ML20248F510
| ML20248F510 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 06/02/1998 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20248F493 | List: |
| References | |
| NUDOCS 9806040304 | |
| Download: ML20248F510 (8) | |
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NRC FORM 374 PAGE 1 oF 8 PAGEs u.s. NUCLEAR REGULATORY commission MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess and transfer byproduct.
source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee l
- 1. Westinghouse Electric Corporation 3. Ucense Number SNM-1107, Amendment 13 l P.O. Box 355
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- 2. Pittsburgh, Pennsylvania 15230-0355 4. Expiration Date November 30,2005
- 5. Docket No. 70-1151 l Reference No.
- 6. Byproduct Source, and/or 7. Chemical and/or Physical 8.3 Maximum amount that Licensee Special Nuclear Material -
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- May Possess at Any One Time 4 7'y U,nder This License A. U-235 A; dny ~
A.DO.35 kg
.a .J 2 B. U-235 r; : B. Any, .except( ' , B.s75,000 kgs y Jmetal! enriched c3
-to not'rrxire .. y, ce A
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than 5.0 w/o vj i
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C. U-233 C. Any
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C. 5 grams D. Pu-238, D. Sehled sources D. 1.5 grams Pu-239
- 9. Authorized place of use: The licensee's existing facilities at Columbia, South Carolina.
- 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.
These sections are part of the license and the licensee is subject to compliance with all listed conditions in each section.
FOR THE NUCLEAR REGULATORY COMMISSION Date: b b By: Michael F. Weber N @
Division of Fuel Cycid SafMy vbr~
and Safeguards Washington, DC 20555 90060A0304 990602 PDR ADOCK 07001151 C PDR
NhtC FoR3 374A U.s. NUCLEAR REGULATORY Commission PAGE 2 of 8 PAGEs Ucense Number SNM-1107 MATERIALS LICENSE Docket or Referenm Number SUPPLEMENTARY SHEET 70-1151 Amendment No.13 SAFETY CONDITIONS i
S-1. Authorized use: For use in accordance with statements, representations, and conditions in the license application dated April 30,1995, and supplements dated May 11 and 18, August 4 and 25, and September 25,1995; November 8, and August 30,1996; July 14 and 25, August 11, November 17, and December 17,1997; and January 9 and 12,1998.
S-2. The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis (CSAs) will define the criticality safety bases utilized throughout the plant and will be completed as described in Sections 6.4.1 and 6.4.2 of the license application for each step of the process. A submittal to the NRC will be made by Westinghouse which will include information which the staff will review against the commitments listed in Section 6.2.3 of the license applicationJThese submittals will not be specific commitments, but are intended as a demonstration of the adequaciof the bases of safety itemized in Section 6.2.3. The contents listed in Section 6,4.2'of the license application are commitments. The demonstration will show the logic used by the Columbia Fuel Fabrication Facility (CFFF) in developing the criticality safety bases, it is understood that this demonstration may change'over time. The submittal will consist of a summary of the CSE or CSA as annotated below for each system (which shall include fault trees for those systems for which a CSE will be done). The adequacy'of the commitments in Section 6.2.3 of the license application will be esaluated and a reply in the form of a letter report will be generated and sent from the staff to Westinghouse <xThe submittal by the CFFF will be provided according to the
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following schedule:
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- . UN tanks'- summary of CSE dO/95 e . URRS Dissolver - summary of CSE - 10/95 e X Solvent Extraction - summary of CSE - TBD*
e 'URRS Scrap Processing >
e Low-Level Waste Processing System - summary of CSA - 9/96 Mop Water System Equipment - summary of CSA - 9/96 {
incinerator System - summary of CSE - 9/96 Ash Recovery System - summary of CSE - 9/96 Liquid Honing System - summary of CSE - 9/96 Ultrasonic Cleaning System - summary of CSE - 9/96 Shredder System - summary of CSE - 9/96 e URRS Waste Treatment - summary of CSA - 11/95 e IDR Conversion - summary of CSE - Prior to Restart
- ADU Conversion - summary of CSE - 4/96 e ADU Pelleting - summary of CSE - 6/96
- Powder Blending - summary of CSE - 1/96 e Miscellaneous:
Ventilation Systems (Geometry Controlled) -
summary of CSE - 3/98**
Ventilation Systems (Moderation Controlled)-
summary of CSE - 3/98" l
- The CFFF has performed a CSA upgrade and does not have a specific date for schedule of this CSE at l this time. !
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NRC FORM 374A U.S. NUCLEAR REGULATORY Commission PAGE 3 of 8 PAGEs Ucense Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.13 i
Scrubber Systems - summary of CSE - 3/98**
Hoods & Containment - summary of CSA - 9/96
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l Laboratories - summary of CSA - 9/96 e IFBA - summary of CSA - 3/96 ]
l e Storage Pad - NCS is based on DOE reports K-1920 and K-1663 e Rods - summary of CSA - 3/96 ;
e Storage - summary of CSE - 4/97 e Final Assembly - summary of CSE - 6/97 {
j e UF, Cylinder Washing - summary of CSE - 12/95 j 1
S-3. The licensee shall maintain and execute the response measures in the Site Emergency Plan, dated April 30,1990, and revisions dated March 31;and September 30,1992; March 25, August 15, and ;
September 30,1994; January 9, February 17, August 17, and October 23,1995; or as further revised by the licensee consistent with 10 CFR 70.32(i).
