ML20216B055
| ML20216B055 | |
| Person / Time | |
|---|---|
| Site: | 07000145 |
| Issue date: | 08/21/1997 |
| From: | Patricia Pelke NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| 301915, NUDOCS 9709050212 | |
| Download: ML20216B055 (69) | |
Text
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NR FORM 374 A g
Lim r4UCLEAR REGULATORY COMMISSION PAGE 1
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g License Number g
y SNM-159 g
y MATERIALS LICENSE Docket or Reference Numter k
g SUPPLEMENTARY SHEET 070 00145 g
N N
y Amendment No. 22
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Case Western Reserve University E
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Environmental Safety 5
N 10900 Euclid Avenue U
N Cleveland, OH 44106 E
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N In accordance with letters dated October'2; 1996fand2 March 5, 1997. License No. SNM 159 E
is hereby terminated.
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Appitcant/ Licensees CASE WESTERN RESERVE UNIVERSITY Received Date 961004 Docket No 7000145 Control No.:
301915 License No.:
SNM-159 Action Types Termination 2.
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CASEWESTERN RESERVE UNIVERSITY October 2,1996 Ms. Patricia Pelke Nuclear Materials Eranch U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351
Subject:
Termination of License # SNM-159
Dear Ms Pelke,
We request that our NRC license number SNM-159 be terminated. The last remaining material (35 mg U235) was disposed on May 9,1996. (See barrel #4 of attached waste manifest number 96-0149.)
Material previously used under th.. acense (16g Pu as a 1 Ci PuBe neutron sealed scurce) was disposed of in April 1995. Records of the April 1995 transfer of the PuBe to Los Ala.mos National Laboratories were inspected during our January 1996 NRC inspection by Wayne Slawinski.
Prior to August 1985 the U235 material was located in Smith 417. A confirmatory survey was performed of the room, even though it was remodelled several years ago into a classroom. A p_ncake G-M survey of the floor areas was performed to verify that no contamination.c radiation exists in this location. No wipe tests were conducted since the floor was covered with carpet. All direct surface probe readings -
were indistinguishable from background radiation levels. A copy of the survey is enclosed.
' A decommissioning survey was performed of the last known location of material use, which was in Smith 313A. The survey consisted of (1, Jirect probe reading of floors and benches in the room and (2) an extensive series of wipe tests for alpha contamination. Since all direct probe readings with a pancake Geiger-Meuller probe were indistinguishable from background, no reports of gamma radiation dose at three feet were required. A copy of the contamination survey is enclosed.
M RECEIVED M thd[NN OCT 0 41996 Department of Occupationa! & Environmental Safety b
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--f uwsa anonss vrsarus ano onMmts Phone 216-36te2906
ase Western Reserve Unrversity Service Bldg First Floor Fax 21 & 368-2236 fg }
2220 Circle Dr~e. best Floor Cleveland, Onio 44106-7227
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1 Page 2 Also enclosed is a copy of the survey instrument's calibration certificate.
We believe this provides all the information required for license termination in accordance with 10 CFR 70.38(j).
Should you have any questions, or require any additional information, please feel free to contact rne at 216-36S-2906.
Sincyrely,'.
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t W. David Sedwick, Ph.D., RSO Dr. Christopher Town, Radiation Safety Committee Chair xc:
Karl Von Ahn, Asst RSO Kenneth Basch, Asst. Treasurer Dr..Agnar Py.:c, President CWRU
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i SURVEY NFORETION SHEET CWRU Radiation Safety Office SURVEY METER NFORWT)ON Ludlum Model 140, SN 68174 Pancake G M Probe model 44 9 Recalibration due 6/17/97 DIRECT PROBE READING MOA CALCULATON MDA = (2XBKG. BKG)/ isotopic efficiency detector effclency caluelated with 2 Pi geometry at contact RADWT)ON LEVEL MEASUREMENTS i
All radiation level measuerments are to be made in units of mR/hr with an ion chamber when contamination survey meter readings are substantially above background.
Make:
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SN Unless indicated otherwise, all radiation level measurements are less thar.
mR/hr, with a normal background reading of m R/hr.
SURVEY MAP SYMBOLS circled number - wipe test areas. All are approximately 100 cm2 unless indicated otherwise.
- direct probe readings. All probe readings less than MDA unless indicated otherwise. Background reading 50 cpm.
s ISOTOPE
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Make:_
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SN Unless indicated otherwise, all radiation level measurements are less than mR/hr, with a normal background reading of mR/hr.
SURVEYMAP SWBOLS circled number wipe test areas. All are approximately 100 cm2 unless indicated otherwise.
- direct probe readings. All probe readings less than MDA unless indicated otherwise. Background reading -50@m.
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% EFF MDA IN DPM Pm147 13.23 378 C14/S35 5.62 890 Cl36 37.85 132 Co60 1.01 4545 Cs137
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ELECTRONIC CALIBR TION CERTIFICATE i
i Caw Western Rewrte University Department of Occupational and Endrnomental Safety Radiation safety Office Owner:
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Calibration Dalet b / / 7/ fY#
undei Number:- M k SN:_6679 Meter Manufacturer l_ U Dl.(/M Probe Types Model Number: N ~[
SN:_ $9 7 f2 Batteries Need Changing:
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Yes No input Sensitisity: 3O mv Post AdjustmentPost*
mR/h* Meter Scale Meter Reading Pulser Setting C.F.
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- f. llC 110 x 10 X 0.1 3,lX 300 x 1 X 0.1 f,;R 110 x 1 All Ranges Calibrated Electronically with Ludlum Model 500 Pulser SN 76517 Calibrated 7 5
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b Date:
Form ECAL a 10/95
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l AUG 211997 W. David Sedwick, Ph.D.
