ML20210K893
| ML20210K893 | |
| Person / Time | |
|---|---|
| Site: | 07000008 |
| Issue date: | 07/21/1999 |
| From: | Mccann G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| NUDOCS 9908060248 | |
| Download: ML20210K893 (19) | |
Text
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u . NUCLEAR RETULAToRev CoMM!sSloN MATERIALS LICENSE CORRECTED COPY Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and spccial nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license !
shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all I cpplicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafterin effect and to any conditions specified below.
Ucensee in accordance with the letter dated l January 11,1999
- 1. B:ttelle MemorialInstitute 3. Ucense number SNM-7 is amended in Bittelle Columbus Operation Jts entirety as follows:
- 2. 505 King Avenue 4b
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- 4. Spilatign date April 30,1988 (on timely renewal)
Columbus, OH 43201-2693 5. Docket Nkt)7p00008 Referer,ce No. Q
- 6. Byproduct, source, and/or special 77 Chemical and/or physical form ' 8. M ' mum amount that licensee may nuclear material 9 4 s ess at any one time under this W j; N*t"f' West Jefferson Site h 4 - p/e Ip\ . , ::la O l
<t SV gQ [ ~A A. Uranium enriched inghe .' Ariy - ,.d Q < , A. k25 grams of contained U-235 isotope -Irradged y ,
p gg .5-235 plus the associated
, { t
{,' .and unseparated plutonium B. Uranium enriched in t '
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B.g@20 grams of contained s U-235 U-235 isotope - Unirradi pd .
y C. Uranium enriched in the b /fC. Plated /$ealed Sources . 1 gram of U-235 total U-235 isotope -Unirradiated O D. Plutonium (any principal isotope Pu-236-244)
D. nyk k k D. 0.1 gram total E. Plutonium (Pu-238 principa; E, Solid Oxide, with multiple E. 10.3 grams isotope) constrainments F. Plutonium (Pu-239 principal F. Solid Metal or Oxide, with F. 17.0 grams isotope) multiple constrainments G. Neptunium-237 G. Sealed Source G. 1.0 microcurie T H. Plutonium (Pu-238 principle H. PuBe Source H. 0.053 grams ij isotope) l 1. Plutonium (PU-238 principal 1. Solid Scrap 1. 3.4 grams f isotope) [
l J. Plutonium (Pu-239 prir',cipal J. Solid Scrap 3.0 grams
- U* t% t' r, n m e 9908060248 990721 ,-
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PDR ADOCK 07000008 -
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I NRC FORM 374A u S. NuCLER RE;tR.ATORY COMMISSION PAGE 2 of 9 PAGES Ucense Number SNM-7 MATERIALS LICENSE W or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17 CORRECTED COPY
- 6. Byproduct. source. and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license K. Uranium 232 K. Any K. 0.99 grams L. Uranium 233 L. Any L. 0.99 grams !
M. Uranium 234 M. Any M. 0.09 gram N. Uranium 235 N. yg REGg N. 0.99 grams O. Plutonium 236 O Any d 0g 4 / O. 0.04 micrograms P. Plutonium 238 D P. Any S 0.6 micrograms Q. Plutonium 239 Any g > Q@.82.0 4 micrograms R. Plutonium 240 lu ny l'/<g l ? R. cj!2.0 micrograms S. Plutonium 242 S.
y /c Q \
ij S. Q.4 micrograms
< c
- _a T. Any byproduct material is
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,000 curies total, not g j've .31 ore than 5,000 curies of
$d T poieME F
. f%te'r!alsp/
9 /'
wny one radioisotope Q '
I 4(excluding items 6.U.
C t- a '
N9 4 through 6.11. below) h ;e F.
