ML20207J772

Amend 17 to License SNM-1107 for CBS Corp Acting Through W Div

ML20207J772
Person / Time
Site:	Westinghouse
Issue date:	03/04/1999
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207J768	List: ML20207J767 ML20207J772 ML20207J777
References
NUDOCS 9903160388
Download: ML20207J772 (9)

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U.S. NUCLEAR REGl*LATORY COSIN11SSION MATERIALS LICENSE Pursuant to the Atomid Energy Act of 1954, as amended, the Erargy Reorganization Act of 1974 (Public Law 93-438), and Title 10 Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in neliance 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 oclow; to use such material for the , mse(s) and at the place (s) designated below: to deliver or transfer such material to persons authorized to receive ,

it in accordance with the regulation < on ,licable 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 sut% m a*1 applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereancr in effect and to any conditions specified below. l Licensee

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1. CBS Corporation, acting through its 3. License Number SNM-1107, Amendment 17 Westinghouse Electric Company division  ;

2. P.O. Box 355 4. Expiration Date November 30,2005 Pittsburgh, Pennsylvan.ia 15230-0355

5. Doctet No. 70-1151

.%. b BREG If Reference No.

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6. Hyproduct Source, and/or g[ 7. Chemical and/or Ph> sical (8. Maximum amount that Licensee Special Nuclear Material ,f Ferm $May Possess at Any One Time '

,t .a. ' Under This License w e. s ,o s' f a%

r A. U-235 .[.' A.' %ny -

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. W s u >If A.%,0.35 kg

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g Phto~notporel& jf '

than,S.0w(o6 f g

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Q C. U-233 Any A C. 5 grams '

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D. Pu-238, D. Sealedsou rces & D. 1.5 grams .

Pu-239 E. Plutonium E. Feedstock with E. 5 grams transuranics and fission products

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

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1 WRC FORM 374A U.S. NUCLEAR REGt'LATORY COMMISSION PAGE 2 or 9 PAGES I

License Number SNM-1107 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-1151 Amendment No.17

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 comp'iance with all listed conditions in each section.

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i FOR THE NUCLEAR REGULATORY COMMISSION Date: V/99 By:

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d{arles W. Emeiah. Actina BYnch Chief Division of Fuel Cycle Safety and Safeguards Washington, DC 20555

,NRC FORM 374A U.S. NUCLEAR REGl'LA10RY COM%llSSION PAGE 3 or 9 PAGL5 License Number SNM-1107

. MATERIALS LICENSE D cLet or Rererence Number SUPPLEMENTARY SHEET 70-1151 Amendment No.17 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, 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, 1998; and February 12,1999.

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 applicable commitments in Chapter 6.0 of the License Application and all other regulatoy requirements.gSurhmaries'5f.the ~

CSEs/CSAs (in the format of License Annexes) will be submitted to NRC for review and approval. Proprietary versions containing Sections 1 and 5 of 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 AnnexesLfor those systems. All completed CSEs/CSAs will be ind4 pendently peer-reviewed in accordance with all applicable regulatory requirements and related procedures. ConfiguratjAn control data packages for ongoing changes to facility structures, systems and componentst and controls will be filed with their respective CSEs/CSAs to provide a substanti that will ultimately opiebec,al.ly complete the Final CFgDesign; Safety (living" frame $mrk Basis described for 4.0 in Chapter systepi lntegrated of the License Application. CFFF will provide the License nexes to the NSC using the fol lowing schedule: '

COMPLETION DATE /Calen' der ean h ' hl0

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> PROCESS SYSTEM

_]r 2098 / UN Tank's

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, 3Q98

• F 'ADU Conversion

• Rods (ADU & IFBA)

UF6 Cylinder Washing 4Q98 ADU Pelleting URRS Dissolver*

Powder Blending (ADU)*

1Q99 Low-Level Waste Processing Hoods & Containment 2099 URRS Scrap Processing Solvent Extraction URRS Waste Treatment 3099 Final Assembly Storage l IFBA (Excluding Rods)

