ML20206H429

Amend 19 to License SNM-1107 for Westinghouse Electric Co

ML20206H429
Person / Time
Site:	Westinghouse
Issue date:	05/03/1999
From:	Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20206H424	List: ML20206H422 ML20206H429 ML20206H436
References
NUDOCS 9905110208
Download: ML20206H429 (9)

Text

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NRC FORM 374 PAGE t OF PAGES U.S. NUCLEAR REGl'LATORY COMMISSION MATERIALS LICENSE Pursuant to th'e 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 by product, 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 l it in accordance with the regulations of J e t.pplicable Part(s). This li .nse 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 I. Westinghouse Electric Company LLC (WELCO) 3. License Number SNM-1107, Amendment 19

2. P O. Box 355

4. Expirati n Date November 30, 2005 Pittsburgh, Pennsylvania 15230-0355

5. Docket No. 70-1151

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6. Byproduct Source, and/or <7.' Chemical and'or Physical ' ' .f 8. Maximum amount that Licensee '

Special Nuclear Material

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Form 'A May Possess at Any One Time

- ;,Under This License 9 jy.. _y '

A. U-235 .. A , Any , f.? A, 0.35 kg g 47, -

(c3 n B. U-23E C-r ~ ~yt e'x cept J B.' 2- An j B.Z75,000 kgs ef LW t metakent. .

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, PAi ' t6'not Wo'rb? " , ir ' .']

l gl * :Qthan'5 .0$ g C. U-233 y$ C.

t Any ql RC, e 5 grams .

D. Pu-238,

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D. ; Sealed sourcet

? D. 1.5 grams j Pu-239 #T% '

I E. Plutonium E. Feedstock with E. 5 grams transuranics and fission products i

9. Authorized place of use: The licensee's existing facilities at Columbia, South Carohna.

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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 >f PAGES I L sense Number SNM-1107

' MATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SilEET 70-1151 Amendment No.19

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.

11. The licensee shall meet all financial assurance requirements within 30 days of the closing of ownership transfer of assets.

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FOR THE NUCLEAR REGULATORY COMMISSION l

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Dat3: @"41 Wp By:_. Theodore S. Sherr. Chief Draision of Fuel Cycle Safety j and Safeguards j Washington, DC 20555 {

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• To be provided to the NRC Office Director by letter or facsimile not later than 30 days after the date of the l Intt:r transmitting this license to the former licensee of ths date the transfer occurred.

l NRC FORM 374A U.S. NUCLEAR REGUtATORY COMMISSION PAGE 3 of PAGES License Number SNM-1107

. MATERIALS LICENSE Docket er Reference Nu:nber SUPPLEMENTARY SHEET 70-1151 Amendment No.19 I

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SAFETY CONDITIONS {

1 S-1. Authorized use: For use in accordance with statements, representatio'ns, and conditions in the license application dated April 30,1995, and supplements dated August 4 and 25, and September 25,1995; November 8, and August 30,1996; July 14 and 25, November 17,1997; and name change {

amendment December 22,1997; and April 3, June 30, July 13, July 23, October 21, and October 30, j 1998; and February 12,1999; and name change amendment September 28,1998; January 18, and {

February 22,1999. j S-2 Criticality Safety Evaluations (CSEs) and Criticality Safety Analyses (CSAs) will define the interim criticality safety bases utilized throughout the.CFFF. All CSEs/CSAs will be upgraded and/or completed in accordance with all applichbid conimitments in Chapter 6.0 of the License Application and ,

all other regulatory requiremenfs? Summaries of the CSEs/CSAs (in the format of License Annexes)

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I will be submitted to NRC for! review and approval. Proprietary versions containing Sections 1 and 5 of I the CSEs/CSAs for UN Tanks, ADU Conversion, URRS Dissolver, and Powder Blending (ADU) will also be provided at the same time as the License 4 CSEs/CSAs will be independently peer-reviewed accordance with all in$nnexes~for those systems. ;

applicable regulatory requirements and related procedures. Configuration control dhta packages for ongoing changes to j facility structures, sysibms and co'niponentsl arid'6ontrols will)e filed with their respective CSEs/CSAs  ;

to provide a substantialjy completejliVing" #amsysork for system Integrated Safety Assessments (ISAs)

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.Application.

that willCFFF ultimately wilfp,rovide the- becorpe - .-the to'the.NRC Licer}se Xridexes Final g CFg',Desig'n Safety Basi1 using the following schedule:

vi t ' a sj) 3 l COMPLETION DATE (Calen'dhr Year)

• PROCESS SYSTEM

., p l 2Q98 S g g .y N 7anks*

3Q98 ADU Conversion * ,

Rods (ADU & IFBA)

UF6 Cylinder Washing {i 4Q98 ADU Pelleting  !

URRS Dissolver* j Powder Blending -(ADU)* j 1

1Q99 Low-Level Waste Processing l Hoods & Containment 2099 URRS Scrap Processing I Solvent Extraction l URRS Waste Treatment )

3Q99 Final Assembly l Storage IFBA (Excluding Rods) ,

Laboratories ]

• Will be done as ISAs (" Final Design Safety Basis")

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NRCh0Rhl 374A U.S. NUCLEAR REGULATORY COMMLSSION PAGE 4 of PAGLS .i License Number SNM-1107 j

. . MATERIALS LICENSE D c'et o' Reference Number SUPPLEMENTARY SHEET 70-1151 1 Amendment No.19 i l

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). l S-4. Deleted by Amendment 12, April 1998. l I

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l SG-1.11 Notwithstanding the first paragrqph of Sect,iong1 of the Plah identified by Condition SG-1.1, the j licensee shall conduct shipper-recelye pansons on allSNM materials received (regardless of 1 whether booked on the basis' offreceik[e :or shipper's values), except for those materials' Section 'i.1 of NURE41065]Ref.2 )'E 2 'tMiny eximptect'from shipper-receiver comparisons.