Radiation Safety Officer Case Western Reserve University Department of Occupational and Environmental Safety 10900 Euclid Avenue Cleveland, OH 44106
Dear Dr. Sedwick:
Enclosed is Amendment No. 22 which terminates your NRC License Number SNM 159 in accordance with your request.
If you have any questions or require clarification on any of the information stated above, you may contact us at (630) 829 9887.
S;ncerely, Orlpinal Si ned By 0
Petricia J. Polke Nuclear Materials Licensing Branch License No.: SNM 159 Docket No.: 070-00145
Enclosure:
Amendment No. 22 DOCUMENT NAME: M:\\ TERM \\07000145.T7 v1 e.c.ev.. copy or ini. ooeum.nt, inow.t. in in, bon c. copy wethe ie.ii chm conck>.ur. e. copy mth.ttachmenvenclosur. 4T'. No copy OFFICE DNMS/ Rill n
l NAME PJPelke:brt /,Qf DATE 08(AM/97 F OFFICIAL RECORD COPY f
3ol9/1 o
07/11/07 18:27 FL ~10 300 !!30 RADIATION Su r!T C002 I.
MDIORANDUM Tv:
Mike McCann From:
Karl Von Ahn, Asst. RSO Date:
July 11, 1997 RE:
S!O!-159 termination question follow-up The following points are to reiterate the items that we discussed earlier this afternoon.
Enclosed is a copy of the survey of room Smith 313A where a probe survey with a pancake GM probe was performed and outsnitted with our initial termination request in October 1996. The dashed lines are where probe surveys were taken, covering approximately 50% of the surface area.
The U-235 was used only as a tracer / standard in the Geology department and was not used in any processing activities. The 35mg of U235 was in an aqueous solution, which we evaporated to dryness at room tenperature. The U-235 was a residue on the inside of a bottle, and disposed as long lived waste in a waste drum for disposal at Barnwell S.C.
We have no records indicating that any other isotopes were ueed in these rooms.
The records of the Pu239-Be transfer shipment to IANL in April 1995 was examined by Wayne Slawinski during an NRC inspection of the SNM-159 license in Jan 1996. The leak test records prior to.
shipping and the shipping documentation did not indicate any removable contamination.
Should you have any additional questions, please call me at 216-368-2906, pena.iiw om.m.s a sa nw sem, Case nemme Urd orey peo0 rhet tocr
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SLR4YNFORMAT10NINEET CWRU Radation Saloty Omoe SURVEYMETRA MORMATION Ludium Model 140. SN 64;'.74 Pancake G M Probe model 44 8 Recal@etion due 8/17/87 DIRECT PROSCREADH3leACM.CULATION MDA = (2XSKG SKOM60lt,,pic effciency
, detector emclency celuclated w4th 2 PI geometry al contad RADMTION LEVE. MEASUREMENTS M todation level measuerments are to be made in units of m8Wr witi an ion chamber when contamination survey meter readings are substanitaly above badground.
Make:
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SN Urdess indicated otherwise al radiaton level measurements are less man mH/hr. with a normal back8round reading of
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SURWYMWSWOOLS circled number. wipe test areas. At are approximateY 100 cm2 Unless indicated otherwee.
- = drect probe seedn0s. As probe readn0s less than MOA unless indcated oiberwise Back0round readng.50@m.
ISOTOPE
% EFF MDA N DPM Pm147 13.23 378 C14/S35 5.82 890 Ct38 37.85 132 Coto 1.01 4545 Cs137
.74 8758 1125
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.42 5434 P32 40.82 122 St40/Y60 73.82 88 Test 18.82 288 81210 38.18 138 Th 230 10.73 488 Bal33
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IELEPHONE CONVERSATION RECORD PERSON CALLED:
W. David Sedwick, Ph.D.
Radiation Safety Officer (236) 368-2906 CALLER:
Mike McCann, Senior Radiation Specialist Decommissioning Branch DATEt June 27, 1997 (9 00 AM -
SUBJECT:
CASE WESTERN RESERVE UNIVERSITY, RIII QUESTIONS RESULTING FROH THE REVIEW OF CLOSE-OUT SURVEY INFORMATION EUBMITTED BY THE UNIVERSITY (MAIL CONTROL NO. 301915)
On the above date, I contacted Dr. Sedwick to discuss their close-out survey information. The following was discussed:
1.
What survey meter (s) was used to perform direct surface measurer,ents.
It appears to have been a microR meter? Or was the direct readinge taken with a count rate type instrument? Direct surface measurements (integrated) are taken at each location where a wipe wap collected.
Typically, the direct measurement is also in dpm/1p)0 cm, and the release criteria are cased on an average value (im, and maximum value.
For example, was the alpha probe used to take a fixed alpha measurement?
Also, was a surface scan of the areas performed using a GM large-area beta probe. This will cover all cases, as far as potential residual contaminations.
2.
Was the us2 of the u-235 limited to 333A7 What was done in 3177 What was the use of the U-2357 Was there a potential for contamination to be generated?
3.
What was the total amount of unsealed U-235 received? How was it used?
This would (if available) bound the quantity of material to have been used in these rooms.
5.
The ADCO waste manifesto show other BPM besides the U-235.
Were other materials used in this room? Were Beta measurements taken?
6.
As far as the Pu-239 sealed sourcero, confirm that they were leak tested and that no removable contamination had been identified while the sources were in use at the Univer;ait).
Af ter discussing the criteria and various guiitance documents with Dr. Sedwick, it was agreed that I would mail NUREG 5849 to the licensee.
I included with the mailing NUREGS 1500 & lbO1, and the NRC Branch Technical Paper for release criter.a for buildings and equipment.