Y %
U. Hydrogen-3 / Ariy (p.
U.
k%.n'
.- 500 curies V. Polonium-210 f2. ny V. 500 curies W. Califomium-252 W. nyk k W. 500 curies X. Sulfur-35 X. Gas X. 1,000 curies Y. Chlorine-36 Y. Gas Y. 1,000 curies Z. lodine-131 Z. Any Z. 1,000 curies AA. lodine-129 AA. Any AA. 60 curies BB. Cobalt-60 BB. Any BB. 5,000 curies l
CC. Cesium-137 CC. Any CC. 5,000 curies
)
l DD. Strontium-90 DD. Any DD. 5,000 curies EE. Carbon-14 EE. Any EE. 2 curies FF. Krypton-85 FF. Gas FF. 500 u
NRC FORM 374A u.S. NuCLD RE!uLAToRY CoMMISSloN PAGE 3 of 9 PAGEs Ucense Number SNM-7 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17 CORRECTED COPY
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license GG Americium-241 GG. Any GG. 10 millicuries HH. Nickel-63 HH. Any HH. 600 millicuries ll. Any byproduct material ll . Any ll. 500 millicuries total not to exceed 100 millicuries per g g REGg radionuclide Kina Avenue Site gV 47 JJ. . Uranium (enriched in JJ. residual contamination @J. 10 micrograms of contained U-235 isotope, irradiated ~ 9 U-235 plus the associated O s 3 A and unseparated plutonium Lu % .o .J cpnd mixed fission products KK. Any byproduct msthal
< .)
'y
@e
/
f'N' v 22 A KK. 600 curies total, not more K{5 - .thu Q M ' 3 Dan 35 curies of any or.e f--
U) gp::f J
,3 gy
,Q' 4:h pdioisotope
/
West Jefferson and Kina Avenue h c/ / ~
Site, O . /' M Q,g
@ ,Ls F LL. Any Source Material y/
L gy , ag f,f '. L(e 50 kilograms Temporary Job sites o 4
MM. Nickel-63 MM.hgd so Jrcepgkered MM. 600 millicuries total. No pursuanfN10 CFR 32.210 single source to exceed 40 and incorporated into gas millicuries.
chromatograph and/or aerosol /airbome contaminant gas and vapor detector as specified in item 10.
NN. Americiurn-241 NN. Sealed sources registered NN. 500 millicuries total. No pursuant to 10 CFR 3? 210 single source to exceed 50 and incorporated into gas millicuries.
chromatograph and/or aerosol /airbome contaminant gas and vapor detector as specified in item 10.
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NRC FORM 374A "
u.s. NUCLKR RE!uLAToRY COMMISSION PAGE 4 of 9 PAGES Ucense Number j SNM-7 i l
MATERIALS LICENSE h r Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17 )
CORRECTED COPY
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license
- 00. Hydrogen-3 00. Titanium tritide sources 00. 3 curies total. No single registered pursuant to 10 source to exceed 200 CFR 32.210 and millicuries. l incorporated into gas l chromatograph and/or l aerpl/agbg 8
I I
$ 6ntaminant gas arld'vgpor g V detector as specified in 4 item 10.
+y O PP. Americium-241 - PP. Sealed sources repisiereMPl@ 400 millicuries total. No O pursuant to 10 CFRyp 10 A single source to exceed 100 uj pnd, incorporated)nto j gillicuries.
F- gup,ing sag h g ;
q cine l I m 1, q QQ. Cosium-137 F" g E steied/ ;QQ. 300 millicuries total. No y) rsua -single source to exceed 50 nifI ,n}[of CFF}G2,21[0.p Nillicuries.
RR. Americium-241 Q
M Y
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D M
RR. Seale r Model One source not to exceed ry No.131)"qe (cpi 0(RR. [i 50 millicuries Yh
- 9. Authorized places of Use:
l A. License materials may be used and stored in buildings and facilities approved by the licensee's I Radiation Safety Committee, at sites indicated above under items 6,7, and 8. The licensee will l
submit final status surveys for buildings or areas which are to be released for unrestricted use via a license amendment.
l B. Licensed materials listed in Subitems MM., NN., OO., PP., Q. and RR. may be used at temporary job sites of the licensee anywhere in the United States where the U.S. Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material. The possession of these devices are in addition to devices authorized under Subitem KK.
