ML20134F125

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Amend 38 to SNM-696 for General Atomics,Deleting Certain Labs as Places of Authorized Use of Licensed Matls
ML20134F125
Person / Time
Site: 07000734
Issue date: 10/30/1996
From: Pierson R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20134F120 List:
References
NUDOCS 9611040291
Download: ML20134F125 (9)
v • d • e


Text

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4 NRC FOrsu 374 g g ej; 0 0,-e0) U.S. NUCLE AR REGULQTORY COMMISSION

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'g 1' MATERIALS LICENSE g 1

B j Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 :p f Code of Federal ReFulations, Chapter I, Parts 30. 31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore p

% made by the licensee, a license is hereby issued authorizing the licensee to receise, acquire, possess, and transfer by product source, and special 'l

1) 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 'E to persons authorized to receive it in accordance with the regulations of the applicable Part(st This license shall be deemed to contain the conditions y Ispecified 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 p j Regulatory Commission now or hereafter in effect and to any conditions specified below. g 1 'E l Ucensee
a il h 1. 3. Ucense number I li General Atomics SNM-696, Il i

%1 Amendment 38 .I ;

i

= 11 2, I P.O. Box 85608 December 31, 1989 i ll San Diego, California 92186-9784

4. Expiration date )l j :j 1
5. Docket or

-il 70-734 i)

1 Reference No j, i!
3 6 Byproduct. source, and/or 7. C?cmical and/or physical 8. Maximum amount that hcensee ;i l 1 special nuclear material I form may possess at any one time  !

under this beense d .i j A. Uranium A. Enriched up to 19.99% A. 200 kilograms U-235 ;l .

i 1 U-235 i J i I B. Uranium B. Enriched 20 to 100% U-235 B. Less than 5000 gm* j

". f l f C. U-233 C. Any C. Less than 2000 gm 3i j f U-233* I l

1 $ ;I I

{ D. Plutonium D. Encapsulated and/or D. Less than 2000 gm Il I

i sealed sources total Pu* i I

1 a yi j'

d E. Plutonium E. Bred but unseparated E. Less than 1000 gm i 3, total Pu* 'l f .!

1 F. Plutonium F. Plated calibration F. Less than 5 grams il 3l source total Pu* il 1 l G. Plutonium G. Solutions, precipitates G. Less than 5 grams ),

f solids and total Pu* ll Ji 1

!!l 1l

li time must be less than 5,000 grams computed by the formula: 1, fd Grams - grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 +

grams plutoniun) ii .

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! 9. Authorized place of use: The licensee's San Diego, California site as specified in I; l the aforesaid application and supplements.

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PAGE 2 or 9 PAGES g License Numte.

-N SNM-696 Amendment 38 MATERIALS LICENSE N omket or sererence samber p SUPPLEMENTARY SHEET 70-734 N i N ,!

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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 j'

11 y subject to compliance with all listed conditions in each section. ,'

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N 'l N i FOR THE NUCLEAR REGULATORY COMMISSION M

! # lil N Date: @M 7 % l'1 T 0 By: Robert C. Pierson i N Division of Fuel Cycle Safety N and Safeguards, NMSS N Washington, DC 20555 lEE 6

N IE

!!! (Provided w/ Amendment 31)  !

Enclosures:

1. License Condition for Leak Testing N

E Sealed Plutonium Sources, dtd 4/93 l! E E

N E g 2. License Condition for Plutonium Alpha  :

y Sources, dtd 4/93 Ni ln ji E

n' 3. Guidelines for Decontamination of :p g! Facilities..., dtd 4/93 N

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evonLw23maOLws GrarararG1XhirafarafarMGraracarMarMMMMMMMMMMMKararararsi FORM 374A U.S. NUCLEAR REGULATORY COMMISSloN PAGE 3 or 9 PAGES License Number ,

I -

SNM-696 Amendment 38

~

! MATERIALS LICENSE Ihket or Reference Number l SUPPLEMENTARY SHEET 70-734 ,

SAFETY CONDITIONS l 3{1 i 3l l 3j i 3 i 3 SAFETY CONDITIONS g 3 i M Authorized use: For use in accordance with statements, representations, and g;fS-1.conditions contained in Part II " License Specifications" dated July 24, 1981, and lig y supplements dated March 16, and December 24, 1982; February 4, November 14, and I, gI November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 198(; I g! December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; l, gl l

March 4, March 9, (2), March 22, April 26, August 22, September 8, and November 2, bl g 1988; May 25, and November 17, 1989; June 27, 1990; April 30 and September 27, 1991; and March 5, March 18, June 24, September 10, 1992, and January 20, 1995; and j

a j in the "SVA Decommissioning Plan" dated April 1, 1990 (submitted by letter dated p, March 30, 1990), August 22, 1990 (submitted by letter dated August 24,1990), G

@W June 15, 1992, July 12, 1994, August 23, 1994, Group 6 Laboratories unrestricted

{

p use request dated August 12, 1994, and March 1, 1995, Group 7 Laboratories i, unrestricted use request dated December 5, 1995, and Group 88 Laboratories gll unrestricted use request dated August 23, 1996. 1(

g S-2. Records of all safety-related reports and analyses shall be retained as follows: hi j

$a a. Copies of criticality and radiation safety analyses shall be retained for at $

2 least 2 years or for 6 months after a project is terminated, whichever is i l

longer.

