ML20043D590
| ML20043D590 | |
| Person / Time | |
|---|---|
| Site: | 07001068 |
| Issue date: | 06/06/1990 |
| From: | Vernetson W FLORIDA, UNIV. OF, GAINESVILLE, FL |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9006080279 | |
| Download: ML20043D590 (14) | |
Text
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NUCLEAR ENGINEERING SCIENCES DEPARTMENT Nuclear Rooctor Facility universRyof Florida 01".%*.%,.
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June 6,1990 leland C. Rouse, Branch Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re:
SNM 1050 License Renewal (Storage Only)
Docket No. 701068 Gentlemen:
It is respectfully requested that Special Nuclear Material License No. SNM 1050 (due to expire June 30,1994 by License Renewal dated June 23,1989) be amended based upon the attached submittal materials (Revision 1 to the previous licence renewal package with replacement pages as labelled). The affected pages include Pages 1 1,12,13,31,41,4 2, t
51,71,81, A 1 and A-2. All changes (additions, deletions and changes) are marked by L
' vertical lines in the margins and by Revision 1 and the date at the 1,ottom. The University l.
of Florida UFSA Safety Review Subcommittee (USRS) for the UFSA Facility covered by p
this lleense has reviewed the status and conditions on several occasions over the past year, L
as well as for this submittal, at their meeting on June 6.,1990 and concluded that all safety l
requirements are met. :Six copics of this cover letter and the supporting document are L
enclosed for your review.
L L
The present status of the UFSA Facility covered by SNM 1050 is essentially as specified in the renewal application dated March 1,1989 except that 1200 of the fuel pins were transferred to a secure facility at Oak Ridge National Laboratory on May 17,1990.
Current plans are to ship the remainder of the fuel to a secure DOE facility within the next few months. This amendment addresses movement of the remaining. 4200 fuel pins to a
/
previous storage location. When this application is approved, the necessary change in the f
security plan will be effected also, f
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. Please let us know if additional information is needed in support of this request.
Thank you for your consideration of this SNM 1050 request for license amendment.
Sincerely, a
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Notary Dafe Notary Put&. State Of Floride At
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J.S. Tulenko MJ. Ohanian W.E. Bolch D.L Munroe N.J. Diaz P.M. Whaley L
SNM 1050 License File L
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,s-SNM-1050 LICENSE AMENDMENT 1
- PAGE CHANGES TO LICENSE RENEWAL PACKAGE DATED MARCH 1,1989 u
(Approved June 6,1990) i
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The following pages, as attached and labelled Revision 1,6/90, are to replace those in the -
licence renewal package dated March 1,1989:
Chapter 1: '
Pages 1 1,12, l 3 Chapter 3:
Pages 31 Chapter 4:
Pages 4-1,4 2 Chapter 5:
Page 5-1 s
Chapter 7:
Pe.p 7-1 Chapter 8:
Page 8-1 Appendix:
Pages A-1, A 2'
-i i
k 1.0 STANDARD CONDITIONS 'AND SPECIAL AUTHORIZATIONS L
1.1 Name and Address -
The full name and address of the educational institution to which the SNM 1050 License is assigned is as follows:-
l-The University of Florida Gainesville, Florida 32611 The names, titles, addresses and principal officers for the University of Florida relative to this SNM 1050 license renewal are as follows:
CITIZEN-NAME TITIF ADDRESS SHIP
' John V. Lombardi-President 226 Tigert Hall U.S.
University of Florida Gainesville, FL 32611-j.
l.
Gene W.' Hemp Interim Provost and 236 Tigert Hall U.S.
Vice President University of Florida.
Gainesville, FL 32611 l
l Winfred M. Phillips Dean-300 Weil Hall-U.S.
College of Engineering University of Florida Gainesville, FL' 32611 l
James S. Tulenko Chairman, Nuclear -
' 202 Nuclear Sciences U.S.
l Engineering Sciences Center, Univ of FL' l
Department Gainesville, FL 32611 It should be noted that Gene W. Hemp is serving as Interim Provost until July 1, 1990 when his successor is scheduled to assume the position.