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NRC FORM 374A u.s. NuCCEAR REIuLAToRY doMMissioN "
PAGE 5 of 9 PAGEs Ucense Number SNM-7 MATERIALS LICENSE om or Rem Nume.r SUPPLEMENTARY SHEET 070 4 0008 Amendment No.17 CORRECTED COPY CONDITIONS
- 10. Authorized use:
A. For use in accordance with statements, representations, and conditions contained in the following portions of the licensee's application for renewal (BCL Document 1081) submitted by letter dated October 23,1981, except as may be modified by the conditions of this license:
- 1. Pages vi through xi, Introduction; 2.
3.
Part I, License Conditions; 4g REG Appendix A, Radiologic (1!$fety Committee Cha erbiggf
- 4. Le+ters dated June 29~>1994, August 19,1994, July 6,1995 (excluding item 1), and August 3, 1995 (excluding I n)1).. O B.
Items E, F, I and J apy auh$'rized for storage only. .q 4 C. The principal use items A. 3d li'u de(Conhitions ,hnd 8, are9s residual contamination at j the West Jefferso orth Site.
/'- Vp O MU ~ .flut4 J
" A g D. Item U .may be uded for tri -
gte in leie dated Jug 21,1999, and as resid material arising froto previo ' p [ E. The principal uses fki em Dio '
- r. are use [fresidual contamination at l BMI's King Avenue ahtf We < D l f
F. Item H. under Conditions used for calibration. 627 andicense trans 8 have }h '*ferred from DOE inventory to be to; G. Items K. through S.. are for resea a de op n nd support of Radiological Laboratory Operation as described in letters dated November 17,1994, March 21,1995, and October 20,1997. , l H. Item FF. is for storage only pending disposal. j
- l. Items GG., HH., and ll.. are for research and development activities as described in letters dated June 29,1994 August 19,1994, and March 21,1995.
J. Item RR. is for use in a Campbell Pacific Nuclear Model 503 portable moisture / density gauge. 1 K. Item EE. is to be used for research and development as described in 10 CFR Part 30, Section 30.4. L. Items MM., through OO. of items 6,7, and 8 are for use in compatible gas chromatograph devices and or aerosol /airbome contaminant gas and vapor devices which have been registered pursuant to 10 CFR 32.210 and distributed in accordance with an NRC or Agreement State specific license to persons specifically licensed by the NRC to receive, possess and use the de
NRC FORM 37!.A u.s. NuCLER RE!uLAToRY Commission PAGE 6 of 9 PAGEs Ucense Number SNM-7 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070 4 0008 Amendment No.17 CORRECTED COPY M. Items PP. through RR. are for use in compatible moisture / density gauges which have been registered pursuant to 10 CFR 32.210 and distributed in accordance with an NRC or Agreement State specific license to persons specifically licensed by the NRC to receive, possess and use the i devices l
- 11. The Radiation Safety Officer for this license is Craig E. Jensen.
- 12. Notwithstanding Table 111 ano Table IV presented in Part I, Sections 3.4 and 3.5, for the release of l materials, equipment, and facilities for ugestrict[d ub,@eff' lensee shall adhere to the provisions of the attached " Guidelines for Decontantnkton i of Facilities and Eqt/tpgent Prior to Release for Unrestricted Use of Termination of Licenses (prByproduct, Source, or SpeciaTNpclear Material," dated April 1993. !
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- 13. Item 10 above incorporatedMppendix A (Radiological Safety Com ittee%harter) of the licensee's renewal application (BClc,J08Qs' c,ondition of the licensejo, jfy and! define more fully administrative procedurg for revie val and audit of acti' ies covere by the license, as described in Section 131nd Secti art 3FDje licie vision to the provisions of Appendix A, based upb written eva f th6 thanges(n'"
Say out NRC a$ oval mak i' it is determined that such changes will not chcrease eMff nes's of " ee in carryig out its functions. Revisions to the Chartbrand su it su%mItted to thq Director, Division of Fuel Cycle Safety and Safeg0ards, . cop / toThe R egig,ill Office, NRC, within 60 rpirlistrstor,C days following such chan es. )
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- 14. In addition to the subjects'fc}entifi L p u 11 lonalg}A' adia@ pendix expos A,s the an60alof radioactive and releases review and appr facilities material overshallinclude the past year with an egard as'!(ey)me to main
" tsuch of elpos nd releases as low as is reasonably achievable, as stated &So ion 20.1101,10 CF3 Part 0.
