ML20217Q990
| ML20217Q990 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 04/29/1998 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20217Q982 | List: |
| References | |
| NUDOCS 9805130067 | |
| Download: ML20217Q990 (8) | |
Text
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u.s. NUCt. EAR REGULATORY Commission l
MATERIALS LICENSE Pursuantto 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 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations birt,tofore made by the licensee,a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such materialto persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shtll be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all tpplicablerules, regulations,and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee 1
- 1. General Atomics 3. License Number SNM-696, A.mendment 45
- 2. P.O. Box 85608 4. Expiration Date December 31,1989 San Diego, California 92186-9784 70-734 REG gj[. Docket No.
Beference No.
h (*,b
- 6. Byproduct Source, and/or T ._7. Chemical and/or Physical'*[
Special Nuclear Material CO V Form hMaximum amount that Licensee May Possess at Any One Time 4/
I~ Q iQ cm .h i
/7 lnder This License O
A. Uranium <f A.I' Ehnchelu'p 19.99% A. C200 kilograms U-235 H W-235" J g W pl3 f' $f Q H f ,",'ll 4
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B. Uranium sc O@ { "
3 BefEnrfs p@to 100%' B.tess than 5000 gm*
C C. U-233 Y ,'
$U kC Any 236*h)
.j
~' ?dy@ 0 C&o Less than 2000 gm j
a i 4 .
U-233*
T 'y&- p Jg 4 D. Plutonium D. Encapsulated and/or D. Less than 2000 gm sealed sources total Pu*
E. Plutonium E. Bred but unseparated E. Less than 1000 gm total Pu*
F. Plutonium F. Plated calibration F. Less than 5 grams source total Pu" G. Plutonium G. Solutions, precipitates G. Less than 5 grams solids and total Pu*
The sum total quantity of strategic special nuclear material possessed at any one time must be less than 5,000 grams computed by the formula:
Grams = grams U-235 in uranit.m enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium) 9805130067 900429 PDR ADOCK 07000734 C PDR
, NRC FbR11374A U.s. NUCLEAR REGULATORY Commission PAGE 2 of 8 PAGES Lic;nsa Number l SNM-696
! occket or Reference Number MATERIALS LICENSE
$UPPLEMENTARY SHEET 70-734 l
l Amendment No. 45
- 9. Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid application and supplements.
- 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.
These sections are part of the license, and the licensee is subject to compliance with all listed conditions in each section.
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$ FQR Hg,NpCLEAR REGULATORY COMMISSION D te: 27 fd By: Michael F. Weber M
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Division of Fuel Cycle Sdfety V M and Safeguards, NMSS Washington, DC 20555 (Provided w/ Amendment 31)
Enclosures:
- 1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93
- 2. License Condition for Plutonium Alpha Sources, dtd 4/93
- 3. Guidelines for Decontamination of Facilities..., dtd 4/93
. NRC FORM 374A u.s. NUCLEAR REGULATORY Co%filsslON PAGE 3 of 8 PAGES Ucansa Numbsr SNM-696 MATERIALS LICENSE Docket or Reference Number
' SUPPLEMENTARY SHEET 70-734 Amendment No. 45 I
SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part II " License Specifications" dated July 24,1981, and supplements dated March 16 and December 24,1982; February 4, November 14, and November 15,1983; April 10, April 12, June 28, September 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, .
1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; I March 5, March 18, June 24, and September 10,1992; January 20,1995; and in the "SVA '
Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22, 1990 (submit +ed by letter dated Aug Group 6 Laboratories unrestricte[u [24R199,d0) request June 15,1992; July 12 and August 23,1994; Au Laboratories unrestricted ufrequest dated Decembe/ 1995; Group 8B gust 12,1994; Laboratories Marchuse unrestricted 1,199 j
request dated August 23,4996; October 15,1996; and 0,1997; Group 9 Laboratories unrestricted use request $ated; July 17,1997; Buildigg;30 ratories unrestricted use release dated and Site issiogng Plan dated October 11 and July December 25,1997, and Jar)6iary 29,%$p 5,1996; Apri18,1997%r 1998. Jariba ,1 S-2. Records of all safety- ted(r h1 all ned as follows:
W.?) lh ,be r$
- a. Copies of criticality dr [ony4 malyses [shalLbe retained for at least 2 ye months after a proj ct is tsminated,HwhicRegis longpr.
