ML20248D702
| ML20248D702 | |
| Person / Time | |
|---|---|
| Site: | 07000157 |
| Issue date: | 09/27/1989 |
| From: | Bidinger G, Robinson C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20248D686 | List: |
| References | |
| NUDOCS 8910040369 | |
| Download: ML20248D702 (1) | |
Text
{{#Wiki_filter:. _ _ _ _ _ DOC ET N0s. 70-157-
' LICENSEE: University of Texas at Austin (UT)
Austin, TX i
SUBJECT:
SAFETY EVALUATION REPORT, LICENSE AMENDMENT APPLICATION DATED JULY 25,1989, RE RELEASE OF ENGINEERING SCIENCE BUILDING ROOM 32N FOR UNRESTRICTED USE Backgrcund By letter dated July 25, 1989, University of Texas requested that Condition 10 of Materials License No. SNM_180 be amended to remove Engineering Science Building (ESB) Room 32N as an authorized place of use under this license. Discussion In the subject application, the 'icensee submitted radiological survey results for ESB Room 32N in sJ use (See Attachment 1)pport . of a request On September to release 1,1989, RegionRoom 32N for aunrestricted IV completed confirmatory radiological survey of Room 32N and established that contamination is within the limits specified in dRC guidelines (See Attachment 2). Accord _ ingly, it is recommended that Room 32N be released for unrestricted use and Condition 10 be revised as follows: Authorized place of use: The Nuclear Engineering Laboratories located in Taylor Hall and Balcones Research Center. This . licensing action terminates the use of Room 32N of the Engineering Science Building. In accordance with 10 CFR 51.22(c)(14)(v), neither an Environmental Impact Statement nor an Environmental Assessment is warranted. Conclusion / Recommendation The staff finds that the proposed change to the license will have no adverse effect on the public health and safety or on the environment. Approval of the amendment application is recommended. In memorandum dated September 13, 1989, Region IV recommended that ESB Room 32N be released for unrestricted use (See Attachment 3). QJ@lhil Signed By* Charles Robinson e91oo40369 890927 Uranium Fuel Section pDs ApocK 07000157 Fuel Cycle Safety Branch C PDC Division of Industrial and Medical Nuclear Safety, NMSS Approved by:
@'l sip 0d BT George H. Bidinger, Section Leader Attachments: As stated 0FC:IMUF: IM IMUF IMUF:
NAME:CRobinson:mh: MHorn: VLTharpe: GHBidinger: DATE:9/11/89_________.._________________________________,//89 9/ @ 89 9/T 9/77/89 0FFICIAL RECORD COPY
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DEPARTMENT OF MECHANICAL ENGINEERING f 8 w .a . ,~ y.. 4-- THE UNIVERSITY OF TEXAS AT AUSTIN p) m
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Office of Nuclear Material Safety and Safeguards U.S.. Nuclear Regulatory Commission Washington, DC 20555 J
Subject:
SNM-180 Survey of area for release to unrestricted use.
Dear Sir:
The enclosed report is provided pursuant to SNM-180 license (item 17). Amendment of the license is requested to remove Engineering Science Building Room'32N from the license description. Release of the room 32N area is for unrestricted use. Sincerely, M 9. ~h Thomas L. Bauer Assistant Director Nuclear Engineering Teaching Laboratory 10100 Burnet Road Austin, Texas 78758 Approved: b h M d N. N Bernard W. Wehring, Dir tor Nuclear Engineering Teaching Laboratory TLB:j gr Enclosure xc: B. Wehring B. Bryant
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DEPARTMENT OF MECHANICAL. ENGINEERING I THE UNIVERSITY OF TEXAS AT AUSTIN f i ? a!qi, x / . NudearEngiraring Tead>ingLaboratory 10100BurnetRaad Austin, Tex.u 78738 (3121471-5787 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of 5 5 The University of Texas 5 at Austin i Docket No. 50-602 i Balcones Research Center i Nuclear Engineering Teaching i Laboratory (NETL) $ AFFIDAVIT Gerhard J. Fonken being duly sworn, hereby deposes and says that he is Executive Vice President and Provost, The University of Texas at Austin; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Request for Amendment of Construction Permit CPRR-123; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge and belief. fk fj\[~ -- Gerhardf.Fonken ! Executive Vice President & Provost ! { STATE OF TEXAS 5 Subscribed and sworg to before me a Notary Public in and for the State of Texas, this S/2 day of , 1989. 0K4ru N. l?t/A ir No,tary Public in and'fo6 the ftate of Texas t l - - - _ _ _ - .-. A
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- 1 Report of Survey License SNM-180 - Room 32N The University of Texas at Austin License Materials on License SNM-180 consist of U-235 suberitical assembly and PuBe neutron sources. Ths Engineering Science Building (ENS)
Room 32N was an experJment area for use of the PuBe sources. At no time was the suberitical assembly used in ENS room 32N. Periodic surveys of the ENS 32N area maintained surveillance for surface contamination on a regular basis. Periodic source swipes monitored the condition of the sealed sources. After removal of all radioactive materials (including agreement state materials such as calibration sources) several contamination surveys of the license area were made. These measurements consist of 3 separate surveys to determine the conformance of area surfaces and equipment to the license requirements of an area to be released for unrestricted use. The first survey consisted of 24 samples of an area of concrete block shield wall. Removal of the wall was necessary before other materials could be removed from the area. Approximate wall dimensions were 8 feet high by 16 feet long. Both sides of the wall were sampled with one sample for each 10 square feet. Swipes were counted by a liquid scintillation counter. The largest count rate per minute uncorrected for efficiency was 72 cpm with a 2-sigma error of 22%. All other count rates were less than 50 cpm. Since the counter efficiency exceeds 90% for all but the lowest energy betas these activity measurements for surface areas fo 100 square centimeters are significantly less than to 1000 dpm for beta gamma activity. Subsequent measurements of specific pieces of equipment, consisting of 15 samples showed similar results. Maximum count rate per minute was 61 cpm at 25% error (2 sigma); all other count rates were less than 50 cpm. Af ter adjustment the count rate for efficiency (90%), is still substantially less than 1000 dpm for a 100 square centimeter area. A final survey was made after removal of equipment and all radioactive materials, shields, and other related materials to other license sites. A total of 90 samples of the area was measured by an alpha-beta proportional counter to provide for detection of either alpha or beta activity. The maximum count rate was 54 cpm with an error of 13 %. An efficiency of 66 % converts the measurement to 82 dpm/100 cm2. No removeable activity was noted in any of the experiment areas, during routine periodic surveys or during the 3 phase cleanup activities in the facility area. Nofixedcontaminagionhasbeennotedbyperiodicarea surveys. A random survey with a 50 cm scintillator probe for alpha-beta activity shows no unusual fixed contamination. Although conditions are not considered credible in 'hich w fixed contamination would be present without removeable activity, several measurement points were made for fixed activity. .Results were negative.