S-4, Deleted by Amendment 12, April 1998.
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o NRC FORM 374A U.s. NUCLEAR REGULATORY CoMMisSloN PAGE 4 of 8 PAGEs License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.13 l
l SAFEGUARDS CONDITIONS SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING l
SG-1.1 The licensee shall follow pages i through xviii and Chapters 1.0 through 9.0 of its " Fundamental Nuclear Material Control Plan for the Columbia Fuel Fabrication Facility," which has been partially revised as indicated by Revision 28 (dated December 18,1997). Any further revisions to this Plan shall be made only in accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34.
SG-1.2 Operations involving special nuclear material which are not referenced in the Plan identified in Condition SG-1.1 shall not be, initiated until an appropriate safeguards plan has been approved by the Nuclear Regulatory Commission. ' O /
SG-1.3 In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use the Forms DOE /NRC-742 and 742C, the licensee may use conFiputer generated forms provided all information required by.the latest printed instructions for completing the particular form is included. m M .
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SG-1.4 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.
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SG-1.5 Deleted Per Amendment 3, August 1996 Commitment now contained in licensee's Fundamental Nuclear Material Control Plan, v -
y SG-1.6 Notwithstanding the requirements of the FNMC Plan ident!fied in License Condition SG-1.1, the licensee may use (1) a single ' standard for measurement control (including daily control limit monitoring and bias corrections) for any linear-response tube or rod scales, in any initially demonstrated to be linear over its range of use within the discrimination of the scale by calculating a bias at four levels across the range of use and demonstrating that the four results are not statistically different, and (2) that the continued linearity of response of the scales is verified by monthly calibration against at least four traceable standards covering the range of use.
SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the licensee's Fundamental Nuclear Material Control Plan, the licensee is exempted from physical inventory requirements relative to the materialidentified in Condition S-4; provided the conditions and commitments contained in the licensee's November 30,1993, letter (identification # NRC 036) are satisfied.
l Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear SG-1.8 Material Control Plan to unpackage and perform an item count upon receipt of special nuclear material, the licensee is exempted from such requirement relative to the material identified in Condition S-4; provided the conditions and commitments contained in the licensee's November 30,1993, letter (identification # NRC-93-036) are satisfied.
NRC FORM 374A u.S. NUCLEAR REGULATORY CoMMISsloN PAGE 5 of 8 PAGEs Ucense Number SNM-1107 MATERIALS LICENSE Docket or Reference Number
, SUPPLEMENTARY SHEET 70-1151 Amendment No.13 '
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SG-1.9 Notwithstanding the requirement of Section ll.A.7, block U, of NUREG/BR-0006, which is incorporated via 10 CFR 74.15, to complete receiver's measurements of scrap receipts (following recovery processing) within 60 days of receipt, the licensee shall not be subject to i any time limit relative to recovering and measuring received UF heels when the block U action code (of DOE /NRC Form 741) is used to book such receipts SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, " allowed number" within the phrase " allowed number of defects"is hereby specified as being:
(i) up to two defects when each item within a batch of items has an assigned value equal to or less than 50 grams U-235;} PM " C U(/,.
. u (ii) no more than one defect when each item wiihin a batch of items has an assigned value of less than 500 grams U-235, but one or more items has an assigned value in excess of 50 grams U-235; and (iii) zero defectAhen any item within a batch of items contains 500 or more grams U-235.
-U SG-1.11 Notwithstandik the first paragrapl the licensee shall conductreceiver shippery of Sdetion comparisons on all SNM7.1'of thisreceived materials Plan identified by (regardless of whether tsooked orYths tiasis of receivef's or shipper's values), except for those materials identified in Section 7.1 of NUREG;1065 (Rev. 2) as being exempted from shipper-receiver comparisons. J Mi Y D? ech SECTION 2.0 - PHYSICAL PROTECTION OF SNM _OF_ LOW STRATEGIC SIGNIFICANCE R %r 1r '^
SG-2.1 The licensee shall follow the " Site Physical Security Plan - Westinghouse Electric Corporation, Columbia, S.C.," dated March 1980 Revision 10.0 dated October 1,1987; the " Revision Record" contained in the approved i 3hysical Security Plan (current to October 1,1994); and as may be revised in accordance with the provisions of 10 CFR 70.32(e).
SECTION 3.0 - INTERNATIONAL SAFEGUARDS SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility Attachment No. 5A dated August 31,1988, to the US/lAEA Safeguards Agreement. Such Transitional Facility Attachment shall be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7.
SG-3.1.1 With respect to Transitional Facility Attachment Code 2:
The reference design information is that dated by the licensee on October 14,1985. >
"Information on the Facility" also includes other facility information submitted via Concise Notes in accordance with 10 CFR 75.11(c).
