ML20129F250
| ML20129F250 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 09/26/1996 |
| From: | Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20129F241 | List: |
| References | |
| NUDOCS 9610010291 | |
| Download: ML20129F250 (9) | |
Text
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NRC FORM W4' U.S. NUCLE AQ REGULATOQY COMMIS$10N OI g
(10 39) tgi MATERIALS LICENSE 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, l (j Cede of Federal Regulations, Chapter I, Parts 30, 31,32,33,34,35, 39,40 and 70, and in rehance on statements and representations heretofore y d made by the licenwe, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special T N
nuclear matenal 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 spcified 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 y y
Regulatory Commission now or hereafter m effect and to any conditions specified below.
I J
I[m f'I Licensee I
N
- 3. License number I:
1.
f't:
l General Atomics SNM-696, Amendment 37 lI 2.
lI:
['
1 P.O. Box 85608
- 4. Expiration date December 31, 1989 I
San Diego, California 92186-9784
,I -
- 5. Docket or 1
it 70-734 ll Reference No jg; ll 6. Byproduct. source, and/or
- 7. Chemical and/or physical
- 6. Maximum amount that licensee
- I' I
special nuclear material form snay possess at any one time jI-I I
under this hcense E.
4 II; I
'I -
I A.
Uranium A.
Enriched up to 19.99%
A.
200 kilograms U-235
[
l U-235 lL l
i B.
Uranium B.
Enriched.20 to 100% U-235 B.
Less than 5000 gm*
t:
L h;I s
C.
U-233 C.
Any C.
Less than 2000 gm I
if I
'U-233*
(
L; D.
Plutonium D.. Encapsulated and/or D.
Less than 2000 gm I
I l
lJ1 sealed sources total Pu*
r; i
I I
E.
Plutonium E.
Bred but unseparated E.
Less than 1000 gm
,h;;
I total Pu*
I h
f l
F.
Plutonium F.
Plated calibration F.
Less than 5 grams source total Pu*
g{J i
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G.
Plutonium G.
Solutions, precipitates G.
Less than 5 grams l
solids and total Pu*
y I
n I
w I
The sum total quantity of strategic special nuclear material possessed at any one o
i l
time must be less 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 +
C I
grams plutonium) l I
l 9.
Authorized place of use:
The licensee's San Diego, California site as specified in the aforesaid application and supplements.
i I
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PAGES Lkense Number SNM-696 Amendment 37 J g MATERI ALS LICENSE LAxlet or Reference Number l
p SUPPLEMENTARY SHEET 70-734 i
N j
4 5
f M,17 E
E M
g N
N N 10.
This license shall be deemed to contain two sections: Safety Conditions and g
N Safeguards Conditions. These sections are part of the license, and the licensee is y
b subject to compliance with all listed conditions in each section.
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FOR THE NUCLEAR REGULATORY COMMISSION N
N E
9 N
N Date:-
M R 6f' By:
Robert C. Pierson N
~' /
Division of Fuel Cycle Safety E
N and Safeguards, NHSS E
E Washington, DC 20555 E
N E
N (Provided w/ Amendment 31)
E N
Enclosures:
- 1. License Condition for Leak Testing E
5 Sealed Plutonium Sources, dtd 4/93 E
N E
N
- 2. License Condition for Plutonium Alpha Ei N
Sources, dtd 4/93 E
i N
E l
N
- 3. Guidelines for Decontamination of E
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Facilities..., dtd 4/93 E
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NR FORM 374 A U.S. NUCLEAR REGULATORY COMMISSION I
PAGE 3
OF 9
PAGES gl g
License Number
! N SNM-696 Amendment 37 glj N
MATERI ALS LICENSE om ket or Reference Number N
SUPPLEMENTARY SHEET 70-734
!g )
g N
g l g
SAFETY CONDITIONS g j N
s N
5 N
E J
N E
N SAFETY CONDITIONS E
N N
S-1.
