ML20216G655
| ML20216G655 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 03/11/1998 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20216G635 | List: |
| References | |
| NUDOCS 9803200060 | |
| Download: ML20216G655 (7) | |
Text
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U.S. NUCLEA2 r!EGULATO2Y CoMMIS$lON
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MATERIALS LICENSE
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g Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, lN I
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Code of Federal Regulations, Chapter I, Parts 30,31,32,33, 34,35, 39,40 and 70, and in reliance on statements and representations heretofore jp l
made by the licensee, a hcene is hereby issued authorizing the licensee to receive, acquire, possess, anu transfer byproduct, source, and s,pecial ;l Nj I
nuclear rnaterial designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material j 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 i 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 g
g Regulatory Commission now or hereafter in effect and to any conditions specified below.
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I Licensee i
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- 3. License number M
i General Atomics SNM-696,
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P.O. Box 85608 Amendment 42 lI I
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December 31,1989
! j San Diego, Califomia 92186-9784
- 4. Expiration date y
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- 5. Docket or 70-734
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Reference No p
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- 6. Byptoduct, source and/or
- 7. Chemical and/or physical B. Maximum amount that licensee fI E
special nuclear material form may possess at any one time lf I
under this license I
A.
Uranium A.
Enriched up to 19.99%
A.
200 kibgrams U-235 lg i
U-235 ji k.
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B.
Uranium B.
Enriched 20 to 100% U-235 B.
Less than 5000 gm*
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U-233 C.
Any C.
Less than 2000 gm g
U-233*
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D.
Plutonium D.
Encapsulated and/or D.
Less than 2000 gm j
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sealed sources total Pu*
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E.
Plutonium E.
Bred but unseparated E.
Less than 1000 gm f
I total Pu*
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F.
Plutonium F.
Plated calibration F.
Less than 5 grams ll I,
source total Pu*
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G.
Plutonium G.
Solutions, precipitates G.
Less than 5 grams lt I
solids and total Pu'
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The sum total quantity of strategic special nuclear material possessed at any one time must be less n
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than 5,000 grams computed by the formula:
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Grams =
grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams
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I plutonium) t I
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NR 70RM 374A U.S. NUCLEAR REGULATORY CoMMisStoN PAGE 2 oF 7 PAGES l
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Lkense Nu nber i
SNM-696 Amendment 42 Ig 1
MATERIALS LICENSE Dudet or Reference Nurnber g
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SUPPLEMENTARY SHEET 70-734
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9.
Authorized place of use: The licens6e's San Diego, Califo nia site as specified in the aforesaid g
1 application and supplements.
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10.
This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.
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These sections are part of the license, and the licensee is subject to compliance with alllisted g
1 conditions in each sec* ion.
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1 FOR THE NUCLEAR REGULATORY COMMISSION g
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Date f fAeen ll, W i
5 By: Michael F. Weber. Chief g
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Division of Fuel Cycle Safety lg and Safeguards, NMSS g
3 Washington, DC 20555 g
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(ProvMed w/ Amendment 31) g W
Encicaures: 1. Ucense Condition for Leak Testing g
3 Sealed Plutonium Sources, did 4/93 g
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- 2. License Condition for Plutonium Alpha g
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Sources, did 4/93 g
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- 3. Guidelines for Decontamination of g
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' NWWWWWW WWWWWWWWWWWWWY D LWWWWWt w w.w w w w w a w w w w w w w w w w n FORM 374A u.s. NUCLEAR REoVLAToRY Commission PQGE 3
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PAGES License Number l
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l SNM-696 Amendment 42 i
l MATERIALS LICENSE Dodet or Reference Number
[
l SUPPLEMENTARY SHEET 70-734
(
l l
l SAFETY CONDITIONS
[
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I SAFETY CONDITIONS r
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I S-1.
