ML20236Q562
| ML20236Q562 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 07/10/1998 |
| From: | Adams M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20236Q539 | List: |
| References | |
| NUDOCS 9807200338 | |
| Download: ML20236Q562 (8) | |
Text
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NRC FOR51374 PAGE 1 OF 8 PAGES U.S. Sl' CLEAR REGl'LATORY Costgggssgoy MATERIALS LICENSE Pursuant'to the Atbmic 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 licensee, o 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 Pan (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 efTect and to any ,;onditions specified below.
Licensee
- 1. CBS Corporation, acting through its 3. License Number SNM-1107, Amendment 14 Westinghouse Electric Company division
- 2. P.O. Box 355
- 4. Expiration Date November 30, 2005 Pittsburgh, Pennsylvania 15230-0355 REG
% g-v j Docket No. 70-1151
-Etfe,rence No.
x
- 6. Byproduct Source, and/or 7. Chemical and/or Physical ASMuimum amount that Licensee Special Nuclear Material ' i form D@ V3 N oh' V Qiay Possess at Any One Time k ?? b. nder This License A. U-235 ,T t-A(
i< t E
)M 3%
fj A.CO.35 kg
@ E- '[ B$75,000 kgs B. U-235 h 5:[An O
& 9%
hCt o gd more*h[] %
d tfiakg,dylo 4N A $
C. U-233 5 grams C.$nykiYg C.
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.
- 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.
FOR THE NUCLEAR REGULATORY COMMISSION I(9 Date: 7!#/98 By: Ma T. Adams. Actino Branch Chief
/ Division of Fuel Cycle Safety and Safeguards
, $^'-Sington, DC 20555 9807200338 980710 '
_--._m.m._-__m -
f-NRC FORM 374A u.S. NUCLEAR RE!uLAToRY CoM'OSloN PAGE 2 of 8 PAGEs
! Liccnse Number l~ SNM-1107
! MATERIALS LICENSE Docket or Reference Number 70-1151 l~ SUPPLEMENTARY SHEET
- Amendment No.14 l
SAFETY CONDITIONS l S-1. Authorized use: For use in accordance with statements, representations, and conditions in the license l application dated April 30,1995, and supplements dated May 11 and 18, August 4 and 25, and l
September 25,1995; November 8, and August 30,1996; July 14 and 25, August 11, November 17, and December 17,1997; and name change amendment December 22,1997; and January 9 and 12, 1998.
l S-2. The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis (CSAs) will define the criticality safety bases utilized throughout the plant and will be completed as described in Sections 6.4.1 and l 6.4.2 of the license application for each step of the process. A submittal to the NRC will be made by Westinghouse which will include ipfo['rpati5Nwpich the staff will review against the commitments listed in Section 6.2.3 of the licensgapplic^ation. Thedetebittals will not be specific commitments, but are intended as a demonstration.bf the adequacy of the Daryas of safety itemized in Section 6.2.3. The contents listed in SectionA4'.2 of the license application dre commitments. The demonstration will show the logic used byi e Columbia Fuel Fabrication Fpctlity (CFFF)in developing the criticality safety bases. It is underst at t onstration ange over time. The submittal will consist of a summary of the CSE 6r.CSA as: 'otated bel ' ach sy!ilem (which shall include fault trees for e
those systems for whi@ a CSE dp'n'e}. equacy3f the commitments in Section 6.2.3 of the license applicatio&will be ev' ted"addapplyIn the form of a letter report will be generated and sent from the staff to Westi ouseDV u m:wrifttel by the CgF will be provided according to the following schedule: p '2 $ '
~
oy -UNJums$phiaggn%
tanks - @
CSS 0/95 e
huRRS Dissokei- su ma0rbf CSE - 10/95 e doivent Extraction - sudNnary of CSE - TBD*
- UR% rag.P ing:
e Low-Lev I VYas@te Processing System - summary of CS Mop Water System Equipment - summary of CSA - 9/96 Incinerator System - summary of CSE - 9/96 Ash Recovery System - summary of CSE - 9/96 Liquid Honing System - summary of CSE - 9/96 Ultrasonic Cleaning System - summary of CSE - 9/96 Shredder System - summary of CSE - 9/96 e URRS Waste Treatment - summary of CSA - 11/95 e IDR Conversion - summary of CSE - Prior to Restart
- ADU Conversion - summary of CSE - 4/96 e ADU Pelleting - summary of CSE - 6/96 e Powder Blending - summary of CSE - 1/96
- The CFFF has performed a CSA upgrade and does not have a specific date for schedule of this CSE at this time.