1.2 ' - Site Location i
u The University of Florida SPERT Assembly (UFSA) fuel pins (SNM-1050 fuel) are L
stored ^within the Nuclear Research Field Building (Bldg. No. 554) on the University of Florida Campus. This building is located on the periphery of the University of. Florida campus about 1/2 miles from the main campus which is located in a well-populated area of the City of Gainesville, Alachua County, Florida. Figure 11 shows the relative location J
of Alachua County within the State of Florida. Figure 1-2 shows the chief population
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' centers in Alachua County outside Gainesville with concentric circles at 5-mile intervals.
l around the-UFSA site. A map of the University of Florida campus showing its relation to l
1-1 Rev.1, 6/90
major arteries of the city of Gainesville is presented in Figure 1.3 clearly showing the UFSA Building #554 just off S.W. Archer Road on the Southwest edge of the campus. The fuel is stored in Room 6 or 5 of this building and will not be used under its renewal SNM 1050 license. The only changes planned are that some of the fuel will be shipped following the -
requirements delineated in the Quality Assurance Program Approval for Radioactive Packages No. 0578, Revision No.1 (Docket No. 71-0578) dated November 5,1987 and with an expiration date of October 31,1992. All loading into containers for shipment will be made within Room 6 or 5 and subsequent loading onto a vehicle for transport to a secure location will occur at the Building #554 site, 1.3 License Number and Period of License The license number for this SPERT fuel is SNM 1050 and the period for which this storage only license renewal is requested is for twelve (12) years to December 31,2001.
1.4 Possession Limits The maximum quantity of special nuclear material (SNM) to be possessed and stored and possibly eventually shipped by the University of Florida under this SNM-1050 license corresponds to the following special nuclear material on site in Room 6 or 5:
- a. Form: SPERT F-1 type fuel pins, 4.81% enriched in UO pellets form, 2
encased in seal-welded stainless steel tubes,
- b. Amount of Fuel: 5400 fuel rods, each containing 2.2 pounds of UO pellets.
2
- c. Amount of SNM: 190 kg of U-235 contained in 4.81% enriched UO2
- pellets,
- d. Status: The fuel is " cold," having a cumulative power history of less than 1 watt-s day with no usage in the subcritical facility since 1983.
Table 1.1 Present Location of Special Nuclear Material No. of Fuel Pins FUEL STORAGE AREA (Room 6 or 5)
OF BUILDING NO. 554 9 00 TOTAL 4200 All SNM is locked under special key in the Fuel Storage Area (Room 6 or 5) as indicated in Table 3.1; the only exception should be for shipment of pins under QA Program approval No. 0578, Revision 1 or for temporary removal within building 554 for surveillance.
2 Rev.1, 6/90
1.5 Authorized Activities Under the storage only SNM 1050 license conditions, the only activities to be authorized are those involved in assuring proper storage, radiation protection, security, surveillances and other checks for the fuel storage facility and to assure fuel integrity as well as any activities involved in movement of the fuel between Rooms 6 and 5 or shipn:ent of the fuel following the OA Program Approval No. 0578, Revision No.1.
1.6 Exemption and Special Authorization An exemption is requested to the requirements for a criticality monitor per 10 CFR 70.24. This exemption is requested to be allowed only for normal storage conditions within the UFSA facility on the basis that there is no need for the alarm in such storage only conditions as delineated in Chapter 4. Whenever work is in progress at the USFA facility L
that involves the movement of fuel such as loading for shipment or for surveillance checks, the proper criticality monitor will be required.
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1 1-3 Rev.1, 6/90
3.0 RADIATION PROTECTION 3.1 General Technical Requirements 3.1.1 Restricted Areas - Access Control Unescorted access to the room where the fuel is stored (Rooms 6 or 5) is strictly limited to personnel described in the Administrative Chart in Figure 1.1, and in special cases, to individuals who are well known to the Director and/or the Radiation Control i
Officer and who have documented training in Radiation Control procedures equivalent to
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that received by the staff members depicted in the Administrative Chart in Figure 1.1.
These individuals should all meet the requirement to be radiation control qualified as radiation technicians at a minimum. The room where the fuel is stored is locked whenever it is not occupied to assure unauthorized or untrained personnel do not enter the facility without an escort.
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Access to the remainder of Building 554 is restricted to those with an approved need l
to access the building after normal hours. Other than these controls, the remainder of the i
i building is subject to the needs of other research facilities utilizing the building, j
The SNM 1050 storage room entrance will be posted as to levels and types of l
radiation involved. In addition, NRC Form 3 as well as emergency instructions, a call list, and a list of individuals approved for unescorted access will be maintained at the entrance.
