ML20248H994

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Amend SG-2 to License SNM-368,revising FNMCP
ML20248H994
Person / Time
Site: 07000371
Issue date: 10/06/1989
From: Mccorkle G
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20248H969 List:
References
NUDOCS 8910120212
Download: ML20248H994 (3)


Text

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if I UNITED STATES NUCLEAR REGULATORY COMMISSION-

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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: UNC Naval Products License No.: SNM-368 Address: 67 Sandy Desert Rd. Safeguards Amendment: SG-2 (MC&A only)

Uncasville, Conn. 06382-0981 ,

Docket No.: 70-371 4 Issuance Date: OCT 0 61989 AReissueofSG1(MC&Aonly)

CONDITIONS SECTION 1.0 ABRUPT LOSS DETECTION Currently there are no conditions'in this section. The necessary informa.

tion and commitments are contained in an approved FNMC Plan which has been incorporated as a condition of license (i.e., Condition 5.1 of this Amendment).

SECTION 2.0 ITEM MONITORING 2.1 Notwithstanding the requirements of 10 CFR 74.55(b) for item monitoring),

testsforallitemcategoriesexceptthoseidentifiedby10CFR74.55(c the licensee is exempt from applying item monitoring tests on NDA calibra-tion and control standards which are two liter or more, but which contain less than 0.10 formula kilograms. Such standards are not, however, exempted from physical inventory requirements.

SECTION 3.0 ALARM RESOLUTION Currently there are no conditions in this section. The necessary information and commitments are contained in an a has been incor orated as a condition of license (pproved FNMC Plan i.e., Condition which 5.1 of this Amendment .

8910120212 8o1006 FDR ALOCK 07000371 C PDC

, lAmendmentNo.SG-2 .- Docket No.70-371 License No. SNM-368 1

SECTION 4.0 QUALITY ASSURANCE 4.1 Notwithstanding the requirements of 10 CFR 74.59(d)(1) to measure the uranium and uranium-235 content of encapsulated fuel items, (1) routinely shipped offsite or, (2) shipped offsite for additional processing and subsequent' return, the licensee may ship and receive such items on the basis of previous measurements, as stated in Section 4.7 of the Plan identified in License Ccndition 5.1, provided the cladding in (1) above q is intact and (2) above has remained intact as shipped by the licensee. i l

4.2 Notwithstanding the requirement of 10 CFR 74.59(d)(1) to measure the urcnium and uranium-235 content of Government Retainer Samples received from off-site, the licensee may accept shipper's values for MC&A account- l ability, as stated in Section 4.7 of the Plan identified in License Condi-tion 5.1, without verification provided the samples are received in tamper-safe condition and seal integrity is maintained.

4.3 Notwithstanding the requirement of 10 CFR 74.59(d)(1) to measure the uranium-235 content of the one-in-four intermediate product sample received from off-site, the licensee may assign, as stated in Section 4.7 of the Plan identified in License Condition 5.1, the isotopic assay determined from the fabricability sample composites provided the intermediate product sample is represented in at least one of the fabricability samples.

4.4 Notwithstandingtherequirementsof10CFR74.59(e)(8)tousecontrol charts to monitor the quality of each program measurement, for control of scales and balances, the licensee shall follow Section 4.4.1.4.1.1 of the Plac identified in License Condition 5.1.

4.5 All measurement systems utilized for material control and accounting purposes, with the exception of the volumetric measurements identified in Section 4.3.2.3 of the licensee's Plan identified in License Condition 5.1, shall be included in the comprehensive measurement control program.

4.6 Notwithstanding the requirement of 10 CFR 74.59(d)(1) to measure the special nuclear material on inventory in standpipes, the licensee shall follow Section 4.5.1 of the Plan identified in License Condition 5.1 for the SSNM holdup in standpipes in MBA-5. The SSNM shall be cleaned out every other inventory, measured and the quantity reconciled with that projected to be present.

4,7 the requirements of 10 CFR 74.13 to complete a Material Notwithstanding(DOE Balance Report /NRC Form-742) in accordance with the printed instru tions for that particular form, the licensee may utilize the computer report generated by NMMSS, as described in Section 4.6.1.5.2 of the Plan identified in Condition 5.1. ,

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Amendment No. SG-2 D3cket No.70-371 License No. SNM-368 4.8 Notwithstanding the requirement of 10 CFR 74.59(d)(1) to substantiate the uranium and U-235 content of SSNM transferred between areas of custodial responsibility, the licensee may transfer, as stated in Section 4.11.1.2 of the Plan identified in License Condition 5.1, scrap materials on estimated values provided that the estimated transfer values are cor-rected upon obtaining actual measurements for the respective material balance period.

4.9 Notwithstanding the requirements of 10 CFR 74.55(b) to verify on a statistical sampling plan basis the presence and integrity of SSNM items using a statistical sampling plan having at least a 99% power of detecting item losses that total 5 formula kilograms or more plant-wide within 60 calendar days, such verification shall be regarded as having been satis-fied by a physical inventory that is conducted within 65 calendar days of the last previous inventory as stated in Section 4.5 of the Plan identified in License Condition 5.1.

SECTION 5.0 GENERAL MATERIAL CONTROL & ACCOUNTING 5.1 In order to achieve the performance objectives of 10 CFR 74.51(a), and to maintain the system capabilities of 10 CFR 74.51(b), the licensee shall follow its " Fundamental Nuclear Material Control Plan," revision 2 dated June 16, 1989. Revisions to this plan shall be made only in accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34.

5.2 Operations involving special nuclear material which are not described in the Plan identified in Condition 5.1 shall not be initiated until an appropriate safeguards plan (describing all new and/or modified MC&A measures to be implemented) has been approved by the Nuclear Regulatory Commission.

For th0 Nuclear Regulatory Commission N(/;m/ Xb?^% Z_~ )

Date: OCT 0 61989 George l. McCorkle, Acting D}rd l Divisio[nofSafeguardsany l Transportation, NMSS l

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