ML20217C367
| ML20217C367 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 10/04/1999 |
| From: | Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20217C361 | List: |
| References | |
| NUDOCS 9910130246 | |
| Download: ML20217C367 (8) | |
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1 NRC FOM M U.S. NUCLEAR REGULATORY COMMISSION l MATERIALS LICENSE I 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 l 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 special nuclear material designated below; to rse such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive l 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 I Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter j in effect and to any conditions specified below. I Licensee j l
- 1. General Atomics 3. License Number SNM-696, Amendment 60 i i
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- 2. P.O. Box 85608 4. Expiration Date December 31,1989 i San Diego, California 92186-9784 g8 REG r noct,, yo. 7o.734 l
[g 1Nfyence No.
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- 6. Byproduct Source, and/or 7 mical and/or Physical ,7 SpMaximum amount that Licensee Special Nuclear Material \ an , O' 4!ay Possess at Any One Time g }N '
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gder This License A. Uranium T ,A.!c chsku)p_to9% A.900 kilograms U-235
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B. Uranium O@ 'BhEnr]h,p : Jyqi % Less than 5000 gm*
4 P D-235 '
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C. U-233 k Any w
[C. Less than 2000 gm U-233*
- dr W 1k Ys D. Plutonium D. Encapsulated and/or D. Less than 2000 gm sealed sources total Po*
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 uranium enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium) 9910130246 991004 PDR ADOCK 07000734 C PDR
l NRC FORM 374A U.S. NULLEAR REGULATORY COMMISSION Page 2 of 8 License Number
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SNM-696 l MATERIALS LICENSE D eket r Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 60 !
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- 9. Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid j application and supplements, j
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- 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. I 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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6ivision of Fuel Cycle Safety 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
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' NRC FORM 374A - U.S. NUCLEAR RECULATORY COMMISSION Page 3 of 8 j
'? License Number !
SNM-696
! ' MATERIALS LICENSE Dder Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 60 l
l l SAFETY CONDITIONS S-1 i Authorized use: For use in accordance with statements, representations, and conditions contained in Part ll " 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, l September 4, an'd September 7,1984; December 5,1985; May 23, September 25, and December 10, l 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; e March 5, March 18, June 24, and September 10,1992; January 20,1995; the "SVA Decommissioning i i
Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22,1990 (submitted by i
' letter dated August 24,1990); June 12 and August 23,1994; Group 6 Laboratories j- unrestricted use request dated , h 1,1995; Group 7 Laboratories unrestricted use E request dated December 5, Group 8B Labora .
unrestricted use request dated August 23,
.1996; October 15,- 1996; 30,~ 1997; Group 9 Labor es unrestricted use request dated July 17, 1997; Building 30 Laborpt es. unrestricted use re! ease, '
July 25,1997; and January 29,1998; Site Decommissioning Q@n d ,1996; April 18,1997; January 15,
! - 1998; Hot Cell Decompussioning
.ctober q dated- 11 and [1998,(houp 10 Labs dated August 14, l Building 27 Roof releasp dated at 2fa lng 30 - Dase 11 dated September 4,1998, j 4ullding 21), Dgsember 22,1998 (SVB) January 12, l October 1,1998,37Novpber February 8 (Buildings arid @9 R 2,:199$(!bn Mll- gli 23,19g9 (TFFF), March 9, May 17, (Radioactive ;
Waste Storage Tanks),g@pne23p[B
' (Building 42). g j.g;15-
,45 Nest-Tower Land), and August 18,1999 d
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- Records of all safety-relat[6r orts and'anhiyses;j Co S-2. sha tretained as follows:
- a. . Copies of criticality and radia#ongfgty qQal%es shall be retained for at least 2 years or for
- 6 months after a project is terminated', whichever is longer.
- b. . Copies of all other safety-related records (e.g., plant alterations and additior.s, abnormal occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, ALARA findings, training and retraining, personnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if mquired by regulations.
S-3. Notwithstanding the statements in Secticn 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
- l. .the Th/U atomic ratio is > 3.6 and the H/U $ 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.
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r I NRC FORM 374A U.S. NUCLEAR RECULATORY COMMISSION Page 4 of 8 License Number l ,
SNM-696 Docket or Reference Number MATERIALS LICENSE l SUPPLEMENTARY SHEET 70-734 Amendment No. 60 l
1 S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall l
! 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 l 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 l inspected.
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 Administration.
sg8REGy S-6. Radiological Work Permits ( @hS) shall be issued fo unplanned or non-routine work with licensed material not covered by a . The RWP shall be sign Health Physics management or a senior l staff member before relat work can commence. A sent taff member shall be a Health Physics n r'adia(ion safety. An evaluation of the safety L Technician having a miguringigyears' p experiepcp)ftion otthe work.
effectiveness of the pqrmit shallyy )ade_upon* p q } O S-7. Radiation safety trainipg, approp ffie-drgp\pe'sneedushall be given to all new employees.
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S-8. . Radiation safety trainingjnd;lr%ctrina . Il be con;ucteYby d the Health Physics Manager or by a similarly qualified individyal. ThMleilt . R_MJhager $y delegate training in that portion of the course to an individual who) uniquely;gua fibd to; pre Gt.
S-9. Continuous air sampling shall be conducted in an area where licensed material can become airborne.
S-10. The location of air samplers shall c ec ed nnually 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 dial 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.
l l Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 199.1 S-13. The licensee shall prepare and submit to the Chief, Licensing and International Safeguards 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 l around the site that constitutes a significant change in parameters that may be affected by the release
- of radioactive materials into the environment.
