ML20133G879
| ML20133G879 | |
| Person / Time | |
|---|---|
| Site: | 07003000 |
| Issue date: | 10/08/1985 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20133G866 | List: |
| References | |
| NUDOCS 8510160169 | |
| Download: ML20133G879 (4) | |
Text
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4 y (5 04 U.S. NUCLEAR REGULATORY COMMISSION PAGE OF PAGES N
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MATERIALS LICENSE g
Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 -438), and Title 10, g
Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y
g heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, g
N source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to l
N deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This l
E license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is I
subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
y Ucensee 1.
Commonwealth Edison Company (CECO)
- 3. License number SNM-1938, revised in l
its entirety One First National Plaza y
- 2. P.O. Box 767 O
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rs Chicago, Illinois 60690 Q,r'
- 4. Expiration #date August 31, 1990, or*
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- 5. Docket or y 7d.3.,000 E
Reference No.
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- 6. Byproduct, source, and/or
- 7. Chemical and/or physical 1 8 Maximum amount that licensee
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special nuclear material form S.may possess at any one time
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,u'nder this license A.
Uranium enriched in A.
In unirradiated 8 A.
3150 kg of U-235 h
the U-235 isotope-
) reactor fuel (ademblies
~ in uranium enriched h
\\hp L to no more than 3.55 y
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B 40g of U-235 at S
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Uranium enriched'in
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the U-235 isotope
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neutroln; detectors' 3 gany enrichment h
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Plutonium-239
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Authorized Use:
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l The materials are for use'in accordance with stateme'nts, representations, and conditions specified in the licensee's ? application dated June 8,1984, k
g and its supplements dated Septembe~r 18"and; November 19,1984, June 7
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g and July 31, 1985.
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- 10. Authorized Place of Use:
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The licensee's Braidwood Nuclear Generating Station, Unit 1, located in k
northeastern Illinois, 3 miles southwest of the Kankakee River, 20 miles f
g south-southwest of the town of Joliet, and 60 miles southwest of j
i Chicago, Illinois, as described in the aforesaid application.
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11.
Procedures, and changes thereto, for the control and handling of k
l nuclear fuel shall be reviewed and approved by an Operating Engineer E
g and the Technical Staff Supervisor. At least one of these individuals g
shall hold a Senior Reactor Operator's (SR0) License or SR0 Certification.
Upon conversion of construction Permit No. CPPR-132 to an operating license, O
p whichever is earlier.
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, l NRO Form 374A U.S. NUCLEAR REGULATORY COMMIS$10N 2
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""'""*'SNM-1938, revised in its
' I MATERIALS LICENSE entirety I
SUPPLEMENTARY SHEET O3 l,
- 12. The minimum technical qualifications for the Station Superintendent I
shall be in accordance with Section 4.2.1, " Plant Manager," of ANSI I
N18.1-1971 before receipt of fuel onsite.
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- 13. The minimum technical qualifications for the Fuel Handling Foreman y
shall be in accordance with Section 4.3.1, " Supervisors Requiring y
AEC Licenses," of ANSI N18.1-1971, with the exception of the licensing i
j requirements, by the date of fuel receipt onsite.
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- 14. The minimum technical qualifications for the Station Health Physicist l
'l shall be in accordance with the requireprts,for Radiation Protection y
i Manager of Regulatory Guide 18,pSeptembdr -1975Q g
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n (g,15. The minimum technical qualifications for the Operating Engineer shall N
be in accordance with Section 4.3.2, " Supervisors Requiring AEC Licenses,"
of ANSI N18.1-1971 before receipt of fuel onsite. However, the Operating l
Engineer need not have a Senior Reactor Operator's (SRO) License or SR0 g
Certification provided the Technical Staff Supervisor has one.
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16.
The minimum technical qualifications for.the Tech'nical Staf f. Supervisor shall be in accordance with;Seition 4.6;1,'" Engineer in Charge," of
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ANSI N18.1-1971 before the rechipt oflfuell onsite, g!
The following training shall dcoifducted,pr f[rko' receipt of, fuel f
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17.
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)6 onsite:
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a.