NRC FORM 374A U.s. NUCLEAR REGULATORY Commission PAGE 6 of 8 PAGEs License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.13 SG-3.1.2 With respect to Transitional Facility Attachment Code 2.2:
Substantive changes to the information provided in the Columbia Plant Design Information Questionnaire (DIO) means those changes requiring amendment of the Transitional 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 in the DIQ means those changes not requiring amendment of the Transitional Facility Attachment. Such changes shall be provided by Concise Note (From DOE /NRC-740M) within 30 days of receiving notification from the NRC that the facility has been identified under Article 39(b) of the US/lAEA Safeguards Agreement.
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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:
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-Q (a) "Any change in the purpose of type of. facility" means:
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,y l' c Any deviation froq the described activities irWolving special nuclear material and any change to the maximum enrichnient and/or du'antities of U-235 currently authorized by License No. SNM-1'10J and/orTas described in Paragraph 5 of the Design Information Questionnaire (DIO) daldfOctober 14,1985(or as modified in accordance with 10 CFR 75.11(c).L included al5o is any deviation from the described special nuclear material (SNM) production activities described in paragraph 6 of the DIO dated October'14,1985, or as modified in accoidance with 10 CFR 75.11(c).
(b) "Any changes in the layout of the facility which affects safeguards implementation of the provisions of the Protocol",means:
Any change in the existing facility and/or site layout or new addition affecting any activity involving SNM as described in Paragraphs 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 Paragraphs 13 and 14 (per the referenced attachments) of the DlO dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).
(c) "Any change that makes the selected Key Measurement Points (KMPs)(as described in Code 3.1.2) inadequate for the Agency's accounting purpose" means:
Any change to the KMPs as described in Code 3.1.2 of the Westinghouse-Columbia
! Transitional Facility Attachment to the US/lAEA Safeguards Agreement, or as modified I in accordance with 10 CFR 75.11(c), that results in any KMP alteration affecting the f purpose of KMPs as stipulated by 10 CFR 75.4(m)
j , NRC FORM 374A u.S. NUCLEAR REGULATORY CoMMISsloN PAGE 7 of 8 PAGEs I
License Number i SNM-1107
) l MATERIALS LICENSE Docket or Reference Number
. SUPPLEMENTARY SHEET 70-1151 Amendment No.13 (d) "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's accounting purposes" means:
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 faci lity.
(e) " Introduction of a significantly less accurate analytical method for accounting purposes" means:
cra RE_cjg Random and Systematic" as listed in Any recalculation Attachment of the 36.2 referenced " Relative Errors;h 36 of the DIQ dated October 14 in Paragrap modified iri 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 or more.
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(f) " Decrease in the frequency of cabbrating measuring equipment if it significantly
( decreases the accuracy of the materials accounting system" means:
( tt Anyt e,change that . Dry results inhr kthe
. :systematic error being affected by a e estimates'of factor f two or'moreJ{j s '
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(g) "Any change in the statistical proce!dures,c used to combine individual measurement error estimates to obtain limits cf error for shipper / receiver (S/R) differences and material unaccounted for (MUF)"jneans:
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( Any deviation from (or modification of) the equations and/or calculations l outlined in Attachments 37.1,37.2, and 37.3 referenced in Paragraph 37 4 ofthe DIQ dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).
SG-3.1.3 With respect to Transitional Facility Attachment Code 3.1.2: ,
KMP* -- This is a KMP in which all shipper receiver differences (SRDs) must be recorded and reported even if numerically zero. SRDs are computed and reported by the Nuclear Materials Management and Safeguards System upon receipt of the receiver's measurement results.
SG-3.1.4 With respect to Transitional Facility Attachment Code 4:
The licensee shall use the material composition codes documented in the DIO dated October 14,1985, and as modified by Concise Notes. Further, notwithstanding any other requirements for advance notification and/or reporting, the licensee may add or delete composition codes for nuclear material routinely processed and on inventory at CFFF immediately upon telephone notification to the Office of Nuclear Material Safety and Safeguards. Follow-up documentation, in the form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment ;
j 34.8 to the DlQ shall be submitted within three regular workdays of the telephone notification.
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I NRC FORM 374A U.S. NUCLEAR REGULATORY CoMMISSloN PAGE 8 of c 8 PAGES License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number
, SUPPLEMENTARY SHEET 70-1151 Amendment No.13 SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1:
Measured discards should be reported as an SN (Shipment to non-safeguards facility) when shipped off-site to an authorized burial ground. (The IAEA system will not process measured discards as loss / disposal (LDs) when they are shipped off-site).-
SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1:
For inventory changes, time of recording,"upon" means: No later than the next regular k 1
workday (Monday through Friday).
For those occasions where natural'5r dehleted uranium is inadvertently enriched above 0.711 percent through commingling with residual enriched uranium in process equipment, the resultant product shall be considered as being produced through a blending operation and the material category change shall be recorded upon' obtaining measurement confirmation that a material category change _has occurred. /.
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SG-3.1.7 With respect to Transitional Facil'ity Attachinent Code 6.2.2:
[2 J, , = . . -) l 'x For Concise Notes describing the anticipated operatioital programme, " anticipated operational programme" rridanst Anticipate (physicallnventory shhedule.
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