!j b. Copies of all other safety-related records (e.g., plant alterations and 5j additions, abnormal occurrences associated with radioactivity releases, audits @t 3l and inspections, instrument calibrations, ALARA findings, training and h 3i retraining, personnel exposures, routine radiation and environmental surveys) ji 3 shall be retained for at least 2 years or longer if required by regulations.

!j S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume ji 5 (Part II), if double batching is not credible, the maximum safe batch size shall be jE 3 no more than 75 percent of the minimum critical mass independent of the degree of jE 3 water moderation and reflection. However, when the Th/U atomic ratio is 2 3.6 and jE 3j the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 i E

sj independent of whether double batching is credible. ;E E

3l:

3 sj S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities and/or E

,E 3

4 corrective action in any situation which, in their judgment, could lead to the je 3 unnecessary exposure of personnel to ionizing radiation, release of radioactive ,E l

3, material, loss or damage of property, or non-compliance with the license or a ,E 9, regulation.

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SNM-696 Amendment 38 i h M ATERIALS LICENSE twet or Reference Number 4 h SUPPLEMENTARY SHEET 70-734 j hl g SAFETY CONDITIONS Y  !

3 S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA i y Committee, shall meet at least annually to review (1) reports of audits and 3 inspections performed sin.e the last ALARA review and (2) employee exposures and !s i

y effluent release deta to determine (a) if there are any upward trends developing in  !

i y!

personnel exposures for identifiable categories of workers, types of operations, or  !

a effluent releases, (b) if exposurrs and releases might be lowered in accordance li ji with the ALARA concept, and (c) if equipment for effluent and exposure control is jl g being properly used, maintained, and inspected. j a

j The CRSC evaluation, recomendations, and corrective actions shall be documented l

and the report shall be sent to the appropriate operations managers and the Vice j(i g President, Finance and Administration.

j S-6. Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine y work with licensed material not covered by a WA. The RWP shall be signed by Health f g

g 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 ((

g g years' experience in radiation safety. An evaluation of the safety effectiveness q H of the permit shall be made upon completion of the work.

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%j S-7. Radiation safety training, appropriate to the employee's needs, shall be given to r 8

f all new employees.

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j S-8. Radiation safety training and indoctrination shall be conducted by the Health 3 d

j Physics Manager or by a similarly qualified individual. The Health Physics Manager 8 j may delegate training in that portion of the course to an individual who is uniquely qualified to present it.

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.E 3 S-9. Continuous air sampling shall be conducted in any area where licensed material can lE s become airborne. y aj E

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llS-10.Thelocationofairsamplersshallbecheckedas,uellyandwhenevera equipment changes are made to verify the representativeness of work area air E

E l  ;

samplirg. In addition, the location of air samplers shall be checked at the y commencenent of operations in any area that has been shutdown for more than 6 f lk months to verify the representativeness of air sampling. y g

9 3lS-II.Thelaboratcriesinwhichplutoniuminadispersibleformmaybeusedshallhave exhatst ventilation systems separate from other building exhausts and shall provide liy E

'd, dual HEPA filtering of the effluent air. y 9

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3lS-12.SealedPlutoniumsourcesshallbesubjecttotheleaktestinoandactionsspecified in the attached " License Condition for Leak Testing Sealed Plutonium Sources,"

'e 3 dated April 1993. ,9 A iE i Plutonium alpha sources shall be subject to the actions specified in the attached y

" License Condition for Plutonium Alpha Sources," dated April 1993.

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NR FORM 374A U.S. NUCLEAR REGULATORY COMMISSION

_ PAGE b OF 9 PAGES 1 g . License Number

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SNM-696 Amendment 38 g' MATERI ALS LICENSE Daket or Reference Number y SUPPLEMENTARY SHEET 70-734 .,

W ,

g SAFETY CONDITIONS ,1 N i R 6, N i!

N S-13. The licensee shall prepare and submit to the Chief, Licensir.g Branch, Division of i!

W Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, is W Washington, DC 20555, a report whenever there is any new residential development ii W within 1 mile around the site that constitutes a significant change in parameters i' W that may be affected by the release of radioactive materials into the environment. I 1

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N S-14 Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 - Il n 1992 and renumbered to S-14 in Amendment 23 dated October 7, 1993). The information i g in License Condition S-23 was incorporated into License Condition S-9 by adding the i g date of May 25, 1989; License Condition S-9 later became S-1. 4 N i y S-15. At the end of plant life, the licensee shall decontaminate the site and facilities,  ;

g authorized as a place of use for special nuclear material, in accordance with the g y general decommissioning plan submitted by your letter dated July 25, 1986, and its l g

g supplement dated October 15, 1986, so that these facilities and grounds can be l g

g released for unrestricted use. The corporate commitment that funds will be made ,

y available for decommissioning the facility, provided by letter dated September 10, y 1986, is hereby incorporated as a condition of the license.