Since the survey had been done by the Assistant RSO (Carl Von Ahn), who was on vacation at the time of my call, Dr. Sedwick could not readily answer all my questions.
Therefore we scheduled a conference call for July 11, 1997, af ter 2:00 PM to discuos this close-out survey, and expectations and criteria for the releaea of other locations in the future.
U 9
Case Western Reserve University I agreed to F'am.Dr. Sedwick a copy of this telephone conversation record.
His f ax number i s 216-368-2236. His E-mail address is WD80po.cwru.edu.
No further.
CC 3. Jorgensen, RIII P. Pelke, RIII License No. SNM-00159 Docket No. 070-00145 PUBLIC
U e* "88' p
U"JTED STATES 4
NUCLEAR RECULATORY COMMISSl!N n
y..
S REGloN lli l
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'I 801 WARRENVILLE ROAD
/
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ustr.stuNols60532 4351 i
.....j August 13, 1997 MEMORANDUM TO:
/K. G. Null, Acting Chief, Materials Licensing Branc FROM:
B. L. Jorgensen,, Chief, Decommissioning Branch
SUBJECT:
DECOMMISSIONING BRANCH REVIEW OF CASE WESTERN RESERVE UNIVERSITY'S CLOSE OUT SURVEY INFORM ATION As requested in Material Licensing Branch's June 12,1997, memorandum, we have reviewed the Case Western Reserve University survey information submitted as part of their request to terminate NRC License SNM 159. Based on our review, we have determined that the licensee has provided sufficient information such that we believe they have satisfactorily demonwnted that the building does not exceed regulatory contamination limits, and can be released for unrestricted use. We also do not believe a confirmatory survey of this buildi1g by the NRC is necessary.
The licensee's survey procedures and survey information were discussed during telephone conversations between the licensee's and Region 111 staff on June 27 and July 11,1997.
Should you or your staff have any questions, or need clarification of the above, please do not hesitate to contact me, Mike McCann or Peter Lee.
License No. SNM 159 Docket No.
070 00145 cc:
P. Palke, Rlli
t#"%
U"lTE3 STATES g,-
. Q[*g NUCLEAR RE!ULATORY COMMZSION REGION 111 U
'E 801 WARRENVILLE ROAD y
k, USLE. ILUNols 6o532-4351 JUN 121997
&(/
b MEMORANDUM FOR:
Bruce Jorgensen, Chief Decommissioni g Brpnch Cps' san)
M Chief
/
J FROM:
az Luclear M eriallLic(nsing Branch e'
SUBJECT:
TECHNICAL ASSISTANCE REQUEST FOR THE REVIEW OF A TERMINATION REQUEST SUBMITTED BY CASE WESTERN RESERVE UNIVERSITY Enclosed is a copy of the termination request submitted by Case Western Reserve University for License Number SNM 159. The license authorized the possession of a sealed plutonium beryllium neutron source and 70 milligrams of uranium 235 "in any form." Based on the information provided by the licensee, it appears that all materials possessed under the license were properly disposed. We requested that the licensee submit the appropriate documentation to address the items outlined in "Information That Should Be Submitted... for Decommissioning and Termination of Licensed Facilities" which we have included as an attachment.
In order to terminate the license, we request your assistance in the following:
1.
Review and evaluate the termination request provided to determine if a close out survey is required; 2.
If required, conduct a close-out inspection and confirmatory survey as appropriate; and 3.
Provide your recommendations for the release of the facilities for unrestricted use and license termination.
If you have any questions, please contact Patricia Pelke of my staff at extension 9868.
License No. - SNM-159 Docket No.
070-00145-
Attachment:
Letter w/ attachments dated October 2,1996 Letter w/ attachments dated March 5,1997 (received June 3,1997)
Deficiency letter dated January 22,1997 cc w/o attachment: R. Caniano, Rlli
_.c
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V 0-O-
1 U.
S. NRC, REGION III Lilse, IL TELEPHONE CONVERSATION RECQRQ PERSON CALLED:
W. David Sedwick, Ph.D.
Radiation Safety Officer (216) 368-2906 CALLER:
Mike McCann, Senior Radiation Specialist Decommissioning Branch DATE:
June 27, 1997 l
SUBJECT:
CASE WESTERN RESERVE UNIVERSITY, RIII QUESTIONS RESULTING FROM THE REVIEW OF CLOSE-OUT SURVEY INFORMATION SUBMITTED BY THE UNIVERSITY (MAIL CONTROL NO. 301915)
On the above date, I contacted Dr. Sedwick to discuss their close-out survey information.
The following was discussed:
1.
What survey meter (s) was used to perform direct surface measurements.
It appears to have been a microR meter?
Or was the direct readings taken with a count rate type instrument?
Direct surface measurements (integrated) are taken at each location where a wipe was collected.
Typically, the direct measurement is also in dpm/100 cm,
2 and the release criteria are based on an average value 2
(im ), and maximum value.
For example, was the alpha probe used to take a fi.ced alpha measurement?
Also, was a surface scan of the areas performed using a GM large-area bet, probe.
This will cover all bases, as far as potential residual contaminations.
2.
Was the use of the u-235 limited to 313A?
What was done in 317?
What was the use of the U-235?
Was there a potential for contamination to be generated?
3.
What was the total amount of unsealed U-235 received?
How was it used?
This would (if available) bound the quantity of material to have been used in these rooms.
4.
The ADCO waste manifests show other BPM besides the U-235.
Were other materials used in this room?
Were Beta measurements taken?
5.
As far as the Pu-239 sealed sources, confirm that they were leak tested and that no removable contamination had been identified while the sources were in use at the University.
When was the last leak test performed?
