ML20210L568
| ML20210L568 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 07/30/1999 |
| From: | Emeigh C NRC |
| To: | |
| Shared Package | |
| ML20210L553 | List: |
| References | |
| NUDOCS 9908090169 | |
| Download: ML20210L568 (7) | |
Text
r V ua
, yo ~4- UNITED STATES 1 8 NUCLEAR REGULATORY COMMISSION l f WASHINGTON, D.C. 20666 4 001 L %,..
/ July 30,1999 l
l
. -DOCKET NO: 152 LICENSEE: Purdue University l West Lafayette, IN
SUBJECT:
SAFETY EVALUATION REPORT: APPLICATION DATED MAY 4,1999, LICENSE RENEWAL i 1
l INTRODUCTION :
1 A. General Purdue University uses special nuclear material (SNM) under U.S. Nuclear Regulatory ,
Commission (NRC) Materials License SNM-142, for research and educational purposes in the i areas of nuclear science and engineering.
B. _ License History Purdue University was first issued License SNM-142 in December 1957. The license was last renewed in January 1994. The current license was scheduled to expire on January 31,1999.
However, because the licensee submitted a renewal application by letter dated December 29, 1998, which met the timely renewal provision of 10 CFR 70.38(a), the license has remained in effect pending NRC review of the renewal application. On March 12,1999, NRC staff sent <
request for additional information (RAl) letter to the licensee. By letter dated May 4,1990, Purdue University responded to NRC's RAI letter by submitting a revised renewal applicatho. ;
The revised submittal replaced the previous renewal application in its entirety.
ll - POSSESSION LIMITS i
Purdue University has requested authorization to possess, use, and/or store the following l materials:
1 Material Form Amount A. Uranium enriched in A. SPERT fuel rods, A.* 81,000 grams the U-235 isotope enriched s 4.8 w/o U-235 ;
B. Uranium enriched in B. Fuel rods, B .* 32,000 grams the U-235 isotope enriched s 1.3 w/o U-235 j C. Uranium enriched in C. Solid helices, C. 200 grams the U-235 isotope enriched s 20 w/o U-235
L
l I
e D. Uranium enriched in D. Solid discs, D. 10 grams the U-235 isotope enriched s 3 w/o U-235 E. Uranium enriched in E. Samples, E. 10 grams the U-235 isotope enriched s 20 w/o U-235 F. Plutonium F. Encapsulated PuBe F. 80 grams i neutron sources )
l G. Natural Uranium G. UO2 pellets clad in G.* 11,760 kilo- )
aluminum grams U H. Natural Uranium H. Samples, any form H. 10,000 grams U
l
- l. Californium 1. 10 doubly 1.
- 0.002 grams l encapsulated sources l
J. Uranium 233 J. Calibration sources J. 0.1 pCi l K. Neptunium 237 K. Calibration sources K. 100 pCi L Plutonium 239 L. Calibration sources L. 100 pCl M. Curium 244 M. Calibration sources M. 100 pCi
- For Storage Only ill ACTIVITIES In the renewal application, the licensee described the proposed activities that will be conducted under this license and the locations where the licensed material will be used and/or stored.
The SPERT fuel rods, fuel rods, UO2 pellets, and californium sources listed undet A,3, G, and I are for storage only. The U-235 enriched solid helices and discs listed under C and D are used to measure the effects of rare earths on the thermal properties of UO2 and to measure the effects of elevated temperatures on the mechanical properties of UO2 . Both enriched and natural uranium samples listed under E and H are used for non-destructive testing. The P;Be sources listed under F are used in activation analysis studies, instrument calibrations, ';nd other neutron studies. Items J through M are used as calibration sources.
The material will be used and/or stored in two locations on the Purdue University Campus.
These locations are the Electrical Engineering Building (Duncan Annex) and the Physics Building Fast Breeder Blanket Facility (FBBF) Laboratory.
l l
i i
p
.- . l l
l
~
l
. The NRC staff has determined that the proposed activities are consistent with the research and development activities specified in the Atomic Energy Act and are in accordance with 10 CFR l 70.23(a)(1). To authorize these activities and place of use and/or storage, the staff l recommends the following license conditions:
Authorized use: For use in accordance with the statements, representations, and conditions specified in the license application dated May 4,1999. ;
1 Authorized place of use: The licensee's existing Purdue University Campus at West Lafayette, indiana.
The SPERT fuel rods, fuel rods, californium sources, and natural uranium pellets were material used in the operations of the subcritical FBBF. These operations have been suspended and I this material will be stored in place at its present location until further notide. This material is authorized for possession and storage only. Notwithstanding Sections 6.0(c) and 9.1(b), the licensee is required to have NRC approval by license amendment before using (e.g., moving) the material. After both NRC and Department of Energy (DOE) approval, it is expected that the material will be returned to DOE. Therefore, to ensure that NRC approvalis required before i use of the material, the NRC staff recommends the following license condition l
Notwithstanding Sections 6.0(c) and 9.1(b) of the application dated May 4,1999, the licensee is required to have NRC approval by license amendment before using (e.g.,
moving) the SPERT fuel rods, fuel rods, califomium sources, or natural uranium pellets.
