ML20206D455
| ML20206D455 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 11/08/1988 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20206D444 | List: |
| References | |
| NUDOCS 8811170088 | |
| Download: ML20206D455 (3) | |
Text
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8A fM6@MT3fi.m n,gg l CC Forth 374 1
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U.S. NUCLEAn REGULATORY COMMISSloN
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' AGES MATERIALS LICENSE j
Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10.
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Code of Federal Regulations. Chapter I, Parts 30,31,32,33,34,35,40 and 70 and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acqui:e, possess, and transfer byproduct, 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). This :l license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as arrended, and is
,1 subject to all applicable rules, regulations cnd orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
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!l ljcensee I
.I 1.
Babcock & Wilcox
- 3. License number Naval Nuclear Fuel Division Amendment No. 6
.I NNFO Research Laboratory
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P.O. Box 11165 Lynchburg, VA 24506-1165
- 4. Expiration date
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.luly 11; 1992
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- 5. Docket or Reference No.
7{L.324
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- 6. Byproduct, source and/or
- 7. Chemical and/or physical
- 8. Maximum amount that licensee I
special nuclear material form may possess at any one time il under this license
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lf A.
Uranium enriched to A.
Encapsulated or A.
3.5 kg con-p
>20% in the U-235 irradiated tained U-235 Tsotope j
B.
Uranium enriched to.
B.
Unencapsulated B
0.53 kg con-
)
>20% in the U-235 and unirradiated tained U-235 Tsotope
!p C.
Uranium enriched >
C.
Encapsulated or-C.
1.2 kg con-k 5% to <20% in the irradiated tained U-235
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U-235 isotope fM 0.
Uranium enriched >-
0.
Unencapsulated D.
0.5 kg con-1 5% to (20% in the and unirradiated tained U-235
't U-235 isotope E.
Uranium enriched >
E.
Encapsulated or E.
55 kg con-l
.711% to <5% in the irradiated tained U-235 g
U-235 isotope k
F.
Uranium enriched >
f.
Unencapsulated F.
11 kg con-D
. 711% to < 5% in the an i /nirradiated tained U-235 U-235 isotope G.
U-233 G.
Any G.
1 gram y
1 k
H.
Plutonium H.
Unencapsulated H.
50 g
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and unirradiated k
I.
Source material I.
Any I.
6,000 kg 0G11170088 891109 f
PDR ADOCK 07000824 I
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U.S. NUCLE AR EE;ULATCY COMMISSION
,aac 2 or 3 RAGES I
NEC Form 374A
- f45848 Lkenne number I
I MATERIALS LICENSE D,77[g%,$,e$r f
m SUPPLEMENTARY SHEET p,g F
NOV 8 1988 y
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n J.
Fission products J.
Irradiated fuel J.
Quantity Ip l
& transuranium contained in
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elements 4 irradiated fuel assemblies r>
K.
Fission products K.
Irraofated fuel K.
5,000,000 Ci and tranr. N elements I)
!>l L.
Any byproduct L.
Irradiated L.
50,000 Ci il material structural il materials &
components y
il l
M.
Bypr.JuJct M.
Any M!
3,000 Ci each jf i
material with total not to il 8
Atomic nos. 3 exceed i
thru 83 1,000,000 Ci l>,
l N.
Troasuranium N.
Any N.
20 millicuries f>
l elements each total. lot to exceed
]l 100 millicuries j
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b 0.
Cf-252 0.
Sealed sources 0.
4 mg
!p l
k i>
P.
Am-241 P.
Sealed sources P.
30 Ci i>
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H-3 Q.
Sealed sources Q.
100 Ci j
k R.
H-3 R.
Oxide R.
3 Ci Y
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S.
H-3 S.
Ni plated Sc 5.
3 Ci j
tritide foil
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- 9. Authorized Use:
For use in accordance with the statements, representations, and
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conditions of Chapters 1 thru 8 of the license application dated November 26, 1985,
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and supplements dated May 27 and June 19, 1986; January 20, April 27, May 26, August
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1 10, September 1, and December 8, 1987; March 30, June 14 and June 20, 1988.
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l l 10. Authorized Place of Use:
The licensee's existing facilities at the NNF0 I
i Research Laboratory except Buildings A and C.
The room that houses the exhaust fan
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I and stack in Building C is an authorized place of use.
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l11.Sealedsourcesshallbetestedinaccordancewiththeenclosed"LicenseC
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for leak Testing Sealed Sources Which Contain Alpha and/or Beta gamma Emitters."
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E 1*3*1*37A A A a NRC Fem U4A U.S. NUCLE AR RECULATGY COMMISSION 3
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lacea number S T1-770 Amendment flo. 6 j
MATERIALS LICENSE I
SUPPLEMENTARY SHEET 70- 4 NOV r mn lp
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- 12. Release of equipment from the plant site to unrestricted areas or to onsite clean areas shall be in accordance with the enclosed "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination y
of License for Byproduct, Source, or Special Nuclear Material" dated May 1987.
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- 13. Within 90 days of the date of the license renewal, the licensee shall submit, for j
NRC's review and approval, a groundwater monitoring program for the detection of
'p potential leakage of the below grade tanks in the Liquid Waste Systcm (Building B).
y The program shall include the location of the wells, monitoring frequency, analysis action levels, and the reporting requirements.
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- 14. At the end of plant life, the licensee shall decontaminate the facility and site
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in accordance with the general Decommissioning Plan submitted with the renewal l,
application dated May 26, 1987, so that these facilities and grounds can be p
released for unrestricted use.
The financial commitment associated with the
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Plan, assuring funds for decommissioning, is hereby incorporated as a condition.
it of the license, j
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- 15. The entire laundry system shall be limited to one safe mass unit as definea in j
Section 4.2.2 for Building 8.
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p FOR THE NUCLEAR REGULATORY COMMISSION j
d'g On8 mal Signed By 1
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[Oate:
By:
Leland C. Rouse, Chief f
d Fuel Cycle Safety Branch i,
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$pth Medical Nuclear Safety Division of Industrial and
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M Office of Nuclear Material Safety P
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A and Safeguards
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