Authorized use: For use in accordance with statements, representations, and conditions contained in I
I Part 11 " License Specifications" dated July 24,1981, and supplements dated March 16 and I
I December 24,1982; February 4, November 14, and November 15,1983; April 10, April 12, J'ine 28,
[
I September 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, I
I 1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and C
I November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; I
I March 5, March 18, June 24, and September.10,1992; January 20,1995; and in the "SVA 1
I Decommissioning Plan" dated Apr31,'1990 (submitted by letter dated March 30,1990); August 22, I
I 1990 (submitted by letter dated August 24,1990); June 15,1992; July 12 and August 23,1994; L
I Group 6 Laboratories unrestricted use request dated August 12,1994; March 1,1995; Group 7 I
I Laboratories unrestricted use request dated December 5.1995; Group 8B Laboratories unrestricted L
I use request r.:sted August 23,1990; October 15,1996, and April 30, and Group 9 Laboratories l-N unrestricted use request dated July 17, and Building 30 Laboratoiies unrestrictred use release dated l
I July 25,1997.
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S-2.
Records of all safety-related reports and analyses shall be retained as follows:
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Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 I
a.
I months after a project is temiinated, whichever is longer.
I-I f
I b.
Copies of all other safety-related records (e.g., plant alterations and additions, abnormal l
I occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, 1
I ALARA findings, training and retraining, personnel exposures, routine radiation and environmental 1
I surveys) shall be ' retained for at least 2 years or longer if required by regulations.
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S-3.
Notwithstandmg the statements in Section 5.4.2 in the License Specification Volume (Part II), if double l
I, batching is not credible, the maximum safe batch size shall be no more than 75 percent of the i
I minimum critical mass independent of the degree of water moderabon and reflechon. However, when l
N the Th/U atomic ratio is 13.6 and the H/U s 20, the maximum safe batch size may be increased to 790 i
N g contained U-235 independent of whether double batching is credible.
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S 4.
The Director QACD, upon recommendation of the appropnate manager within QACD, shall have r
I authonty to require immediate termination of activities and/or corrective action in any situation which, in I
I theirjudgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of -
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radioactive material, loss or damage of property, or non-compliance with the license or a regulation.
N N
S-5.
The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall I
meet at least annually to review (1) reports of audits and inspections performed since the last ALARA I
review and (2) employee exposures and effluent release data to determ ne (a) if there are any upward I
trends developing in personnel exposures for identifiable categones of wonters, types of operations, or I
effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA N
concept, and (c) if equipment for effluent and exposure control is being property used, maintained, and l
inspected.
l The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate opershons managers and the Vice President, Finance and l
Administration.'
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PAGES NRc FORM 374A U.s. NUCLEAR REGULATORY Commission PAGE bl
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Lwense Nurnber g
SNM-696 Amendment 42 H
MATERI ALS LICENSE Net or Reference Numter 70-734 g
SUPPLEMENTARY SHEET 5
SAFETY CONDITIONS Pl IM
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S-6.
Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine work with licensed 9
material not covered by a WA. The RWP shall be signed by Health Physics management or a senior gl f
staff member before related work can commence. A senior staff member shall be a Health Physics gl j
Technician having a minimum of 5 years' experience in radiation safety. An evaluation of the safety gl g
effectiveness of the permit shall be made upon completion of the work.
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S-7.
Radiation safety training, appropriate to the employee's needs, shall be given to all new employees.
E aj S-8.
Radiation safety training and indoctrination shall be conducted by the Health Physics Manager or by a g
similar1y qualified individual. The Health Physics Manager may delegate training in that portion of the g
course to an individual who is uniquely qualified to present it.
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1 S-9.
Continuous air sampling shall be conducted in any area where licensed material can become airbome.
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The location of air samplers shall be checked annually and whenever any process or equipment
.glj S-10.
y changes are made to verify the representativeness of work area air sampling. In addition, the location g
g of air samplers shall be checked at the commencement of operations in any area that has been gl g
shutdown for more than 6 months to verify the representativeness of air sampling.