A
- 15. Sections 2.1 and 3.10, Part I refer to provis s krang and periodic retraining of empio>ees, as appropriate and related to employee work assignments with radioactive and fissionable materials. Such training shall be conducted, as appropriate, for new employees and prior to initiating new operations approved by the Radiological Safety Committee and retraining shall be conducted on topics appropriate to employee work assignments at least annually. Documentation of such training and retraining shall be maintained.
- 16. Section 5.0, Part I, of the licensee's renewal application incorporates the text of previous amendments issued by NRC to Special Nuclear Material License No. SNM-7 and Byproducts Materials License No.
34-06854-05 covering decontamination and decommissioning plans applicable to the Battelle Hot Cell laboratory. It is hereby affirmed that the provisions to these decontamination and decommissioning plans, including financial arrangements, continue in effect under this renewed license. he 07
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NRC FORM 374A u.S. NUCLb RE7ULAToRY Commission PAGE 7 of 0 PAGEs C**inse Number SNM-7 MATERIALS LICENSE Ddet or Reference Number SUPPLEMENTARY SHEET 0704 0008 Amendment No.17 CORRECTED COPY
- 17. At such time that facilities covered by this license are decontaminated for proposed unrestricted release (in accordance with Annex C), the licensee shall submit a report that identifies the facilities where radioactive materials were used and stored, or disposed on the site. The report shall briefly describe operations conducted and radioactive materials used in the facilities and shall assess the results of the decontamination activities. The report shall provide the basis for unrestricted release of the facilities and the site, including a description of sampling and survey methods and instrumentation used, and shall include final contamination survey data for the facilities and grounds. The licensee may segment the report to obtain release of certain areas of facilities or individual structures if it is demonstrated that ;
ongoing activities in other areas will not lead to r contamination of the area or structure proposed for release. gR egg l
- 18. Moisture density gauges contairSnklicensed materials shall onlyNepsed by, or under the supervision l and in the physical presenc9 tif, individuals who have received the tra[r)ing described in letters dated '
June 29,1994 and August 8,1994, or by the device manufacturer of pprsons licensed to provide such training, and have been gypro ' ting by the Radiation Safety Officet Leak test may be performed by individuals approvedgy the R . afety Officer. %
- 19. When performing testEt tempora s, t hor r shall not Gave the moisture / density gauge unattended. Up n completi tiikdedice 'h'all 65 locked in th,3 licensee's vehicle or a secure building to preYent unau + E egg ;
- 20. The licensee is authorize otr a e /d gaug nly in accordance with the provisions of 10 CFR Pa 1, " T' s Material."
'qpp Radioact
- 21. Each portable nucleargaugphall ave hiesigned to prevent unauthorized or accidental och r0mqval of the ce from'its s seale@gu$r locf contai d position. The gauge or its container must be locked when in9an der the direct surveillance of an authorized user. rt, storage, or wh}n ot
- 22. Sealed byproduct material sources shall be subject to the leak testing and actions specified in the attached procedure titled " License Condition for Leak Testing Sealed Byproduct Material Sources," dated April 1993. Sealed plutonium sources shall be subject to the leak testing and actions specified in the attached procedure titled " License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.
- 23. A. Sealed sources and detector cells shall be tested for leakage and/or contamination at intervals not to exceed 6 months or at such other intervals as specified by the certificate of registration referred to in 10 CFR 32.210.