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- NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 5 of 8 License Number i SNM-696 l Docket or Rererence Number
! MATERIAI.S LICENSE l SUPPLEMENTARY SHEET 70-734 j l
Amendment No. 60 l I
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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. j f
S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of (
use for special nuclear material, in accordance with the general decommissioning plan submitted by l 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 j available for decommissioning the facility, provided by letter dated September 10,1986, is hereby '
I incorporated as a condition of the c nge.R Eeg S-16. d'br s packages to the unfeytricted area or to uncontrolled areas onsite Release shall of equipment, be in accordance withh facilit(he attached " Guidelines forigcontamination of Fa
)ses for Byproduct, Source, or Special Prior to Release for UnresYricted Use or Termination of Lice)J-Nuclear Material," date@prifL1 s ',
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() i S-17. Deleted by Amendment'37, Sep ber 1996 A facility)has been decommissioned and released for general u.se. A i; ' M { /,,, g D
S-18. Notwithstanding the stgmentjoySec R% f[ g s' 1 1 , Partfof th$ license, the trip levels will be readjusted after each monthly test qbthe gdticall Jr 3 if the aIfrm point fails to activate within approximately 5 seconds ore'than ofice ,(of 'r triap !
4* O I S-19. Notwithstanding the statemen in Section 4.2.14 Pddll of the license, no material handling shall be C
allowed in any area in which the rEquigdgritiglit? 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; and Revision Date 10/98; or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(l). <
S-24 The licensee shall develop individual survey plans for each facility or group of laboratories and provide 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 FORM 374A ? U.S. NUCLEAR REGULATORY COMMISSloN Page 6 of 8 License Number f SNM-696 MATERIALS LICENSE Docket or Rererence Number SUPPLEMENTARY SHEET 70-734 Amendment No. 60 l
I 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 procedures will be required that have not been used by the licensee in previous decommissioning activities or have not been identified in the Site Decommissioning Plan dated October 11,1996, as amended December 5,1996; April 18,1997; and January 15, 1998- .
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- 2. Workers would be entering areas where surface contamination and radiation levels are ,
significantly higher than routinely encountered during previous decommissioning operations; l itidighfichrbejter airborne concentrations of radioactive materials
- 3. than Procedures have been precouldfat resul(Tn previous decommi(spning operation A O
- 4. Procedures cot lldYesult in significantly greater reTepses of radioactive material to the environment if th5s$ asociated with prptfs de6ommissioning operations.
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' NIC EORM 374A ' U.S. NUCLEAR REGULATORY COMMISSION Page 7 of 8
, License Number SNM-696 D eket w Reference Number MATERIALS LICENSE
- SUPPLEMENTARY SHEET 70-734 Amendment No. 60 l
SAFEGUARDS CONDITIONS l l
SG-1.0 Currently there are no Material Control and Accounting license conditions. The necessary information has been incorporated into an approved Fundamental Nuclear Material Control Plan dated March 1999.
SECTION 1.0 - FACILITY ORGANIZATION D:leted by Amendment 58, August 1999.
SECTION 2.0 - FACILITY OPERATION i 998REGy j SG-2,1 Deleted by Amendmen @hSeptember 1996 helppplicable under a possessiol SG-2.2 Deleted by Amend t-3 , September 1996. Not Jicable under a possession only license.
SG 2,3 Deleted by Amen # ment 3 tember.49 . t appligable under a possession only license.
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SG-2.4 Deleted by Amendment:37/ gmbEik ot appligble under a possession only license. f m ?. ' b'hy' ". y , .y , '
SECTION 3.0 -- MEASUREMENTS ; N 9% An :..,5 q SG-3.1 Deleted by Amendme t 37, Septe j996 Not ap'plicable under a possession only license.
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9 SG-3.2 Deleted by Amendncot O, Spptember 1996. Nbbapplicable under a possession only license.
V A 4 ,)r Y SG-3.3 Deleted by Amendment 37, Septemb'er 1996. 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.
1 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 license.
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.
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 8 of 8 i License Number SNM-696 MATERIALS LICENSE Docket or Rererence Number SUPPLEMENTARY SHEET 70-734 Amendment No. 60 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 1996. 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 Se bg9 6 Not applicable under a possession only license.
SECTION 7.0 -INTERNAL CONTR6h SG-7.1 Deleted by Amendry#p7,,ent '
$o 1996. Not appJicable under a September
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SECTION 8.0 - MANAGEMEb
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SG-8.1 Deleted by Amerldment 37, S'e,ptgmbeH Not applicable under a possession only license. j
- W ,L , %$f fl .# .. W s i ll ; ' MENTS'FORTORMULA QUANTITIES OF SECTION 9.0 - PHYSICAL PROTEC% ION NEQ !
STRATEG!C SPECIAL NUCLEAR MATBRihWy)
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o s SG-9.1 The licensee shall folloQe measiires desen ed ittt l s e physical protection plan entitled, " Fixed )
l Site and Transportation Plan for the Protection o'tSpecial Nuclear Material of Moderate and Low l Strategic Significance," datediMapt9p9,gutIinitted by letter dated May 8,1989; and as it may be j further revised in accordance with the provisions of 10 CFR 70.32(e).
l SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS j q
SG-10.1 Deleted by Amendment 31, dated July 1995. i
! SG-10.2 Deleted by Amendment 31, dated July 1995.
SG-10.3 Deleted by Amendment 31, dated July 1995. O l
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