ML20207F293
| ML20207F293 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 09/26/1986 |
| From: | Brown W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207F276 | List: |
| References | |
| NUDOCS 8701050520 | |
| Download: ML20207F293 (4) | |
Text
i I
UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE AMENDMENT FOR SPECIAL NUCLEAR MATERIAL SAFEGUARDS Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization 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 requirements for special nuclear material.
Licensee:
Name: Rockwell International Corporation License No: SNM-21 Rocketdyne Division Atomics International Safeguards Amendment: SG-1 Address: 6633 Canoga Avenue Docket No.: 70-25 Canoga Park, California 91304 Date Issued: September 26, 1986 CONDITIONS 1.0 FACILITY ORGANIZATION Currently there are no license conditions in this section. The necessary information has been incorporated into an approved plan.
2.0 FACILITY OPERATION 2.1 The licensee shall follow the Fundamental Nuclear Material Control Plan titled: " Fundamental Material Controls for Special Nuclear Material," RI/RD86-190, dated May 9, 1986, and as may be amended pursuant to the provisions of 10 CFR 70.32(c)(2)(1).
2.2 Operations involving special nuclear materials which are not described in the Fundamental Nuclear Material Control Plan identified in Condition 2.1, shall not be initiated until an appropriate
- safeguards plan has been approved by the Nuclear Regulatory Commission.
2.3 All SNM not in transit shall be physically within an MBA or an ICA.
l 8701050520 860926 j PDR ADOCK 07000025
- C PDR
2
(
Amendment SG-1 Docket No. 70-25 i.icense No. SNM-21 3.0 MEASUREMENTS 3.1 The licensee or his designated agent shall measure, except as specified in Conditions 3.1.1 and 3.1.2, the uranium, uranium-235, and/or uranium-233 and plutonium content of all special nuclear material receipts, shipments, waste discards, and material inventoried.
3.1.1 Notwithstanding the requirements of 10 CFR 70.58(e) to measure the uranium, U-235, and plutonium element content of all SNM received, on inventory, or shipped, the licensee shall perform measurements in accordance wit 5 Section 3.1 of the Plan identified in Condition 2.1.
3.1.2 For those materials measured by non-destructive assay, the licensee may calculate the elemental content based on isotopic abundance measurements which can be demonstrated to be representative of the material.
3.2 All internal transfers from MBAs shall-be based on measurements, except as specified in Conditions 3.1.1 and 3.1.2. Plutonium transfers shall be measured for element, and uranium transfers shall be measured for both element and isotope content except as specified in Condition 3.1.2.
4.0 MEASUREMENT CONTROL 4.1 Notwithstanding the requirement of 10 CFR 70.57(b)(8) to generate random errors for bulk and NDA from replicate measurements on process i materials, the licensee shall follow Section 4.4 in the Plan i
identified in License Condition 2.1.
.4.2 Notwithstanding the requirements of 10 CFR 70.57(b)(10) to perform bias calculations and corrections and determine limits for systematic errors, the licensee shall follow Sections 5.11.2 and 6.1.4.1 in the Plan identified in License Condition 2.1.
4.3 Two authorized individuals sN11 observe and certify the loading of the shipping cans for repackaged fuel from decladding activities at the ESG Hot Laboratory.
4.4 Notwithstanding the requirements of 10 CFR 70.51(e)(4)(i) and 70.58(e), limit of error calculations are not required for the ESG Hot Laboratory decladding activities.
5.0 INVENTORY 5.1 The Nuclear Materials Manager, or his designated representative, shall verify the completeness of each physical inventory.
6.0 RECORD 5 and REPORTS l
l l
l r . , - , _ _ . - - , . - - , - - - , - _ _ . . - , - - , . , , . --.
s 3
i Amendment No. SG-1 Docket No. 70-25 License No. SNM-21 6.1 In lieu of the requirements for final measurement data and limits of error contained in the printed instructions referenced in 10 CFR Part 70.54, the licensee may transfer material to the on-site license exempt facility provided;
- a. Form NRC/00E-741 is completed in accordance with the printed instructions for the Form except for final measurement data and limit of error. The best available data shall be used for element and isotope data.
- b. A corrected Form NRC/00E-741 shall be completed with measured values and limits of error within thrity (30) days of the transfer.
- c. The on-site transfer is for storage only.
- d. The material shall be in tamper-safed containers or sealed sources.
- e. Violated tamper-safed containers or sealed sources shall be immediately returned to the licensed facility for verification
, of the special nuclear material content.
- f. Measurement for plutonium isotopic content is required only if the SNM will subsequently be shipped off-site.
7.0 INTERNAL CONTROL 7.1 The same individual shall not sign a document as both the Shipper and the Receiver.
( 7.2 Accurate records shall be established and maintained which provide on a daily basis knowledge of the identity, location, and quantity of all SNM contained within the plant in discrete items and containers.
8.0 MANAGEMENT 8.1 Any apparent loss of a discrete item or container of SNM which cannot be resolved by an immediate investigation shall be reported to the Director, Nuclear Safety and Licensing, who shall promptly notify the Regional Office of the Nuclear Regulatory Commission, and shall conduct an investigation of the loss. The Director, Nuclear Safety and Licensing, shall document the results of his investigation and maintain the record for five years.
8.2 Notwithstanding the requirements of 10 CFR 70.57(b)(2), (b)(3), and 70.58(c)(2) to conduct management reviews and audits at intervals not to exceed twelve months, the licensee shall follow Sections 4.1.4 and 8.2.1 of the Plan identified in Condition 2.1. For the purpose of
s 4
i Amendment SG-1 Docket No. 70-25 License No. SNM-21 this Condition, the maximum 15-month interval between Review Comittee briefings is hereby defined as a period not to exceed 460 calendar days.
9.0 PHYSICAL PROTECTION REQUIREMENTS FOR SPECIAL NUCLEAR MATERIAL OF-MODERATE STRATEGIC SIGNIFICANCE 9.1 The licensee shall follow the security plan titled, " Physical Security Plan for the Protection of Moderate Strategic Quantities of Special Nuclear Material at the Hot Laboratories of the Energy Systems Group of Rockwell International," dated May 19, 1980 and as amended by Revision 1, dated August 19, 1980.
For the Nuclear Regulatory Comission Nk0 -
Willard B. Brown, Chief Safeguards Material Licensing and International Activities Branch Division of Safeguards, NMSS Date of Issue: SEP 2 6 35 ,
'i i
., _