ML20210E992
| ML20210E992 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 07/23/1999 |
| From: | Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20210E989 | List: |
| References | |
| NUDOCS 9907290109 | |
| Download: ML20210E992 (8) | |
Text
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1 SRC FORM 374 PAGE I OF R PAGES U.S. NUCLEAR REGULATORY COMMIS510N MATERIALS LICENSE 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 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 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 applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee
- 1. General Atomics 3. License Number SNM-696, Amendment 57
- 2. P.O. Box 85608 4. Expiration Date December 31,1989 San Diego, California 92186-9784 5. Docket No.70-734
-. Reference No.
- 6. Byproduct Source, and'or ,7. Chemical and'or Physical 8. Maximum amount that Licensee Special Nuclear Material Form May Possess at Any One Time
B. Uranium B. Enriched 20 to 100% B. Less than 5000 gm*
C. Less than 2000 gm U-233*
D. Plutonium D. Encapsulated and/or D. Less than 2000 gm i
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 uranium enriched to 20% or more plus 2.5 (grams U-233 + grams l plutonium) 9907290109 990726 PDR ADOCK 07000734 l C PDR I
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NR,C FORM 374 A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 of 8 PAGES License Number SNM-696 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-734 Amendment No. 57
- 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.
FOR THE NUCLEAR REGULATORY COMMISSION Date: 7/J 3 JM C.11. bA .
By: Theodore S. Sherr. C ief Division 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 l
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f NitC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 or 8 PAGES I i License Number
! SNM-696 Dwket r Reference Number MATERIALS LICENSE SUPPLEMENTARY SIIEET 70-734 Amendment No. 57 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part 11 " 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; March 5, March 18, June 24, and September 10,1992; January 20,1995; the "SVA Decommissioning Plan" dated April 1,1990 (submitted by .'etter dated March 30,1990), August 22,1990 (submitted by letter dated August 24,1990); June 15c1992LJuly 12 and August 23,1994; Group 6 Laboratories unrestricted use request dated August 12,1994T March 1,1995; Group 7 Laboratories unrestricted use request dated December 5,1995; Group 8B Laboratories unrestricted use request dated August 23, 1996; October 15,1996; April 30,1997; Group 9 Laboratories unre'stricted use request dated July 17, 1997; Building 30 Laboratories unrestricted use release dsted July 25,1997; and January 29,1998; Site Decommissioning Plan dated October 11 and December 5,1996; April 18,1997; January 15, 1998; Hot Cell Decommissioning Plan dated April 22,1998, Group 10 Labs dated August 14, Building 27 Roof release dated August 25 and Building 30 - Phase 11 dated September 4,1998, October 1,1998, November 2,1998 (Buildings. 27 and 21), December 22,1998 (SVB) January 12, February 8, (Buildings 37 and 39, Room 0498); March 23,1999 (TFFF), March 9 and June 23,1999, (Building 35-1,36,45, Test Tower Land);
S-2. Records of all safety-related reports and analyses shall be retained as follows:
- a. Copies of criticality and radiation safety analyses 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 additions, 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 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 > 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.
l S-4. The Director QACD, upon recommendation of the appropriate manager within OACD, shall have authority to require immediate termination of activities and/or corrective action in any situation which, in theirjudgment, 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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NRQ lORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of 8 PAGES
, Liceme Number SNM-696 )
D eket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SIIEET 70-734 Amendment No. 57 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.
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. _g ,
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S-6. Radiological Work Permits (RWPS) shall be issued for.all unplanned or non-routine work with licensed material not covered by a $ d. The RWP shall be signekt3y Health Physics management or a senior staff member before related work can commence. A senior, staff member shall be a Health Physics Technician having a minimum of.5 years' experience in radiation safety. An evaluation of the safety effectiveness of the permit shall be,made upon completion of the work.