B. Notwithstanding Paragraph A of this Condition, sealed sources designed to ernit alpha particles shall be tested for leakage and/or contamination at intervals not to exceed 3 months. C. In the absence of a certificate from a transferor indicating that a leak test has been made within 6 months prior to the transfer, a sealed source received from another person shall not_'be put irito use until tested. \dN
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1 NRC FORM 374A " U.S. NUCLN RE7uLAToRY CdMMisSloN PAGE 8 of 9 PAGEs . Ucense Number SNM-7 MATERIALS LICENSE W r Reference Number SUPPLEMENTARY SHEET 070 4 0008 Amendment No.17 CORRECTED COPY D. Each sealed source fabricated by the licensee shall be inspected and tested for construction l defects, leakage, and contamination prior to any use or transfer as a sealed source. E. Sealed sources need not be leak tested if: (i) they contain only hydrogen-3; or (ii) they contain only a radioactive gas; or (iii) the half-life of the isotope is 3gddys obs5 @ g (iv) they contain not more3hYn 100 microcuries of beta anNopgamma emitting material or not more than 10 mic oc\ ries of alpha emitting material; or C (v) they are not d 'gnedk'ep alpha particles, are i rag 6, and.are not being used. However, wh hey are re oved from storagej se or transfe ed to another person, and have not be n ested wk . " 7equireTapk tes f a' l, they s 11 be tested before use or transfer. N ealed source. 'electoibe shall _ t'ored for a $iod of more than 10 years
' l without bein ested for le & on? g l F. The leak test shal:.be cap p,rewn 0, 5 microcuries of radioactive material on the test sample. the O.00 icrocu or more of removable contamination, a re sha : d gulato ommission in accordance .
with 10 CFR 30.50(b and rem mmedia y from service and I or dispos o "rdanceMith Co ission regulations. The report decontaminated, shall be filed within 5 days repai $pf the date the Est result'is k with the U.S. Nuclear Regulatory Commission, Region 111,801 @a e ville Road, Lisle, I 6053 ATTN.: Director, Division of Nuclear Materials Safety. The report sha pe th ou i Ived, the test results, and corrective action l l G. Tests for leakage and/or contamination shall be performed by the licensee or by other persons , specifically licensed by the Commission or an Agreement State to perform such services. ' i 1 I
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NRC FORM 374A u.S. NUCL" EAR RE!ULAToRY CoMMtssioN 9 of C PAGES Ucense Number SNM-7 MATEPl^,'.S LICENSE Docket er Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17 CORRECTED COPY
- 24. Except as specifically provided otherwise in this license, the licensee shall conduct its program in accordance with the statements, representations, and procedures contained in the documents, including any enclosures, listed below. The U.S. Nuclear Regulatory Commission's regulations shall govem unless the statements, representations, and procedures in the licensee's application and correspondence are more restrictive than the regulations.
A. Letters dated October 11,1995 (with attachments), September 29,1997, two letters dated October 20,1997, December 24,1997, December 30,1997, September 15,1998, January 11, ( 1999, January 26,1999, February 5,1999, F bruary 26,1999, April 12,1999, May 14,1999, and May 21,1999. pR egg G* Ar D O Y .. .
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By
- George M. l@cCann' p Materials Licensing Branch l Region ill ~
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O . . O j##" %\ UNITED STATES NUCLEAR REGULATORY COMMISSION g
., o REGloN 111 G j 801 WARRENVILLE ROAD g UsLE. ILUNols 60532-4351 July 21,1999 Mr. Craig Jensen, Manager Safety, Health and Environmental Support Battelle MemorialInstitute Columbus Operations 505 King Avenue Columbus, OH 43201-2693
SUBJECT:
CORRECTED LICENSE AMENDMENT No.17 FOR NRC LICENSE SNM-7
Dear Mr. Jensen:
Er closed is corrected license Amendment 17 per your requests contained in letters dated June 11,1999 and July 21,1999. If you have any questions or require clarification on any of the information stated above, you may contact us at (630) 829-9887. Sincerely,
& . ( -
- George M. McCann, Senior Radiation Specialist Decommissioning Branch License No. SNM-7 Docket No. 070-00008
Enclosures:
As stated.
