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) | |
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U.S. NUCLF AR REGULATORY COMMISSION
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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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Carolina Power & Light Cogany
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North Carolina Eastern Municipal Power SNM-1939 k
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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 k
i Reference No.
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. 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
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under this bcense i
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Uranium enriched in A.
In unirradiated reactor A.1,900 kilograms of g
f; the U-235 isotope fuel assenblies U-235 in uranium 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 the U-235 isotope sources uranium at any 1
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enrichment I,
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Uranium-neptunium C.
Contained in sealed C.130 milligrams sources Np-237 and 80 I
milligrams U-238 l.
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Californium-252 0.
Primry startup D. 300 millicuries
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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:
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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
l County, North Carolina, as described in the aforesaid application.
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- 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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MATERIALS LICENSE
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SUPPLEMENTARY SHEET 70-2997 j
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- 11. Procedures, and changes thereto, for the control and handling of nuclea
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p fuel shall include the review and approval of the Reactor Operator and y
the Manager, Technical Support.
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- 12. The minimm technical qualifications of the Manager, Operations, shall be 14
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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
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- 14. The minimm qualifications for the Reactor Operator responsible for criticality 6
1 safety for fuel asse21y handling shall be in accordance with the following:
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The Reactor Operator shall have held a Commission Reactor Operator's 8
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j license at another facility and have had direct fuel handling experience, or l
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The Reactor Operator shall have held a responsible position in charge of j,
1 new fuel receipt and handling at another facility.
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- 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
Radiation Protection Mana Selection and Training." ger specified in Regulatory Guide 1.8, " Personnel j
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- 16. No more than 60 shipping containers, containing fuel, shall be stored in a s
f single array.
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- 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.
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- 18. No more than one fuel assedly shall be out of its shipping container or storage 1
location in the staging area or New Fuel Pool at any given time.
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- 19. The minimm edge-to-edge distance between a fuel asse21y outside its shipping 1l container or storage rack and all other fuel asseelies shall be 12 inches.
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- 20. Fuel asse211es shall be stored in such a manner that water would drain freely p
1 from the asse211es in the event of flooding and subsequent draining of the D
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fuel storage area.
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- 21. The licensee is hereby exegted from the provisions of 10 CFR 70.24 insofar as j
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this section applies to material held under this license.
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22.
The personnel exposure monitoring devices shall be mad daily and an individual's
'N dose shall be estimated at least every two weeks and recorded.
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- 23. The licensee shall cogly with the provisions of Annex A, 'ticense Conditions for l
I:l Leak Testing Sealed Sources Wich Contain Alpha and/or Deta-Gama Emitters."
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N C Fo,m 374A U.S. NUCLEAn HEGULATORY COMMISSION 3
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- 24. The licensee shall maintain and fully implement all provisions of the y
ll Commission approved Physical Security Plan, including changes made pursuant I.;
l 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,
Preparation for Transport of Special Nuclear Material of Low Strategic i
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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).
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1 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.
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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 removable contamination, the licensee shall immediately withdraw i
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, and the corrective action taken. A copy of the report shall be i
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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