Radiation safety training, appropriate to the employee's needs, shall be given to all new employees. l S-7. -
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S-8. Radiation safety training and Indoctririation1shall be conducted'by the Health Physics Manager or by a similarly qualified individual. The Health Phjsics Manager may delegate training in that portion of the course to an individual who is uniquely qualified to,presen,t it.
S 9. Continuous air sampling shall be conducted in any area 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 L eak 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 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 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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J pl NRC FORM h74A U.S. NUCLEAR REGULATORY COMMIS$10N PAGE $ of 8 PAGES
, License Number SNM-696 [;
MATERI ALS LICENSE Docket or Reference Number f SUPPLEMENTARY SilEET 70-734 Amendment No. 57 l
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, authorized 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 r
incorporated as a condition of the q pnlicense. R c r_li ,
S-16. Release of equipment, facilities,'or packages to the unrestricted area or to uncontrolled areas onsite shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated' April 1993.
I S-17. Deleted by Amendment _37, September 1996. Th,e SVA facility has been decommissioned and l released for general use.
I S-18. Notwithstanding the statement in SectiorM1,4, Part il of the license, the trip levels will be readjusted after each monthly test 6f the criticality alarm'syste,m'if the alarm point fails to activate within approximately 5 seconds, more than once out of four trials.
l S-19. Notwithstanding the statements in Section 4.2.1.4, Part 11 of the license, no material handling shall be allowed in any area in which the required criticality 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 Mensee l on October 3,1988.
l 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).
I 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 roRui74A U.S. NUCLEAR REGULATORY COMMIS$10N PAGE 6 of 8 PAGES
, Licenw Number SNM-696 Docket or Reference Number MATERI ALS LICENSE SUPPLEMENTARY SilEET 70-734 Amendment No. 57 ,
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: l
- 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, j 1998;
- 2. Workers would be entering areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations;
- 3. Procedures could result in sigriificintl/ greater airborne concentrations of radioactive materials than have been present'in previous decommissioning operations; or
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- 4. Procedures could r'esult in significantly greater releases of radioactive material to the environment than those associated with previous decommissioning operations.
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NRc FORM 374 A U.S. NUCLEAR REGUI.ATORY CO%1%!!SS10N PAGE 7 of 8 PAGES
, License Nurnber SNM-696 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SilEET 70-734 Amendment No. 57 SAFEGUARDS CONDITIONS SECTION 1.0 - FACILITY ORGANIZATION Currently there is no license condition in this section. The necessary information has been incorporated into an approved Fundamental Nuclear Material Control Plan, dated February 1998.
SECTION 2.0 -- FACILITY OPERATION SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-2.2 Deleted by Amendment 371 September 1996., Not applictble under a possession only license.
SG-2.3 Deleted by Amendmen,t 37, September 1996. Not applicable under a possession only license.
SG-2.4 Deleted by Amendment 37,. September 1996. Not applicable under a possession only license. l SECTION 3.0 - MEASUREMENTS l
SG-3.1 Deleted by Amendment 37, September;1996. Not applicable under a possession only license.
SG-3.2 Deleted by Amendment 37, Septembdr'1996. Not applicable under a possession only license.
SG-3.3 Deleted by Amendment 37, September 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.
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 PAGES
'* . License Number SNM-696 Docket r Reference Number MATERIALS LICENSE SUPPLbMENTARY SIIEET 70-734 Amendment No. 57 I
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, Sep,ternberi' 199.6. Not applicable under a possession only license.
, .,3 r n SECTION 7.0 -- INTERNAL CONTROL' '
. l SG-7.1 Deleted by Amendmd 37, September 1996. Not applicable under a possession only license.
SECTION 8.0 - MANAGEMENT SG-8.1 Deleted by Amendment 37, September 1996 Not applicable under a : ossession only license.
SECTION 9.0 - PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA QUANTITIES OF STRATEGIC SPECIAL NUCLEAR MATERIAL SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, " Fixed Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low I
Strategic Significance," dated May 1989, submitted 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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