f , JUL-21-1999 12:09 P.02/06 O p O OBattelle l'utting Technology To Work 505 King Avenue Columbus, Ohio 43201-2693 Telephone (614)424 6424 Facsimile (614) 424-5263 l July 21,1999 I Mr. G. Mike McCann U.S. Nuclear Regulatory Commission l Region III 801 Warrensville Road j Lisle,IL 60532-4351 i Addstional Clarifkation to Amendment 17 to Materials Lkense No. SNM-7
Dear Mr. McCann:
Per your request, ! am transmitting a copy of the e-mail of f sent you today as well as a copy of the June 11,1999 letter identifying corrections to be considered for Amendment 17. Please consider the signature below as sufficient authentication for both pieces of correspondence. As always, ifyou have any questions, please contact me at your convenience at 614-424-5170 or by digital pager at 614-786-0415. Sincerely, f. Craig Jensen, RSO Battelle Columbus Attachments (2) l l I l
. JUL-21-1999 12:10 P.03/06 Jensen, Craig E From: Jensen, Craig E Sent: Wednesday, July 21,1999 8:52 AM Tc: 'G. Mike McCann'
Subject:
Response to your request for clarification Mike, As we had talked and e-malled I failed to clarify the need for this particular use in our previous communications about Amendment 17. I am requesting that Battelle be authorized to use up to 7 Cl of tritium contained in a sealed tube neutron generator, principally in the tritium target, at our West Jefferson facility. The generator is manufactured commercially by MF Physics and is part of a system that Battelle is performing R&D activities for government clients. The system's safety evaluation and use will be reviewed and approved by the Battelle Radiation Safety Committee before being authorized to first conduct work. As is usual, there is some urgency in getting approval to use this system. Please !ct me know if you need further details to proceed with this request. Sincerely, Craig Jensen, RSO Battelle Columbus Jensen@Battelle.org 614.424.5170 1
T. JUL-21-1999 12:10 P.04/06 For Review and Approva! . Project No. C2693383-07 Internal patribution Name Intnais Date Onsinator L. Sand e f2) Concurrence A. O mnoc G. Kirsch Approved C. Jansen L Sanders RSC(T. Walker Secr.) ES&H RP 13.23,3.3 June 11,1999 Mr. G. Mike McCann U.S. Nuclear Regulatory Cornmission 4 Region III 801 Warrensville Road Lisle,IL 60532-4351 l
Dear Mr. McCann:
Commener and Clarifications to Annendment 17 to Materials License No. SNM-7 Battelle Memorial Institute has carefully reviewed the SNM 7 License, Amendment 17, recently issued by the NRC. Battelle is requesting that you make the following changes, most of which are typographical in natum, or have othetwise been previously discussed. These changes are consistent with Battelle's current operations. Sections 6,7, and 8
- 1. Item 8.T., should be restated to the correct exclusion as: "50,000 Curies total, not more than 5,000 Curies of any one radioisotope (excluding Items 6.U through 6.II)".
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- 2. Item 8.V., should be restated to the correct possession limit: "500 curies."
- 3. Battelle requests that Item 8.11., be increased to, "500 mci total, not to exceed 100 mci per radionuclide," for R&D and support of the Radicanalytical Laboratory to include projected work scope.
- 4. Bauelle requests that the authorized place of use in Section 9.B. be modified to allow use of the device at our King Avenue and West Jefferson facilities in addition to storage.
- 5. It is Battelle's understanding that the use and storage of the devices as specified in Section 9.B. at temporary job sites when the U.S. Nuclear Regulatory Commission maintains jurisdiction does not preclude the use and storage of these devices in Agreement States, upon approval of the Agreement State. Please contact me if this understanding is incorrect.
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'-- JUL-21-1999 12:10 P.05/06 O _ o Mr. G. Mike McCann 2 kne 11,1999 l Condidana ( 1. Battelle requests that license condition 10. B., be extended to include residual contamination l at the West Jefferson North site, excluding JN-4. l
- 2. Battelle requests that license condition 10. C. be modified by removing, "and as sealed l source shielding." 'Ihis is to clarify that no source material shielding containers are in use or l storage, nor have they been in the last 5 years.
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- 3. Add a license condition that states, " Items E, F, I and J are in storage and awaiting disposition at the direction of the DOE."
