ML20206B149
| ML20206B149 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 04/01/1987 |
| From: | Brown W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20206B147 | List: |
| References | |
| NUDOCS 8704080353 | |
| Download: ML20206B149 (5) | |
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UNITED STATES NUCLEAR REGULATORY C0t9tISSION LICENSE AMENDMENT FOR SPECIAL NUCLEAR MATERIAL SAFEGUARDS Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganiza-tion 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.
Llcensee:
Name:
Westinghouse Electric Corporation License No.: SNM-1107 Nuclear Fuel Division Safeguards Amendment: SG-3 Address: Drawer R Columbia, South Carolina 29205 Docket No.: 70-1151 Date Issued: April 1, 1987 A Reissue of SG-2 in its entirety CONDITIONS Section 1.0 --- Material Control & Accounting 1.1 The licensee shall follow Chapters 1.0 through 10.0 of its "Funda-mental Nuclear Material Control Plan for the Columbia Fuel Fabrica-tion Facility," dated April 1, 1987, and which was submitted pursuant to 10 CFR 74.31(b). Revisions to this Plan shall only be made in accordance with the provisions of either 10 CFR 70.32(c) or 70.34.
1.2 Operations involving special nuclear materials which are not refer-enced in the Plan identified in Condition 1.1 shall not be initiated until an appropriate safeguaros plan has been approved by the Nuclear Regulatory Commission.
1.3 In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use the Forms 00E/NRC-742 and 742C, the licensee may use computer generated forms provided all information required by the latest printed instructions for completing the particular form is included.
8704080353 870403 PDR ADOCK 07001151 C
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Amendment No. SG ' Docket No. 70-1151-License No. SM-1107~
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In lieu of the requirements contained in CFR 70.54 and 74.15 to use the DOE /NRC Form-741, the licensee may use computer generated forms provided all information required by the latest printed instructions for completing the particular form is. included.
Section 2.0 --- Physical Protection of SNM of Low Strategic Significance 2.1 The licensee shall maintain and fully implement all proviiions of the approved security plan titled " Site Physical Security Plan, Westing-house Electric Corporation, Columbia, S.C.." dated March 1980; as amended by letters dated September 2,1980; April 9,1981; January 25, 1984; September 1, 1984 (revised pages labelled Revision 2);
December 1,1984 (revised pages labelled Revision 3); March 1,1985 (revised pages labelled Revision 4); September 1,1985 (revised pages' labelled Revision 5); December 1, 1985 (revised pages labelled Re-
)
vision 6); and March 1, 1986 (revised pages labelled Revision 7);,
and as may be revised in accordance with the provisions of 10 CFR 70.32(e).
Section 3.0 --- International Safeguards 3.1 The licensee shall follow Codes 1. through 7. of Facility Attachment No. Sb dated October 1, 1986 to the US/IAEA Safeguards Agreement.
Such Facility' Attachment shall be interpreted in accordance with Conditions 3.1.1 through 3.1.6.
3.1.1 With respect to Facility Attachment Code 2.2:
Substantive changes to the information provided in the Columbia Plant Design Information Questionnaire (DIQ) means those changes requiring amendment of the Facility Attachment. Such changes shall be provided by letter to the NRC Office of Nuclear Material Safety and Safeguards at least 70-days in advance of implementation.
Non-substantive changes to the information provided in the DIQ means those changes not requiring amendment of the Facility Attachment.
Such changes shall be provided by Concise Note (FORM 00E/NRC-740H) as part of the routine quarterly update of the DIQ.
The types of modifications with respect to which information is required, under 10 CFR 75.11, to be submitted in advance are those items stated in Code 2.2, specifically:
3 Amendment No. SG-3 Docket No. 70-1151-License No. SNM-1107 (a) "Any change in the purpose or type of-the facility" means:
'Any deviation from the described activities involving special nuclear material and any change to the maximum enrichment and/or quantities of U-235 currently authorized by License No.
t ShM-1107, and/or as described in Paragraph 5 of the Design Infonnation Questionnaire (DIQ) dated October 14,1985, or as modified in 'accordance with 10 CFR 75.11(c).
Included also is any deviation from the described special nuclear material (SNM) production activities described in Paragraph 6 of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c).
(b) "Any change in the layout of the facility which affects the implementation of safeguards" means:
Any change in the existing facility and/or site layout or new-addition affecting any activity involving SNM as described in Paragraph 10 and 11 (per the ~ referenced attachments) of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c).
Included also is any modification to or deviation from the data provided in Paragraph 13 and 14 (per the referenced attachments) of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c).
(c) "Any change that makes the selected KMP's (as described in Code 3.1.2) inadequate for the Agency's accounting purpose" means:
Any change to the Key Measurement Points (KMP's) as described in Code 3.1.2 of the Westinghouse-Columbia Facility Attachment to the US/IAEA Safeguards Agreement, or as modified in accordance with 10 CFR 75.11(c), that results in any KMP alteration affecting the purpose of KMP's as stipulated by 10 CFR75.4(m).
(d) "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's account-l ing purposes" means:
J Any change to the description data contained in Paragraph 34 (per the referenced attachments) of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c), that would not permit the Agency to conclude an SNM material balance for the Westinghouse-Columbia facility.
I
o Amendment No. SG-3 Docket No..
70-1151 License No. SM-1107 (e) "Any change that adversely affects the accuracy of measurements at any KMP (as described in Code 3.1.2) by a factor of.2 or.
more" means:
Any recalculations of.the " Relative Errors-Random and Systematic" as listed in ' Attachment 36.2 referenced in
. Paragraph 36 of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c), that results in the estimates of the random and systematic errors being affected by a factor of two (2) or more.
(f) "Any change. in the statistical procedures used to combine individual measurement error estimates to obtain limits of error for S/R differences, the book inventory and physical inventory, and MUF" means:
Any deviation from (or modification of) the equations and/or calculations outlined in Attachments 37.1, 37.2, and 37.3 referenced in Paragraph 37 of the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c).
3.1.2 With respect to Facility Attachment Code 3.1.2:
KMP * - This is a KMP in which all S/R differences must be recorded and reported even if numerically zero. This means that the operator must record S/R differences and that the U.S. Government must calculate and report the S/R differences to the IAEA.
3.1.3 With respect to Facility Attachment Code 4:
4 Notwithstanding any other requirements for advance notification and/or reporting, the licensee may add or delete composition codes for nuclear materials routinely processed and on inventory at CFFF imediately upon telephone notification to the Office of Nuclear Material Safety and Safeguards.
Follow-up documentation, in the f
form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.6 to the Design Information Questionnaire, shall be submitted within three regular workdays of the telephone notification.
3.1.4 With respect to Facility Attachment Code 4.1:
Messured discards should be reported as an SN (Shipment to non-safeguarded facility) when shipped off-site to an authorized burial ground.
(The IAEA system will not process measured discards as LD's when they are shipped off-site.)
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v Amendment No. SG-3 Docket No.-. 70-1151
~ License No. SNM-1107 3.1.5 With respect to Facility Attachment Code ~ 5.1.1:
For inventory changes, time of recording, "upon" means:
No later than the next regular workday (Monday through Friday).
3.1.6 With respect to Facility Attachment Code 6.2.2:
For concise notes describing the anticipated operational programe,
" anticipated operational programme" means:
Anticipated physical inventory schedule.
For the Commission t
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I w 2tc J r3 6 Willard B. Brown, Chief Safeguards Material Licensing and International Activities Branch Division of Safeguards, NMSS I
Date Issued: April 1, 1987
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