IV PERFORMANCE HISTORY ,
Since the license was last renewed in 1994, the Region lll Office performed two safety inspections. The inspections were conducted on July 11 15,1994, and December 15-19,1996.
No violations were observed during eitherinspection. i I
V ORGANIZATION AND ADMINISTRATION ,
I The licensee has established a Radiological Control Committee (RCC) which is composed of the Chairman and representatives from departments whose expertise may be of value to the RCC. The Radiation Safety Officer (RSO) and a Health Physicist serve as ex officio RCC members. The RCC meets at least quarterly. The duties and responsibilities of the RCC include the following:
- Establish policy and safety standards in radiological safety for all university programs.
Review and approve the university procedures involving SNM.
Review and grant permission for the use of radioactive material or radiation-producing devices at the university.
- Review the university annual audit findings and make recommendations to the radiation safety staff for action.
V L
The RSO has the responsibility for the administratiori of the radiation safety staff, with the overall responsibility of managing the radiation safety program, providing training and j L recommendations to individuals who use radioactive material, and acting as the agent of the i
RCC,' to ensure that use of radioactive material is consistent with recommendations and requirements of the RCC.
- The renewal application specifies the minimum education and experience requirements for the i principal members of the radiation safety staff. . The NRC staff has determined that the L licensee's proposed qualifications and experience are acceptable.
Th'e renewal application demonstrates that there is adequate technical staff with appropriate' qualifications and experience to administer an effective safety program. j i
' The following sections contain a description of the licensee's safety program, along with j
additional conditions developed by NRC staff; j
. VI - RADIATION PROTECTION A. Training Program - d Radiation safety training is required for all new employees and/or students. The training instruction is provided by the RSO or a qualified Health Physicist. At the conclusion of the !
- training, each individual will be tested on radiation safety principles covered in the training. The licensee proposed to use the Annual Reactor Emergency Drill in place of refresher training.
The NRC staff has determined that the licensee's proposal is not acceptable. Accordingly, the staff recommends the following license condition:
Notwithstanding Section 8.5 of the application dated May 4,1999, refresher training that ,
covers radiation safety procedures shall be conducted on an annual basis (maximum l interval 15 months) for all employees and students who use licensed material.
B. Personnel Exposure Control All personnel monitoring for exposure to radiation will be performed in accordance with 10 CFR
-20.1502.- At Purdue University, film badge dosimeters are used and processed monthly for 4 dose reading and personnel exposure records are routinely reviewed. If an individual's monthly dose exceeds 100 millirem (i.e.,2% of the regulatory limit), the RSO will take appropriate action. .
There is no formal bioassey program. Air sample results collected from the Physics Building have historically shown no radioactivity attributable to licensed activity. However, the RSO has
. the authority to require a bioassay program if necessary. l C.- Contamination' Control A radiological surface contamination survey of the work areas are conducted monthly, not to exceed 6 weeks. When contamination levels exceed specified levels, decontamination efforts will be promptly initiated. Protective clothing is used whenever the possibility of contamination
. . exists. Hands, feet, and clothing are monitored whenever the potential for personnel contamination exist. The licensee has committed to the following: if personnel clothing or skin contamination levels are above background, personnel shall not exit an area without approval from the RSO. Because the licensee did not define criteria for releasing contaminated equipment or packages from a restricted area to an unrestricted area, the NRC staff recommends the following license condition:
Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" dated April 1993.
The licensee has established a leak test program for plutonium sources that is comparable to l the standard leak test condition developed by NRC staff. Therefore, the leak test program is acceptable.
D. . Calibration of Instruments The licensee uses a variety of radiation survey instruments. They are calibrated annually.
E. Waste Manaaement There is little waste generated as a result of the licensed activities. This is usually in the form of dry solid waste such as gloves and paper. This solid waste will be transferred to a licensed ;
waste disposal facilitv.
Vil NUCLt:AR CRITICALITY SAFETY A. Duncan Annex Storaae Facility (Rooms B77A and B84)
SNM is stored in rooms B77A and B84 of the Duncan Annex, which is constructed of a steel frame with concrete and brick and no window openings. Some SPERT fuel rods (4.8 weight percent enriched UO2 ) are stored in room B77A and all the fuel rods (1.3 weight percent enriched UO2) are stored in room B84. The rest of the SPERT fuel rods are stored in the Physics Building.