- 4. Revisc license condition 16 to reference the current approved Decommissioning Plan (s)
(BCLDP and the rem =irdar of Battelle Columbus Operations) and state that the Battelle Retired Research Reactor falls within the BCLDP envelope as specified in Battelle's letter to the NRC, dated,21 May,1999 as follows:
"In addition to the above Battelle requests that the license explicitly state that the retired reactor
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I facility is not subject to any separate requirements from the rest of the BCLDP. The discharge I of all retired re : tor facility requirements would reside within the umbrella of BCLDP, e.g., l that no additi' or separate financial assurance vehicle or mechanism would be requirM, for l example, tha. tom 10CFR50."
- 5. As previous.y dLe'ued, please mrmve license condition 18, as this condition was already captured in Secdons 6.JJ. of the =memiment.
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- 6. It is Battelle's understanding that leak testing for Inoisture density gauges may be performed by properly trained staff; e.g. Radiation Protection Staff, who do not need to perform this function under the requirements of Condition 19 and 22, i.e. by or under the supervision of trained gauge users. Battelle requests that the NRC confirm this position. In addition, please correct the typographical error in condition 19, gauge (sic) is usually spelled gauge or gage.
- 7. Please evaluate Battelle's letter to the NRC, dated, May 4,1999, regarding Battelle's request to replace an existing compactor at Battelle's King Avenue site and include in license condition 25.A. If approved.
- 8. Battelle has revised its Radiation Safety Committee Charter and incorporated the Charter into its Radiation Safety Manual. The Radiation Safety Manual revision has been reviewed and approved by the Radiation Safety Committee, the Radiation Safety Officer and Batte11e's CEO.
Included as an attachment is an uncontrolled copy of Battelle's Radiation Safety Manual and the pre .as Radmtion Safety Committee Charter for your review. Please, reevaluate license condition 13 based on this review.
- 9. In condition 17, please change the " Annex C" reference to, " approved Decommissioning Plans."
. JUL-21-1999 12:10 P.06/06 O .
o Mr. G. Mike McCann 3 June 11,1999 l Battelle will continue to reevaluate our current possession limits and will submit other amendments as needed based on these evaluations. If you have any questions concerning our review of this amendment or need further information, please do not hesitate to contact me at 614-424-5170. Sincerely, Craig E. Jensen, CHP Battelle MemorialInstitute Radiation Safety Officer I l TOTAL P.06
#UL-13-1999 19:08 P.02/04
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For Rotew and Approval Proyec No C249338341 fniemal Dktnhutan ms, Concurver.co A. Chance C=f G. Khh Approved C. Jcruca L sanders ASC(T. Waker Sect.) ESaH RF l.3,2.3,13 June 11,1999
)
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Mr. G. Mike McCann ! U.S. Nuclear Regulatory Commission RegionIll . 801 Warrensville Road Lisle,IL 60532-4351
Dear Mr,
McCann: Conennente and Cterficaalones to Annembenent i 7 to Materials License No. ShM-7 Battelle Memorial Institute has carefully reviewed the SNM-7 License, Amendment 17, recently issued by the NRC. Battelle is requesting that you make the following changes, most of which are typographical in nature, or have otherwise been previously discussed. These changes are consistent with Battelle's current operations. Sections 6, 7, and 8
- 1. Item 8.T., should be restated to the correct exclasion as: "50,000 Curies total, not more than 5,000 Curies of any one radioisotope (excluding items 6.U through 6.II)".
- 2. Item 8.V., should be restated to the correct possession limit "500 curies."
- 3. Battelle requests that item 8.11., be increased to, "500 mci total, not to exceed 100 rnCl per radionuclide," for R&D and support of the Radicanalytical Laboratory to include projected work scope.
- 4. Battelle requests thst the authorized place of use in Section 9.B. be modifwd to allow use of the device at our King Avenue and West letiert.on facilities in addition to storage.
- 5. It is Battelle's understanding that the use and storage of the devices as specified in Section 9.B. at temporary job sites where the U.S. Nuclear Regulatory Commission maintains jurisdiction doca mot preclude the use and storage of these devices in Agreement States, upon approval of the Agreement State. Please contact me af this understanding is incorrect.