l I
I
NRc FORM 374A U.S. NUCLEAR REOULAToRY COMMISSION PAGE 3 of 8 PAGEs
~
Uc;nse Number SNM-1107 MATERIALS LICENSE Docket or Reference Number
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SUPPLEMENTARY SHEET 70-1151 Amendment No.14 e Miscellaneous:
Ventilation Systems (Geometry Controlled) -
summary of CSE - 3/98" Ventilation Systems (Moderation Controlled)-
summary of CSE - 3/98" Scrubber Systems - summary of CSE - 3/98**
Hoods & Containment - summary of CSA - 9/96 Laboratories - summary of CSA - 9/96 e IFBA - summary of CSA - 3/96 e Storage Pad - NCS is based on DOE reports K-1920 and K-1663 e Rods - summary of CSA - 3/96 e Storagegpuhnmarygf CSE - 4/97 e FioM Assembly - sumq1 e hFe Cylinder Washing p ofof CSE siummary - 6/97 CSE - 12/95 N O S-3. The licensee shall mair(tgin and execute the response med6ures in ti.e Site Emergency Plan, dated April 30,1990, and reviglons ptembfr 30,1992; March 25, August 15, and September 30,1994; Benuary 9, . March aryc17,31, g and , i 17, ar@ October 23,1995; or as further by the licensee consis@nt with j J"0.32(i> 1 O H ,$1 \ /,f, 3 S-4. Deleted by Amendment 12, g-
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" These systems are to be coupled with the Columbia Plant Risk Management Program (RMP) to be done for the EPA.
NRC FORM 374A u.S. NUCLEAR REGULATORY Commission PAGE 4 of 8 PAGEs Ucansa Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.14 SAFEGUARDS CONDITIONS SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTING SG-1.1 The licensee shall follow pages i through xviii and Chaptors 1.0 through 9.0 of its " Fundamental Nuclear Material Control Plan for the Columbia Fuel Fabrication Facility," which has been partially revised as indicated by Revision 28 (dated December 18,1997). Any further revisions to this Plan shall be made only in accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34.
SG-1.2 Operations involving special nuclear material which are not referenced in the Plan identified in Condition SG-1.1 shall not.be initialed until an appropriate safeguards plan has been approved by the Nuclear VRegulato( d8niinission'." U($
SG-1.3 In lieu of the requitarnents contained in 10 CFR 74)1 DOE /NRC-742 and 7420, the licensee may puteruse com,3(a)(1) generated and (a)(2) forms provided all to use t information regged b9dtje latest printed inyptions'for completing the particular form is included. h -
O n :d n 3 c3y-:. <
Q, J o SG-1.4 in lieu of the requirement [qo(ntainddirLOJR'70,54 >74.15 to use the DOEa/NRC Form-741, the licensee ntBy use pufef gnrat65formspro ed all information required by the latest printed instructgs f6r pidy 7 14 Narticulaffor included.
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SG-1.5 Deleted Per Ame(idjneb< A % p%g,l nt now ugustj996Qpmmitp$
contained in licensee's 8O Fundamental Nucib(p Material Control Plan.
O SG-1.6 Notwithstanding the requi tapf ty $lMC Plan identified in License Condition SG-1,1, the licensee may use (1) a single s aridart 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 statist;cally 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 036) are satisfied.
SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear l' Material Control Pian 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 l Condition S-4; provided the conditions and commitments contained in the licensee's '
November 30,1993, letter (identification # NRC-93-036) are satisfied.
l l
NRc FORM 374A u.S. NUCLEAR PEGULAToRY COMMISSION PAGE 5 of 8 PAGEs License Number SNM-1107 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.14 b
} 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 (fo!!owing 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.
3 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 eacg5 jtem i in a batch of items has an assigned value equal to or less than 50 grams U-235;- p n gj, v u (ii) no more than d orfaD(Ifect when each item withh a batch of items has an less than 500 graml U-235, but one cr more ilegs'has an assigned value in excess of 50 grams U-235; a6d > ,. '/.
(iii) zero defe hen an wi b fitems ntains 500 or more grams U-235.
