ML20215J744
| ML20215J744 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 06/18/1987 |
| From: | Bidinger G, Horn M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20215J642 | List: |
| References | |
| NUDOCS 8706250095 | |
| Download: ML20215J744 (9) | |
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JUN 18198I j FCUF:MLH-l DOCKET NO: 70-152 l
LICENSEE: Purdue University 1 West Lafayette, Indiana l
SUBJECT:
SAFETY EVALUATION REPORT, APPLICATION DATED i SEPTEMBER 17, 1986, RE LICENSE RENEWAL $
Backcround
'Purdue University (PU) was first issued Special Nuclear Material License No.
SNM-142 in December 1957. The license was last renewed in October 1981. The ,
current license was scheduled to expire on October 31, 1986; however, on !
September 17, 1986, PU submitted an application for renewal. Accordingly, the !
license has remained in effect in accordance with the timely renewal provisions j of Subsection 70.33(b) of 10 CFR 70. The licensee submitted additional )
information on emergency plans and calibration sources on May 11, 1987.
l Scope of Review I The review of PU's renewal application included the application of September 17, 1986, and the licensee's compliance history during the past 6 years.
l The topics of review include an evaluation of the applicant's radiation safety f and nuclear criticality safety programs and the organization. The renewal application was discussed with NRC Region III staff.
Discussion i
The renewal application demonstrates that PU has an adequate technical staff !
with the proper qualifications to administer an effective and safe radiological {
safety program. The following sections contain a description of PU's organization '
and radiological safety program, along with additional conditions developed by j FCSB staff. <
3 Possession Limits !
PU requests authorization to possess and use the following material:
Material Form Quantity !
h A. Uranium enriched in A. SPERT fuel. rods, A. 81,000 grams !
the U-235 isotope enriched < 4.8 w/o U-235 l 8706250095 B70618 PDR ADOCK 07000152 <
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'Purdue University, SER 2 18 OI B. Uranium enriched in B. Fuel rods, enriched B. 32,000 grars I
. the U-235 isotope 1 1.3 w/o U-235 ;
i C. Uranium enriched in C. Solid helices, C. 200 grams i the U-235 isotope enriched 1 20 w/o U-235 D. Uranium enriched in D. Solid discs, D. 10 grams 1 the U-235 isotope enriched 5 3 w/o U-235 ;
E. Plutonium E. Encapsulated PuBe E. 80 grams Pu I neutron sources l F. Plutonium F. Waste as metal, salts F. 1 gram j and solution 1 G. Natural Uranium G. U0 pellets clad in G. 11,760 kilograms albminum U H. Californium H. Up to 10 doubly H. 0.007 gram Cf encapsulated sources l
I. Uranium 233 I. Plated source I. 0.01 pCi U-233 j (10.5pg) !
l J. Neptunium 237 J. Plated source J. 100 pCi-(0.014 gram)
K. Plutonium 238 K. Plated source K.'100 pCi (0.58 ug)
L. Thorium 230 L. Plated source L 100 pCi (0.5 mg)
M. Actinium 227 M. Plated source M,_100 pCi (0.14 pg)
N. Curium '244 N. Plated source N. 100 pCi (0.12 pg)
Activities ,
The use of U-235 enriched solid helices and discs is to measure the effects of rare earths on the thermal properties of U0 and to measure the effects of elevated temperatures on the mechnical prope,rties of U0 . The Pu-Be neutron sourcesareemployedinactivationanalysisstudies,fof.instrumentcalibrations, and for neutron studies in a subcritical assembly. The SPERT fuel rods, the fuel rods enriched not to exceed 1.3 w/o, natural U0, pellets, and californium sources are used in the operation of the Fast Breeder BTanket Facility'(FBBF). . Items I - N are used as calibration sources. The' staff recommends the following license condition: ,
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'Purdue University, SER 3 JUN 18 N 1 Authorized use: For receipt, possession, and use in accordance with the j statements, representations, and conditions specified in'the licensee's j application dated September 17, 1986, and addenda dated August 12, 1981 1 (page 5 part a).