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SECTION 2.0 -- PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE I e

SG-2.1 The licensee shall follow the " Sits Physical .Sec0rity Plan - Westinghouse Electric Corporation, l Columbia, S.C.," dated March 1980; Revision 10.0 dated October 1,1987; the " Revision Record"  :

contained in the approved Physical Security Plan (current to October 1,1994); and as may be l revised in accordance with the provisions of 10 CFR 70.32(e).  !

n 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 l on the Facility" also includes other facility information submitted via Concise Notes in accordance with 10 CFR 75.11(c).

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n NRC FORM 374A U.S. NUCLEAR REGULATORY CO3tMISSION PAGE 7 of PAGLS License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SilEET 70-1151 Amendment No.19 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 (DlQ) means those changes requiring amendmeat of the Transitional Facility Attachment. Such changes shcIl 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 shcIl be provided by Concise ,

Note (From DOE /NRC-740M) within 30 days of receiving notification from the NRC that the facility  !

has been ident$ied under Article 39(b) of the US/lAEA Safeguards Agreement.

iu y, The types of modifications with respect to which information is required under 10 CFR 75.11, (to be I submitted in advance); are those items stated in Code 2.2, specifically: l (a) "Any change in the purpose of type of facility' means:

Any ddviation fhohthe discribe etivities involving special nuclear material and any charige to tiie maximum enrichthent and/or fuantities of U-235 currently authorized by License' No/SNM-1307liiridof~as descritdin Paragraph 5 of the Design Information  !

Questionnalr'e (DiQ) dated! October;14; 1985; or as modified in accordance with 3 10 CFR 75.11(c)Alncilided his'o is any devia" tion from the described special nuclear i material'(S,NM) production activities described in paragraph 6 of the DIO dated October 1471985, or as modified in accordance with 10 CFR 75.11(c).

v w l (b) "Any changes in tke layout of th$ facility which affects safeguards implementation (,f I 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 OlO dated October 14,1985, or as modified in acccrdance 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 DIQ 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 in accordance with 10 CFR 75.11(c), that results in any KMP alteration affecting the purposc of KMPs as stipulated by 10 CFR 75.4(m).

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. NRC FORM 374A U.S. NUCLEAR REGULATORY COMMLSSION PAGr. 3 of PAGES License Number '

SNM-1107  !

' MATERIALS LICENSE D cket r Reference Number SUPPLEMENTARY SHEET 70-1151 l

Amendment No.19 I

(d) "Any change in the physical inventory procedures that would adversely affect the  !

inventory taking for the Agency's accounting purposes" means: I I

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-Columbio facility. I I

(e) " Introduction of a significantly less accurate analytical method for accounting purposes" means:

Any recalculatiokohth " e a ve Nrrors-Random and Systematic" as listed in Attachment 36.'2referenced in Paragr'aph 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 l random. and systematic errors being affected by a factor of two or more. )

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(f) " Decrease in the,frequer!cy of calibrating me~asuring equipment if it significantly

. decresses the accuracy of the'rhaterials accounting system" means:

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Any c6ang. .... estima tes of t[e systematic error being aff factory two or moreA F '

(g) "Any cha6ge in the statistical pr6ckdures idsed to combine individual measurement

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error estimaje,s to obtain limits of erro[for shipper / receiver (S/R) differences and "J

material unaccounted er 4 g Jg for (MUF)&neans:

Any deviation from (or modification of) the equations and/or calculations outlined in Attachments 37.1,37.2, and 37.3 rcferenced in Paragraph 37 of the DlO 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.

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, NRC FOILM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 9 3r PAGES License Number SNM-1107

' MATERIALS LICENSE Docket or Rererence Number SUPPLEMENTARY SHEET 70-1151 l

Amendment No.19 SG 3.1.4 With respect to Transitional Facility Attachment Code 4:

The licensee shall uso the material composition codes documented in the DIQ 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 . 1 appropriate changes to Table 1 of Attachment 34.8 to the DlQ shall be submitted within three j regular workdays of the telephone notification. ]

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l SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1: i y ^*! 7

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Measured discards should be reported as an SN (Shipment to non-safeguards facility) when shipped off-site to an authorized burial ground. (The lAEA system will not process measured 4 discards as losa/disposaf(LDs) when they aie shippdd off-site).

b M, . #) l' f3 O SG-3.1.6 With respect to1Trans.itional Facility Atta ment Code 3.1.1:

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p For inventory c6ang'es[tind6G ddidiS"Upo'n',' mealis: No later than the next regular il f d j w w *f # '

workday 4 (Mondgy throi.igl1 For those occasiops wh'ere'natu'raf$r d ed uralitum isFriday)dl@+h c7 inadvertently enriched above 0.711 percent through coriirpipgling with rdsidual'enric6e'd uranium in process equipment, the

. resultant product shall be considered as b9 inc7 produced through a blending operation and the material category change shall beJecord d upon obtaining measurement confirmation that a material category change has occurred.

i SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2:

For Concise Notes describing the anticipated operational programme, " anticipated operational i programme" means: Anticipated physical inventory schedule.

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