Authorized use:
For use in accordance with statements, representations, and E
N conditions contained in Part II
" License Specifications" dated July 24, 1981, and E
N supplements dated March 16, and December 24, 1982; February 4, November 14, and E
N November 15, 1983; April 10, April 12, June 28, Jeptember 4, and September 7, 1984; E
N December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; E
- E R
March 4, March 9, (2), March 22, April 26, August 22, September 8, and November 2, lE N
1988; May 25, and November 17, 1989; June 27, 1990; April 30 and September 27, N
1991; March 5, March 18, June 24, and September 10, 1992; January 20, September 26, lE Nl 1995; June 14, and July 19, 1996; and in the "SVA Decommissioning Plan" dated E
4 Nl April 1, 1990 (submitted by letter dated March 30,1990), August 22, 1990 E
N (submitted by letter dated August 24, 1990), June 15, 1992, July 12, 1994, E
)
N August 23, 1994, Group 6 laboratories unrestricted use request dated August 12, E
4 W
1994, and March 1, 1995, Group 7 laboratories unrestricted use request dated E
N December 5, 1995, and Hot Cell Facility Decommissioning plan dated July 6, 1995 E
2 N
with revisions dated November 20 and 30, and December 18, 1995.
E N
E N
S-2.
Records of all safety-related reports and analyses shall be retained as follows:
E R
R R
a.
Copies of criticality and radiation safety analyses shall be retained for at g
B least 2 years or for 6 months after a project is terminated, whichever is q
N longer.
g B
s g
b.
Copies of all other safety-related records (e.g., plant alterations and i
g additions, abnormal occurrences associated with radioactivity releases, audits y
2 y
and inspections, instrument calibrations, ALARA findings,' training and g
1 g
retraining, personnel exposures, routine radiation and environmental surveys) g y
shall be retained for at least 2 years or longer if required by regulations.
g l
S-3.
Notwithstanding the statements in Section 5.4.2 in the License Specification Volume ll' g
(Part II), if double batching is not credible, the maximum safe batch size shall be g
g no more than 75 percent of the minimum critical mass independent of the degree of g
g water moderation and reflection. However, when the Th/U atomic ratio is 1 3.6 and g
y the H/U 1 20, the maximum safe batch size may be increased to 790 g contained U-235 g
y independent of whether double batching is credible.
g l
1 S-4.
The Director QACO, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities and/or yj y
g' corrective action in any situation which, in their judgment, could lead to the g
unnecessary exposure of personnel to ionizing radiation, release of radioactive y!
material, loss or damage of property, or non-compliance with the license or a y
regulation.
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NR FORM 374A U.S. NUCLE AR REGULATORY COMMISSION g
PAGE 4
OF 9
PAGFS g
LKense Number l
I
. g SNM-696 Amendmnet 37 i
l i
1 !
W M ATERIALS LICENSE IMehdeference Number SUPPLEMENTARY SHEET 70-734 l
l N
I I g
SAFETY CONDITIONS I l l
S-5.
The Criticality and Radiation Safety Comittee (CRSC), functioning as an ALARA b'
g Comittee, shall meet at least annually to review (1) reports of audits and j
E inspections performed since the last ALARA review and (2) employee exposures and
{E y
effluent release data to determine (a) if there are any upward trends developing in N
personnel exposures for identifiable categories of workers,. types of operations, or N
N effluent releases, (b) if exposures and releases might be lowered in accordance E
N with the ALARA concept, and (c) if equipment for effluent and exposure control is E
f being properly used, maintained, and inspected.
N The CRSC evaluation, recomendations, and corrective actions shall be documented EI N
and the report shall be sent to the appropriate operations managers and the Vice E
N President, Finance and Administration.
E N
E N
S-6.
Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine E
work with licensed material not covered by a WA.
The RWP shall be signed by Health E
N Physics management or a senior staff member before related work can comence. A E
N senior staff member shall be a Health Physics Technician having a minimum of 5 E
B years' experience in radiation safety. An evaluation of the safety effectiveness E
N of the permit shall be made upon completion of the work.
E N
E B
S-7.
Radiation safety training, appropriate to the employee's needs, shall be given to E
N all new employees.
E N
.E B
S-8.