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i S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation l l systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.
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S-1;. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached y
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" License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.
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y Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for gl
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lI Plutonium Alpha Sources," dated April 1993.
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S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and g!
Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever Igl ll j
there is any new residential development within 1 mile around the site that constitutes a significant
'g change in parameters that may be affected by the release of radioactive materials into the environment.
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S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and jl renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition l
g S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License l
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j Condition S-9 later became S-1.
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S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of g
use for special nuclear material, in accordance with the general decommissioning plan submitted by g
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your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and WI 9
grounds can be released for unrestricted use. The corporate commitment that funds will be made l
g available for decommissioning the facility, provided by letter dated September 10,1986, is hereby
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incorporated as a condition of the license.
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L Rc FGRM 374A U.S. NUCLEAR RE!ULAToRY Commission PAGE 5
or 7
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d MATERIALS LICENSE tw Leuer Referena r:umner SUPPLEMENTARY SHEET 70-734
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SAFETY CONDITIONS 4
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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 c
Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special lgl c
Nuclear Material," dated April 1993.
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d S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and d
released for general use.
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d S-18. Notwithstanding the statement in Section 4.2.1.4, Part 11 of the license, the trip levels will be readjusted q
after each monthly test of the criticality alarm system if the alarm point fails to activate within g
d approximately 5 seconds, more than once out of four trials.
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d S-19. Notwithstanding the statements in Section 4.2.1.4, Part ll of the license, no material handling shall be g
allowed in any area in which the required criticality alarm system is inoperative.
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S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and g
d released for general use.
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S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee gll on October 3,1988.
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c S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and gl
-l released for general use.
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S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan g
d dated August 1995 (letter dated August 30,1995), and as revised by letter dated June 6,1996, with g
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pages dated May 1996; or as further revised by the licensee consistent with the provisions of 10 CFR g
d 70.32(i).
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NRc FOnM 374A u.S. NUCLEAR REcVLAToRY CoMMISsloN PAGE 6
OF 7
PAGES Il LKeme Number ll g
l SNM-696 Amendment 42 Il gI,
g MATERIALS LICENSE Doc ket or Reference Number g
SUPPLEMENTARY SHEET 70-734 I
l l l SAFEGUARDS CONDITIONS y
5 SAFEGUARDS CONDITIONS l ll B
6 l
5 SECTION 1.0 - FACILITY ORGANIZATION l
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5 Currently there are no license conditions in this section. The necessary information has been incorporated into l l
5 cn cpproved plan.
, l N
N SECTION 2.0 - FACILITY OPERATION N
E SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-2.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-2.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
f SG-2.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SECTION 3.0 - MEASUREMENTS SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
l 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 3 der a possession only license.
N l SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
g 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 AmenC nent 37, September 1996. Not applicable under a possession only license.
SECTION 5.0 -- lHVENTORY SG-5.1 Deleted by Amendment 37, September 19%. Not applicable under a possession only license.
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I GG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
g SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license, gl 4
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PAGES g g "NRC FORM 374A fg!
ucense Numtier g
SNM-696 Amendment 42
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MATERIALS LICENSE wei or Referexe Numte i
g SUPPLEMENTARY SHEET 70-734 l
lll 5
SAFEGUARDS CONDITIONS g
5 ll 5
SECTION 6.0 - RECORDS AND REPORTS
!l n
l5 SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
ll 5
SECTION 7.0 - INTERNAL CONTROL SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
f SECTION 8.0 - MANAGEMENT SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
N 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 f Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low g
Strategic Significance," dated May 1989, submitted by letter dated May 8,1989; and as it may be g
J further revised in accordance with the provisions of 10 CFR 70.32(e).
g i
N SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS g
SG-10.1 Deleted by Amendment 31, dated July 1995.
f SG-10.2 Deleted by Amendment 31, dated July 1995.
SG-10.3 Deleted by Amendment 31, dated July 1995.
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