-U o
l 2
Case Western Reserve University After discussing the criteria and various guidance documents with Dr. Sedwick, it was agreed that I would mail NUREG 5849 to the licensee.
I included with the mailing NUREGS 1500 & 1501, and the NRC Branch Technical Paper for release criteria for buildings and equipment.
Since the survey had been done by the Assistant RSO (Carl Von Ahn), who was on vacation at the time of my call, Dr. Sedwick could not readily answer all my questions.
Therefore we scheduled a conference call for July 11, 1997, after 2:00 PM to discuss this close-out survey, and expectations and criteria for the release of other locations in the future.
I agreed to Fax Dr. Sedwick a copy of this telephone conversation record.
His fax number is 216-368-2236.
His E-mail address is WDS9po.cwru.edu.
No further.
y L
CC B. Jorgensen, RIII P. Pelke, RIII License No. SNM-00159 Docket No. 070-00145 PUBLIC
l h'/-
Wo-O y
U. S. NRC, REGION III Lilse, IL TELEPEONE CONVERSATION RECORD PERSON CALLED:
W. David Sedwick, Ph.D.
Radiation Safety Officer (216) 368-2906 CALLER:
Mike McCann, Senior l Radiation Specialist Decommissioning Branch DATE:
June 27, 1997 (9:00 AM -
July 11, 1997 (2pm)
SUBJECT:
CASE WESTERN RESERVE UNIVERSITY, RIII QUESTIONS RESULTING FROM THE REVIEW OF CLOSE-OUT SURVEY INFORMATION SUBMITTED BY THE UNIVERSITY (MAIL OONTROL NO. 301915)
On the above date, I contacted Dr. Sedwick to discuss their close-out survey information. The following was discussed:
1.
What survey meter (s) was used to perform direct surface measurements.
It appears to have been a microR mater? Or was the direct readings taken with a count rate type instrument? Direct surface measurements (integrated) are taken at each location where a wipe wag collected.
Typically, the direct measurement is also in dpm/1p)0 cm,
and the release criteria are based on an average value (im, and maximum value.
For example, was the alpha probe used to take a fixed alpha measurement?
Also, was a surface scan of the areas performed using a GM large-area beta probe. This will cover all bases, as far as potential residual contaminations.
July 11, 1997 The R50 and Assistant R50 indicated that an approximate 100% surface scan of the work areas were performed. They indicated that they would rend me survey results of these scans. I advised them that I would get back to them by next Wednesday.
2.
Was the use of the u-235 limited to 313A7 What was done in 3177 What was the use of the U-2357 Was there a potential for contamination to be generated?
July 11, 1997 This material was used as a reference source only. No chemical or physical process was performed.
3.
What was the total amount of unsealed U-235 received? How was it used?
This would (if available) bound the quantity of material to have been used in these rooms.
July 11, 1997 It was indicated that the 35 og was the total amount of material possessed.
O 5.
The ADCO waste manifeste show other BPM besides the U-235.
Were other materials used in this room? Were Beta measurements taken?
July 11, 1997 No other Byproduct material was usad in the rooms of concern. ite U-235 was 14corporated into a waste shipment containing radioactive waste from the University's other licenses.
8 As far as the Pu-239 sealed sources, confirm that they were leak tested and that no removable contamination had been identified while the sources were in use at the University.
July 11, 1997 The license indicated that Wayne slawinski checked these records during his 1996 inspection.
After discussing the criteria and various guidance documents with Dr. sedwick, it was agreed that I would mail NUREG 5849 to the licensee.
I included with the mailing NUREGS 1500 & 1501, and the NRC Branch Technical Paper for release criteria for buildings and equipment.
Since the survey had been done by the Assistant RSO (Carl Von Ahn), who was on vacation at the time of my call, Dr. Sedwick could not readily answer all my questions. Therefore we scheduled a conference call for July 11, 1997, after 2:00 PM to discuss this close-out survey, and expectations and criteria for the release of other locations in the future.
Case Western Reserve University I agreed to Fax Dr. Sedwick a copy of this telephone conversation record.
His fax number is 216-368-2236.
His E-mail addrosa is WDS0po.cwru.edu.
No further.
CC B. Jorgensen, RIII P. Pelke, RIII License No. SNM-00159 Docket No. 070-00145 PUBLIC
U O
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=
CASEWESTERN RESERVE'JNIVERSITY March 5, 1997 Patricia Pelke Nuclear Materials Licensing Branch U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 RE:
Control Number 01915 - Tel Aination of StM-159
Dear Ms. Pelke,
We request that our license number SNM-159 be terminated.
Additional information is provided to answer questions we received from you on Januar,y 27, 1997 in response to our original request for license termination dated October 2, 1996.
The radioactive materials used under the StM-159 license fell into two categories, scaled sources (PuBe) and a trace (35 mg,
- pproximately 100,000 dpm) of U235 in nitric acid (Uranyl Nitrate)
- r geological soil sal.iples.
Four of the 1-Curie PuBe sources were stored in out waste facility and transferred to Los Alamos National Laboratories in August 1991.
The remaining 1-Curie PuBe (which was used and stored in Rockefeller 218C) was transferred to Los Alamos National Laboratories in April 1995.
None of these sealed sources were leaking.
In regards to the U235, no record or evidence of any spills or contamination was identified.
Prior to l'.s85, the U235 was stored and used in Smith 417.
After 1985, the material was stored in Smith.s13A.
The uranyl nitrate was in 4.pproximately a nalf gallon of water.
After evaporating the water in the container in t: 0 Radiation Safety Office laboratory, the U235 was disposed ano sent to Barnwell, SC, via our waste broker ADCO Services.