SNM is used and/or stored in three locations on the PU campus; the Duncan Annex, the Pharmacy Building, and the Physics Building. SNM is stored in 4 Room B-84 of the Duncan Annex. The Pu-239 waste materials are stored in 1 Room G-59 of the Pharmacy Building or in Room B-84 of the Duncan Annex. The f FBBF is housed in Room B28c of the Physics Building. Room 828c is a concrete j housing constructed within Room B28 to enclose the FBBF, The fuel storage cabinets are in Room B28. The staff recommends the following license i condition: i Authorized place of use: The materials specified in A through N above shall be used in locations specified in the application. dated September 17, j 1986. j Organization ,
The applicant has established a Radiological Control Committee (RCC) which' is composed of the Chairman (appointed by the University President), l a qualified Radiological Control Officer (RCO), and representatives from 1 departments whose expertise may be of value to the Committee. The duties and responsibilities, including review of all procedures involving SNM, are ] l explicitly defined in the application. The RCC meets at least three times a year.
The RC0 has the responsibility for the radiation safety review of all procedures l presented to the RCC, radiation surveys and monitoring of all. radioisotope and '
radiation facilities, personnel monitoring including film badge processing and exposure records and bioassay, and the overall administrative direction of the University Radiation Safety Program. The RC0 may hire qualified individuals to i assist him in his duties. These individuals are part of the Radiological Services Staff.
The FBBF and the SNM under this license are under the direct control of the Nuclear Engineering Department as authorized by the RCC. The Head of the Department of Nuclear Engineering appoints the Director of the FBBF. The '
Director reports to the RCC through the RCO.
The license application specifies the minimum education and experience 4 requirements for the principal members of the radiation safety staff. The current RC0 and the FBBF project director have sufficient academic training and experience to meet these requirements.
Training Radiation safety training is required for all.new employees and/or students.
The principles of radiation safety, as required by 10 CFR 19, are covered in a slide and tape presentation which was developed by the RC0 and his staff.
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'Purdue University, SER 4
, JUN 181987 l
In addition, students in nuclear engineering associated with the FB8F receive I training via formal classroom instruction and testing in nuclear engineering. ,
No refresher training course is provided for personnel on the basis that their '
usual stay at the University is limited to a time span that precludes the need for retraining. Because there may be students who are present for a number of l years as well as staff members who need refresher training, the staff recommends ~
the following condition:
Refresher seminars which cover radiation safety procedures shall be conducted on an annual basis (maximum interval 15 months) for all employees and/or stuuents who use radioactive material. , l 1
Ra,diation Safety Control
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Control of Personnel Exposure l 1
Film badges for personnel are read monthly and the exposure records are reviewed annually. In addition, use of criticality foils is required in the room housing Q the FBBF. Pocket dosimeters are used for temporary or occasional ocupancy. There is no formal bioassay program; however, the RCO has the authority to require 1 a bioassay program if necessary.
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Control of Contamination i Protective clothing is used whenever the possibility of contamination exists.
Hands, feet, and clothing are monitored when leaving a lab in which j radioisotopes are used. Contaminated clothing must be left in the lab, and skin is decontaminated until the contamination levels return to background. {
There is no reporting procedure described in the event that these levels cannot l be achieved; therefore, the following condition is recommended:
If personal clothing and/or skin contamination levels are above I background, persons shall not exit an area without approval of the Radiological Control Officer.
l Surface contamination surveys are conducted monthly at the FBBF facility.
Surface decontaminaticn begins when contamination exceeds specified action levels. The action levels for Pu are comparable to levels of allowable contamination developed by NMSS staff for release of facilities for unrestricted use; therefore, they are acceptable. The decontamination procedures are well defined in the application as they apply to surface and personal decontamination; however, there is deficiency in the lack of criteria for releasing contaminated equipment and packages from the facility for unrestricted use. To correct this deficiency, the following condition is recommended:
Release of equipment or material from Purdue University for unrestricted use shall be in accordance with the enclosed " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" May 1987.
