ML20198E837
| ML20198E837 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 12/17/1998 |
| From: | Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20198E834 | List: |
| References | |
| NUDOCS 9812240157 | |
| Download: ML20198E837 (8) | |
Text
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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.
l Licensee
- 1. CBS Corporation, acting through its 3. License Number SNM-1107, Amendment 16 Westinghouse Electric Company division j
- 2. P.O. Box 355 4
- 4. Expiration Date November 30, 2005 l Pittsburgh, Pennsylvania 15230-0355 l
- 5. oocket uo. 70-1151 l
\hpS REG I/ Reference No.
Y pY 7. Chemical l
- 6. Byproduct Source, and/or and/or Physical Q. Maximum amount that Licensee ,
Special Nuclear Material 7s Form _, $May Possess at Any One Time (
,,JJnder This License '
A. U-235 h
} ;% Af}h}y t
r
=y[A ('yi h, A. 0.35 kg l B. U-235 g UB.xAn ptMS ,p : B.pma75,000 kgs O
Ik.
w g h h Co sg g g"sthap)@A, ): ~.W/o q ' g C. U-233 19. Any $ C. 5 grams D. Pu-238, D. ehecfsot#ce D. 1.5 grams l Pu-239 l
- 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 liwnsee is subject to compliance with all listed conditions in each section.
! FOR THE NUCLEAR REGULATORY COMMISSION i
t::_Aa>4.u V. b Date: M //7 / ' P Dy: Charles W. Emeiah. Acfina Branch Chief Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 9812240157 981217 PDR ADOCK 07001151 C PDR .
! NRd FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 of 8 PAGES License Number !
SNM-1107 l MATERIALS LICENSE Docket or Reference Number )
SUPPLEMENTARY SHEET 70-1151 l
Amendment No.16 l
l i 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 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.
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 applip,abg ;ommitments in Chapter 6.0 of the License Application and all other regulatory requirement e CSEs/CSAs (in the format of License Annexes) will be submitted to NRC tew andfor rpy,sgpummarlds9g#roprietary versions con approval.
the CSEs/CSAs for UN Tanks, ADU Conversion, URRS pi,ssolver, and Powder Blending (ADU) will also be provided at the sinie time as the License Annexesfpr those systems. All completed CSEs/CSAs will be indipendSntippeer-reviewed irt accordance with all applicable regulatory requirements and relaled procedures. Configuratioricontrol data packages for ongoing changes to facility structures, systems and c6f p'one'nts(akdfdontrols wIlfbe filed with their respective CSEs/CSAs to provide a substantii!!y completh " fra
. t Integrated Safety Assessments (ISAs) that will ultimately behppie t6e Fina g'Q%mework for sysye$ Safely Basis described l Application. CFFF wihgroviddthe Dce3 neies'to the ftf3C using the following schedule:
j MM ; IL 7 ~
g COMPLETION DATE (Calerfderhe$d 6 AP OCE$S SYSTEM 2Q98 Q UN Tan $
3098 k Y ID 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 3Q99 Final Assembly Storage IFBA (Excluding Rods)
Laboratories
- Will be done as ISAs (" Final Design Safety Basis")
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! NRC FORM 374A U.S. NUCLEAR RECULATORY COMMISSION PAGE 3 of 8 PAGES j License Number SNM-1107 Docket or Rererence Number
, h1ATERIALS LICENSE SUPPLEMENTARY SHEET 70-1151 Amendment No.16 l
l S-3. The licensee shall maintain and execute the response measures in the Site Emergency Plan, dated j 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 l by the licensee consistent with 10 CFR 70.32(i).
S-4. Deleted by Amendment 12, April 1998.