As indicated in the attached decommissioning surveys, the survey of Smith 313A consists of (1) wipe tests, for removable contamination and dose measurements with an ion chamber at three feet from the floor.
Only dose rates were taken in Smith 417 since it was converted to a classroom in 1985-1986.
RECEIVED JUN 0 31997 oe
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i ELECTRONIC CALIB TION CERTIFICATE Case Western Reserve University Department of Occupational and Environmental Safety Radlation Safety Ofnee Owntn TC MR CalibrationDate: [/ /
Meter Manufacturen L U D E UM Model Numben O SN: /O b 7% f Probe Type:
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Yes N
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Comments:
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Model 43 2 SN PR104105 RELATIVEISOTOPIC EFTICIENCY Isotope DPM net CPM CPM /DPM Ratio
% Efficiency NIST or Estimated Th 230 15,300 2753
.18 18 NIST 1
DIRECT PR DING MDA CALCULATION -
MDA = (2XBKG - BK f topic efficiency detector efficiency calculate
'th 4 Pi geometry Background reading = 4 cpm D.nc.mOh ISOTOPE
% EFF IN DPM Th230-18.0 Certificate of calibration for Th230 source used for efficiency calculation is attached.
Isotope and efficiency calulations performed by:
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Date: Nf4[97 1
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Fladiation standards and check sources 2810 Siler Lane Santa Fe, NM 87501 (505)473 9538 FAX (505)473 5805 Certificate of Calibration
/
(Alpha Source)
The
'!horh n n o in a gss proportional counter using P 10 as counting gas _ alpha source was emissions from the surface of the source were measured The alpha voltage to determine its 2x cpm rate.
plateau background, colncidence loss and backscatter factots whCorrections were Alpha standard _
90'm4704627A en applicable.
source used in establishing NIST traceability._ is our WIST referenced R EF.PO#.
AA414 Active Diameter (or area)- 19m Mounting MaterlaL Total Diameter (or area)- 22m Thickness _
ss 8,000
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_ cpm.t_ t 400 0.00712
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_cptn 2x 790 08-31-93
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_ date of measurement s.01 source serial number
_overall uncertainty (percent)
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Michael A. Ortiz Calibration Manager
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Charles L Gor ales less than 20 Quality Assurance Manager teak test results (dpm / source or100cm )
2 The overall uncertainty of the measurement is three time found from combining quadratically'the sum of the over ll s the value reported by HISTilnAho radioscilvity measurements assurance a
uncertainty program; the standard deviation of the mean for the NIST standard measured in the system used for calibration and the standa d deviation of the mean for the source measur;ements as r
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Survey Meter Calibration Report / Certificate of Calibration Customer CASE WESTERN RESERVE UNIVERSITY Cust PO # HC4759P Victoreen # Repair 44826 Model-450 P Serial # 2462 l
CALIBRATION NOTES Radiation levels are based on sta'ndards whose calibrations are traceable to the N.I.S.T..
The suggested re-calibration date is only a suggestion.
The actual frequency of re-calibration may vary depending on Federal, state or local requirements.
It is up to the user to determine this.
During calibration the survey' meter was positioned with the detector perpendicular to the beam axis.
The source used for calibration was Cs-137.
All readings below 10 mR/h were corrected for Background Radiation.
-The formula for 7. Error ist
(( Reading
-Rate ) / Rate ) X 100 IMPORTANT Any corrections made to'the instrument reading ( e.g.
Energy Dependence ) are up to the user to apply.
Care must be used in applying those factors.
1 The test response data.is on page two (2) of this report.
6000 Cochran Road develand. Oh6o 44139 3395 (216)248-9300 fax (216) 248 930 DATA (2 t6) 248-9043 (1)
Victcre:n, Inc.
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% Error Comments (uR/h)
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0 - 500 N/A 13 N/A 390 407 4.36 Cal Point 129 130 0.78 (mR/h)-
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Suggested re-cal due 09-Dec-97 Traceable to the N.I.S.T.
Test No. DG9852/95 Dated Jan. 25,1995 PTW Chamber Model N23331 Serial No. 174 6000 Cochran Road -
Temperature 21.2 *C Cleveland. Ohio 44139 3395 (zi6) 248-93oo Humidity 39 %
fax (216) 248-930i DATA (216) 248-9043 4
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SNM-159 MDA Calculation Meter : Ludlum Model 2200 Scalar Serial Number 106743 with alpha probe Ludlum Model 43-2 5 minute integrated count time background count rate of 4 counts / minute 2.71 + 4.65 44*5 MDA for Th230 =
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caoooo UNCIASSIFIED cococo c'4/19/7 5 J.S. DEPARTMENT OF ENERGY AND C" n NUCLEAR REGUIATORY COMMISSION DOE /NRC FORM 741 NUCLEAR MATERIAL TRANSACTION REPORT PAGE 1 OF 3 PAGES TRANSFER SERIES: ZDD -AUA -000002
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1 1.LHIP-RIS 2.RCVR-RIS
- 3. TRANSFER-NO
- 4. CORR-NO
- 5. PROCESS-CODE
- 6. ACTION-CODE COPY 1 OF 3 COPIES ! DISTRIBUTION
- DB AUA 000002 SHIPPER :
OF COPIES RECEIVER: A B
- 1. AUA -ZDB 1
- 2. AUA -QFA
! O.A NAME/ADDR OF SHIPPER 110.A NAME/ADDR OF RECEIVER I 11.NO OF DATA LINES
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- 13. SHIP FOR ACCT (ZDB ) 114. SHIP TO ACCT (XXXX)
! UNIVERSITY
! GROUP FSS-12 MS-E508 1
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! QUAIL SAFETY OFFICE P.O. BOX 1663
! CASE WESTERN RESERVE I
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! CLEVELAND OH I I4S ALAMOS NM i UNIVERSITY 16.
