ML20203B936
| ML20203B936 | |
| Person / Time | |
|---|---|
| Site: | 07003008 |
| Issue date: | 04/09/1986 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20203B934 | List: |
| References | |
| NUDOCS 8604180300 | |
| Download: ML20203B936 (4) | |
Text
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ancr 373 1 3 l cp.se AE M PAMS U.S. NUCLEAD REGULATORY COMMISSION MATERIALS LICENSE l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10. I Coda of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations heret: fore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, g sourc2, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below;to l
-delivIt or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This i lic:nse 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 I conditions specified below. {Qpy l ucensee s* I Duquesne Light Company 'j Ohio Edison Company S?ti-1954
- 3. U. cense number
- 1. The Cleveland Electric Illuminating Company )I The Toledo Edison Company %
i
- 2. Robinson Plaza II , y Suite 210 '
- 4. Expiration date March 31,1991, or ** p PA Route 60 e' 5. Docket or 'i Pittsburgh, Pennsy1vania 15205' 70-3008 I
, Reference No. p
- 6. Byproduct, source,and/or 7. Chemical and/or physical 8. Maximum amount that licensee ,N special nuclear material form may powss at any one time 'l
_N under this license i M6 -
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- 6. Material 27DForm -
- 8. Quantity W i
N A. Uranium enriched A.; In unirradiated A. 2,000 kg of U-235 in in U-235 isotope ffuil: assemblies ^ uranium enriched to no !
- ;1;?- more than 3.15 w/o !
- ;ik -
- U-235 !
% yiNk*p B. Uranium enriched B.q Neutron detectors ,B.
85 g of U-235 in in U-235 isotope uranium at any enrichment l
C. Californium
<C. Primary source rods C. 200 uCi of Cf-252, maximum 100 uCi per rod
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D. Cs-137 D. Various calibration D. 300 millicuries of ;
and check sources Cs-137,maximumof100l and monitors millicuries per source i E. Ba-133 E. Calibration source E. 2 microcuries of !
Ba-133, maximum of 1 -
microcurie per source
- Duquesne Light Company (DLC) is authorized to act as agent for the Ohio Edison Company, the Cleveland Electric Illuminating Company, and the Toledo Edison Company, and has yl 4
cxclusive responsibility and control over the physical construction, operation, and B maintenance of the facility. .
W
- Upon ccnversion of Construction Permit No. CPPR-105 to an operating license, whichever l is carlier. p 1
COPY.
8604180300 860409 I PDR ADOCK 07003008 I y- C PDR ,,___________________)
NftC Foam 374A U.S. NUCLEA') CEGU LATOftY COMMIS$40N 3 PAGE OF ,,,,,
Lkelse number MATERIALS LICENSE _ SNM-1954 I ,
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SUPPLEME'NTARY SHEET 70-3008 l' y
COPY l' A
I F. C1-36 F. Various calibration F. 10 microcuries y and check sources i '
I G. U-234, U-238 G. Area monitors with G. I mg of U-234 I check sources and 2 mg U-238 l
l
- 9. Authorized Use: y R-For receipt, possession, inspection, storage, and packaging of fuel assemblies and l' other special, source, and byproduct materials for delivery to a carrier in I accordance with the statements, representations', andf conditions specified in DLC's application dated September ,28,1984, its revision'datedmSeptember 13, 1985, and its l<
supplements dated October .9;,J985, and February 10,1986; e,xcept as specifically provided otherwise by this' license. '/;
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- 10. Authorized Place of Use h .,.-O G? _3 -
'4 !
