ML20236D289

Amend SG-2 to License SNM-1257 for Advanced Nuclear Fuels Corp,Adopting Revised Fundamental Nuclear Matl Control Plan

ML20236D289
Person / Time
Site:	Framatome ANP Richland
Issue date:	05/01/1987
From:	Brach E NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20236D267	List: ML20236D264 ML20236D289
References
NUDOCS 8707300396
Download: ML20236D289 (2)

Text

. i UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE AMENDMENT FOR SPECIAL NUCLEAR MATERIAL SAFEGUARDS Pursuant to the Atomic Energy Act of 1954, as amer.ded, the Energy Reorgani-zation Act of 1974, and Title 10, Code of Federal Regulations, Chapter 1, Part 70, the following amendment to the special nuclear material license identified below is hereby issued, incorporating specific safeguards require-  ;

ments for special nuclear material.

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Licensee:

1 Name: Advanced Nuclear Fuels Corporation License No.: SNM-1227 Address: P.O. Box 130 Safeguards Amendment: SG-2 2101 Horn Rapids Road  !

Richland, Washington 99352 Docket No.: 70-1257 A reissue of SG-1 in its entirety Date issued: May 1, 1987 i CONDITIONS Section 1.0 --- Material Control & Accounting 1.1 Tb licensee shall follow Chapters 0.0 through 8.0 and Appendix A of its Fundamental Nuclear Material Control plan, submitted pursuant to 10 CFR 74.31(b), titled " Nuclear Materials Safeguards Procedures Description for the Fuel Fabrication Plants," designated "XN-12, Revision 17," and dated October 1986, except for pages 1-8, 1-12, 1-13, 1-14, 1-23, 1-24, 4-2, 4-48, 4-51, 5-1, 5-2, 5-4, 5-5, 5-7 through 5-1., 7-16 through 7-34, 8-3, 8-0, and 8-7, all of which are dated March 1987. Revisions to this Plan shall only be made in accordance with the provisions of either 10 CFR 70.34 or 70.32(c).

1.2 Notwithstanding Chapter 0.0 of the Plan identified by Condition 1.1, which comits to meeting all Affirmation Statements contained in NUREG-1065 (Rev. 1), the licensee is hereby granted a limited exception from the first Affirmation contained in Section 4.3 of NUREG-1065 in that receipt of returned fuel rods and/or fuel assemblies (that were originally fabricated at the licensee's facility and whose SNM encapsulation has not been compromised) need not be measured if the original fabrication values are booked as receipt values.

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., a 1.3 A special shutdown, cleanout physical inventory shall be initiated whenever:

(i) a loss / theft indication involving a SNM quantity equal to or greater than the licensee's Detection Quantity (as defined in Section 8.2.7 of the Plan identified oy Condition 1.1) cannot otherwise be resolved within 60 days of the initial recognition of such indication, and (ii) a Regulatory ID (as defined in Section 5.13 of the Plan identified in Condition 1.1) equals or exceeds the licensee's Detection Thres-hold Quantity (as defined in Section 8.2.7 of the Plan identified by Condition 1.1).

Whenever a special inventory is required by either (i) or (ii) above, all unsealed and unencapsulated SNH imems tiiat are on hand at the time that

such a situation is determined to exist, shall be measured (even if previously measured) for SNM content.  !

l 1.4 Operations involving special nuclear materials which are not described in )

the Pian identified in Condition 1.1 shall not be initiated until an appropriate safeguards plan has been approved by the appropriate safeguards licensing authority of the Nuclear Regulatcry Comission.

Section 2.0 --- Physical Protection For SNM of Low Strategic Significance 2.1 The licensee shall follow the security plan titled, " Exxon Nuclear Company Physical Protection Plan for Material of Low Strategic l Significance," Revision 2, dated October 1981, as revised by Revision 3, dated July 23, 1982, Revision 4, dated December 2, 1982, Revision 5, dated Spetember 27, 1983, and Revision 6, dated May 14, 1984, and as may be amended pursuant to the provisions of 10 CFR 70.32(e).

2.2 The licensee shall ensure that the U0 2Building is locked when unuccupied.

Section 3.0 --- International Safeguards

, 3.1 The licensee shall follow, as applicable, Codes 2. through 7. of l Transitional Facility Attachment No. la dated May 1, 1986 to the US/IAEA Safeguards Agreement.

3.2 Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility data on forms supplied by the Commission (including IAEA DIQs), the licensee may submit required data in the Advanced Nuclear Fuels Corporation license paper format.

For the Commission l

E. William Brach, Acting Chief Safeguards Licensing Branch Division of Safeguards and Transportation, NMSS Date Issued: May 1, 1987

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