- Table 1 - 5 summarize the survey measurements. The data in Table 3
. includes data taken before and after removal of equipment from the room.
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9' t Table 1~ Source Leak' Test Data 1p ,
~ Source"f, Date~ ,
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*Nomeasurablealphaactivjtywasdetectedforthesesources sensitivity less than 10- microcuries.
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. Table 2 Phase I Wall Removal Survey l Sample # CPM DPM/100cm ' Sample # CPM' DPM/100cm l '- 37.5' 39.5- 13 - -
26.5' 27.9u 14 4.5 4.7
. 3' 8.5 -8.9 15 31.0 32.6 4 39.0 41.1. .16 '10.5 11.1
'5 46.5 '48.9L 17 49.0' l51.6 r .'
-6 -4.0 4.2 18 72.0 75.8'
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8 -7.0- 7.4 20 8.5 8.9
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9 7.5 7.9' 21 33.0 34.7 10 - - 22 ~16.0 16.8 11 . 13.5. 14'.2 23 32.5 34.2 12 '~ 23.5 24.7- 24 43.0 45.3' 1 , --
- Note' liquid scintillation counter efficiency of 95%.
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. Table 3
- 3. Phase'2.- Component Survey Item # ' CPM- DPM /100cm DPM /100cm "
9 ~ q ;. ; , t 1 l20.5' 21.6 - 2'
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2- 38.5l 40.5 L 9 3 '- 18'.0 18.9 2 4' 13.0 13.7- 2
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- 6' 49.0 51.6 8
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32.5 34.2 2 10 9.0 9.5 12 4
, 11 20.5 21.6 3
' 12' 22.5 23.7' -
13 '- 16.0 16.8 - 14 '13.5 14.2 3 15 61.0 64.2 2 16 8 17 6
*. Note (1) Liquid scintillation counter efficiency -95%
(2) Proportional counter results of fixed room componenets, fans sinks, exhaust etc. l r
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b . Table'4 Phase 3' . Cleanup Supey-J;g ,
. Data in DPM/100cm Floor - floor. '
Floor Grid:#' ,Arei.- Grid # Grid # fArea. . Area T l' ..- .13- .3 - 25. - 2' - 14' 8 26 - 3 -- 15 5 27 3 4 ;.-' 16' - 28' 82
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29 2 6 - 18 5 30 - 7- 5 19 -
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20 - 5 32 3
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- South West North East South West- ' North East
- Grid-f- Wall Wall Wall Wall. Grid # Wall : Wall- Wall Wall
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. i Table 5 Survey for Fixed 2
DPM/100cm Location Counts / minute (1) beta - gamma M111irem/hr l' 197 450 0.35 0.50 0.45 2 160 80 0.40 0.30 0.35 3 213 610 0.35 0.45 0.35 4 202 500 0.50 0.60 0.45 5 216 640 0.50 0.45 0.50 6 236 840 0.50 0.40 0.35 7 140 - 0.40 0.35 0.45 8 194 420 0.50 0.60 0.60 9 187 350 0.30 0.65 0.70 10 212 600 0.30 0.50 0.55 11 165 130 0.30 0.35 0.40 12 213 610 0.40 0.50 0.35 13 237 850 0.40 0.55 0.45 14 194 420 0.40 0.30 0.50 15 216 640 0.40 0.75 0.30 16 17 18 19 20 Background 152 0.40 0.30 0.35
- 1) Bicron Frisk-Tech with AB50 probe calibration - 5/25/89; assume 20% efficient, Tc 99 beta
- 2) Bicron - Microrem meter calibration - 5/25/89 I
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t 4 y.:- , : 4 GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE-OR.TERMINATI'ON OF LICENSES-FOR BYPRODUCT, SOURCE. OR SPECIAL NUCLEAR MATERIAL I U.S. Nuclear Regulatory Commission Division of Industrial and Medical Nuclear Safety Washington, DC 20555 l Auoust 1987 i 1 Mb' AM f Ic9h b ~
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 abandonment or talease for. unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for
.which the radiological considerations pertinent to their use may be different.
. 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 & survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort i 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.
- 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-tem storage or standby status.. Such requests must: j
- a. Provide detailed, specific infomation describing the premises, !
equipment or sc' rap, radioactive contaminants, and the nature, extent, ' and degree of rcsidual surface contamination.
- b. Provide a 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.
- c. Describe the scope of the survey and general procedures followed,
- d. 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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