I Whenever the fuel is handled, an RWP will be available to control operations and '
i document contamination control requirements as well as actual and limiting radiation exposures and the means to assess them.
l For the storage-only license, protective clothing requirements are considered to be minimal. These will be specified in applicable RWPs but could be expected to include laboratory coats, coveralls, and possibly shoe covers, all of which will be made available as needed. If further anti-contamination or protective clothing should prove necessary, full anti-contamination clothing is available to the Radiation Control Officer or the UFSA w
Director from that available at the UFTR (R-56) facility.
i For normal biweekly inspections as well as quarterly, semiannual and other surveillances not involving fuel handling or movement, no personnel exit survey is considered necessary. When fuel handling or movement is involved, a control point will be set'up inside the entrance to the storage room with a step off pad and frisking to be performed using hand held thin window instruments for individuals leaving the room per any applicable RWP under which such work must be performed. For positive indications, the individual will be decontaminated using standard techniques with swipes used to isolate the source of contamination. Subsequent decontamination will be used to restore the area in question below the action levels of 50 dpm alpha and 100 dpm beta-gamma applicable
- at the UFTR R-56 facility and elsewhere on the University of Florida campus. Since the only realistic sources of contamination would be fuel pins which have lost their integrity or fuel shipment containers contaminated elsewhere, such items will be segregated, labeled and i
prevented from contributing to spreadable contamination by appropriate means.
3d Rev.1,6/90
4.0 NUCLEAR CRITICALITY SAFETY The UFSA fuel storage area is located in an isolated and shielded Room 5 (or fenced off and partially shielded Room 6) in the Nuclear Research Field building located approximately 11/2 miles from the main University campus. The Nuclear Research Field Building (Building No. 554) is located on a plot assigned to the College of Engineering for research activities. The building and the area immediately surrounding it are under the control of the Department of Nuclear Engineering Sciences, the Division of Environmental Health and Safety and the Innovative Nuclear Space Power Institute which is currently using most of the laboratory and office space in the building for research being performed by various faculty in the Nuclear Engineering Sciences and other departments of the University.
A floor plan showing major walls and partitions of the Nuclear Research Field building is shown in Figure 4.1 with an approximate scale. This Room 5 and several of the surrounding rooms are also provided with an automatic fire alarm system although flammable material in the storage facility is strictly limited. Room 6 consists of a metal roof and sides over concrete blocks. The front is also concrete except for the wood door.
Flammable materials are minimal and are not present in sufficient quantity to pose a fire threat to the facility. Each SPERT fuel rod consists of 4.81 0.15 w/o U 235 uranium dioxide pellets contained in stainless steel tubing. The fuel pellets are right circular cylinders with a nominal diameter of 0.42 inches. The active fuel length of the rod is 36 inches as shown in the isometric diagram of Figure 4.2.
The overall storage arrangement consists of three arrays 14 feet long and at least 40 inches apart edge to edge. Each array is a vertical slab of steel framed storage containers that accommodate rows of seven fuel rods. The vertical length of a storage container is 28 inches. In its Safety Evaluation Report dated 5 April 1988,- the NRC staff calculated this array assuming a maximum enrichment of 5.0 w/o U 235 and utilizing the Hansen Roach 16 group cross-section set which is found in the SCALE program, along with KENO V.a.,
a Monte Carlo code. Staff determined the k.tr for the storage array to be about 0.84. No
, credit was taken for the absorption qualities of the stainless steel clad or the steel containers, and the k.tr is independent of the degree of water moderation within and between the arrays or the degree of concrete reflection surrounding the array.
To ensure that the SPERT rods will remain safely subcritical when removed for surveillance or for shipment preparations, no more than 20 rods will be removed from the storage containers at any one time for surveillance checks or for packaging for shipment.
The 20 rods correspond to no more than 787 grams of U-235. The staff has independently confirmed that this mass is below 45 percent of the critical mass for 0.4-inch and 0.6-inch diameter rods with UO - water lattices as specified in DP-10145.
To ensure that the SPERT fuel will remain safety suberitical when moved for shipment, no more than one storage container will be handled and moved at any one time.
Based on the calculations above, subcriticality is assured.
In addi: ion, a criticality monitoring system capable of measuring 500 R/hr will be maintained at all times when fuel is being moved to include removal of single pins for mspection purposes.
4-1 Rev.1,6/90
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I 5.0 ENVIRONMENTAL PROTECTION 5.1 Effluent Control Systems.