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 or 8 PAGES Liceme Number SNM-1107 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-1151 Amendment No.16 SAFEGUARDS CONDITIONS 1
l S_ECTION 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.
l SG-1.2 Operations involving special nuclear material which are not referenced in the Plan identified in l Condition SG-1.1 shall not be ir;itijat$ uptigagropriate safeguards plan has been approved by I
the Nuclear Regulatory C r$seron.
i) and (a)(2) to use the Forms DOE /NRC-SG-1.3742 Inand lieu of the 742C, requiremeQts the licggsee contained may use computer generatein 10 CFR 74.13(al'djorms provided a the latest printed instructions.f6t completing theparticular form is included.
I Ihi N l'/M C SG-1.4 In lieu of the requirements contained in CFRs 70.54 and 74!f5 to use the DOE /NRC Form-741, the licensee may use computer gen' ~etatedf6FmQdvided all irifdrmation required by the latest printed instructions for com'pIeting fhe.parITcM Witiasincluded. 3 4
p ,2G sd 2' SG-1.5 Deleted Per Amendmeht 3,"4ddliiONM$mi(m#ent n6w' contained in licensee's Fundamental Nuclear Material ControfP an. 'Q 9) $
SG-1.6 Notwithstanding the requiremerits of the FNMCflaWidentified in License Condition SG-1.1, the licensee may use (1) a single stEdilrdjpr stebsurement 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 i requirements relative to the materialidentified in Condition S-4; provided the conditions and i commitments contained in the licensee's November 30,1993, letter (identification # NRC-93-036) are satisfied.
i
- 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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- NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 5 of b DAGES l License Nurnber SNM-1107 MATERIALS LICENSE D cket r Rererence Number SUPPLEMENTARY SHEET 70-1151 Amendment No.16 l
l SG-1.9 Notwithstanding the requirement of Section ll.A.7, block U, of NUREG/BR-000S, 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 l Form 741) is used to book such receipts.
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- SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, " allowed number"within '
l the phrase " allowed number of defects"is hereby specified as being:
l (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; g reg (ii) no more than one defeqbvhen each item withinIbatch of items has an assigned value of less i i than 500 grams U-235,but one or more items has an assigned value in excess of 50 grams U-235; and q,
g' N;p -
, -, {
s -
7 (iii) zero defect wheirany itery lp a batch ms contiIns 500 or more grams U-235.
< : e 1 O l SG-1.11 Notwithstanding thd-first p$radr^ of'($e bdlof the PliiH identified by Condition SG-1.1, the l o I licensee whether shall booked on thecond68 basis %fje,cdi shihrecelyFM$
n L ,hippjfs va1Q$s s' nsexcept on al%),M materials for those materials received identified in Section 7.1 of NUREGh065}Reir2i i E mpted%om shipper-receiver comparisons.
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SECTION 2.0 - PHYSICAL PROTECTION Oh khiOF LOWhRATEGIC SIGNIFICANCE
'/ f SG-2.1 The licensee shall follow the "Sfti Rhysjcal;Se6drity Plan - Westinghouse Electric Corporation, Columbia, S.C.," dated March 1980; Revision 10.0 dated October 1,1987; the " Revision Record" l 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).
- SECTION 3.0 - INTERNATIONAL SAFEGUARDS 1
SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility Attachment No. 5A dated l August 31,1988, to the US/lAEA Safeguards Agreement. Such Transitional Facility Attachment shall l be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7.
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NnC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 of 8 PAGES
- License Number l SNM-1107 MATERIALS LICENSE D chet r Reference Number
- SUPPLEMENTARY SHEET 70-1151 l
l Amendment No.16 1
l- 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 l 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 (DlQ) means those chenges requiring amendment of the Transitional Facility Attachment. Such changes spagtg pM letter to the NRC Office of Nuclear Material Safety and Safeguards at least 7ggihys in advance lementation.
