ML20133Q429
| ML20133Q429 | |
| Person / Time | |
|---|---|
| Site: | 07002997 |
| Issue date: | 10/28/1985 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20133Q414 | List: |
| References | |
| NUDOCS 8511010542 | |
| Download: ML20133Q429 (4) | |
Text
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i ; m s4) U.S. NUCLF AR REGULATORY COMMISSION """ 1 --U# 3 PA W h
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MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public L.iw 93 -438). .md Title 10 4
i Code of Federal Regulations. Chapter I Parts 30. 31. 32,33,34,35,40 and 70. and m rehance on statements and representations
'! heretofore made by the licensee.a heense is hereby issued authonzing the beensee to receae, acquire, poness, and transfer by produet, p i source, and special nuclear matenal designated below; to use such matenal for the purpose (s) and at the placet s) designated below; to y y deliver or transfer such material to persons authonzed to receive it m accordance with the regulations of the appheable Partist This -
i license shall be deemed to con *.am the conditions specified in Section 183 of the Atomie Energy Act of 1954. as amended. .ind is 1 subject to all appheable rules. regulations and orders of the Nuclear Regulatory Commission now or hereafter m cifect and to any N conditions specified below.
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! 1. Carolina Power & Light Cogany Cop :
- 3. Ueense number i North Carolina Eastern Municipal Power SNM-1939 k I
Agency j2. 411 Fayetteville Street (i, i P.O. Box 1551 4. Expiration date October 31, 1990 or* y ;
Raleigh , North Carolina 27602 E
- 5. Docket or 70-2997 i
k Reference No. p3
. 6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maximum amount that licensee Pi special nuclear matenal form may possess at any one time B
( under this bcense i J A. Uranium enriched in In unirradiated reactor A.1,900 kilograms of
, A. g the U-235 isotope fuel assenblies U-235 in uranium >
f; enriched to no more F than 3.15%, in lf-235 k i
$ gl B. Uranium enriched in B. Contained in sealed B. 2.5 grams of g i
k C. Uranium-neptunium C. Contained in sealed C.130 milligrams ,!;
sources Np-237 and 80 I
$ milligrams U-238 l D. Californium-252 0. Primry startup D. 300 millicuries ;te
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- 9. Authorized Use: p le
, ! The naterials are for use in accordance with statements, representations, p and conditions specified in the licensee's revised application dated j Septerrber 17, 1984, and its supplement dated October 10, 1985.
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- 10. Authorized Place of Use: ft i The licensee's Shearon Harris Nuclear Power Plant, Unit 1, located in the y l southwest corner of kke County and the southeast corner of Chatham R County, North Carolina, as described in the aforesaid application.
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l *Upon conversion of Construction Permit No. CPPR-157 to an operating license, )
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8511010542 851028 $
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'J NRC Form 374A U S. NUCLEAR QECULATORY COMMISSION I 2 .>
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1 MATERIALS LICENSE g g ,,, - j.
SUPPLEMENTARY SHEET 70-2997 '
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- 11. Procedures, and changes thereto, for the control and handling of nuclea /
p fuel shall include the review and approval of the Reactor Operator and g i y the Manager, Technical Support. 4
< ll 4 h 12. The minimm technical qualifications of the Manager, Operations, shall be 14 T in accordance with Section 4.2.2, " Operations Manager," of ANSI /ANS-3.1-1978.
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- 13. The minimm technical qualifications of the Manager, Technical Support, shall be in accordance with Section 4.2.4, ' Technical Manager," of ANSI /ANS-3.1-1978. (
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.J 14. The minimm qualifications for the Reactor Operator responsible for criticality 6 1
J safety for fuel asse21y handling shall be in accordance with the following: 8 p
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- a. The Reactor Operator shall have held a Commission Reactor Operator's 8 license at another facility and have had direct fuel handling experience, or l
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i 1, b. The Reactor Operator shall have held a responsible position in charge of j, -
1 new fuel receipt and handling at another facility. > l i 1 y i J
] 15. The minimm qualifications of the Manager, Environmental and Radiation Control, > l
- and the Supervisor, Radiation Control, shall be in accordance with that of the E 1 Radiation Protection Mana j l 1 Selection and Training." ger specified in Regulatory Guide 1.8, " Personnel i
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- 16. No more than 60 shipping containers, containing fuel, shall be stored in a s f single array.
