ML20198R057
| ML20198R057 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 11/04/1997 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20198R056 | List: |
| References | |
| NUDOCS 9711130142 | |
| Download: ML20198R057 (9) | |
Text
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%C FORM 374 U.S. NUCLEAn CE!ULATORY COMMisslON w' l M ATERI AI.S 1.lCENSE 7,
ip f g Pursumut to the Atomic i:ncrF) Att of 1954, as amended, the Eneig) Heorganisation Act of 1974 (Public l.aw 93 438), and htle I ederaf Rc'gulations, Chapter I. Parts 30,31,32,33,34,35,36,39,40. and 70, and in reban6e on statement
- and representations heretofore rnade R yl by the licer ec, a license is heretiy inucs' authortrin: the licensee to recen e, acquire, pourts, and transfer by product, source, and specia I mziertal designated below; to uw such rnaterial for the purpo6e(0 and at the place (O designated below, to deliner or transfer such material to f
%j persons authoriied to reten e it in accordance with the reputatiom of the applica N
specified in Section 183 of the Atomic rnergy Act of 1954, a amended, and is subject to all applicable rules, reputations, and orders of the ej
% Nutlear Regulatory Commissmn nc w or ' reafter in ef fect and to any (onditmns specified below, y
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$y Licensee l.
3,1,icense Number jel 8(
N General Atomics SNH 696, Miendment 40
$j 2.
"'P '"' i"" D"
December 31, 1989 n$1 i
N P.O. Box 85608
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San Diego, California 92186 9784
- s. noctet or f
iteference No..
70 734 g!
- 6. flyproduct, Source, and/or
- 7. ChemicC and/or Physical
- 8. Maximum Amour,1that Licensee
$l l
Special Nuclear Material Form May Powess at Any One Time Ql a
Under This License gl g
,.3 p,
I A.
Urtnium A.
Enriched up to 19.99%
A.
200 kilograms U-235 6
l U-235 i
B.
Uranium B.
Enriched 20 to 100% U-235 8.
Less than 5000 gm*
A C.
U-233 C.
Any C.
Less than 2000 gm U-233*
rl y
D.
Plutonium D.
Encapsulatedand/or D.
Less than 2000 gm j
sealed sources total Pu*
g s
c!
i E.
Plutonium E.
Bred but unseparated E.
Less than 1000 gm 3
total Pu*
gl
- t F.
Plutonium F.
Plated calibration F.
Less than 5 grams jel 9
source total Pu*
gl ai Ml G.
Plutonium G.
Solutions, precipitates G.
Less thar. 5 grams solids and total Pu*
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The sum total quantity of strategic special nuclear material possessed at any one l
/
time must be less than 5,000 grams computed by the formula:
2 Grams -
grams U-235 in uranium enriched to 20% or iaore plus 2.5 (grams U-233 +
9 Ml p
grams plutonium)
[
The licensee's San Diego, California site as specified in 2+
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9.
Authorized place of use:
/
the aforesaid application and supplements.
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FORM 374A U.S. NUCLEAR REGULATORY COMM:SSION PAGE 2
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SNM-696 Amendment 40 g
I MATERI AI,S I,1 CENSE twrt tv Hefereswe Numter SUPPLEMENTARY SHEET 70-734 g
i E
E E
E 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, c p B R E c; yl g n
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By:
Michael F. leber E
Division ofrfuel Cycle Safety
'E Y M and, Safeguards, NMSS R-Washington, DC 20555 E
N (Provided w/ Amendment 31)
E
Enclosures:
- 1. License Condition for Leak Testing E
Sealed Plutonium Sources, dtd 4/93 E
E
- 2. License Condition for Plutonium Alpha E
Sources,dtd4/93 E
E
- 3. Guidelines for Decontamination of E
Facilities..., dtd 4/93 E
E E
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FORM 374A u.s.NUCLEAQ MOULATORY COMMIS8 ton MGE 3
or 9
PAGES.g Lkenne Nutut:3t g.
SNM 696 Amendment 40 g
MATERI Al,S I,1 CENSE (Met w Reimw Nundet g
1 S
SUPPLEMENTARY SHEET 70-734 4
E i
SAFETY CONDITIONS N
t a
N N
SAFETY CONDITIONS N
N S 1.
Authorized'use:
for use in accordance with statements, representations, and 8
conditions contained in Part II
" License Specifications" dated July 24, 1981, and N
N.
supplements dated March 16 and December 24, 1982; february 4, Wovember 14, and W
November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; M
December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; W
March 4, March 9 (2), March 22, April 26, August 22 Septemb.er 8, and November 2, t
1988; May 25 and Nove.nber 17, 1989; June 27 -1990; April 30 and September 27, 1991; E
March 5, March 18, June-24, and September 10, 1992;. January 20, 1995; and in the N
"SVA Decommissioning Plan" dated April 1, 1990 (submitted by letter dated March 30, W
1990); August 22, 1990-(submitted by letter dated August 24, 1990); June 15, 1992; d
July 12 and August 23, 1994; Group 6 Laboratories unrestricted use request dated W
August 12, 1994; March 1, 1995; Group 7 Laboratories unrestricted us9 request dated W
W,i December 5, 1995;~ Group.88 Laboratories unrestricted use reques. dated August 23, a
1996; October 15, 1996, and April 30, 1997; April 30, July 2, and August 13, 1997 g
gj gj (non-impactedareasunrestricteduse).