In room B77A, the SPERT fuel rods are stored in two metal racks designed to hold the rods vertically in a safe slab geometry. The racks are fastened to the opposite walls of the room and are separated by 1.98 meters. The licensee imposes an 8.7 cm slab thickness limit on each rack. Tids limit is below the subcritical limit from ANSl/ANS-8.1-1983 for 4.8% oxide fuel (Figure 3h which is approximately 10.0 cm.
l In room B84, the fuel rods are stored in six steel cabinets arranged in two adjacent arrays of ;
three cabinets each. The cabinets are designed to hold the rods vertically in a safe slab geometry and are fastened to the walls of the room. The licensee imposes a 14.0 cm slab thickness limit on each array. This limit is below the subcritical limit from ANSI /ANS-8.1-1983 for 1.3% oxide fuel (Figure 3), which is approximately 28.0 cm.
r:
B. Physics Buildina Fast Breeder Blanket Facility Laboratory (Room B28)
The SPERT fuel (4.8 weight percent enriched UO2) that is not in the Duncan Annex is stored in two stainless steel converters that are welded shut and located in the Physics Building in the FBBF Laboratory (Room 828). Room B28 contains the FBBF and an area surrounded by a wire mesh cage.
One converter with SPERT fuel is in the FBBF. Two independent sets of calculations regarding the reactivity of the FBBF have been performed and been reviewed by the staff (see NRC l Safety Evaluation Report issued December 17,1976). The calculations include a conservative ;
uncertainty estimation. Under normal operating conditions (i.e., water is not present), including i i
current storage conditions, the calculated k-eff is approximately 0.43. Under credible abnormal conditions (i.e., water flooding of the room), the calculated k-eff is approximately 0.74.
The second converter with SPERT fuel is in the wire mesh cage. This second converter had been operated in the FBBF under the same k-eff restrictions as described above. This second converter has been removed from the FBBF and split into two assemblies that are welded shut. 1 The k-eff of the second converter outside the FBBF in two assemblies is less than the k-eff of the converterin the FBBF.
The licensee has installed remote area monitors in the FBBF Laboratory (Room B28). These monitors are intended to serve as a Criticality Accident Alarm System that meets the requirements of 10 CFR 70.24 and ANSI /ANS-8.3-1997.
C. Exemotions The area monitors in the FBBF Laboratory (Room B28) meet the requirements of 10 CFR 70.24; however, the licensee has requested, pursuant to 10 CFR 70.24(a), an exemption from the provisions of 10 CFR 70.24(a)(1) for special nuclear material stored in the Duncan Annex (Rooms B77A and B84). The SPERT fuel rods and fuel rods are only authorized for storage, are being stored in safe slab geometry, and an inadvertent nuclear criticality is not possible.
Therefore, the NRC staff recommends that the existing license condition regarding criticality safety monitors exemption be continued as follows:
The licensee is hereby exempted from the requirements of 10 CFR 70.24 insofar as the Section applies to the stored materialin the Duncan Annex.
! Vill DECOMMISSIONING l
l Pursuant to 10 CFR 70.25, the licensee provided a decommissioning cost estimate and a r
statement of intent that funds for decommissioning would be available at the time of l decommissioning. NRC approved this certification in the letter dated April 16,1999.
l l
l
L .. .
.. _. IX~ PHYSICAL SECURITY The security plan submitted by Purdue University meets the requirements of 10 CFR 73.67 for l SNM of moderate strategic significance. Therefore, the NRC staff recommends that the existing license condition regarding the physical security plan be continued as follows:
l l- As it pertains to License SNM-142, the licensee shall fully implement and maintain in ~
- l. effect all provisions of the approved 10 CFR 73.67 physical security plan, including l changes and amendments made pursuant to 10 CFR 70.32(e) and 10 CFR 70.34. The approved physical security plan, which was submitted by letter dated May 15,1987, I l
l consists of a document containing Safeguards information entitled, " Security Plan for I
the Purdue University Reactor, the Fast Breeder Blanket Facility and the Nuclear Fuel Storage A ' reas," Revision 3, dated May 15,1987.
L X EMERGENCY PLAN l
l 10 CFR 70.22(l)(1) requires Purdue University to either: (1) perform an evaluation that l demonstrates that the maximum dose to a member of the public offsite, from a release of radioactive materials, would not exceed certain specific dose levels, or (2) submit an emergency plan. By letter dated February 16,1993, Purdue University submitted an evaluation.
NRC staff accepted the licensee's evaluation at the last license renewal in 1994. The staff has i reaffirmed the previous determination that the licensee is not required to submit an emergency plan.
- XI - ENVIRONMENTAL REVIEW The Commission has determined that the proposed activities do not adversely affect public
- health and safety nor the environment because the activities involve the use of radioactive materials for research and development or for educational purposes. Such activities are categorically excluded from the requirements to prepare a site-specific environmental assessment. Therefore, in accordance with 10 CFR 51.22(c)(14)(v), neither an environmental assessment nor an environmental impact statement is warranted for this action.
XII CONCLUSION On completion of the safety review of the Purdue University's renewal application, the staff
-concludes that Purdue University has an adequate safety program. Therefore, the staff recommends that Materials License SNM .142 be renewed for a 10-year period in accordance with the application and subject to the recommended license conditions.
The Region Ill inspection staff has no objection to this proposed action.
PRINCIPAL CONTRIBUTORS Sean Soong Harry Felsher -
Andy Rayland j,g,$ (
4 L