ML20155C507

Amend 15 to License SNM-1107 for Westinghouse Electric Co

ML20155C507
Person / Time
Site:	Westinghouse
Issue date:	10/07/1998
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20155C486	List: ML20155C482 ML20155C507 ML20155C516
References
NUDOCS 9811020253
Download: ML20155C507 (8)

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K ORM M U.S..VCLEAR REGl'LATORY 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 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the beensee, a heense 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 authonzed to recen e it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the cond:tions 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

1. CBS Corporation, acting through its

3. License Number SNM i107, Amendment 15 Westinghouse Electric Company division 1

2. P.O. Box 355

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

5. Docket No. 70-1151 i

j Reference No.

6. Byproduct Source, and/or

7. Chemical and'or Physical

8. Maximum amount that Licenser Swat Nuclear Material Form May Possess at Any One Time 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 D.

Pu-238, D.

Sealed sources:

D.

1.5 grams Pu-239 9.

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

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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 alllisted conditions in each section.

FOR THE NUCLEAR REGULATORY COMMISSION

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w.ui Date: /c/'7/9/s By: dharles W. Emeigh. bling.BrancA bhief Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 9811020253 981007 PDR ADOCK 07001151 C

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SRU FORNI 374 A U.S. NOCI. EAR REGULATORY Coil %IISSION PAGE 2 of 8 PAGLs License Number SNM-1107 MATERIALS LICENSE wet or kercrcnce wreer

' SUPPLEMENTARY SilEET 70-1151 Amendment No.15 l

SAFETY CONDITIONS S-1.

Authonzed 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 June 30, July 13, and July 23,1998.

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 cil 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 CSEs/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:

COMPLETlON DATE (Calender Year)

PROCESS SYSTEM 2098 UN Tanks

• 3Q98 ADU Conversion

• Rods (ADU & IFBA)

UF6 Cylinder Washing 4Q98 ADU Pelleting URRS Dissolver*

Powder Blending (ADU)*

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

Laboratories

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

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l 3Rc FORN! 374A l'.S. Nt' CLEAR REGl'LATORY COND11SSION PAGE 3 of 8 PAGES License Number SNM-1107 l

BIATERIALS LICENSE Docket or Rererence Number SUPPLE 31ENTARY SilEET 70-1151 Amendment No.15 l

S-3.

The licensee sha" 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.

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O N RC FORM 374 A U.S. Nt'CLI'AR RECELATORY COMMISSION PAGE 4 or PAGLS License Number SNM-1107 MATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SilEET 70-1151 l

Amendment No.15 l

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 Operations involving special nuclear material ahich 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 licenses may use computer generated forms provided all inicrmation 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 Fcrm-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-1.6 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

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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 leveis acrose 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 reqt.irements relative to the materialidentified 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).5 of the licensee's Fundamental Nuclear 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.

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b NRC FORM 374A U.S. Nt'Cl. EAR REGl'LATORY CO\\tMISSION PAGE 5 of PAULS lacense Number SNM-1107 MATERIALS LICENSE M" or Reference N=ber SUPPLEMENTARY SIIEET 70-1151 Amendment No.15 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 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; (ii) ne more than one defect when each item within 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 defect when any item within a batch of items contains 500 or more grams U-235.

SG-1.11 Notwithstanding the first paragraph of Section 7.1 of the Plan identified by Condition SG-1.1, the licensee shall conduct shipper-receiver comparisons on all SNM materials received (regardless of 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 PROTEGILON_OE SNM OF LOW STRATEGIC SIGNIFICANCE 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 (current to October 1,1994); and as may be revised in accordance with the provisions of 10 CFR 70.32(e).

SECIlON 3.0 -- INTERNATIONAL SAFEGUARDS SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility Attachment No. SA 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.

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m rOR\\i 374A ti.s. NtTLEAR REGt'I.ATORY CO\\lillSSION PAGE 6 of PAGLS License Number SNM-1107 MATERIALS LICENSE Dwket or Reference Number SUPPLEMENTARY SilEET 70-1151 Amendment No.15 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).

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 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 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, ('o be j

submitted in advance), are those items stated in Code 2.2,'specifically:

(a)

"Any change in the purpose of type of facility" means:

I Any deviation from the aescribed 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 descriMd in Paragraph 5 of the Design Information i

Questionnaire (DIO) 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 DIO dated October 14,1985, o. as modified in accordance with 10 CFP 75.11(c).

(b)

"Any changes in the layout of the facility which affects safeguards implementation of l

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 DIO dated October 14,1985, or as modified in accordarce with 10 CFR 75.11(c). Included also is any modification to, or deviation from, the c 4'a

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provided in Paragraphs 13 and 14 (per the referenced attachments) of the D'O dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).

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sachOnu 374A U.s. st' CLEAR REGl I.ATORY COMMISSION PAGE 7 of 8 P AGl.S License Number SNM-1107 MATERIALS LICENSE Duket r Refaence Numba 70-1151 SUPPLEMENTARY SilEET Amendment No.15 (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 stlpulated by 10 CFR 75.4(m)

(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-Ran' dom and Systematic" as listed in 6.2 referenced in Paragraph 36 of the DlO 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 or more.

(f)

" Decrease in the frequency of calibrating measuring equipment if it significantly decreases the accuracy of the materials accounting system" means:

Any change that results in the estimates of the systemat:' 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 DIO 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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tr.s.xt ct. EAR REGl't.ATORY cO\\l%IISSION f PAGE 8 of O PAGLS NRc rORsi 3744 Ucense Nurnber SNM-1107 MATERf ALS LICENSE Docket or Reference Number 70-1151 SUPPLE 31ENTARY SIIEET Amendment No.15 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 1

Safeguards. Follow-up documentation,in the form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.8 to the DIO 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 res! dual 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 i

material category change has occurred.

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

For Concise Notes describing the anticipated operational programme, " anticipated operational l

programme" means: Anticipated physical inventory schedule.

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