Laboratories

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

' suc MRM M4A U.S. NUCLEAR REGl LATORY COMMISSION PAGE 4 of 9 PAGES License Number

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SNM-1107 MATERIALS LICENSE Docket or Reference Number 70-1151 SUPPLEMENTARY SHEET Amendment No.17 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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.NRC FORM 3744 U.S. NUCLEAR REGt:LA10RY COM4flSSION PAGE 5 of 9 PAGES Liceme Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.17 SAFEGUARDS CONDITIONS SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING '

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 Operat;ons involving special nuclear material which are not ieferenced in the Plan identified in Condition SG-1.1 shall not be initiated unti! an appropriate safeguards plan has been approved by the Nuciear Regulatory Com, mission. vi y-s SG-1.3 in lieu of the requirementYcontained in 10 CFR 74.13'(a)(1) and (a)(2) to use the Forms DOE /NRC-742 and 742C, the licensee may use computer generated forms provided all information required by the latest printed instnictions for completing the particular form is included.

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SG-1.4 in lieu of the requirem:ents 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

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instructions for com'p'leting the pardcillkff6Irfn is included. 5 SG-1.5 Deleted Per Amendment Q ' kfMN4 [ d 3[, A'ugustib96Mommitment no'w contained in licen

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Nuclear Material Contro[P,lan.

% .u SG-1.6 Notwithstanding the requir5n$ents of the FNMC Plarildentified in License Condition SG-1.1, the licensee may use (1) a single stahdard _for measurement control (including daily control limit

, monitoring and bias corrections) for any linear-response tube or rod scales, in any initially demonstrrted 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 l Fundamental Nuclear Material Control Plan, the licensee is exempted from physical inventory j requirements relative to the material identified in Condition S-4; provided the conditions and -

commitments contained in the licensee's Novemtsr 30,1993, letter (identification # NRC-93-036) are )

satis'ied. j

. SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear Material f 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 licensec's November 30,1993, letter (identification # NRC-93-036) are satisfied.

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• NRC FORM 374A U.S. Nt' CLEAR REGl'LATORY COMMISSION PAGE 6 of 9 PAGES License Number SNM-11Di '

Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-1151 j

Amendment No.17 i

1 SG-1.9 Notwithstanding the requirement of Section ll.A.7, block U, of NUREG/BR-0006, which is 4 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 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.

i i SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, " allowed number"within j the phrase " allowed number of defects"is hereby specified as being:

i' (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; , p REo

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(ii) no more than one defect when each item withirNbatch 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;

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, (iii) zero defect when any item within a batch of items contsins 500 or more grams U-235.

'4 i(,~ , in . O SG-1.11 Notwithstanding ths-first paragrap'h of Section 7.'1'of the Plan identified by Condition SG-1.1, the licensee shall conduEt shipper-recel d6dpiirisons On alljNM materials received (regardless of whether Section 7.1 of booked on the ba' sis' of'recei@'as'Mfns exempted from shipper NURE'G-10651Reic2) fi,. ',[ . &y $

SECTION 2.0 -- PH(SICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE

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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 Physical Security Plan (cu'rrent 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 8 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 I be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7. 1 J

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SRC FORM 374A U.S. Nt' CLEAR REGl'LATORY COMMISSION PAGE 7 of 9 PAGES License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number  !

SUPPLEMENTARY SiiEET 70-1151 Amendment No.17 )

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SG-3.1.1 With respect to Transitional Facility Attachment Code 2:

1 The reference design information is that dated by the licensee on October 14,1985. "Information on the Facility" also includes other facility information cubmitted via Concise Notes in accordance with 10 CFR 75.11(c).

