ML20235Z296
| ML20235Z296 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 10/07/1987 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20235Z279 | List: |
| References | |
| NUDOCS 8710210076 | |
| Download: ML20235Z296 (4) | |
Text
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L PAGE~
OF PAGES 6 84 U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE Pursuant to the Atomic Energy.Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, l
Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y
heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, i
source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below;to I
deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part{s)J This I
I license shall be deemed to wnain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations end orders of the Nuclear Regulatory Commission now or hereafter in effect and to any -
conditions specified below.
i Licensee
'l
'I Energy Systems Group SNM-21, as renewed 3 meense numbu Rockwell International Corporation June 28, 1984 i
l me_
b Q [Ej,ftik4 ate June 30, 1989 l
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8900 DeSoto Avenuc
- 5. Docket or 7 70-25 l
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Canoga Park, CA 91304 h Reference No.
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- 6. Byproduct, source,and/or
- 7. Chemical and/or physical U Maximum amount thatlicensee N
ay possess at any one time special nuclear material form Mder thislicense m
h N.
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I p.
n eb A.
kilograms U-235*
A.
Uranium enriche in U-235 isotepe I rmhp)enUp e
i B.
Pu (principall u-23 B
'B.
aximumof2.0 kilograms l
otal Pu*
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h G
p $y y
NSSFL" Site! Hot' l
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y:
Laboratory - up i
L x h to 2.0 kilograms H
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Pu in irradiated i
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and/or unirradiated
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fuel with less than l
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1.0 kg Pu in process 2.
A maximum of 2 g.
W total Pu for. gamma N
i spectroscopy and l
radiometric counting y
analysis used in any y,
authorized building p
at the SSFL' site in H
accordance with NRC B
N approved radiation
" safety criteria.
W CEnriched uranium and plutonium in combination not to exceed 5.0 formula kg calculated by 2
P kgU-235+(2.5)(kgPu).
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'NBC Form F4A U.S. NUCLEAR REGULATORY COMMISSION 2
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License number f
MMEIUALS LICENSE ts SUPPLEMENT ARY SHEET 70 25-E, i
E' I
i I
i C.
Pu (principally Pu-239)
C.
Sealed sources C.
1.0 kilograms total I
(as Pu-Be sources)
Pu in any authorized I
building at the.SSFL I
I
' site in accordance with l
NRC approved radiation safety criteria.
l R.
i I 9.
Authorized use: For use in accordance with statements, representations, and P.
! conditions contained in Part I of the licensee's application dated August.20,1982, and
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l supplements dated October 29, and Decembe 17 82 March 2, March 7, May 29, and g
June 12, 1984, and September 22, 198 g
\\' ding 020 and other aut buildings at the g
i 10. Authorized Place of Use:
i licensee's Santa Susana Fiel oratory in Chatsworth, Cal
, as described in
! the referenced application supplements and as specified in dition 8.B.2 and 8.C.
N Notwithstanding the stateme ts in Section 1.2, the Canoga Pa fafflitiesandBuilding ttriglicense.
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l 055attheSSFLsiteare(ogtaMhor,zedasplacesofuse n
decladding, removal of @nding mat r: h,, exd ;;i tlo,
ly for he purpose of I
l 11. Notwithstanding Sec on 1.5(' 5 P1 shaLi ha
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4.tepackagig r
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E E
! 12. Notwithstanding t state t
'ec W
. eNanuf ctureyf fuel element 4
l l assemblies and related tivi althc is (censeh
- a, '
l l
5 g
4 j
d i 13. TheminimumqualificAtion$
t g d feg' AdviTor and the Physicist p.
{
! on the Fuels Committee sha'il beli i
J f Physi h Sciences and a y !
i minimum of two years' expefencE Q ticalit f. safety analyses.
E j All personnel, prior Yodiosupervi ed wo
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i se al n ' lear materials, shall 14 l1 l rec.eiveformaltraininginnukle#Tcritical land /or radiat safety. The
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y effectivenessofthetrainingprodramshallbemeasuredby\\mittenexamination.
g E
Y ktf E
Copies of nuclear safety analys6s, afIitic'a itf(studies, and other reports prepared l
F l
i 15.
E
! by the Criticality Safeguards Coordinator br Criticality Safeguards Advisor regarding E
E radiation or nuclear criticality safety shall be maintained for a period of at least.
l 2 years or for 6 months after a proiect is tehninated, whichever is longer.
l-E-
s 16. Process designs shall incorporate sufficient factors of' safety to require at least g
i two unlikely, independent, and concurrent changes in process conditions before a E
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! criticality accident is possible.
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E
!I E
i R
E I
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! by kg U-235 + (2.5)(kg Pu).