Under the requested storage-only renewal of the SNM 1050 license, the only radioactivity usually present in the facility will be that contained within the SPERT fuel pins. The uranium in oxide form is essentially the only radioactivity present. Since no radioactivity is expected in gaseous or liquid forms, the need to specify action levels for responding to radioactivity in gaseous and liquid effluents is not considered necessary.
All solid effluents, primarily in the form of contaminated swipe and cleaning materials, will be monitored as part of general facility periodic surveillances performed on a semiannual schedule at intervals not to exceed seven (7) months. Basically, the action levels for swipes and 50 dpm/100 cm' for alpha and 100 dpm/100 cm' for beta gamma based on swipes to be counted on a gas flow proportional counter or equivalent system which will be tested and calibrated semiannually at intervals not to exceed 7 months.
Whenever these action levels are exceeded, a more detailed swipe surveillance will be undertaken to isolate and identify possible loss of integrity of some fuel pins or other source of contamination. If and when any pins are identified as having lost integrity, the identified pins will be segregated and the storage area decontaminated to below the contamination action levels identified above. Any other source of contamination will be similarly addressed. Any waste will be disposed of via the University disposal facility with shipment ultimately for burial following approved procedures of the Radiation Control Office.
5.2 Environmental Monitoring The SNM 1050 storage facility and its contents will be visually inspected at least once every two weeks. The results of these visual inspections will be recorded in a log book maintained at the facility. The radiological monitoring program consists of a film badge (or alternatively a thermoluminescent dosimeter) located outside Room 5 to provide a monthly record of the maximum dose for individuals occupying the Nuclear Research Field Building No. 554. The record of the dose recorded by this monitoring device will be maintained as part of the facility records by the Radiation Control Office after being reviewed by the Radiation Control Officer and the Facility Director or their designated alternates. Values significantly above background (>30 mR/ month) will be brought to the attention of the UFSA Safety Review Subcommittee for further consideration.
A radiological survey consisting of radiation level readings at various locations within and outside of Building No. 554 including the area within the storage facility in Room 5 or 6 as well as random swipes taken of the fuel and surrounding area within the Room 5 or 6 storage facility will be taken and recorded on a semiannual basis at intervals not to exceed seven (7) months. The results of these surveys will be reviewed by the Radiation Control Officer and by the Facility Director or their designated alternates to assure and document that the facility conditions are maintained with negligible radiological effect on building occupants and the environment.
5-1 1
Rev.1, 6/90
7.0 PECOMMISSIONING PLAN When the SPERT fuel held under the SNM 1050 license is finally no longer potentially needed or of use, the remaining fuel from the facility will be shipped back to a secure Department of Energy or other facility. Since Room 5, where the fuel can now be stored, was decontaminated in order to allow implementation of SNM 1050 License Amendment No.10, and since this license renewal is for " storage only" activities also, it is unlikely that any significant contamination will occur in Room 5 or 6 or elsewhere in Building 554 from the current storage or the anticipated storage only and transfer for shipment activities.
Nevertheless, upon eventual removal of the fuel, radiation and contamination surveys will be conducted to assure that the facility can be released to unrestricted use before making such release.
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The facility location and equipment will be decontaminated in accordance with the
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses Byproduct, Source, or Special Nuclear Material," August,1987. The facility was previously so decontaminated-to allow the authorized movement of the SPERT fuel to its present Room 5 storage location from Room 3 with Room 3 released to unrestricted use in April-May,1988. On this basis and since this license amendment request is for " storage only, with movement allowed to Room 6,"
no significant effort is anticipated to be involved in decontamination of the facility for -
eventual decommissioning of the facility.
The resultant costs for performance and documentation of such decontamination and radiation surveys as will be needed are also expected to be minimal.
7-1 Rev.1,6/90
8.0 RADIOLOGICAL CONTINGENCY PLAN The Radiological Contingency Plan for the USFA facility consists of emergency procedures addressing response to radiological, fire, and security related emergencies. The facility has a call list posted at Storage Room 5 or 6 and at the main entrance to Building 554 indicating the personnel to be contacted in the event of a facility emergency. Personnel in the building are all made cognizant of the facility emergency procedures and the initial steps to be taken to include prompt evacuation of the building and initiation of the call list for all facility emcrgencies.
The existence of a fire alarm system in most of the building, with audible alarm and a criticality monitor with audible alarm (when fuel is being moved or handled) provides reasonable assurance that Rooms 5 and 6 and the remainder of Building No. 554 will be evacuated in the event of a facility emergency requiring evacuation.