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 (DIQ) means those changes requiring amendment of the Transitional Facility Attachment. Such changes shall be proylded.by letter to the NRC Office of Nuclear Material Safety and Safeguards at least 70-days in advarice 6f implementation.

g My Non-substantive changes to the information in the DIO 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.

The types of modificatioris with' respect tb whIEh'information is required under 10 CFR 75.11, (to be submitted in adva'nSe), ars thosditefrid state'd in Code 2.57specifically:

"AnyQ  ?% in the}purp&h.

change y- 2.* ,

(a) ose of type of facility" means: 1

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, M w Any devi$ tion,from the'Sescribed activitie's involving special nuclear. material and an change to the maximum enrichrnent and/or quantities of U-235 currently authorized by License No. SNM-1107,,and/or as described in Paragraph 5 of the Design Information 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 DlO dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).

"Any changes in the layout of the facility which affects safeguards implementation of I (b) the provisions of the Protocol" me. s:

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 OlO dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).

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• NRC FORM 374A U.S. NUCID.R REGUI.ATORY COMMISSION PAGE O or 9 PAGES 1.icense Number SNM-1107 D cket r Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 704151 Amendment No.17 1

i (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 i modified in accordance with 10 CFR 75.11(c), that results in any KMP alteration affecting the purpose of KMPs as stipulated by 10 CFR 75.4(m) l (d) "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's accounting purposes" means:

- B R REa r Any change to the description data contained in Paragraph 34 (per the referenced I attachments) of the DIQ dated October 14,1985, or as modified in accordance with 1 10 CFR 75'11(c), that would not permit the Agency to conclude an SNM material balance for the Westinghouse-Columbia facility. <

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(e) " Introduction of a significantly less'accurateinalytical method for accounting Purposes" means:( f O r~ ,

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Any rehalculatioriot the}'3eJatife Errors-RaMom and Systematic" as listed in Attachtpent'36.2

' teferenped in, Paragraph 36 of the DIQ dated October 14,1985, or as modified in aciio'rdince'with'10~CFR 75.1.f(cI), that results in the estimates of the random'a'nd systematic e'rrors b'sihg affe'cted by a factor of two or more.

~Q .O' (f) " Decrease in khe frequency of cal,ibrating measuring equipment if it significantly decreases the aciuracy of the materials accounting system" means:

Any change that results in the astimates of the systematic error being affected by a factor of two or more.

(g) "Any change in the statistical procedures used to combine individual measurement error estimates to obtain limits of error for shipper / receiver (S/R) differences and material unaccounted for (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 ofthe DlO dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).

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' NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISMON PAGE 9 or 9 PAGES License Number SNM-1107 l D 'ket or Reference Number AIATEllIALS LICENSE SUPPLEMENTARY SHEET 70-1151 Amendment No.17 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 DlQ dated October 14,1985, and as modified by Concise Notes. Further, notwithstanding any other requirements for advance,notificatior[and/o,r reporting, the licensee may add or delete composition codes for nuclear material routinely processed and on inventory at CFFF immediately upon tele' phone notification to the Office of Nuclear Material Safety and Safeguards. Follow 2up documentation, in the forrri of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.8'to the DlO sha" be submitted within three

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regular workdays of the telephone notification.

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SG-3.1.5 With respect to1Transitiondi Facilifh Attac$ent Code'4.1:

y ,  ; q( j; abn SN (Shi[y ment to non-safeguards facility) when Measured discards sMuld shipped off-site _to ari authorized 13ur . bErdd6@}a! ground l!(ThejAEA system discards as loss /disposil (LDs)Myn'they afe shippied off-site).

, y y SG-3.1.6 With respect to Tr$risitional Facility Attachrnent 'Cdde 5.1.1:

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For inventory changes, tirde of, recording,Supon" means: No later than the next regular workday (Monday through Friday).

For those occasions where natural or depleted 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.

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

For Concise Notes describir.g the anticipated operational programme, " anticipated operational j programme" means: Anticipated physicalinventory schedule.

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