

e Describe the scope of the survey and general procedures followed.

c.

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State the findings of the survey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

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IAULL 1 ACCLPIABLE SUHFACE CONTAMINATION LEVELS NUCLIDES*

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MAX IMUM** '

REMOVABLLs7rr U-nat, U-235, U-238, and associated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm 2

2 2

Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-231, 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm 2

2 2

Ac-227, I-125, 1-129 Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, 1000dpm/100cm 3000 dpm/100 cm 200 dpm/100 cm 2

2 2

I-131, I-133 Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous 5000 dpm By/100 cm 15,000 dpm Gy/100 cm 1000 dpm By/100 cm 2

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fission) except Sr-90 and others noted above.

• Where 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 As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumenta. tion.

'Heasurements of average contaminant should not be averaged over more than I square meter.

less surface area, the average should be derived for each such object.

For objects of dThe maximum contamination level applies to an area of not more than 100 cm.

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'The amount of removable radioactive material per 100 cm 2 of surface area should be determined by wiping that area with dry filter or sof t absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

'The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad more than 7 milligrams per square ce/hr at ' cm and 1.0 mrad /hr at I cm, respectively, measured through not ntimeter of total absorber.

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o WASHINGTON, D.C. 20885 September 10, 1992 DOCKET N0: 70-1374 LICENSEE:

Idaho State University (ISU)

Pocatello, Idaho

SUBJECT:

SAFETY EVALUATION REPORT, APPLICATION DATED MARCH 13, 1991, RE LICENSE RENEWAL BACKGROUND Idaho State University (ISU) was first issued Special Nuclear Material License No. SNM-1373 in July 1973. The license was subsequently renewed in April 1981 and May 1987. The current license expired on May 30, 1992; however, on March 13, 1991, ISU submitted an application for renewal. Accordingly, the license has remained in effect in accordance with the timely renewal provisions of Subsection 70.33(b) of 10 CFR Part 70.

Scope of Review The safety review of ISU's renewal application includes the application dated March 13, 1991, supplementary information dated June 8, July 1, and July 13, 1992, and the compliance history of the license during the past S years. The topics of review include an evaluation of the licensee radiation safety and nuclear criticality safety programs. The renewal application was discussed with Robert A. Brown, NRC Region IV Inspector.

The following sections contain a description of the licensee organization, safety program, and proposed license conditions developed by the fuel Cycle Safety Branch staff.

Possession Limits The possession limits for special nuclear materials requested by ISU are unchanged from their current license. However, the limit in License Condition

6. A clad uranium-aluminum fuel plates, is increased from 1510 grams U-235 to 1511 grams, because ISU's calculation shows that the total amount now possessed is a fraction of a gram greater.

Thus, the recommended possession limits are as follows:

Material f.9ED Amount A.

Uranium enriched in A.

Clad uranium-A.

1511 grams U-235 the U-235 isotope aluminum fuel plates l

B.

Uranium enriched in B.

Uranium-aluminum 8.

I gram U-235 the U-235 isotope foils and fission counters 4Q.hh h

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Idaho State University 2

C.

Plutonium C.

Encapsulated C.

20 grams Pu Pu-Be neutron sources Activities Authorized use: The materials specified in A, B, and C above shall be used in accordance with the statements, representations, and conditions specified in the application dated March 13, 1991, and in supplements dated June 8, July 1, and July 13, 1992.

i Authorized place of use: The materials specified in A and B shall be used in the Lillibridge Engineering Laboratory at Idaho State University. The materials specified in C shall be used in the Lillibridge Engineering Laboratory when the subcritical assembly is in operation and shall be stored in a neutron howitzer in a vault in the Physical Science Building basement at other times.

Oroanization Operated by the State of Idaho, ISU has its principal office at Pocatello.

Idaho.

The board members and officers are all citizens of the United States.

The Dean of the School of Engineering is responsible for the safe storage and use of the licensed materials. No activities are performed without prior approval of the Dean. A Reactor Safety Comittee has reviewed and approved all plans and procedures for the usage of the materials in the subcritical assembly. The licensee has not, however, comitted to having the comittee review new activities or procedures. Therefore, continuance of the following license condition, which is in the current license, is recomended:

Condition 11: The Reactor Safety Comittee shall review all new t

activities and procedures and any changes to the plans and procedures for the usage of licensed materials prior to implementation.

The Reactor Safety Comittee was formed to review procedures for the ISU AGN-201 reactor, licensed under Reactor License No. R-110. Membership and duties are specified in the reactor license. There are six members of the committee, other than the Reactor Supervisor and the Dean of the School of Engineering, who are ex officio members. The members have education and experience in the various technical disciplines needed to evaluate the safety of the reactor and suberttical assembly operations. The committee meets at least once a year.

The Dean, School of Engineering, the Reactor Supervisor, and the Radiation Safety Officer have direct responsibility for the operation of the subcritical assembly. The application does not specify who is responsible for calibration

Idaho State University 3

of radiation instruments, leak testing sealed sources, reviewing radiation exposure, and conducting radiat10n surveys. However, the Radiation Safety Officer has been assigned these responsibilities under the reactor license.

To ensure performance of these functions under this license, the following condition is recommended:

Condition 12. The Radiation Safety Officer shall be responsible for ensuring periodical performance of instrument calibrations, radiation surveys, and leak tests and reviewing radiation exposure records.

Technical Oualifications The resumes of the individuals in safety positions show that their education and experience are sufficient for the responsibilities they are assigned.