- b. Copies of all other sa y9 elated (e.g., p alterations and additions, abnormal occurrences associated withga 'vit elpses, audits and inspections, instrument calibrations, ALARA findings, training and rettsin , rsonnel exposures, routine radiation and environmental j surveys) shall be retained for at least 2 years or longer if required by regulations. '
S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double batching is not credible, the maximum safe batch size shall be no more than 75 percent of the minimum critical mass independent of the degree of water moderation and reflection. However, when the Th/U atomic ratio is 2 3.6 and the H/U.s 20, the maximum safe batch size may be increased to 790 g contained U-235 independent of whether double batching is credible.
S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have
-authority to require immediate termination of activities and/or corrective action in any situation which, in
' their judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of radioactive material, loss or damage of property, or non-compliance with the license or a regulation.
, NRC FORM 374A u.s. NUCLEAR REGULATORY Commission PAGE 4 8 PAGES of l Lic9nse Number SNM-696 MATERIALS LICENSE Docket or Reference Number
' SUPPLEMENTARY SHEET 70-734 Amendment No. 45 S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall meet at least annually to review (1) reports of audits and inspections performed since the last ALARA review and (2) employee exposures and effluent release data to determine (a) if there are any upward trends developing in personnel exposures for identifiable categories of workers, types of operations, or effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA concept, and (c) if equipment for effluent and exposure control is being properly used, maintained, and inspected.
1 The CRSC evaluation, recommendations, and corrective actions shall be documented and the report '
shall be sent to the appropriate operations managers and the Vice President, Finance and j Administration.
gB REGg
'S-6. Radiological Work Permits S) shall be issued foIall unplanned or non-routine work with licensed material not covered by at . The RWP shall be signed 3y Health Physics management or a senior i staff member before related'workcan commence. A seniodta'f member shall be a Health Physics Technician having a meiinumFyears' exper' ^ id radiklon safety. An evaluation of the safety effectiveness of the pe it shallO 'ade n etion of e work. I S-7. Radiation safety train %ig, a % d @te er, rietes to t ee'slneed,ib shall be given to all new employees. ,
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S-8. Radiation safety training %nd'i rj[plyballbejondu by the Health Physics Manager or by a similarly qualified indivi . TtisNealth Physics Manage course to an individualw e'is niquel[q6aMiidMr sp .ay delegate trainin S-9.
Continuous air sampling shall be opngcip iganKarea where licensed material can become airborne S-10. The location of air samplers shall be checked annually and whenever any process or equipment changes are made to verify the representativeness of work area air sampling. In addition, the location of air samplers shall be checked at the commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.
S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.
S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached
" License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.
Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 1993.
S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever there is any new residential development within 1 mile around the site that constitutes a significant change in parameters that may be affected by the release of radioactive materials into the environment.
.NRC FORM 374A u.s. NUCLEAR REGULATORY COCMissioN PAGE $ of 8 PAGES Lic2nse Number SNM-696 MATERIALS LICENSE Docket or Reference Number
' SUPPLEMENTARY SHEET 70-734 Amendment No. 45 i
S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License Condition S-9 later became S-1. ,
S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, cuthorized as a place of use for special nuclear material, in accordance with the general decommissioning plan submitted by your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and grounds can be released for unrestricted use. The corporate commitment that funds will be made available for decommissioning the facility, provided by letter dated September 10,1986, is hereby incorporated as a condition of the i noe.REGg S-16. Release of equipment, facilit[s', or packages to the uNetricted area or to uncontrolled areas onsite shall be in accordance wi$tTie attached " Guidelines for f$c,ontamination of Facilities and Equipment j l
Prior NucleartoMaterial,"
Release datedforApril Unreptricted 1993N pse or Terminatior(1of Liceges for Byproduct, Sourc S-17.
@h) % [ i k SVA facility'has been decommissioned and released Deleted by Amendmef37, Septe'mbep1996, for general use. .g g@Qh h g=
M S-18. Notwithstanding the sta@ entin:Secgor1Mdh, Part ll of
- F .'?g license, the trip levels will be readjusted after each monthly test ' e critichlity alarm s iif t arm point fails to activate within approximately 5 seconds, rp,o than once odt 'r J s. ;
S-19. Notwithstanding the statements irtSectiog 4.2J Apart il of the license, no material handling shall be allowed in any area in which the requi$d ditihlity alarm system is inoperative.
S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.
S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee on October 3,1988.
S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.