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I fMIC Form 374A U.S. NUCLEAR REGULATORY COMMISSCN
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'I PAGE OF PAGES (5 84)
MATERIALS LICENSE
- "'***}[2 SUPPLEMENTARY SHEET 7
U i
l
- 17. Notwithstanding the use of alternative methods of calculation specified in Section 4.2.1 of Part I of the license application, only methods.of analysis for calculating nuclear criticality safety parameters, satisfactorily demonstrated to the Commission and approved by it, shall be used in the evaluation of nuclear criticality safety.
- 18. The license shall check the director of air flow in the hot cell facility each month. When adverse air flows are detected, corrective action shall be taken and documented.
@loREsegjing in-plant airborne sampling
- 19. The licensee shall comply with
[
and monitoring:
(
i
' a.
Notwithstanding the statq inSection3.2.4.2(1)of plication, the breathing zone air, in work area Q re the dispersible form of radi tive material is handled, shall be sampRv for airborne radioactive material ing the normal operations.
Cry N
A b.
The fixed air samp shall e ed,anDuq11y enever process or equipment 41rbo alko e ion of oactivity collected changes are made t rify thq
. Rof hei ai o{$ breathed workers.- In attheselocationsTerepreseg)t' addition, prior to djece c
w T4 aratha@asbeenshutdown 4
for more than 6 mogtas, t c
fFr sai
's h e cDasked to verify the representativeness W9 the s mg
- 20. The licensee's bio pf{g lo A
u 1 1 1
th lowing:
area (whe [O f
~
. ulated G shall submit urine a.
Employees working in t
e 3
g s
3 samples at least quart r) for routine ym ysis i
consecutive 7-day period, o$d to greater than 40 MPChrs of plutonium If an employee has been exp j
b.
r if tgLina sis sh s>
2 dpm of Pu per day, then fecal
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analysis shall be performed to efU u e@c f fecal analysis indicates a i
significant exposure to plutonium, t ifPv lung counting shall also be performed.
]
l c.
If in-vivo lung counting indicates an individual has a MPLB, the employee shall be j
immediately removed from further exposure.
d.
The dose commitment from Am shall also be considered in the above Pu bioassay
)
program.
j l,.
1 R
- 21. The licensee shall comply with the following regarding the surface contamination:
I a.
Prior to exiting a restricted area, all individuals must monitor hands, head, y
personal clothing and shoes for radiation contamination.
b.
The licensee shall not allow an individual whose skin, personal clothing or shoes are found contaminated above background levels to exit a restricted area without l
prior approval of the Radiation and Nuclear Safety Unit.
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P I,
_______________________________J j
NT C Form 37[.A U.S. NUCLEAR REGULATORY COMMISSION 4
4 pg y
Lic'"5' "*"b
SNM-21 h
I MATERIALS LICriNSE E
I ooctei or aererence number SUPPLEMENTARY SHEET 70-25 li I
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- 22. The licensee shall conduct leak tasting of the encapsulated plutonium in accordance with Annex A. " License Condition for Leak Testing Seale j Plutonium Sources," dated November 1979.
l-L
- 23. Release of equipment and packages from the plant site or to unrestricted areas onsite shall be in accordance with Annex B, " Guidelines for Decontamination of Facilities and Equipment Prior to release for Unrestricted Use or Termination of Licenses for
{ Byproduct, Source or Special Nuclear Material," dated August 1987,
- 24. The licensee shall mainta h and execu e es onse measures of his Radiological Contingency Plan submitted to the C Ts 8, 1981, and revised on March 3, E
1982.
The licensee shall also pr Th maintain nting procedures for his
{
Radiological Contingency Plan a essary to implement i n.
The licensee shall g
in his Radiol Contingency Plan that wo 1 ecrease the response t
make no change,f the Plan effectiveness o ut prior Commission approval as idenced by a license
[
amendment. The licensee m y.make changes to his Radiological ngency Plan without t
l prior Commission approva f
anges do not decrease e
s e effectiveness of
[
s the Plan. The licensee 11 ma ' '
records of cha t ar de to the Plan
[
te of he change and shall without prior approval a peri F wo fr dustria}d snd Medical Nuclear i
Safety, NMSS, U.S. Nucigr Regula@T gach i
furnish the Chief, Fue ele Safe y
n, DC 20$,20, a report and the p
'L i
n W appropriate NRC Region L1 Offic p"ec 1 pp 10 CFR Par E
containing a descripti51rof h
Nthin six a le the ange is made.
E thkacilityandsitein
- 25. At the end of plan life c N' q s u 1 1
'conta accordance with the gen dec a l r ;
tt the eqclosures to letter p
dated March 15, 1978, so t th
>can b leased for g
unrestricted use. The f
)cial o
ha s wil available for
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3 letter e
2 i
reby incorporated as a
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decommissioning, submitt'e yh
, 78, Q F
condition of the license.
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- 48 l
E E
p p
E FOR THE NUCLEAR REGULATORY COMMISSION higiM'. Signed By:
l 7g U"8 By:
Date:
Division of Industrial and Medical N
l Nuclear Safety N
Washington, DC 20555 l
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