N a
NlS-2. Records of all safety related reports and analyses sh'11 be retained as fo g
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Copies of criticality and radiation safety analyses shall be retained for at a
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least 2 years or for 6 months after a project is terminated, whichever is a
a.
p longer.
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Copies oi all other safety-related records (e.g., plant alterations and y
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additions, abnormal occurrences associated with radioactivity releases, audits In l
p and inspections, instrument calibrations, ALARA findinc, + aining and g
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retraining, personnel exposures, routine radiation ane ;.n ;.onmental surveys) y l
gl shall be retained for at least 2 years or longer if required by regulations.
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S-3.
Notwithstanding the statements in Section 5.4.2 in the License Pccification Volume Ig g!
(PartII),ifdoublebatchingisnotcredible,themaximumsafebatchsizeshallbeI g!
no more than 75 percent of the minimum critical mass independent of the degree of gl water moderation and reflection. However, when the Th/U atomic ratio is 2 3.6 and !gg l
the H/0 s 20, the maximum safe batch size may be increased to 790 g contained U-235 Ig g
g independent of whether doubic batching is credible.
l l
y S-4.
The Director QACD, upon reconnendation of the appropriate manager within QACD, g!
shall have authority to require immediate-termination of activities and/or l
corrective action in any situation which, in their judgment, could lead to the
!gn g
ua.secessary exposure of personnel to ionizing radiation, release of radioactive lg material, loss or damage of property, o, non-compliance with the license or a
!g regulation.
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SNM-696 Amendment 40
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l M ATERI Al,S 1.lCENSE Meur McInnu Numkt Ill g
SUPPLEMENTARY SHEET 70-734 l
SAFETY CONDITIONS
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g S-5.
The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA E'
Committee, shall meet at least araually to review (1) reports of audits and E
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 int personnel exposures for identifiable categories of workers types of operations, ore effluent releases. (b) if exposures and releases might be lowered in accordance j(
with the ALARA concept. and (c) if equipment for effluent and exposure control is N
being properly used, maintained, and inspected.
W E
The CRSC evaluation, recoranendations, and corrective actions shall be documented g
4
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and the report shall be sent to the appropriate operations managers and t.he Vice gll g
N President. Finance and Administration!' t~'
7 I
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f S 6.
Radiological Work Permits (RWPS) shall be issued for=all un)lanned or non routine h p
r work with licensed material not covered by a WA.
TheRWPslallbesignedbyHealth(
h Physics management'or a senior staff member before related work can commence.
A l
l senior staff member shall be a Health Physics Technician having a minimum of lhl 5 years' experience in radiation safety.
An evaluation of the safety effectiveness!
of the permit shall be made upon completion of the work.
I l
l S-7.
Radiation safety training, appropriate to the employee's needs shall be given to !
l all new employees.
I l
l S-8.
Radiation safety training and indoctrination shall be conducted by the Health l
l l
Physics Manager or by a similarly qualified individual.
The Health Physics Manager may delegate training in that portion of the course to an individual who is uniquely qualified to present it.
(
S-9.
Continuous air shmpling shall be conducted in any area where licensed material can l
gl become airborne S-10.ThelocationofairsamplersshallbecheckedannuallyandwheneveranyprocessorM l
equipment changes are made to verify the representativeness of work area air
.5 sampling.
In addition, the location of air samolers shall be checked at the
'E commencement of operations in any area that has'been shutdown for more than E
6 months to verify the representativeness of air sampling.
S-11. The laboratories in which plutonium in a dis)ersible form may be used shall have exhaust ventilation systems separate from otler building exhausts and shall provid(
dual HEPA filtering of the effluent air.
S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specifietM in the attached " License Condition for Leak Testing Sealed Plutonium Sources."
,E l E
dated April 1993.
Plutonium alpha sources shall be subject to the actions specified in the attached l l
" License Condition for Plutonium Alpha Sources " dated April 1993.
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PAGES Lkerne Number lg SNM-696 Amendment 40
(
MATERI Al.S 1,1 CENSE poaci o, acrevence Numter
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SUPPLEMENTARY SHEtIT 70-734 g
SAFETY CONDITIONS g
E 4
4 W
S-13. The licensee shall prepare and submit to the Cnief. Licensing Branch Division of I
Fuel Cycle Safety and Safeguards NMSS U.S. Nuclear Regulatory Commission.
B Washington, DC 20555. a report whenever there is any new residential development j
within 1 mile around the site that constitutes a significant change in parameters lj that may be affected by the release of radioactive materials into the environment.
E S-14 Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 -
g 1992 and renumbered to S-14 in Amendment 23 dated October 7. 1993).
The y ;,
information in License Condition S-23,was, incorporated into License Condition S-9 g
by adding the date of May 25.1989fLicense[ Conditions-9.laterbecameS-1.
g.