l f 17. There shall be an edge-to-edge separation of at least 20 feet between groupings fI 1 of 60 fuel asse21y-bearing shipping containers. i i 1 1
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- 18. No more than one fuel assedly shall be out of its shipping container or storage location in the staging area or New Fuel Pool at any given time. >l 1
1: 19. The minimm edge-to-edge distance between a fuel asse21y outside its shipping )g 1l container or storage rack and all other fuel asseelies shall be 12 inches. p
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- 20. Fuel asse211es shall be stored in such a manner that water would drain freely
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- from the asse211es in the event of flooding and subsequent draining of the D '
j j fuel storage area.
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I 1 l 21. The licensee is hereby exegted from the provisions of 10 CFR 70.24 insofar as this section applies to material held under this license.
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l 22. The personnel exposure monitoring devices shall be mad daily and an individual's 'N l h. dose shall be estimated at least every two weeks and recorded. j
- 23. The licensee shall cogly with the provisions of Annex A, 'ticense Conditions for l Leak Testing Sealed Sources Wich Contain Alpha and/or Deta-Gama Emitters." l p
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N C Fo,m 374A U.S. NUCLEAn HEGULATORY COMMISSION p 3 y 3 , g I '
. License number l 1 SNM-1939 p 1 MATERIALS LICENSE g, ,,,,,,,,,, , y SUPPLEMENTARY SHEET I' 70-2997
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!, i 1; 24. The licensee shall maintain and fully implement all provisions of the y l Commission approved Physical Security Plan, including changes made pursuant I.;
ll to the authority of 10 CFR 70.32(e). The approved Physical Security Plan ,
)j consists of Revision 1 to the Plan for Receipt, Possession, Storage, and i, 3
Preparation for Transport of Special Nuclear Material of Low Strategic i l Significance for Shearon Harris Nuclear Power Plant, Unit No. 1, dated i J April 12, 1984, and as revised July 8,1985. The Physical Security Plan !, ,
lj; shall be withheld from public disclosure pursuant to 10 CFR 2.790(d). l 1
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U(, FOR TiiE NUCLEAR REGULATORf COMMISSION
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Divd sion _ f fuel Cycle apd, Mate lifSafety L) l u.; r.. '
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, ANNEX A i 1
1.lCENSE CONDITION FOR LEAK TESTING SEALED SOURCES WHICH CONTAIN ALPHA AND/0R BETA-GAMA EMITTERS j A. 1. Each sealed source containing licensed material, other than Hydrogen-3, with a half-life greater than 30 days and in
- any form other than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months. In the
- absence of a certificate from a transferor indicating that a i test has been made within 6 months prior to the transfer, a
, sealed source received from another person shall not be put
- into use until tested.
l 2. Nothwithstanding the periodic leak test required by this condition, i any licensed sealed source is exempt from such leak tests when the j source contains 100 microcuries or less of beta and/or gamma emitting j material or 10 microcuries or less of alpha emitting material.
4 i 3. The periodic leak test required by this condition does not apply to i sealed sources that are stored and not being used. The sources shall l be tested for leakage prior to any use or transfer to another person unless they have been leak tested within 6 months prior to the date i
of use or transfer.
B. The test shall be capable of detecting the presence of 0.005 micro-curie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from appropriate accessible
, surfaces of the container, or device in which the sealed source is mounted 1 or stored on which one might expect contamination to accumulate. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Comission.
j C. If the test reveals the presence of 0.005 microcurie or more of i removable contamination, the licensee shall immediately withdraw i 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.
j Within 5 days af ter determining that any source has leaked, the j licensee shall file a report with the Division of Fuel Cycle and Material Safety, U. S. Nuclear Regulatory Comission, Washington, i D.C. 20555, describing the source, the test results, the extent of j contamination, the apparent or suspected cause of source failure, i
and the corrective action taken. A copy of the report shall be sent to the Administrator of the appropriate NRC Regional Office i listed in Appendix 0 of Title 10, Code of Federal Regulations, Part 20.
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