ML20204D697

Amend 18 to License SNM-1107 for W

ML20204D697
Person / Time
Site:	Westinghouse
Issue date:	03/10/1999
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20204D603	List: ML20204D624 ML20204D697 ML20204D718 ML20204D742 ML20204D916 ML20204E000
References
NUDOCS 9903240268
Download: ML20204D697 (12)

Text

1 SRC IORM 374 . , PAGE I Of 9 PAGES MATERI ALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Recrganization Act of 1974 (Public 1.aw 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 reliance on statements and renresentations her-tofore 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 uw such material for the purpose (s) and at the place (s) designated below; to delis er or transfer such material to persons authorized to receis e it in necordance 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 hereaner in etl'ect and to any conditions specilled below.

I.icensee il

1. Westinghouse Electric Company LLC (WELCO) 3.1.icense Number SNM-1107, Amendment 18

2. P.O. Box 355

4. npiration n te November 30,2005 Pittsburgh, Pennsylvania 15230-0355

5. Docket No. 70-1151 Reference No

6. llyproduct Source.and'or 7. Chemical and'or Physical 8. Maximum amount that ! ' ensee Special Nuclea- Material Form May Possess at Any Oi ime Under This License A. U-235 A. Any A. 0.35 kg B. U-235 B. Any, except B. 75,000 kgs metal, enriched to not more than 5.0 w/o C. U-233 C. Any C. 5 grams L. Pu-238, D. Sealed sources D. 1.5 grams Pu-239 E. Plutonium E. Feedstock with E. 5 grams transuranics and fission products l

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

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r SRC FOR\1374% L'.h. Nt'Cl. EAR REGl'LA10RY CO\l%115510N PAGE 2 of 9 PAGES Lxense Number SNM-1107 Docket or Reference Number SIATERIALS LICENSE SUPPLEMENTARY SilEET 70-1151 Amendment No.18 1

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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.

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

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FOR THE NUCLEAR REGULATORY COMMISSION

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Date: Date of closinq* By: Charles W. Emeich. Actina BFanch Chief Division of Fuel Cycle Safety and Safeguards Washington, DC 20555

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

NHCIOR\l374% t '.%. N . i DR HI Gl'lXI ORY CO\l%Il% ION PAUL 3 or 9 was lucnse Number SNM-1107 MATERIALS LICENSE Ddd or Reference Number SUPPLEMENTAlW SilEET 70-1151 Amendment No.18 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions in the license application dated April 30, 595, and supplements dated August 4 and 25, and September 25,1995; l 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; and name change amendment September 28,1998; January 18, and February 22,1999. l l

S-2 Criticality Safety Evaluations (CSEs) and Criticality Safety Analyses (CSAs) will define the interim cnticality 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 regulatory requirements. Summaries of 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 Annexes for those systems. All completed l CSE3/CSAs will be independently peer-reviewed in accordance with all applicable regulatory requirements and related procedures. Configuration control data packages for ongoing changes to facility structures, systems and components, and controls will be filed with their respective CSEs/CSAs to provide a substantially complete 'living" framework for system Integrated Safety Assessments (ISAs) that will ultimately become the Final CFFF Design Safety Basis described in Chapter 4.0 of the License Application. CFFF will provide the License Annexes to the NRC using the following schedule:

COMPLETION DATE (Calender Year) PROCESS SYSTEM 2Q98 UN Tanks

• 3098 ADU Conversion

• Rods (ADU & IFBA)

UF6 Cylinder Washing l

l 4Q98 ADU Pelleting l 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 IFBA (Excluding Rods)

Laboratories

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

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NRC H)R\1374A l' N. StTI. EAR REGl I.AIORY C0%1%11%I0% f PAGE 4 of 9 PAGl.S l lxcnse Number SNM-1107 MATERIALS LICENSE D cketo' Refc'c"c' Numbe' SUPPLEMENTARY SilEET 70-1151 l

Amendment No.18 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 l OR%137M U.R RlTIIAH REGl'lXIORY CO\l\ll% ION PAGE 5 or 9 Pacts lacense Number SNM-1107 Dodcue Referena Number MATERIALS LICENSE SUPPLEMENTARY SilEET 70-1151 Amendment No.18 SAFEGUARDS CONDITIONS SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTING SG-1.1 The licensee shall follow pages i through xviii and Chaptera 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.

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 computer generated forms provided all information required by the latest printed instructions for completing the particular form is included.

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, SG-1.5 Deleted Per Amendment 3, August 1996 Commitment now contained in licensee's Fundamental Nuclear Material Control Plan.

SG-1.6 Notwithstanding the requirements of the FNMC Plan identified 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 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.

SG-1.8 Notwithstanding the requirement of Section 6.2.1(a 7 of the licensee's Fundamental Nuclear Material Control Plan to unpackage and perform an item em . pon receipt of special nuclear material, the licensee is exempted from such requirement relativu to the matenalidentified in Condition S-4; provided the conditions and commitments contained in the licensee's November 30,1993, letter (identification # NRC-93-036) are satisfied.