SG- 1.11 Notwithstandihthefpt pa'regp q pec}ior);73 of !! e Plan ident:fied by Condition SG-1.1, the licensee shall condu;ct sht rmdver corppari s on all SNM materials received (regardless of 69therbooke,d gtwjasispf fece' s or shipper's values), except for those 106 ev. 2) as being exempted from shipper-receiver compari gmaterials g identi f in Sectfon {qg ' VdyNy SECTION 2.0 - PHYSICAL PROTE TIQN OF SNM ORLO STRATEGIC SIGNIFICANCE n g g g T~
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 provision 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 shan 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 on the Facility" also includes other facility information submitted via Concise Notes in accordance with 10 CFR 75.11(c).
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NRC FORM 374A u.S. NUCLEAR REGULATORY CoMMisSloN PAGE 6 of 8 PAGES Ucense Number SNM-1107 MATERIALS LICENSE D cket r Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.14 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 (DIO) 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 requi;ing 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 r Article 39(b) of the US/lAEA Safeguards Agreement.
that the facility has 2 been identigdgrglui The types of modificat[ons with respect to which information is required under 10 CFR 75.11, (to be submitted inM!vance), are those items st in Code 2.2, specifically:
T (a) "Any c{ tinge {n Age purpose of type.otfhci y" mer.ns:
Any viation bd\ ren / ,M the desen.be Activities i Iving special nuclear material and any cha to the, ' m enrich $nt and/or antities of U-235 currently authorized by Lice No?SNM2 07 'is describe
~
Paragraph 5 of the Design Information Que i'onndeljDlO)d a ober 1 CFR f5111 n 'ih any%"
d6viat on47 from98thegor as modified described in accordance w special nuclear materip(t:).;tncidhh NM)'pfoductWractK/Jtles' des d in paragraph 6 of the DIO dated October ig1985, or'as modifiedifn ac ance with 10 CFR 75.11(c).
(b) "Any change injpe Ipyout of thgac ty which affects safeguards implementation of the provisions of theTroiccoM 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 f rom, 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)
NRC FORM 374A u.s. NUCLEAR RE uLAToRY CoMZ:OsloN PAGE 7 of 8 PAGEs License Number l SNM-1107 MATERIALS LICENSE 'Docka'IRo'erence Number SUPPLEMENTARY SHEET 70-1151 Amendment No.14 (d) "Any change in the physical inventory procedures that would adversely affect the l inventory taking for the Agency's accounting purposes" means:
Any change to the description data contained in Pamgraph 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:
g p2 R EGy, Any recalculdi,on of the " Relative Errors-Random and Systematic" as listed in ^
Attachmenf36.2 referenced in Parag 36 of the DlO dated October 14,1985, or as modifie randog,diri ac_cordance with 10 CFR 75. d{c), th and systematic errors bei affected by a factor of two or more.
g i T % '/ g (f) "De se in the us.iicy.of rpting measuring equipment if it dgnificantly decr ses the ~ nting system" means:
. racy'of.the, , erials a%a Any c'liang@elha@t m o resul Fr A j ; jge Westima systematic o
~f error being affected by factor 40 . [g '
g (g) "Any ch in the st istical p ur Ised to combine individual measurement error esti to obtairilirnits of er r shipper / receiver (S/R) differences and material una
$e fo M F) pans:
l 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 l ofthe DlO dated Ociober 14,1985, or as modified in accordance with 10 CFR 75.11(c).
SG-3.1.3 With respect to Transitional Faci!ity 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.
l The licensee shall use 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 appropriate changes to Table 1 of Attachment 34.8 to the DIO shall be submitted within three regular workdays of the telephone notification.
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NRC FORM 374A U.S. NUCLEAR RE0uLAToRY CoMCSloN PAGE 8 of 8 PAGEs Ucense Number SNM-1107
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MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1151 Amendment No.14 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 rEsOafofhyd uranium is inadvertently enriched above 0.711 percent through co nin'g1Ing with residual enriched uranium in process equipment, the resultant product be considered as being'pl uced through a biending operation and the material category 71ange shall be recorded upon@ pining mea material categ .tha l as occuned. gg ,4 SG-3.1.7 V!ith respect t s .a //
ransiti6n 2.2:
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y tCodep For Concise es _.
s r!! _d pp'erational programme, " anticipated operational programme" meansp..Anticip n p <>r ( 4cafinveptory
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