All radiation-safety. personnel'shallibe, trained in radiation le safety and CECO radiation p'r'ot'ectioffprocedures related.to fuel lF
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g assembly handling.
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b.
All operations personnel involved in~ ~ uel handling shall receive f
h'i training in proper fuel handling procedures, including the related lp health and safety aspects &of the activities.-
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- 18. All preoperational testing of fuel handling' equipment, related to
@f activities authorized by this license, shall be conpleted and the test results shall be reviewed and approved by CECO engineering before y
receipt of fuel onsite. This includes the testing of the following:
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a.
The fuel assembly handling fixture tool.
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The Rod Cluster Control Assembly (RCCA) handling fixture, P
c.
The fuel storage racks in the new fuel vault, and l
d.
The fuel handling building crane.
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y,N C Fem 374A U.S. NUCLEAR REGULATORY COMMISSION 3
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SNM-1938, revised in its ~ t i
MATERIALS LICENSE entjrcly h
I SUPPLEMENTARY SHEET 70-3000 a
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- 19. Fuel assemblies shall be stored in such a manner that water would
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drain freely from the assemblies in the event of flooding and f
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subsequent draining of the fuel storage area.
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- 20. New fuel assemblies may be stored in the Spent Fuel Storage Pool I
subject to the following additional conditions:
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The maximum U-235 enrichment shall be 3.22 w/c.
l The fuel assemblies shall be\\s8rebin3a]heckerboard pattern.
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The Fuel Handling (oreman shall verify correct'ftfels assembly l
c.
I; location after insert' ion of each fuel assembly in'to^the assigned f
s. rage rack in,accordance with a prepared written p7rocedure j$
gj approved by an Operating Engineer and the Technical Staff Supervisor.
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d.
An independent loading. verification;s, hall be made by a Quality Control Insp ctor.
The Fuel Handling Foreman {and'the Qual'ityJontr'ol Inspector jij S
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shall each ' sign a documeiit antir.ing roper /s}irage,ofeach; h
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fuel assemblyi i
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The fuel assemblies 9hallIbetprotec d'tohrec g)j i
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preserve fuel tassembly~cleanlineis'MillNfu's1h,lude damage andis store'd;in the l1 i
Spent Fuel Storage Pool.
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j 21. No more than 60 shippingscontainers, containing fuel, yhall be stored j(
d onsite at any one time. //
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- 22. No more than one fuel assembly'$all belout/of Id shipping container lj or storage location at any given tim'e. '
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- 23. The minimum edge-to-edge distance between the fuel assembly outside iI; l
its shipping container or storage rack and all other fuel assemblies l
shall be 12 inches.
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The licensee is hereby exempted from the provisions of 10 CFR 70.24 I!
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as this section applies to material held under this license.
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- 25. Records of the radiation surveillance of the shipping containers with p
ljl the neutron detectors and of the detectors, when surveyed, shall be maintained gj f
and a copy of the results of each surveillance submitted to the Station F!
Health Physicist.
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- 26. The Post Accident Neutron Monitoring Detectors shall be stored in their shipping
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q containers in the locked calibration facility. The key to the calibration I
facility shall be under the control of the Shif t Engineer.
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- 27. A physical inventory of the neutron monitoring detectors shall be taken monthly j
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to confirm the presence of all the detectors.
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- 28. A 24-hour fire watch -shall be present in the areas adjacent to the fuel storage Il locations whenever fuel assemblies are onsite and the. automatic alarm system l
l is not functional.
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- 29. The licensee shall maintain and fully implement all provisions of the Commission i
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g approved Physical Security Plan, including changes made pursuant to the authority of 10 CFR 70.32(e). J The approved Physical Security,ESecurity for Commonwe q
P_lan consists of Revision 1 H
to the " Security Plan for Special Nuclear Materials I
t Edison Company, Braidwood Station," submitted with -the letter dated April 19, f
ql pursuant to 10 CFR 2.790(d).
f;N 1985.
The Physical Security Plan <shall be withheld from public disclosure 8
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f FOR THE U.S. NUCLEAR REGULATORY COMMISSION n
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Date:
By:
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Division of Fuel Cycle and
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g Washington, D.C.
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