DLC's Beaver Valley Power Stationbunit 2, located 4nf'ShTppingport Borough, Beaver [
County, Pennsylvani,a,,~as descri, bed i the;aforesai lfcation
- 11. The minimum technicIl qualifications'for,.the Plant \ Manager shall.be in accordance with i:
Section 4.2.1, "P1 ant Manager,": ANSI;N18.1 %
1971./d f ,, p [
- e. 79 z % s ;w pw a y
- 12. The minimum technical l qualifications forzthe Op_erations :Qua'lity Control Inspector y
shall be in accordance,with'Section S ,4.5,5l," Qual.ity Assurance,"JANSI/ANS-3.1-1981. g W '9$ .Mi! ! ! !! i % w N p
- 13. The minimum technicalsqualifications'for the Refuel,ing Supervis'or shall be in accor-s I'
dance with Section 4.3.2', " Supervisors Not'Requir,i_ng AEC 'j Li, censes," ANSI N18.1-1971.
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,14. Thebe inminimum accordance technical with thequalifications requirements for'the Radiological for " Radiation 30perations Pro'tection Coordinator Manager,',' Regulatoryshall !,
j i Guide 1.8, September 1975. , .c ly 5 ,
- ,c ,e . .s r' 't
- 15. The following training shall be complete <l prior to receipt of fuel onsite: N 9
a.- All radiation safety personnel involved in fuel handling operations shall be l trained in radiation safety and DLC radiation protection procedures related to t fuel assembly handling. E li
- b. All operations personnel involved in fuel handling operations shall receive I training in proper fuel handling procedures, including health and safety aspects l of the activities, y 1
- 16. a. No more than two fuel assemblies shall be out of approved shipping containers or I fuel assembly storage racks at any one time. I f
- b. The minimum edge-to-edge distance between the above two fuel assemblies,'the l shipping container array, and the storage rack arrays shall be 12 inches. y 1
COP 1 l
. . . . . . . . . ... . . . . -_____________________________.]
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NRC Form 37!A U.S. NUCI EA;) C EGULATORY COMMISSION j
PAGE 3 o, 3 ,,cc, g
, License number l MATERIALS LICENSE SNM-1954 i SUPPLEMENTARY SHEET b
70-3008 g COPY I hl
- 17. Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage a rea .
1 18. DLC is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials held under this license.
l 1
- 19. OLC shall comply with the provisions of Annex A, " License Condition for Leak Testing p Sealed Byproduct Material Sources," dated November 1979. d b
- 20. The licensee shall maintain and fully impleinent all provisions of the Comission approved Physical Security Plan, including changes made pursuant to the authority of f 10 CFR 70.32(e). The approved Physical Security Plan consists of " Plan to Control the g) p BVPS-2 Fuel Buil, ding for Jemporary Storage of Fuel," transmitted by letter dated g February 26, 1986. The_ Physical Security Plan shall be withheld from public disclosure W pursuant to 10 CFR 2.790(d). ; F s D' f 'k .
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t FOR THE U.S. NUCLEAR REGULATORY COMMISSION NN y l
& Original signed by:
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- Dato: APR 0 91986 By- (E Division of Fuel Cycle and F Material Safety, NMSS E by/ 7 0 Washington, D.C. 20555 COPY, !
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________-__-___-______________J .
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APR 9 1986 Annex , A LICENSE CONDITION FOR LEAK TESTING SEALED BYPRDDUCT MATERIAL SOURCES November 1979 i
A. Each source shall be tested for leaktge at intervals not to exceed six (6) months. In the absence of a certificate from a transferor indicating that a test has been made within six (6) months prior to the transfer, the sealed source shall. not be put into use until tested.
B. The test shall be capable of detecting the presence of 0.005 micro-curie of contamination on the test sample. The test sample shall be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission.
C. If the test reveals the presence of 0.005 microcurie or more of renovable contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Commission regulations. Within five (5) days after determining that any .
source has leaked, the licensee shall file a report with the Director, Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, describing the source, the test results, the extent of contamination, the apparent or suspected cause of source failure, and the corrective action taken. A copy of the report shall be sent to the Director of the nearest NRC Inspection and Enforcement Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.
D. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six (6) months prior to the date of use or transfer.
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