I 44108 87545 I QUAIL SAFETY OFFICE
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13 U.C.C. SECTION 1001: ACT OF JtJNE 25 1948: 62 STAT. 749 MAKES IT A CRIMINAL OFFENSE TO MAKE A WILLFULLY FAISE STATEMENT OR REPRESENTATION TO ANY DEPARIMENT OR AGENCY OF,THE UNITED STATES AS TO ANY MATTER WITHIN ITS JURISDICTION
- UNCLASSIFIED ******
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~
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~C4/19/25 U.S. DEPARTMENT (F ENERGY AND U.S. NUCLEAR REGUIATORY COfeUSSION-DOE /NRC FORM 741 NUCLEAR MATERIAL TRANSACTION REPORT PAGE 2 OF ' 3 PMBES TRANSFER SERIES: ZDS -AUA -000002 g-
! 24. SHIPPER'S DATA
! A. SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED:
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. WEIGHT IDE PERCENT WEIGNT IDE !
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RECEIVER REMARKS GC1 IAN#1986;NMT-4;ACCTf 777;PROJf 380;IDESfM324;COEIf 781; L-GC2 1
1 PU-BE NEUTRON TEST SOURCE (ERN RESERVE COLLEGE (ZDB);
PRIVATELY OWNED) DONATED TO IDS AIAMOS(AUA) BY CASE WEST GC3 1
GC4 REF: RECEIVING PIAN / CAT-IV SEALED NEUTRON SOURCES 4/1/93 GC5 AJ/ EXT-INf 596337;AB/TRANSf 598868 AND #598885.
i 18 U.S.C. SECTION 1001; ACT OF JUNE 25 1948; 62 STAT. 749 MAKES IT A CRIMINAL CFFENSE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATION TO ANY DEPARTMENT OR AGENCY OF,THE UNITED STATES AS TO ANY MATTER WITHIN ITS JURISDICTION
- UNCIASSIFIED ******
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~
- UNCIASSIFIED **@***
04/19/05 U.S. DEPARTMENT OF ENERC,Y AND U.S. NUCLEAR REGUIAiVRY COfttISSION DOE /NRC FORM 741 NUC12AR MATERIAL TRARSACTION REPORT PAGE 3 0F ' 3 PAGES - -
TRANSFER LERIES: ZDB -AUA -000002 RECEIVERS ITEM AND PARTS DETAIL INFORMATION SEQ LE ASMBLYS PROJECT O PRCNT CONP TY MET ELENENT WElGFf-ISO 1V.rE EIDE ISTPE DECAY C'
NO. VN ITEM IDENTIFICATION ITEMS SUBS NUMBER ' C ASSAlf CODE IC MT WEIGHT NEIGHT PERCENT WEIGMT IDE IDE DATE SL F 001'32 M222 00 00 AGE 0348060 G 781 52 16.00 6.2000.
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- UNCIASSIFIED ******
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'JAN 2 21997 W. David Sedwick, Ph.D.
Radiation Safety Officer Case Western Reserve University Department of Occupational and s
Environmental Health 10900 Euclid Avenue Cleveland, OH 44106
Dear Dr. Sedwick:
We have reviewed the information submitted in your October 2,1996 letter requesting termination of NRC License No. SNM-159 and find that we will need additional information in order to terminate the license. Enclosed you will find a copy of "Information that Should be Submitted... for Decommissioning and Termination of Licensed Facilities" which identifies the information that needs to be provided in order to review your request for license termination. Please resubmit your termination request in acccrdance with the enclosed guidance. Note that this is relatively new guidance that has only recer:tly been available.
We will continue our review upon receipt of this information. Please submit your response, in duplicate, within 30 days and refer to Control Number 01915. If you have any questions, please contact me at (630) 829-9868.
Sincerely, 4
/
Original Signed By Patricia J. Pelke Nuclear Materials Licensing Branci.
License No. SNM-159 Docket No. 070-00145
Enclosure:
Termination / Decommissioning Packet DOCUMENT NAME: M:\\07000145.DF7 To receive a copy of tNs document. Indicato ir. the box: "C" = Copy without enclosures "E" = Copy with enc'osures "N" = No copy OFFICE DNMS/ Rill hG l
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l NAME PPELKE: jaw /'F DATE 01/7/97
~V OFFICIAL RECORD COPY J
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i CASEWESTERN RESERVE UNIVERSITY October 2,1996 f
Ms. Patricia Pelke Nuclear Materials Branch U.S. Nuclear Regulatory Commission
[Q 801 Warrenville Road Lisle, IL 60532-4351 V
Subject Termination of License # SNM-159
Dear Ms Pelke,
We request that our NRC license number SNM-159 be terminated. The last remaining material (35 mg U235) was disposed on May 9,1996. (See barrel #4 of attached waste manifest number 96-0149.)
Material previously used under this license (16g Pu as a 1 Ci PuBe neutron scaled source) was disposed of in April 1995. Records of the April 1995 transfer of the PuBe to Los Alamos National Laboratories were inspected during our January 1996 NRC inspection by Wayne Slawinski.
Prior to August 1985 the U235 material was located in Smith 417. A confirmatory survey was performed of the room, even though it was remodelled several years ago into a classroom. A pancake G-M survey of the floor areas was performed to verify that no contamination or radiation exists in this location. No wipe tests were conducted since the floor was covered with carpet. All direct surface probe readings were indistinguishable from background radiation levels. A copy of the survey is enclosed.