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8-1 Rev.1, 6/90 1
,y A.0 DEMONSTRATION APPENDIX A.1 License History The history of the SNM 1050 license for the SPERT fuel held at the University of Florida dates from first issuance in December 11,1967 for storage only up to the present limited usage license. This license history is summarized in Table A.I.
The first license was issued for storage only on December 11,1967 to allow fuel to be received and held in storage subject to approval of planned experiments. The license allowing usage of the SPERT fuel was first issued on March 27,1968 with two amendments to the usage approved in 1968. The full license was rcnewed on December 5.1969 and again on December 20,1971. Subsequently, twelve amendments have been issued to the license. Amendments 1-4 were issued primarily to extend and revise allowed and licensed usage of the SPERT fuel for various experiments related to research, education, and training.
Beginning with Amendment No. 5 issued on August 26,1983, the SNM 1050 license was amended and extended for storage only pending a decision on the use of the fuel and the UFSA facility. With Amendment No. 8 effective on April 29,-1987, Dr. William G.
Vernetson was listed in a license condition as the individual responsible for direction and administration of the UFSA facility. Amendment No. 9 was issued on November 17,1987 extending the " storage only" license to April 30, 1988. Subsequently, on April 5,1988, Amendment No.10 was issued authorizing movement of the fuel from Room 3 to Room 5 for storage, removing Room 3 from the allowed storage or usage of the fuel and authorizing non-destructive testing (NDT) of up to 20 fuel pins at a time in an area adjacent to the Room 5 storage area. Subsequently, Amendments 11 and 12 were issued to allow continuation of the NDT work with the license extension due to expire on March 31,1989. Subsequently a renewal license submittal for storage only was made in a timely manner on March 1,1989. The SNM 1050 storage only license was then renewed effective June 23,1989, expiring on June 30,1994.
A.2 Education and Experience of Kev Personnel The education and experience of key personnelis presented via the enclosed resumes of Dr. William G. Vernetson, the Director of the University of Florida Training Reactor (UFTR) who also serves as the individual responsible for direction and administration of the UFSA facility and Mr. Donald L Munroe, the Radiation Control Officer for the University of Florida and the UFTR who also serves as the Radiation Control Officer for the UFSA facility. In their respective positions, both have extensive experience in the use and handling of various radioisotopes as well as the SNM-1050 fuel and the high enriched plate-type fuel held and used under the R 56 license for the University of Florida Training Reactor.
A-1 l
Rev.1, 6/90
TABLE A.1 LICENSE HISTORY '
DOCKET NO. 70-1068 SNM 1050 Issuance Date License Tvoe Expiration Date Dec.11,1967 For Storage Only Dec. 31,1969 Mar. 27,1968 Usage for Experiments and Requiring Oamma Survey Instrument Capable of Monitoring to 500 R/hr Dec. 31,1969 May 31,196",
Amendment No.1 Dec. 31,1969 July 29,1968 Amendment No. 2 Dec. 31,1969 Dec. 5,1969 Renewal Dec. 31,1971 Dec. 20,1971 Renewal Dec. 31,1973 Dec. 21,1973 Amendment No.1 Dec. 31,1978 L
Oct.16,1974 Amendment No. 2 Dec. 31,1978 Aug.1,1975 Amendment No. 3 Dec. 31,1978 Nov. 9,1978 Request for Extension to Dec. 21,1985 May 26,1981 Amendment No. 4 July 31,1983 Aug. 26,1983 Amendment No. 5 (Storage Only)
Aug. 31,1984 j,
May 28,1985 Amendment No. 6 (Storage Only).
Sept. 30,1985 Sept.17,1985 Amendment No. 7 (Storage Only)
Sept. 30,1986 l
L
- Aug. 29,1987 Amendment No. 8 Oct. 31,1987 l
(Dr. Vernetson responsible for l
Direction / Administration of UFSA L
Facility)
L Nov.17,1987 Amendment No. 9 (Storage Only)
April 30,1988
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April 5,1988 Amendment No.10 April 30,1988 (Change Storage Location and Allow j.
NDT Under RWPs) l' April 28,1988 Amendment No.1l (NDT continued)
Sept.30,1988 l
l Oct.14,1988 Amendment No.12 (NDT continued)
March 31,- 1989 l
June 23,1989 Renewal for Storage Only June 30,1994 A-2 Rev.1,6/90