S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan dated October 10,1997, supplemented by letter dated November 6,1997, or as further revised by the licensee consistent with the provinions of 10 CFR 70.32(i).
S-24 The licensee shall develop individual survey plans for each facility or group of laboratories and t.. ovide NRC a 30-day notification, prior to GA initiating a final survey, to allow the NRC to schedule in-process inspections / surveys if required.
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, NRC FoR] 374A u.s. NUCLEAR REGutAToRY Commission PAGE 6 of 8 PAGEs LicQnso Number SNM-696 MATERIALS LICENSE Docket r Reference Number
- SUPPLEMENTARY SHEET 70-734 l Amendment No. 45 S-25 The licensee must submit for review and approval to NRC residual contamination and characterization data and planned decommissioning procedures for areas where
- 1. Decommissioning procedurec will be required that have not been used by the licensee in previous decommissioning activities or have not been identified in toe Site Decommissioning Plan dated October 11,1996, as amended December 5,1996; Apri.18,1997; and January 15, ,
1998- I l
- 2. Workers wou!d be entering areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations; gB REGf I
- 3. Procedures could resufjIsignificantly gre'atery airbome concentrations of radioactive materials than have been present in previous decommissioning operations; or Xs Qe l 1
- 4. Procedures could result in significantly greater releases
^
of radioactive material to the ;
environment th'an thoie fa^ssociated with p Yvi6us decommissioning operations.
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. NRC FoRJ 374A U.s. NUCLEAR REGULATORY Commission PAGE 7 of 8 PAGEs Lic:nse Numtnr SNM-696
' MATERIALS LICENSE Docket or Reference Number
' SUPPLEMENTARY SHEET 70 734 Amendment No. 45 SAFEGUARDS CONDITIONS SECTION 1.0 - FACILITY ORGANIZATION Currently there are no license conditions in this section. The necessary information has been incorporated into en approved plan.
SECTION 2.0 - FACILITY OPERATION SG-2.1 Not applicable under a possession only license.
Deleted by Amendment 37 SpeJtibR{l SG-2.2 Deleted by Amendmerthf , September 1996. ks licable under a possession only license.
SG-2.3 Deleted by Amendmenti3,7(W, September 1996. Not. app cable under a poss SG-2.4 f %
Deleted by Amendtnent 37/
. /
pmbit,1990 Not applObie under a possession only license.
R Q4 V SECTION 3.0 -- MEASUREPl% A. . A ) Q[! @Sk[% l SG-3.1 Deleted by Amen q
nt~3g,pjt r}t ..h 'zy'ap[@$
996.qNof able under a possession only license.
SG-3.2 Deleted by Amendmed , Se thnh (Nb N licable under a possession only license.
SG-3.3 Deleted by Amendment 37, 8pp*gmgr g9% Not applicable under a possession only license.
SECTION 4.0 - MEASUREMENT CONTROL SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only licerca.
SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
, NRC FoR'.2 374A U.S. NUCLEAR REGULATORY CoMMisSloN PAGE 8 of 8 PAGES Licznst Number SNM-696
' MATERIALS LICENSE Docket or Reference Nun $t[er
' SUPPLEMENTARY SHEET 70-734 Amendment No. 45 SECTION 5.0 - INVENTORY SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-5.2 Deleted by Amendment 37, September 1976. Not applicable under a possession only license.
SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SECTION 6.0 - RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, Sparpb6r11996 Not applicable under a possession only license.
rv l SECTION 7.0 - INTERNAL CONTRot'. if y o, SG-7.1 3 Deleted by Amendment40 up (7 September f
- 1996. p&ot app!hable under a posses SECTION 8.0 - MANAGEMENT 3 O u
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n , a sm ' i) . ,! O SG-8.1 Deleted by Amergent 3.7,'Septprater 1996].iNot'applidia,ble under a possession only license.
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SECTION 9.0 - PHYSICAL PROTECTION REQ JIREMENTS'FORYORMULA QUANTITIES OF STRATE SPECIAL NUCI'EA' R MATERIAQQ~
4, QMi' q SG-9.1 The licensee shall follo#pe measures describedin the physical protection plan entitled, " Fixed Site and Transportation Plan $rge Pdoteptip of Special Nuclear Material of Moderate and Low Strategic Significance," dated Mdy' 1989}, hubmitted by letter dated May 8,1989; and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e).
SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995.
SG-10.2 Deleted by Amendment 31, dated July 1995.
SG-10.3 Deleted by Amendment 31, dated July 1995 ;
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