A decommissioning survey was performed of the last known location of material use, which was in Smith 313A. The survey consisted of (1) direct probe reading of floors and benches in the room and (2) an extensive series of wipe tests for alpha contamination. Since all direct probe readings with a pancake Geiger-Meuller probe were indistinguishable from background, no reports of gamma radiation dose at three feet were required. A copy of the contamination survey is enclosed.
RECEIVED OCT 0 41996 3
Department of Occupational & Environniental Safety
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- f REGION III WWG ADOMiss verCRS ANoofuktmES Phone 216-366-2906
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Case Westem Reserve University Service Oldg First Floor Fax 216 368-2236 O
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2220 Circle Drive First Floor Cleveland. Onio 4410G-7227
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1 Page 2 Also enclosed is a copy _of the survey instrument's calibration certificate.
We believe this provides all the information required for ilcense termination in
' accordance with 10 CFR 70.38(j).
Should you have any questions, or require any additional information, please feel free to contact me at 216-368-2906.
Sincerely,3 7
l l
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W. David Sedwi k, Ph.D., RSO Dr. Christopher Town, Radiation Safety Committee Chair xc:
. Karl Von. Ahn, Asst. RSO Kenneth Basch, Asst. Treasurer Dr. Agnar Pytte, President CWRU
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Make:
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Calibration Date: b _/ f 7/
Meter Manufacturer: [VbbUM Model Number:
IG SN:hhhI Probe Type:_
ModelNumber: N i SN:_ 89 7 f_2-Batteries Nced Changing:_
Yes _V No High Voltage:
O, k ku Internal Adjustment Required:_ Yes No input Sensitivity: 3O mv Post AdjustmentPost*
mR/h Meter Scale Meter Reading Pulser Setting C.F.
Meter Readino mR/h 3 /\\
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110 x 10 X 0.1
- 3. / X 300 x 1 X 0.1 LIR 110 x 1 All Ranges Calibrated Electronically with Ludlum Model 500 Pulser SN 76517 Calibrated 7 5
-O mR/h readings are NOT dose readings, but are only visual readings from the meter fxe.
Comments:
g4p 50fm ff J V C [E D f E S Q 05' "'&I VE '
Calibrated By:
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Date:
Form ECAL a 10/95
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CASEWESTERN RESERVE UNIVERSITY March 5, 1997 Patricia Pelke Nuclear Materials Licensing Branch U.S. Nuclear Regulatcry Commission 801 Warrenville Road Lisle, IL 60532-4351 RE:
Control Number 01915 - Termination of SNM-159
Dear Ms. Pelke,
We request that our license number SNM-159 be terminated.
Additional information is provided to answer questions we received from you on January 27, 1997 in response to our original request for license termination dated October 2, 1996.
The radioactive materials used under the SNM-159 license fell into two categories, sealed sources (PuBe) and a trace (35 mg, approximately 100,000 dpm) of U235 in nitric acid (Uranyl Nitrate) for geological soil samples.
Four of the 1-Curie PuBe sources were stored in our waste facility and transferred to Los Alamos National Laboratories in August 1991.
The remaining 1-Curie PuBe (which was used and stored in Rockefeller 218C) was transferred to Los Alamos National Laboratories in April 1995.
None of these sealed sources were leaking.
In regards to the U235, no record or evidence of any spills or contamination was identified.
Prior to 1985, the U235 was stored and used in Smith 417.
After 1985, the material was stored in Smith 313A.
The uranyl nitrate was in approximately a half gallon of water.
After evaporating the water in the container in the Radiation Safety Office laboratory, the U235 was disposed and sent to Barnwell, SC, via our waste broker ADCO Services.
As indicated in the attached decommissioning surveys, the survey of Smith 313A consicts of (1) wipe tests for removable contamination and dose measurements with an ion chamber at three feet from the floor.
Only dose rates were taken in Smith 417 since it was converted to a classroom in 1985-1986.
RECEIVED JUN 0 31997 Department of Occupational & Environmental Safety bhfh ff wtwo accarss psirons w otovews Phone 216-368-2906 Case Western Reserve University Service Bldg 'irst Floor Fax 216-368-2236 2220 Circie Dnve. First Floor Cleve6and, otuo 44106 7227 l
JUN 0 3 W i
A
W L
Dose rate readings were taken three feet above the floor with a Victoreen 450P SN 2462 pressurized ion chamber.
The background of the meter was 10 microRad per hour.
All dose readings were indistinguishable from background.
Wipe tests for removable contamination were performed as indicated on the att(.hed survey map.
The samples were analyzed with an alpha probe (model 43-2) on a Ludlum Model 2200 single channel analyzer.
The MDA for 100 cm2 wipes was 26 dpm.
For our calculations, the counting efficiency for alpha particles was based on an NIST traceable Th230 alpha standard.
The survey criteria for releasing an area for unrestricted use were:
surveys for fixed contamination and dose rates at three feet were indistinguishable from a background dose rate of 10 uR/hr.
any loose removable contamination was less than 50 dpm/100cm2 (5% of the required action levels for removable U235 alpha contamination).
The accompanying verification of the last licensed material disposed are copies of:
(1) Manifest #96-0149 dated 5-9-96 for the 35 mg of U235 and (2) NRC Form 741 dated 4-19-95 for the PuBe source disposal.
Sincerely yours, i
' Gyt*
W. David Sedwick Radiation Safety Officer
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Model 43 2 SN PR104105 RELATIVE ISOTOPlc EFFICIENCY Isotope DPM net CPM CPM /DPM Ratio
% Efficiency NIST or Estimated Th 230 15.300 2753
.18 18 NIST DIRECT PR ADING MDA CALCULATION MDA = (2XBKO BK topic efficiency detector efficiency calculate
'th 4 Pi geometry Background reading = 4 cpm.