Radiation safety training and indoctrination shall be conducted by the Health El N
Physics Manager or by a similarly qualified individual.
The Health Physics Manager El B
may delegate training in that portion of the course to an individual who is El y
uniquely qualified to present it.
E!
N E'
g S-9.
Continuous air sampling shall be conducted r any area where licensed material can g
g become airborne, g
N E
y S-10. The location of air samplers shall be checked annually and whenever any process or g,
y equipment changes are made to verify the representativeness of work area air j
g sampling.
In addition, the location of air samplers shall be checked at the y
g commencement of operations in any area that has been shutdown for more than 6 g
g months to verify the representativeness of air sampling.
g 5
E y
S-11. The laboratories in which plutonium in a dispersible form may be used shall have g
y exhaust ventilation systems separate from other building exhausts and shall provide j y
dual HEPA filtering of the effluent air.
g l
S-12. Sealed Plutonium sources shall be subject to the leak testing and actioas specified E
E in the attached " License Condition for Leak Testing Sealed Plutonium Sources,"
g dated April 1993.
f y
! l Plutonium alpha sources shall be subject to the actions specified in the attached l
" License Condition for Plutonium Alpha Sources," dated April 1993.
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NR FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 5
OF 9
PAGES f l' g
LKense Number
! l
. p SNM-696 Amendment 37
! ll W
MNTERIALS LICENSE twLei or Reference Number g
SUPPLEMENTARY SHEET 70-734 l1 h
ll g
SAFETY CONDITIONS ll n
li B
l S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, I l y
g Washington, DC 20555, a report whenever there is any new residential development I
l within 1 mile around the site that constitutes a significant change in parameters H
g gl that may be affected by the release of radioactive materials into the environment.
f S-14 Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 -
E!.
l 1992 and renumbered to S-14 in Amendment 23 dated October 7, 1993). The information ElI 5
in License Condition S-23 was incorporated into License Condition S-9 by adding the Ej date of May 25, 1989; License Condition S-9 later became S-1.
4 S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, fE 5j authorized as a place of L.
-or special nuclear material, in accordance with the E
lE general decommissioning plar, abmitted by your letter dated July 25, 1986, and its N
supplement dated October 15, 1986, so that these facilities and grounds can be jE N
released for unrestricted use.
The corporate commitment that funds will be made j
s' available for decommissioning the facility, provided by letter dated September 10,
- l, N
1986, is hereby incorporated as a condition of the license.
j ll m
i W
S-16. Release of equipment, facilities, or packages to the unrestricted area or to l l 5
uncontrolled areas onsite shall be in accordance with the attached " Guidelines for H
Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use
! l!
lE 9
or Termination of Licenses for Byproduct, Source, or Special Nuclear Material,"
r 5
dated April 1993.
j B
E 5
S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned lE N
and released for general use.
E N
!E y
S-18. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the trip Ig y
levels will be readjusted after each monthly test of the criticality alarm system ls y
if the alarm point fails to activate within approximately 5 seconds, more than once l5 g
out of four trials.
!g B
E y
S-19. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no gl g
material handling shall be allowed in any area in which the required criticality
,gl gl alarm system is inoperative.
g 4
h S-20. Deleted by Amendment 37, September 1996.
The SVA facility has been decommissioned j
y and released for general use.
g W
~
g S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to y
the licensee on October 3, 1988.
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l 5
y1 S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned I l l
gl and released for general use.
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6
OF 9
PAGES License Number l
g SNM-696 Amendmnet 37 i
MATERI ALS LICENSE tw Lei or Reference Number SUPPLEMENTARY SHEET 70-734
! l N
sil gI SAFETY CONDITIONS gl B
E S-23. The licensee shall maintain and execute the response measures described in the E
Emergency Plan dated June 1994 (letter dated July 1, 1994) and as revised by letter E
dated January 30, 1995 with pages dated January 1995; revision dated May 1996 El (letter dated June 6, 1996) or as further revised by the licensee consistent with El the provisions of 10 CFR 70.32(i).