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- - Mr. O. Mike McCann 2 June 11,1999 l
l Conditions
- 1. Battelle requests that license condition 10. B., be exter.ded to include residual contaminet:on at the West Jefferson North site, excludmg JN-4.
- 2. Battelle requests that license condition 10. C. be modified by removing, "and as sealed source shieldirag.' This is to clarify that no source material shielding containers are in use or storage, nor have they been m the last 5 years.
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- 3. Add a license condition that states, " Items E, F, I and J are in storage and awaiting disposition at the direction of the DOE."
- 4. Revise licer.w coralition 16 to reference the current approved Decomrnissioning Plan (s)
(BCLDP and the remainder of Battelle Colambas Operations) and state that the Battelle Retued Research Reactor falls within the BCLDP envelo;e as specified in Battelle's letter to the NRC, dated,21 May,1999 as follows:
"In addition to the above Battelle requests that the license explicitly state that the retired reactor !
facility is not subject to any separate requirements from the rest of the BCLDP. The discharge of all retired reactor facility requirements would reside whhin the umbrella of BCLDP, e.g., that no additional or separate financial assurance vehicle or mechanism would be required, for example, those from 10CFR50." i
- 5. As previously discussed, please remove license condition 18, as this condition was already ]
captured in Sections 6 J1. of the amendment. '
- 6. It is Battelle's understanding that leak testing for moisture densky gauges may be performed by properly trained staff; e.g. Radiation Protection Staff, who do not need to perfonn this function under the requirements of Condition 19 and 22, i.e. by or under the supervision of trained gauge users. Battelle requests that the NRC confirm this position. In addition, please correct the typographical error in condition 19, gauge (sic) is usually spelled gauge or gage.
- 7. Please evaluate Battelle's letter to the NRC, dated, May 4,1999, regarding Battelle's request to replace an existing compactor at Battelle's King Avenue site and include in license coadition 2$.A. if approved.
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- 8. Banelle has revised its Radiation Safety Committee Chaner and incorporated the Charter i into its Radiation Safety Manual. The Radiation Safety Manual revision has been reviewed and approved by the Radiation Safety Committee, the Radiation Safety Officer and Battelle's CEO.
Included as an attachment is an uncontrolled copy of Battelle's Radiation Safety Manual and the previous Radiation Safety Comuuttee Charter for your review. Please, reevaluate license condition 13 based on this review.
- 9. In condition 17, please change the "Anr.ex C" reference Io, " approved Decommissioning l Plans. " ;
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I JUL-13-1999 19:09 P.04/04 l
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(- O . e o Mr. G. Mike McCann 3 June 11,1999 Baticile will continue to reevaluate our current possession limits and will submit other amerdrnents as l needed based on these evalaations. If you have any questions concerning eur review of this amendment l or need further information, please do not hesitate to contact me at 614-424 5170. l Sincerely, Craig E. Jensen, CHP Battelle MemorialInstitute Radiation Safety Officer l 1 l 1 TOT 4t_ P.04 l
j George McCann - R:sponse 13 your rannest for clarification ,
. Pag 31]
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- From: "Jensen, Craig E" <jensen@BATTELLE.ORG) !
To: "'G. Mike McCann'" <GMM@NRC. GOV > Date: Wed,Jul21,1999 7:52 AM
Subject:
Response to your request for clarification Mike, As we had talked and e-mailed I failed to clarify the rised for this particular use in our previous communications about Amendment 17. I am requesting that Battelle be authorized to use up to 7 Ci of tritium contained in a sealed tubs neutron generator, principally in the tritium target, at our West Jefferson facility. The generator is manufactured commercially by MF Physics and is part of a system that Battelle is j performing R&D activities for govemment clients. The system's safety i evaluation and use will be reviewed and approved by the Battelle Radiation Safety Committee before being authorized to first conduct work. As is usual, there is some urgency in getting approval to use this system. Please let me know if you need further details to proceed with this request. 1 Sincerely, Craig Jensen, RSO Battelle Columbus Jensen@Battelle.org 614.424.5170}}