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'Purdue University, SER S 30 10 W The applicant has established a leak test program for plutonium sources that is comparable to the standard leak test condition developed by NMSS staff, therefore, the leak test program is acceptable to this reviewer. ,
Calibration of Instruments The licensee uses a variety of radiation detection instruments. The j instrumentation is calibrated every 6 months. .
I Effluent Control !
Solid wastes are removed from work areas as required and are transferred, after volume reduction, to a licensed burial ground.
In general, liquid wastes are not generated but could result from decontami. nation and other unanticipated procedures. Liquid wastes are either fixed for disposal i by land burial or disposed of by release into the sewage system in conformity with the regulations.
Air contamination is not generated per se in the operation of the FBBF facility but could result from leakage. Isokinetic probes are used to sample exhaust :
before and after a HEPA filter which is located in the exhaust trains. Filters I are counted weekly to monitor for potential leakage.
Nuclear Criticality Safety A. General >
SNM will be used and/or stored in three locations on the Purdue University j Campus - the Duncan Annex Storage Facility, the Pharmacy Building Radiological r Dispensing Facility, and the Physics Building Fast Breeder Blanket Facility Laboratory. The application failed to discuss the criticality controls with respect to storage operations and the justification for such controls. The applicant requested, as per conservation with Dr. Born on May 14, 1987, that a letter from Purdue to the Commission dated August 12, 1981, be. included in the license to rectify the absence of missing information. Accordingly, the staff recommends the following license condition:
Storage of U0, fuel rods in the Duncan Annex Storage Facility and the FBBF shall be in accordance with representations for Duncan Annex, page 5, of the Addenda enclosed with the licensee's letter dated August 12, 1981.
The FBBF control and operating procedures, as well as the storage of SNM, are under the control of the Department of Nuclear Engineering. I
- 8. Duncan Annex Storage Facility The Duncan Annex Storage Facility (Room B-84), which will be used for storage of the 1.3 percent enriched U0 fuel, is constructed of a steel frame with concrete and brick. The steel2storage cabinets are arranged in two adjacent i arrays of three cabinets each. The cabinets, designed to hold the rods
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'Purdue University, SER 6 JUN 181987 vertically in a safe slab geometry, are fastened to the walls of the room. ]
The applicant has imposed a 14 cm slab thickness on the 1.3 percent enriched fuel. This is well below the subcritical limit for slab thickness as stated )
in ANSI /ANS-8.1-1983.
l C. Pharmacy Building Radiological Dispensing Facility i Pu-239 waste materials will be stored in Room G-59 of the Pharmacy Building !
in a wall isotope storage vault. Since the possession limit for the Pu-239 l waste is minimal (1g), there is no criticality concern. :
D. Physics Building Fast Breeder Blanket Facility Laboratory (Room B-28) i The Building is constructed of a steel frame with concrete and brick. The steel fuel storage cabinets are fastened to the southwest wall of Room B-28 j and are surrounded by a wire-mesh cage. The applicants are imposing a 14 cm 1 slab thickness on the 1.3 percent enriched fuel and a 3.5 cm slab thickness on ]
the 4.8 percent enriched fuel. Both of these figures are well below their I respective subcritical limits for slab thickness as stated in ANSI /ANS-8.1-1983.
l Two independent sets of calculations, which have been reviewed and determined satisfactory by the staff, regarding the reactivity of the FBBF have been L performed; and the two are in good agreement (See NRC Safety Evaluation Report !
issued December 17,1976). The calculations including a conservative uncertainty j estimation, indicates that k-eff ~ 43. This assessment assumes that water is j not present which would be the case under normal operating conditions. With .i flooding of the room, the calculated k eff is ~ 0.74. Therefore, it has been determined that nuclear criticality safety is assured. No changes in the j
current model were proposed in the application; therefore, it is recommended that the existing condition governing criticality be continued as follows:
The Fast Breeder Blanket Facility shall not be operated with a measured j normal operation k-eff greater than 0.45. In addition, the fuel. loading i shall be limited such that the calculated k-eff would not exceed 0.75 if 1 the FBBF were accidentally flooded with water. I E. Handling of Fuel Rods
-l The applicant reported, as per conversation with Dr._ Born on May 14, 1987, that fuel will be transferred in 8-inch diameter cylinders (similiar to 00T 6M 2R) with only a single. cylinder being moved and handled at one time. Eight inches is below the subcritical limit for 4.8 percent enriched uranium as 1
stated in ANSI /ANS-8.1-1983. Accordingly, the staff recommends the following ,
condition: '
Fuel shall be transferred in 8-inch diameter cylinders. Fuel handling procedures shall be carried out in such a way that no more than one loaded cylinder will be in the storage area, in transport, or in the FBBF at the same time.