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NR FORM 374A U.S. NUCLEAR REGULATORY COMMISSION g
PAGE 7
OF 9
PAGES g
LKense Number I
j
- y SNM-696 Amendment 37 I
!g y
M ATERI ALS I,ICENSE IMet or Reference Number
(
g SUPPLEMENTARY SHEET 70-734 g
N E
1 l
g SAFEGUARDS CONDITIONS g
N s
N E
SAFEGUARDS CONDITIONS N
N E
N N
N SECTION 1.0 -- FACILITY ORGANIZATIQH E
E Currently there are no license conditions in this section.
The necessary information has N
been incorporated into an approved plan.
N SECTION 2.0 -- FACILITY OPERATION E
N E
N SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a ' possession E
N only license.
E N
E N
SG-2.2 Deleted by Amendment 37, September 1996.
Not applicable under a possession E
N only license.
E N
E N
SG-2.3 Deleted by Amendment 37, September 1996. Not applicable under a possession E
N only license.
E R
E N
SG-2.4 Deleted by Amendment 37, September 1996.
Not applicable under a possession E
N only license.
E i
N E
N SECTION 3.0 -- MEASUREMENTS q
N E
N SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession g
i l
N only license.
E'l N
E s
SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession g
g only license.
g N
lE y
SG-3.3 Deleted by Amendment 37, September 1996.
Not applicable under a possession g
g only license.
g N
E y
SECTION 4.0 -- P.ASUREMENT CONTROL g
N E
y SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession g
l y
only license.
g l
N E
l g
SG-4.2 Deleted by Amendment 37, September 1996.
Not applicable under a possession g
g only license.
gj l
SG-4.3 Deleted by Amendment 37, September 1996.
Not applicable under a possession j
y only license.
g l
SG-4.4 Deleted by Amendment 37, September 1996.
Not applicable under a possession ll g
only license, gj l
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'9 PAGES lxeme Number g.
. gl SNM-696 Amendment 37 I
~
N MATERIALS L.ICENSE t>x tei or neference Number g
i p
SUPPLEMENTARY SHEET 70-734 l
!g N
E y
SAFEGUARDS CONDITIONS
!g N
E N
E N
E p SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession s
i y
only license.
i i
N E
y SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession g
g only license.
g N
E,'
g SG-4.7 Deleted by Amendment 37, September 1996. Not app?icable under a possession g
y only license.
l SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession y
only license.
g SECTION 5.0 -- INVENTORY l
SG-5.1 Deleted by Amendment 37, September 1996.
Not applicable under a possession l
l only license, g
y 3
l E
SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
l y
l SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession N
g only license.
N N
SECTION 6.0 -- RECORDS AND REPORTS E
N E
N SG-6.1 Deleted by Amendment 37, September 1996.
Not applicable under a possession E i !
E only license.
E N
E E
SECTION 7.0 -- INTERNAL CONTROL E
N E
N SG-7.1 Deleted by Amendment 37, September 1996.
Not applicable under a possession E
R only license.
E N
E B
SECTION 8.0 -- MANAGEMENT E
B El N
SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession E
N only license.
E N.
E B
SECTION 9.0 -- PHYSICAL PROTECTION RE0VIREMENTS FOR FORMULA OUANTITIES OF STRATEGIC E
B SPECIAL NUCLEAR MATERIAL El N
El' B
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 E
lj M Special Nuclear Material of Moderate and Low Strategic Significance," dated May E
l N 1989, submitted by letter dated May 8, 1989; and as it may be further revised El 4
in accordance with the provisions of 10 CFR 70.32(e).
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 9
OF 9
pacts
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SNM-696 Amendment 37 I l N
MATERI ALS LICENSE
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SUPPLEMENTARY SHEET 70-734 g
i N
E l
W SAFEGUARDS CONDITIONS g
4 E
N E
N E
E SECTION -10.0 -- TEMPORARY OR ONE TIME CONDITIONS E
N E
N SG-10.1 Deleted by Amendment 31, dated July 1995.
N Nj E
N; SG-10.2 Deleted by Amendment 31, dated July 1995.
E 5
Ell N' SG-10.3 Deleted by Amendment 31, dated July 1995.
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