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
mm,mmmmmmmmmmm-------mmmmmdammmmmkmmmmmmdummmmmmmmmmmmu I wnC ronu n4 PAGE 1 OF 7 PAGESlg U.S. NUCLEA2 r!EGULATO2Y CoMMIS$lON .
l (10-49)
I !I i MATERIALS LICENSE !g I
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 g l 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 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 Nj 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 g
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. g g
I I
iM Licensee I 3. License number i
1~
General Atomics SNM-696, ,p I P.O. Box 85608 Amendment 42 lI:
I I l
i 2' December 31,1989 y
San Diego, Califomia 92186-9784 4. Expiration date ! j i !i i i
- 5. Docket or 70-734 :p Reference No p I
1, 6. Byptoduct, source and/or 7. Chemical and/or physical B. Maximum amount that licensee f E special nuclear material form may possess at any one time I I under this license lf A. Uranium A. Enriched up to 19.99% A. 200 kibgrams U-235 lg I
i U-235 ji k.
I i l
B. Uranium B. Enriched 20 to 100% U-235 B. Less than 5000 gm*
[
l Less than 2000 gm '1 y C, U-233 C. Any C. g i U-233* 't
[
l l D. Plutonium D. Encapsulated and/or D. Less than 2000 gm lI j
total Pu*
l sealed sources f i I
E. Plutonium E. Bred but unseparated E. Less than 1000 gm I f
r I total Pu*
I I
't Plated calibration F. Less than 5 grams I, F. Plutonium F.
total Pu*
ll source jg i
- l l G. Plutonium G. Solutions, precipitates G. Less than 5 grams lt I solids and total Pu' 'I I
't I {tI l i
l i i
- The sum total quantity of strategic special nuclear material possessed at any one time must be less n i than 5,000 grams computed by the formula: L I Grams = grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams !i I plutonium) f I i t
I t.
I I
1 I
I I I I I I I I I ~
I i
9803200060 980311 i PDR ADOCK 07000734 g i C PDR 4 l
I Il
i amuy = = = = w_w_w m_w w = w w w w W W s = = w i w i W W W W W W m w w w w i w w w w w w w i NR 70RM 374A U.S. NUCLEAR REGULATORY CoMMisStoN PAGE 2 oF 7 PAGES Lkense Nu nber l l l
i SNM-696 Amendment 42 Ig 1 MATERIALS LICENSE Dudet or Reference Nurnber g
( '
SUPPLEMENTARY SHEET 70-734 .gl I
1 El 4 ql 1 (l I N 1 9. Authorized place of use: The licens6e's San Diego, Califo nia site as specified in the aforesaid g 1 application and supplements. g ,
1 N 1 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. g 1 These sections are part of the license, and the licensee is subject to compliance with alllisted g ,
1 conditions in each sec* ion. g.
1 N 1
1 g l 1 5
, -7 jA b b l~3g(3, (, g i
1 ,s
~
c'v ,
4,/ y a
W l '
W 1
' f,j.s q 1 {: g 1
<f g
j 1 E a
g 1 N 1 .
E 1 FOR THE NUCLEAR REGULATORY COMMISSION g 1 E 1 , E
) :.4 FUN f 5
1 Date f fAeen ll, W i
By: Michael F. Weber. Chief g i Division of Fuel Cycle Safety
$ and Safeguards, NMSS lg g
3 Washington, DC 20555 g !
$ g 3 (ProvMed w/ Amendment 31) g W Encicaures: 1. Ucense Condition for Leak Testing g 3 Sealed Plutonium Sources, did 4/93 g 3 5
( 2. License Condition for Plutonium Alpha g
( Sources, did 4/93 g 5 %
( 3. Guidelines for Decontamination of g Facilities..., did 4/93 g d
4 q 8 g ll W gl .
i 4 4 4 a I a 4 N a g l 4ranrar arm = = m mt m ana m m m m m m m m m m m m -
. m m m m , m m.. . . . . .. . . J I
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 or 7 PAGES License Number l [
l SNM-696 Amendment 42 i l MATERIALS LICENSE Dodet or Reference Number [
l SUPPLEMENTARY SHEET 70-734 (
l ' '
l l SAFETY CONDITIONS [
I L I [
I r I SAFETY CONDITIONS r I I 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.
r E F U Records of all safety-related reports and analyses shall be retained as follows: I S-2.
I I I a. Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 I 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. l l . ,/ l I 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. I I
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 - I N 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 inspected.
l The CRSC evaluation, recommendations, and corrective actions shall be documented and the report :
l shall be sent to the appropriate opershons managers and the Vice President, Finance and Administration.'
l I
- MMMMMMMMMMMMmaaaaaaaaaaaaaaaaaaaaaaggaggg, Prenied on recycled papr
r q p y x wyLw w w w w w w_wjaustw w w w w w w w w w w w w w w w w w w w w w w w w w w w w wT*Cl NRc FORM 374A U.s. NUCLEAR REGULATORY Commission PAGE 4 oF 7 PAGES .k
{ N' *i'* Lwense Nurnber bl g !
SNM-696 Amendment 42 H MATERI ALS LICENSE Net or Reference Numter SUPPLEMENTARY SHEET 70-734 g .