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NHC FOR%I 374A U.S. SUCLEAR REGLI.A IORY CO4Dl!5510N PAGE 6 of 9 PAGES lxense Number SNM-1107 MATERIALS LICENSE Ikcket or Referente Number SUPPLEMENTARY SilEET 70-1151 Amendment No.18 5

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 any time limit j- relative to recovering and mcasuring 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, "a// owed 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; (ii) no more than one defect when each item within a batch of items has an assigned value of less I than 500 grams U-235, but one or more items has an assigned value in excess of 50 grams U-235; and (iii) zero defect when any item within a batch of items contains 500 or more grams U-235.

1 SG-1.11 Notwithstandir'g the first paragraph of Section 7.1 of the Plan identified by Condition SG-1.1, the l licensee shall conduct shipper-receiver comparisons on all SNM materials received (regardless of I whether booked on the basis of receiver'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.

SECTION 2.0 --PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE CG 2.1 The licensee shall fo' low the " Site Physical Security Plan - Westinghouse Electric Corporation, Columbia, S.C.," dated March 1980; Revision 10.0 dated October 1,1987; the " Revision Record" I contained in the approved Physical 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. l SG-3.1.1 With respect to Transitional Facility Attachment Code 2:

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

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t NRC } OR%13744 l'.S. NETI. EAR RF GI 1.ATORY CO\l%11% ION PAGE 7 of PAGES LKense Number SNM-1107 MATERIALS LICENSE IMeut Rdmna Numba )

SUPPLEMENTARY SIIEET 70-1151 l

Amendment No.18 )

i SG-3.1.2 With respect to Transitional Facility Attachment Code 2.2:

1 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 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 infcrmation 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 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:

(a) "Any change in the purpose of type of 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. 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 DIQ dated October 14,1985, or as modified in accordance 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 stachments of the DIQ dated October 14,1985, or as modified in accordance with 10 CM 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 purpose of KMPs as stipulated by 10 CFR 75.4(m)

NHC FOR%1374 l'.S. St'Cl EAR REGt'lXI ORY CO%I%IlsslON PAGE 8 of 9 Pacts lacense Number SNM-1107 MATERIALS LICENSE Nc'" o' Ref"ca" Nua*"

SUPPL.EMENTARY SilEET 70-1151 Amendment No.18 (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 facility.

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

Any recalculation 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 j modified in accordance with 10 CFR 75.11(c), that results in the estimates of the i m" dom and systematic errors being affected by a factor of two or more. l (f) nrease in the frequency of calibrating measuring equipment if it significantly decreases the accuracy of the materials accounting system" means: J l

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

I (g) "Any change in the statistical procedures used to combine ir.dividual 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 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 measure:nent results.

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e NRC IOR\l 37tt 13. NL CLEAR RI Gt'IATORY LOil%IINSION PAGE 9 or 9 PAots License Number SNM-1107 MATERIALS LICENSE Net or Refennce Nunkt gi,,,l EMENTARY SilEET 70-1151 Amendment No.18 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 Mate,-ial Safety and Safeguards. Follow-up documentation, in the form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.8 to the OlQ shall be submitted within three regular workdays of the telephone notification.

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 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 restJtant product shall be considered as being prcduced through a blending operation and the material category change shall be recorded upon obtaining measurement confirmation that a material category change has ocurred.

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

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

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i ATTACHMENT 4 License Number, StlM-770 Waltz Mill Site l

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'f ',4 UNfTED STATES

-y ,e<  ; NUCLEAR REGULATORY COMMISSION 5 l' 9,

g l nsG,os t m NENDALE PGAD _i'

'%e e M%G OF PPD 5%. PEN';5 y U/ a V A ?940614'5 March 1,1999 Docket Nos. 030-06134 License Nos. 37-05809-01 030-06135 37-05809-02

.030-32414 37-00497-15 070-00698 SNM-770 070-01143 SNM-1120 070-01503. SNM-1460 040-08976 SMB-1527 Control Nos. 126122 126123 126133 126125 126124 126126 126134 Louis J. Brinkman -

Executive Vice President and General Counsel CBS Corporation 51 West 52 Street New York, NY 10019-6188

Dear Mr. Brinkman:

This refers to your license amendment requests for License Nos. 37-05809-01,37-05809-02, 37-00497-15, SNM-770, SNM-1120, SNM-1460 and SMBc1527. Enclosed with this letter are the amended licenses.

Please review the enclosed documents carefully and be sure that you understand and fully implement a'l the conditions incorporated into the amended license. If there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region i Office, Licensing Assistance Team, (610) 337-5093 or 5239, so that we can provide appropriate corrections and answers.

r L. Brinkman 2 Thank you for your cooperation Sin ly,

. v)M i ff Pamela J. Henderson,. Acting Chief Ism Nuclear Materials Safsty Branch 2 Division of Nuclear'IAaterials Safety

Enclosures:

1. Amendment No. 23 for License No. 37-05809-01

2. Amendment No.18 for License No. 37-05809-02

3. Amendment No. 3 for License No. 37-00497-15

4. Amendment No.19 for License No. SNM-770

5. Amendment No.14 for License No. SNM-1120

6. Amendment No. 8 for License No. SNM-1460

7. Amendment No. 3 for License No. SMB-1527 I