9 (l3 1 y 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

((

g y Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use y or Termination of Licenses for Byproduct, Source, or Special Nuclear Material,"

dated April 1993.

j y i, S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned y

and released for general use. j S-18. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the trip E levels will be read,iusted after each monthly test of the criticality alarm system E E if the alarm point fails to activate within approximately 5 seconds, more than once j!!

% out of four trials. f S i jE 3lS-19.NotwithstandingthestatementsinSection4.2.1.4,PartIIofthelicense,no i E

% material handling shall be allowed in any area in which the required criticality jE E

j alarm system is inoperative. f M i B; S-20. Deleted by Amendment 37, September 1996.

and released for general use, The SVA facility has been decommissioned lE E

% jE B) ;E Mj S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to y M the licensee on October 3, 1988. fi f'

>lS-22 B

b,

. Deleted by Ameadment 37, September 1996. The SVA facility has been decommissioned and released for general use.

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MATERIALS LICENSE SNM-696 Amendmnet 38 Docket or Reference Number g! SUPPLEMENTARY SHEET 70-734 y SAFETY CONDITIONS N

N .

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N S-23. The licensee shall maintain and execute the response measures described in the t-

, N Emergency Plan dated August 1995 (letter dated August 30,1995), and as revised by i

N letter dated June 6, 1996, with pages dated May 1996; or as further revised by the i-.

N licensee consistent with the provisions of 10 CFR 70.32(i). ;_

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. 3 SNM-696 Amendmer.t 36 3 MATERI ALS LICENSE tw Let or Reference Number 3 SUPPLEMENTARY SHEET 70-734 W

I 3 SAFEGUARDS CONDITIONS I

B 3

a j SAFEGUARDS CONDITIONS Bj >

3' ,

&a! SECTION 1.0 -- FACILITY ORGANIZATION ,

Currently there are no license conditions in this section. The necessary information has jlbeenincorporatedintoanapprovedplan, y'

3 5

g SECTION 2.0 -- FACILITY OPERATION l

fSG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession I y only license.

l l SG-2.2 Deleted by Amendment 37, September 1996.

only license.

Not applicable under a possession I

g 3 SG-2.3 3

Deleted by Amendment 37, September 1996. Not applicable under a possession I only license. i' 3 i 5 SG-2.4 Deleted by Amendment 37, September 1996. i Not applicable ;nder a possession only license. il 3 P 5 SECTION 3.0 -- MEASUREMENTS i 3 5 3 SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession E 3 only license. E 3  ;#

3 SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession 3 only license. lE ji s

alSG-3.3only license.

E Bj Deleted by Amendment 37, September 1996. Not applicable under a possession !i E

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3lSECTION4.0--MEASUREMENTCONTROL a.

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s E Deleted by Amendment 37, September 1996. Not applicable under a possession 3lSG-4.1only license.

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SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession 3

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, I SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession 'E l

I only license. !s E I 'E F2 SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession  %

, l9 only license. 's b

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. N ,- SNM-696 Amendment 38 g MATERIALS LICENSE om tei or wei cr surnber '

p SUPPLEMENTARY SHEET 70-734 N

g SAFEGUARDS CONDITIONS N

N N

y SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession g only license.

N ,1 g SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession ,l g only license. ,

N i y SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession y only license. h!

3 N i I g SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

ji y ,l l SECTION 5.0 -- INVENTORY [j l l SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession  !

only license. l,

. SG-5.2 Deleted by Amer.duent 37, September 1996. Not applicable under a possession i only license.

l l l SG-5.3 Deleted by Amendment 37, September 1996. Not applicattle under a possession I only license.

5 SECTION 6.0 -- RECORDS AND REPORTS N

W SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession N only license.

N

N SECTION 7.0 -- INTERNAL CONTROL N lI i B SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession liI N only license.

N N SECTION 8.0 -- MANAGEMENT liE

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N B SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession lE jE '

N only license. E d I h SECTION 9.0 -- PHYSICAL PROTECTION RE0VIREMENTS FOR FORMULA OUANTITIES OF STR 'EE N SPECIAL NUCLEAR MATERIAL N

fE jE i Nj SG-9.1 The licensee shall follow the measures described in the physical protection E N plan entitled, " Fixed Site and Transportation Plan for the Protection of I' I Special Nuclear Material of Moderate and Low Strategic Significance," dated May N

1989, submitted by letter dated May 8, 1989; and as it may be further revised ls E

bll N in accordance with the provisions of 10 CFR 70.32(e). s g'i l#

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l SG-10.1 Deleted by Amendment 31, dated July 1995. l SG-10.2 Deleted by Amendment 31, datd July 1995.

I SG-10.3 Deleted by Amendment 31, dated July 1995.

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