D h Non-substantive char $es to the information in the Di@means those changes not requiring changes shall be provided by Concise l
amendment of the TJansitional Note (From DOE /N8C-740MXwithin Facility Attachment.nS%gmotification 30 days,ofreceivin f I has been identified under Art ch 39(b);of,ttp (IAEA Safeguards Agreement.
l < d t O l
The types of modificatioris Witb(/ 'ir)". format
') is required under 10 CFR 75.11, (to be submitted in advaTee), hrEthose N Fatiidln Co'de 21@specifically:
(a)
O Wf "Any chinge idtke pu{rpone"of1 k $? & pe of fac4ty" means:
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Any deviatop/ rom the~ described a h
s involving special nuclear material and any change to the mayimum enrichrt en d/or quantities of U-235 currently authorized by License No. SNff-it(7,$ndkrn 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).
(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).
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NIC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 7 of O PAGES License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.16 i (c) "Any change that makes the selected Key Measurement Points (KMPs) (as described l in Code 3.1.2) inadequate for the Agency's accounting purpose" means:
l 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 j modified in accordance with 10 CFR 75.11(c), that results in any KMP alteration l affecting the purpose of KMPs as stipulated by 10 CFR 75.4(m)
I (d) "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's accounting purposes" means: l Any change Jothe cription atatcontained in Paragraph 34 (per the referenced attachments) 6f the DlO dated Octo6fp14,1985, or as modified in accordance with 10 CFR 7 11(c), that would not permit the Agency to conclude an SNM material balance-f[or the. Westinghouse-Columbia ffcjity.
- 46 hCN fQ,IT l (e) " Intro' duction of a'significantly q accurate =, analytical method for accounting purp es" O aa 2 4 Any rEcalc},i$ bony 'Fti ve'Erdrp-Ra om and Systematic" as listed in Attacignent4Birefek m ghgar ~ (sph 3tfof the DlQ dated October 14,1985, or as i modifiedin ad6Sase's eti10C 75.1 f random systerna(i ),6[s Mg affeh(c), thatofresults by a factor in the estimates o two or more.
(f) " Decrease inhefrequency of caljbr g measuring equipment if it significantly decreases the adeuracyAf tije disterials accounting system" means:
Any change that results in the estimates of the systematic error being affected by a l
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 DlQ dated October 14,1985, or as modified in accordance with 10 CFR 75.11(c).
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l NRC FORM 374A U.S. NUCLEAR REGULATORY COM%IISSION PAGE Q of b PAGES License Number l SNM-1107 MATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SHEET 70-1151 l
l Amendment No.16 l
l SG-3.1.3 With resoect to Transitional Facility Attachment Code 3.1.2:
I KMP* -- This is a KMP in which all shipper receiver differences (SRDs) must be recorded and I reported even if numerically zero. SRDs are computed and reported by the Nuclear Materials l Management and Safeguards System upon receipt of the receiver's measurement results. j
- l l SG-3.1.4 With respect to Transitional Facility Attachment Code 4
]
l 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 l
requirements for advance p(tifjc,atprgrid/or reporting, the licensee may add or delete composition codes for l
immediately upon phone tele,. nuclear notification to the^materialYobtitjejy Office of Nuclear Materialprocessed Safety and and on inv Safeguards. Follo;wYup documentation, in the forriPof a Concise Note accompanied by appropriate cha0ges to. Table 1 of Attachment 34.8gthe D!Q shall be submitted within three regular workday (of the telephone notificatidn[
A iW) ility4tta(
'M O l SG-3.1.5 . With respect t6"Transitionaf i Code 74.1:
ent
} 4. V e r' .? ,
shipped off-site'to arGlJth'o rirdd fgroundi(Thtj[p.
Measured disoErds AIMuld T@ l isiin SN:(Shj ment to non-safeguards facility) when AEA system will not process measured e ship discards as loss /d sposyl'(LDs{ . he off-site).
SG-3.1.6 With respect to TraffsjyonalIftachmegDode Fa51 5.1.1: )
For inventory changes, tiny 6 of;regordingkupon" means: No later than the next regular workday (Monday through Friday).
For those occasions where naturai 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: l For Concise Notes describing the anticipated operational programme, " anticipated operational programme" means: Anticipated physical inventory schedule. !
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