1 S-15. At the end of plant lif51 the licensee shall decontaminite the site and facilities.
l authorized as a place'of use for special nuclear material. in accordance with the anditsf g
general decommissioning plan submitted by your letter' dated July 25, 1986, supplenient dated October 15. 1986, so that these facilities and grounds can be g
released for unrestricted use.
The corpor W commitment that funds will be made available for decommissioning the facility. m )vided by letter dated September 10.
y.
i 1986, is hereby incorporated as a condition of the license.
I S-16. Release of equipment. facilities, or packages to the unrestricted area or to uncontrolled areas ensite shall be in accordance with the attached " Guidelines for jU:
y i
g Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use E
or Termination of Licenses for Byproduct. Source, or Special Nuclear Material."
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dated April 1993.
j N
S-17. Deleted by Amendment 37A September 1996.' The SVA facility has been decommissioned lE f
and released for' general ~use.
I S-18. Notwithstanding he statement in Section=4.2.1:4. Part II of the license, the trip 4
levels will be readjusted after each monthly test of the criticality alarm system E
E if the alarm point fails to activate within appruimately 5 seconds, more than oncce E
out of four trials.
ju E
S-19. Notwithstanding the statements 'in Section 4.2.1.4. Part 11 of the license, no E
material handling shall be allowed in any area in which the required criticality 4
alarm system is inoperative.
N 8
9 S-20. Deleted by Amendment 37. September 1996.
The SVA facility has been decommissioned W P
and released for general use.
E E
S-21. Deleted by Amendment 31 dated September 1995.
Fuel elements were shipped back to the licensee on October 3. 1988.
W 4
S-22. Deleted by Amendment 37. September 1996.
The SVA facility has been decommissioned l
l 5
and released for general use.
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lg MATERIALS LICENSE IMet w Referenn Number 1
SUPPLEMENTARY SHEET 70-734 E
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. S 23. The licensee shall maintain and execute the response measures described in the E
Emergency Plan dated August 1995 (letter dated August 30,1995), and as revised by E
letter dated June 6, 1996, with pages dated May 1996; or as further revised by the E
licensee consistent with the provisions of 10 CFR 70.32(1).
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SAFEGUARDS ;0NDITIONS E
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I SECTION 1.0 -- FACILITY GRGANIZATION t
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t Currently there are no license conditions in this section.
The necessary information has t
been incorporated into an approved plan.
E E
i SECTION 2.0 -- FACILITY OPERATIQN E
SG-2.1 Deleted by Amendment 37, Seipt'e r1 6 t[',applicableunderapossession I
only license.
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E DeletedbyAmendme'nh37, September 1996. Notapplica6leunderapossession g
SG-2,2 only license.
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!SG-2.3 Deleted by Amendment 37,l eptember 1996. Not applicable'under a possession g
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SECTION 3.0 -- MEASUREMENTS s4 <
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SG-3.1 Deleted by Amendment 37, September 1996.;f Not applicable under a possession l,
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,o SG-3.2 Deleted by Amendment 37, September 1996. Notapplicab.le'under a possession f
%b only license.
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E SG-3.3 Deleted by Amendment <37, September 1996.
Not applicable under a possession only license.
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- I SECTION 4.0 -- MEASUREMENT CONTROL E
I 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 E
j only license.
E E
SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession
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only license.
- E E
q j SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession E
i only license.
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e SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession E
E only licer:se.
E SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession i
only license.
I E
SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession i
only license.
E E
DeletedbyAmendment37, September 1996.-(Notapplicable,underapossession 3
SG 4.8 only license.
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SECTION 5.0 -- INVENTORY d.) "
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SG 5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession g
only license.
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g SG 5.2 Deleted by Amendment 37,? September 1996. Not applicable t'nder a possession y
y onlylicense.J p'
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!SG5.3 DeletedbyAadndment37, September 1996.'Ndapplicableut,erapossession t
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g g] SECJION 6.0 -- RECORDS!'AND REPORTS
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p SG 6.1 Deleted by Amendment 37. September :1996.? Not applicable.under a possession g
only li:anse.. ;
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p SECTION 7.0 -- INTERNAL CONTROL J
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SG-7.1 Deleted by Amendment,37, September 1996. Not applicable under a possession I
only license.
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SECTION 8.0 -- MANAGEMENT is E
I SG 8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession E
only license.
E N SECTION 9.0 -- PHYSICAL PROTECTION REOUIREMENTS FOR FORMULA OUANTITIES OF STRATEGIC E
E SG-9.1 The licensee shall follow the measures describeo in the physicci protection E
E plan entitled, " Fixed Site and Transportation Plan for the Protection of lE Special Nuclear Material of Moderate and Low Strategic Significance," dated May 1989, submitted by letter dated May 8, 1989; and as it may be further revised E
inaccordancewiththeprovisionsof10CFR70.32(e).
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SECTION -10.0 -- TEMPORARV OR ONE TIME CONDIll.0HS E
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W SG-10.1 Deleted by Amendment 31, dated July 1995.
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I SG 10.2 Deleted by Amendment 31, dated July 1995.
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SG-10.3 Deleted by /vnendcent 31, dated July 1995.
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