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. 'Purdue University, SER 7 Jgg i g 1987 l
F. Exemptions The area monitors in the FBBF facility meet the requirements of.10 CFR 70.24; however, the applicant has requested, pursuant to 10 CFR 70.'24(a), an exemption from the provisions of 10 CFR 70.24 for special nuclear material stored in the Duncan Annex and the Pharmacy Building. The applicant's reasons for requesting the exemption are that the fuel rods are stored in critically safe racks, procedural controls preclude situations in which nuclear criticality may occur, ,
and the Pharmacy Building will not have quantities exceeding 450 graras of '
plutonium. ;
The applicant's reasons for the exemption are valid, and good cause exists for the exemption. The storage racks provide physical protection to ensure subcriticality. The procedural controls provide reasonable assurance that I nuclear criticality will not occur during fuel handling,.and monitoring is not needed. Even if procedural controls were violated, optimum conditions of neutron moderation and physical. spacing would be required for the fuel rods I to be in a critical situation. 1 This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.
Accordingly, the followir.g license condition is recommended:
The licensee is hereby exempted from the requirements of 10 CFR 70.24 insofar as the Section applies to the stored material in the Duncan Annex an' '.e Pharmacy Building. i Emergency Planning !
The licensee has established procedures that are to be followed in the event of emergencies or accidents involving actual or potential radiation hazards. ,
The procedures cover such events as fires, spills, unauthorized entry, accidental !
criticality, and injury. I 1
Environmental Protection l
1 The licensing of the PU activities is in accordance with 10 CFR 51.22(c)(14)(v), {
and therefore, neither an Environmental Impact Statement nor an Environmental Assessment is warranted for this action. ,
i Physical Security i i
The Division of Safeguards and Transporation has reviewed the security plan !
submitted by PU and has determined that the plan meets the requirements of 10 CFR 73.67 for SNM of moderate strategic significance, subject to the following j condition: a i
The licensee shall follow Revisions 1 and 2 to the " Security Plan for the !
University Reactor, the Fast Breeder Blanket Facility, and the Nuclear Storage Areas," dated March 31, 1980, and October 24, 1980, respectively.
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I Jrdue University, SER 8 JUN 181987 irapliance History le inspection and enforcement record of the licensee since the last renewal ts reviewed and discussed with Region III staff. There were no violations
! ported during this period. The Region feels the license as written addresses 1 of Region III's concerns from an inspection and enforcement perspective and
's no objection to the issuance of the renewal.
f inclusion and Recommendation on completion of the safety review of the licensee's application and discussion th the Region III staff, the staff has concluded that the licensee has the essary technical staff to administer an effective radiological safety program.
nformance by the licensee to their proposed conditions, as well as those veloped by FCSB staff, should ensure a safe operation, a quick detection of favorable trends or effects, and result in corrective actions being taken.
, sed on the discussion above, it is recommended that the license be renewed for 5 year period in accordance with the application and subject to the recommended
,nditions.
hW*f. W Merri L. Horn Uranium Fuel Section Fuel Cycle Safety Branch Division of Fuel Cycle, Medical, prisinal Signed By proved by:
George H. Bidinger Uranium Fuel Section p: FCUF :FCUF :FCUFA m : :
p . _ _ ., htlY. :
NE:MLL n/ht/as:VL L.________________Narpe: GHBidinger: : : :
fE:6//7/87 :6/h/87 :6/r7/87 : : : :
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