ML19209B829
| ML19209B829 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 09/07/1979 |
| From: | Partlow J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Sherman F TEXAS INSTRUMENTS, INC. |
| References | |
| NUDOCS 7910110010 | |
| Download: ML19209B829 (5) | |
Text
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-',o, UNITED STATES h
NUCLEAR REGULATORY COMMISSION
' -. j WASHINGTO N, D. C. 20555
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SEP 7 1979
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/0-33 Texas Instrument.;, Inc.
ATTN: Mr. Fred Sherman, Manager Energy Products Department 34 Forest Street Attleboro, Massachusetts 02703 Gentlemen:
Reference is made to cur letter dated September 20, 1978 which approved your Measurement Control Plan and transmitted a revision to Sections 1.0 through 8.0 of Amendment No. MPP-1 to your License No. SNM-23. When this letter was sent, exemptions should have been granted for various statements in your Measurement Control Plan which deviate from the reggerements of the regulations. Regretfully, license conditions addressing these needed exemptions were not incorporated at the time of our letter.
In addition to this, three current license conditions are obsolete and should be deleted.
In order to correct both o? these situations, we are adding License Conditions 4.2, 4.3, and 4.4; deleting License Conditions 2.3, 2.4, and 7.1, and renumber-ing other existing license conditions as necessary. Accordingly, Amendment No. MPP-1 to your License No. SNM-23 is hereby revised to indicate these changes, effective immediately, as reflected in the enclosure to this letter.
SincerelyL
_O tu.t.e Jam 3s G. Partlow, Chief Material Control & Accountability dicensing Branch Division of Safeguards
Enclosure:
As stated O
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I Enclosure Revision of Sections 1.0 Through 8.0 In Their Entirety To Materials and Plant Protection Amendment MPP-1 To License No. SNM-23 Effective SEP 7 1979 t
l.0 FACILITY ORGANIZATION 11 The Manager, HFIR Project shall have the responsibility for the overall planning, coordination, and administration of the material control functions for special nuclear material (SNM).
2.0 FACILITY OPERATION
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2.1 The licensee shall follow the Fundamental Nuclear Mat ~erial Control Plan submitted January 23, 1975, as revised according to the schedule of revisions dated August 15, 1979, and as amended in accordance with the provisions of 10 CFR 70.32(c).
2.2 No statement in the licensee's Plan identified in Condition 2.1 shall relieve the licensee of a requirement of 10 CFR Part 70 uniess granted in a specific exemption or exception set forth as a conditica of this license.
2.3 The custody of all special nuclear material within each MBA and ICA shall be the responsibility of a designated individual.
2.a Operations involving special nuclear material which are not described in the Plan identified in Condition 2.1 shall not be initiated until an appropriate safeguards plan has been approved by the Nuclear Regulatory Commission.
3.G MEASUREMENTS 3.1 The licensee or his designated agent shall measure, except as specified in Conditicn 3.1.1, the uranium and U-235 content of all special nuclear material receipts, shipments, waste discards, and material inventoried.
3.1.1 Measurements are not required on sealed PuBe sources, and those samples intended for analysis and testing which have been determined by other means to contain less than ten grams U-235 each.
3.2 All internal transfers of uranium from MBAs shall be based on measure-ments for element and isotope, except as specified in Conditions 3.1.1 and 6.5.
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Amendment No. MPP-1 Page 2 of 4 Docket No. 70-33 License No. SNM-23 4.0 MEASUREMENT CONTROL 4.1 When counting statistics are used to establish random error variances, licensee shall demonstrate that other errors are negligible, and document these findings.
4.2 Notwithstanding the requirements of 10 CFR 70.57(b)(8) and (10) to make bias corrections and to use systematic error variances in calculating limits of error, the licensee may use those de minimus quantities stated in Section 4.2.4 of the Plan identified in License Condition 2.1.
4.3 Notwithstanding the requirements of 10 CFR 70.57(b)(8), the licensee is not required to generate bulk and NDA random errors from process materi als.
4.4 Notwithstanding the requirements of 10 CFR 70.57(b)(11) to use control charts to monitor the quality of gamma counting measurements, the licensee shall follow Section 4.5.1 of the Plan identified in License Condition 2.1.
5.0 INVENTORY 5.1 All special nuclear material shall be measured at the time of physical inventory except those items previously measured whose integrity has been maintained by tamper-safing and those items exempted by Condition 3.1.1.
Edch such item shall be checked for verification of its physical presence in its assigned location, and for verification of intact tamper-indicating devices.
6.0 RECORDS AND REPORTS 6.1 The licer.see shall report on a monthly basis all intentional discards and material unaccounted for.
The MUF shall be that which has been determined during the month as a result of completing a material balance around a single operation, a number of operations, or the entire plant. This report shall be made within fifteen (15) days after the end of the month in which the discard was made or the material unaccounted for was determined.
Reports shall be sent to the Regional Office of the U.S. Nuclear Regulatory Ccrmission.
6.2 In lieu of the requirement in 10 CFR 70.54 that the Form NRC/ DOE-741 be completed and distributed within 10 days af ter receipt of nuclear aaterial, the licensee may use a Form NRC-284 to acknowledge receipt where measurements cannot be completed in the time specified.
Receipt measurements shall be completed and reported on the Form NRC/ DOE-741 within 30 days af ter receipt of material.
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Amendment No. MPP-1 Page 3 of 4 Docket No. 70-33 License No. SNM-23 6.3 The licensee shall use his or his designated agent's measured values for ShM accounting, except as specified in Co.nditions 3.1.1 and 6.5.
6.4 Shippers' values may be posted in the accounting records provided:
6.4.1 Shippers' limit of error values on grams uranium and uranium-235 are less than 0.5% for each material type in each shipment.
6.4.2 Independent receiver measurements shall be made for the total element and isotope content with limit of error values less than 0.5% for each material type in each shipment.
6.4.3 Shipper-receiver differe"nces are not statistically significant at the 95% confidence level for each shi pment.
6.4.4 Shippers' values are pcsted as a standard procedure subject to Conditions 6.5.1 and 6.5.2.
6.5 If the licensee posts shippers' values in his accounting record pursuant to Condition 6.4, the following procedures shall be followed in completing the Form NRC/ DOE-741:
6.5.1 The results of the receiver's ceasurements made pursuant to Condition 6.4.2 shall be recorded in the appropriate Black of Form NRC/D0E-741 in accordance with Condition 6.3.
6.5.2 The licensee shall clearly certify on Form NRC/ DOE-741 that shippers' values are accepted on the basis of independent measurement verification.
7.0 INTERNAL CONTROL 7.1 Any transfer of special nuclear material from the vault and from cperating hoods and boxes shall be observed or accompanied by a second person in addition to the person performing the transfer.
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 within each plant in aiscrete items and containers.
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Amendment No. MPP-1 Page 4 of 4
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Gocket No. 70-33 License No. SNM-23 8.0 MANAGEMENT 8.1 Any apparent loss of a discrete item or container of special nuclear material which cannot be resolved by an immediate investigation shall be reported to the Manager, HFIR Project, who shall promptly notify the Regional Office of the Nuclear Regulatory Connission, and shall con-duct an investigation of the loss. The Manager of Nuclear Materials shall document the results of his investigation and maintain the record for five years.
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