Control of Personnel Exoosure The faculty and students wear gamma, beta, and neutron-sensitive film badges, when in the subcritical assembly room. Visitors are required to wear pocket dosimeters. When operations involving special nuclear materials in the subtritical assembly are in progress, a minimum of two persons are required to be present in the room. Personnel are required to actively pursue the ALARA policy. The principal risk of exposure in such facilities is from gamma and neutron radiation. The data submitted show that radiation at the surface of the subcritical assembly tank is less than 7.5 mr/hr. Considering that personnel are unlikely to be near the surface for long periods of time, the staff considers the risk of overexposure minimal.

Control of Contamination The subcritical assembly consists of 150 clad uranium-aluminum fuel plates that are loaded in various lattice arrangements in a water-filled tank.

Disposable plastic gloves or other hand coverings are used when handling the fuel plates. The uranium-aluminum foils are handled using disposable plastic gloves or tongs, as appropriate.

The Pu-Be neutron sources are handled with tongs or source holders in such a manner that the sources are a minimum of 3 feet away from any person. The materials are handled under the direct supervision of the Reactor Supervisor or the Radiation Safety Officer.

The licensee has committed to leak testing 10 percent of the fuel plates, using the standard smear test for alpha contamination, prior to each experiment and at normal inventories at least twice a year. The foils are tested in conjunction with the fuel plates. A general area contamination survey is performed in conjunction with the fuel plate and foil surveys.

In addition, a monthly contamination survey and general area radiation survey are performed.

Idaho State University 4

In the application, the licensee has not committed to leak testing the sealed Pu-Be neutron sources in the application. Therefore, it is recommended that

'i adherence to the standard leak test condition should continue to be a part of the license. The proposed condition is as follows:

Condition 13. The licensee shall comply with the attached

" License Condition for Leak Testing Sealed Plutonium Sources," August 1987.

The staff also recommends continuance of a condition which specifies criteria for the release of equipment and materials from the restricted areas to unrestricted areas. The condition reads as follows:

Condition 14.

Release of equipment or materials for unrestricted use or from contaminated to clean areas onsite shall be in accordance with the attached, " Guidelines for Decontamination of Facilities and Equipment Prior to i

Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Materials,"

August 1987.

Calibration of Instruments The licensee has an adequate range 'of radiation monitoring and measuring instruments listed in the renewal application, but has not specifically committed to calibrating the instr"ments. Therefore, the staff recommends the following condition:

Condition 15. The licensee shall calibrate all radiation detection instruments used in connection with this license prior to each use, unless the instrument has been calibrated within the 6 months preceding such use.

Trainino The subcritical assembly is used to teach basic concepts to undergraduate and graduate students. The instructions include information on radiation hazards, dose measurements, and laboratory procedures. Experiments are performed under the supervision of the laboratory staff or knowledgeable students who have been approved by the Reactor Safety Committee.

Vaste Discosal Contaminated materials (e.g., gloves and smear papers) are controlled and disposed of by health physics personnel in accordance with Procedure RPR54, Radioactive Waste Management, of the University's Radiation Safety Manual.

The staff finds the procedure adequate.

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Idaho State University 5

Nuclear Criticality Safety Experiments have been conducted with the assembly in a variety of fuel arrangements that show that the assembly remains subcritical with normal water reflectors and moderators. However, the assembly could be made critical through the use of effective reflectors or moderators, such as heavy water, beryllium, and graphite (other than the graphite base of the suberitical assembly). Although these materials are allowed into the laboratory only in very limited quantities, there is a slight chance that the assembly might be made critical accidentally. Therefore, a criticality alarm system is installed and maintained in the laboratory, and the experimenters are instructed in the criticality emergency procedures. The criticality alarm signal is wired to the assembly tank drain valve, so that activation of the alarm automatically drains the moderator. The criticality alarm is tested annually.

In view of the demonstrated subcriticality of the assembly and the controls on unusual moderators-reflectors, this frequency for checking the alarm response is deemed sufficient.

Environmental Protection The licensing of the ISU activities is in accordance with 10 CFR Section 51.22(c)(14)(v), and therefore, neither an Environmental Assessment nor an Environmental Impact Statement is warranted for this action.

Emeroency Plannino The licensee maintains a criticality sensor above the assembly and has emergency procedures covering an accidental criticality.

In the supplementary information dated June 8,1992, the licensee states that ti.a emergency equipment is verified to be operational on a monthly basis. The communication and alarm systems, however, were last tested in April 1990. The staff feels that all emergency equipment should be tested at least annually. The staff, therefore, recommends the following license condition to correct the deficiency:

Condition 16. The licensee shall review emergency procedures; conduct drills; and maintain, inspect, and test all emergency equipment, including the communication and alarm systems; on a periodic schedule consistent with good industry practice, but at least once a year.

Comoliance History The licensee's inspection and enforcement record since the last renewal was reviewed and discussed with Robert A. Brown, Region IV Inspector. There has been one inspection during this period, and no violations were reported. Mr.

Brown has no objection to the issuance of the renewed license.

Idaho State University 6

September 10, 1992

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i CONCLUSION AND RECOMMENDATION Upon completion of the safety review of the licensee's application and supplements, the staff concludes that the licensee has the necessary technical staff to administer an effective radiological safety program. Compliance with their own proposed conditions and with those developed by the staff should ensure safe operation of the facility. Therefore, it is recommended that the license be renewed for a 5-year period in accordance with the application and supplements and subject to the recommended conditions.

/S/

Amar Datta Uranium Fuel Section fuel Cycle Safety Branch 4

Division of Industrial and Medical Nuclear Safety, NMSS i

Approved by:

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Michael Tokar, Section Leader i

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