CLsn eOh ISOTOPE
% EFF N DPM Th230 18,0 Certificate of calibration for Th230 source used for efficiency calculation is attached.
Isotope and efficiency calutations performed by: b vu de- { Date:. /leff7 r
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Radiation standards and check sources 2410 Siler Lane Santa Fe, NM 87501 (505)473 9538 FAX (505)473 8805 Certificate of Calibration
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The hrh= 210 in a gas proportional counter using P 10 as counting gas._ alpha source was m voltage to determine its ta cpm rate. emissions from the surface of The alpha Corrections were applied for background, coincidence loss and backscatter factors when applicable Alpha standard 90ZH4704627A l
source used in establishing NIST traceability._ la our NIST referenced REF.PO#
AA414 Active Diameter (or area) 19m Mounting Mat Total Diameter (or area)_
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_ date of measurement 5.01 source serial number i
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Survey Meter Calibration Report / Certificate of Calibration-Customer CASE WESTERN RESERVE UN! VERS!TY Cust PO # HC4759P Victoresn # Repair 44826 Model 450 P Serial # 2462 CALIBRATION NOTES Radiation levels are based on standards whose calibrations are traceable to the N.1.S.T..
. The suggested re-calibration date is only a suggestion.
The actual frequency of're-calibration may vary depending on Federal, state or local requirements.
It is up to the user to determine this.
During calibration the survey meter was positioned with the detector perpendicular to the beam axis.
The source used for calibration was Cs-137.
All readings below 10 mR/h were corrected for Background Radiation.
The formula for */. Error ist
(( Reading - Rate ) / Rate ) X 100 IMPORTANT
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The test response data is on page two (2) of this report.
6000 Cochten Road Ckwland, OhW 44139 3395 (216)248-9300 FAX (216) 248-9301 DATA (216) 248 9043
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% Error Comments (uR/h)
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Test No. DG9852/95 Dated Jan. 25,1995 PTW Chamber Model N23331 Serial No. 174 6000 Cochran fload Cleveland, Ohio 441391395 Tamperature 21.2 *C (216)248-9300 Humidity 39 */.
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- * * * *
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-04/19/95 U.S. DEPARTMENT OF ENERGY AND U.S. NUCLEAR REGULATORY COMMISSION DOE /NRC FORM 741 NUCLEAR MATERIAL TRANSACTION REPORT PAGE 2 OF 3 PAGES TRANSFER SERIES: ZDB -AUA -000002 t
! 24. SHIPPER'S DATA
! A. SIGNATURE OF AUTHORIZED OFFICIAL AND DATE SIGNED:
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'JAN 2 81997 W. David Sedwick, Ph.D.
Radiation Safety Officer Case Western Reserve University Department of Occupational and Environmental Health 10900 Euclid Avenue Cleveland, OH 44106
Dear Dr. Sedwick:
We have reviewed the information submitted in your October 2,1996 letter requesting termination of NRC License No SNM 159 and find that we will need additionalinformation in order to terminate the license. Enclosed you will find a copy of "Information that Should be Submitted... for Decommissioning and Termination of Licensed Facilities" which identifies the information that needs to be previded in order to review your request for license termination. Please resubmit your termination request in accordance with the enclosed guidance. Note that this is relatively new guidance that has only recently been available.
We will continue our review upon receipt of this information. Please submit your response, in duplicate, within 30 days and refer to Control Number 01915. If you have any questions, please contact me at (630) 829 9868.
Sincerely, b
Original Signed By Patricia J. Pelke Nuclear Materials Licensing Branch License No. SNM 159 Docket No. 070-00145
Enclosure:
Termination / Decommissioning Packet DOCUMENT NAME: M:\\07000145.DE7 To receive a copy of this document, Indicate in the box: "C" = Copy without enclosures
- E" = Copy with enclosures "N" = No sory OFFICE DNMS/ Rill 3G l
NAME PPELKE: jaw /##
DATE 016//97
' r' OFFICIAL RECORD COPY 1
--_ ____u
O O
am:g*,
uana sans NUCLEAR RECULATORY COMMISSION S-REGION lli Ei 8
801 WARRENVILLE ROAD USLE. ILUNOIS 60632-4351 October 8.- 1996 W. David Sedwick, Ph.D.
Radiation Safety Officer Case Western Reserve University De)artment of Occupational &
Environmental Safety 10900 Euclid Avenue Cleveland. OH 44106 SUBJ.ECT: ACKNOWLEDGEMENT OF CORRESPONDENCE (Letter Dated 10/02/96)
Dear Licensee:
-In-response to your request, we have completed the initial processing, which is an administrative review of your application for a(n):
New License Amendment Renewal X Termination Auth User (Amendment not required)
Other No administrative deficiencies were identified during this initial review.
However, it should be noted that a technical review may identify omissions in the submitted information.
It appears that your request is routine (see 1-3 below, as applicable).
1.
New and amendment actions are normally processed within 90 days, unless we find major deficiencies, or policy issues requiring central program office assistance.
2.
Renewal actions are normally processed within 180 days, however, under timely filing-(before expiration). you may continue to operate under your existing license.
3.
Termination actions -are normally processed within 90 days, unless confirmatory surveys following decontamination / decommissioning activities are' involved.
A copy of your correspondence has been forwarded to our Licensing Fee and-Debt Collection Branch (301/415-6097) for approval of the fee category and amount if required.
If you have a compelling safety or business-related reason for requesting expedited review. please contact the Materials Licensing Branch at (630) 829-9887.
We will try to complete your request as soon as practicable.
Any correspondence about this request should reference the control number.
Nuclear: Materials Support Branch Mail Control No. 301915 License No. SNM-159 I
0