5 SAFETY CONDITIONS Pl I
M )l b $l l
di @
n h
l 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 staff member before related work can commence. A senior staff member shall be a Health Physics f
g j Technician having a minimum of 5 years' experience in radiation safety. An evaluation of the safety gl gl y effectiveness of the permit shall be made upon completion of the work. g S-7. Radiation safety training, appropriate to the employee's needs, shall be given to all new employees.
a E j
S-8. Radiation safety training and indoctrination shall be conducted by the Health Physics Manager or by a similar1y qualified individual. The Health Physics Manager may delegate training in that portion of the g
g course to an individual who is uniquely qualified to present it. j E'
1 S-9. Continuous air sampling shall be conducted in any area where licensed material can become airbome. g j
Ei 3 The location of air samplers shall be checked annually and whenever any process or equipment S-10. .g y
changes are made to verify the representativeness of work area air sampling. In addition, the location g lj 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. l i
- l 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. g g
g F y
S-1;. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached y
" License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993. gl g
El 4
y Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for gl +
Plutonium Alpha Sources," dated April 1993. g y
di E lI y 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 j there is any new residential development within 1 mile around the site that constitutes a significant 'g I y
change in parameters that may be affected by the release of radioactive materials into the environment. g G>
ll 4
y 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
g S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License ! l y Condition S-9 later became S-1. j ;
y 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 ll y
y your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and WI l grounds can be released for unrestricted use. The corporate commitment that funds will be made l 9
g available for decommissioning the facility, provided by letter dated September 10,1986, is hereby ! l y incorporated as a condition of the license. l N l N El
- ,.o r-nirs1m m m m m m m m m m = = m m m m m m m m m m m m s Prented nn ervrled perf
- - _ ____ - _ ______-_______-____ _ _a
~--
L f---------"---
pluum 3sLwJuuuuuuuumaeustwJutw_w3ii w w w wlwXwXh.#3iitGE3kX%3 Rc FGRM 374A U.S. NUCLEAR RE!ULAToRY Commission PAGE 5 or 7 PAGES !!
l** Ln ertse Nurnhi r !l SNM-696 Amendment 42 !l d
~
MATERIALS LICENSE tw Leuer Referena r:umner II SUPPLEMENTARY SHEET 70-734 (!
} ,
ll C SAFETY CONDITIONS 4 9b e
q S-16. Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite c shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment g(l c Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special lgl c Nuclear Material," dated April 1993. pl c
d S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and Il
{
d released for general use. g' d
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. y CI g d S-19. Notwithstanding the statements in Section 4.2.1.4, Part ll of the license, no material handling shall be g o allowed in any area in which the required criticality alarm system is inoperative. g, c S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and Ef g
d released for general use. g d El 4 S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee c on October 3,1988. gll C
gl g
c S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and gl c released for general use. -l in 9
4 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 d pages dated May 1996; or as further revised by the licensee consistent with the provisions of 10 CFR g l, d 70.32(i). g
- E Ei i
$ lE!
N lNl W El E!
N E
W E
b E
W i l N' k lui p
N l 8 l 8 l 8 !
l p.
bwsinnensomonnsnansnet a mrunnt a m m m ansomamounmirac l
n, ms;, j
gn.m.m m_mxm.m_w_m m m a m m m m m m m MMirirWEiDirarKarirMarWWirMirMiriririririric]
NRc FOnM 374A u.S. NUCLEAR REcVLAToRY CoMMISsloN PAGE 6 OF 7 PAGES Il g
LKeme Number ll l SNM-696 Amendment 42 Il gI g
, MATERIALS LICENSE Doc ket or Reference Number !!
I g SUPPLEMENTARY SHEET 70-734 l
y SAFEGUARDS CONDITIONS ll 5 SAFEGUARDS CONDITIONS B l ll 6 l 5 SECTION 1.0 - FACILITY ORGANIZATION l lU l 5 Currently there are no license conditions in this section. The necessary information has been incorporated into l 5 cn cpproved plan. l N ,l N SECTION 2.0 - FACILITY OPERATION E
N 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 SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. gl 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. l l
g i I
g GG-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, gl 4 0
1 m m m m m m m m m m = = = = = m m m = = = = = = =nerrs1mr= = = = = "*d""""*'"
gausr_.Ju_r waayrJmusamtw_jm_mamLwJuust w w w wWWFFFwPAGE w FFFFiffffsifffififfFifidyl U.S. NUCLEAR REGULATonY CoMMisSloN 7 OF 7 PAGES g g "NRC FORM 374A ucense Numtier fg!
g g SNM-696 Amendment 42 !El
, i g MATERIALS LICENSE wei or Referexe Numte i g , , SUPPLEMENTARY SHEET 70-734 l 5
g SAFEGUARDS CONDITIONS lll 5 ll!
5 SECTION 6.0 - RECORDS AND REPORTS n !l l5 5
SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. ll 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 Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low f
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.
. (
N El B jEl N Wf a al E,
m p N 6
N n n 8
N ,
5 I l
y i N !: !
n p Ei N E!
W W; E E; p E; 5
R W !El N Nl n n t _ ........x..........................Jl Prmied <m recw led einer