ML20198Q283
| ML20198Q283 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 12/30/1997 |
| From: | Schwink W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20198Q276 | List: |
| References | |
| NUDOCS 9801220389 | |
| Download: ML20198Q283 (8) | |
Text
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. Il; MATERIALS LICENSE g Ij I l
Pursuant to thq Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, y Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore g l
l' made by the licensee, a liceme is hereby issued authorizing the licensee to receive, acquire, possen. and transfer byprmluct, source, and special l I 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 I to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This liceme shall be deemed to contain the conditions y
specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to at pplicable rules, regulations and orders of the Nuclear g l
! Regulatory Commission now or hereafter m effect and to any conditions specified below. l l
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l Ucensee l lI ll 1. Westinghouse Electnc Corporeuon 3. Ucense number SNM-1107 I!
I Amendment 9 I I
I P.O. Box 355 A.[Exp9 tion date wh
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Nj 6. Byproduct, source, and/or y 7. Chemical and/or physical 8. Maximum amount that licensee 1
special nuclear material form mcy possess at any one time i !
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I 0.$5 kg Ij A. U-235 A. JAny A. i B. U-235 B. s Any, except - 8. 75,000 kgs i ll ..
d li ' metal, enriched l to not more Ili ,. than 5.0 w/o
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gl l C. U 233 , , ,
C, 'Any- - . C. i D. Pu-238, J< D. Sealed sources D. 1,5 grams .g l-Ij '
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Authorized place of useO The licensee's existing ficilities at Columtna, South Carolina.
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g g! 10. This license shall be doomed to contain two sectsons Safety Conditions and Safeguards Conditions, g i These sections are part of the license and the licensee is subject to compliance with all listed conditions I I . In each section.
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1 I I l l FOR THE NUCLEAR REGULATORY COMMISSION g I
i i I Date: /2/b 7 bkk By W "- S. SCAM Actino Chief h
l g l Division of Fuel Cycle Safety )i
! I and Safeguards F l Washengton, DC 20555 I j l l l I I I I I I I I I I l i I l 1 I
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,8UPPLEMENTARY SHEET 1151 i I I I SAFETY CONDITIONS g g
I i SAFETY CONDITIONS g l l .
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1 S1 Authorized use. For use in accordance with statements, representations, and conditions in the u i license application dated April 30,1995, and supplements dated May 11 and 18, August 4 and g i 25, September 25,1995; hly 14 and 25, August 11, November 17, and Decembw 17,1997. l l
l l I . S 2. The Crihcahty Safety Evaluations (CSEs) and Crihcahty Safety Analysis (CSAs) will define the g; I cnticality safety bases utilized throughout the plant and will be completed as described in g" l Sedions 6.4.1 and 6.4.2 of the hoense apphcation for each step of the process. A submittal to g i the NRC wiH be made by Westinghouse whiehydd information whidi the staff will review g I against the commitments listed in*Soction s.t.5: incense apphcahon These submittals wiu q
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( not be specific commetrnents, liut are intended as a. stration of the adequacy of the bases q,
, I of safety itemized in Seehon' 6.2.3. The contents listed iri Section 6.4.2 of the license appbcabon g
- I are commitments. The demonstration will show the logic used by the Columbia Fuel Fabrication g 1 Facility (CFFF) in developing the criticality safety bases, it is understood that this demonstration g 4
may change over time. ~The submittal will consist of a summary of the CSE or CSA as annotated g i below for each'aystem (which shan include fault trees for those systems for which a CSE will be g done). The adequacy of the' commitments in Section 6.2.3 of the license apphcstion will be g
- i i evaluated and a reply in the form of a letter report will be generated and sent from the staff to u Westinghouse. The submittal by the CFFF will be provided according to the following schedule
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I e UN tanks - summary of CSE -10/95 ,
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- URRS Dissolver - summary of CSE - 10/95 -- R g 4
l e Solvent Extraction (summary of CSE - TBD* j g*
e URRS Scrap PE-: ~ ' ,g: "
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l e Low-Level Waste Pmcessing System "- summary of CSA - 9/96 J g' l Mop Watysystem Equipment - summary of CSA - 9/96 y g i incineratorySystem - summary of CSE 9/96 ,
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Ash Recovery System - summary of CSE - 9/961 g Liquid Honing System - summary of CSE - 9/96 s g l
, 1 Ultrasonic Cleaning System - summary of CSE - 9/96 y g l Shredder System ' summary of CSE - 9/96 ,
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- i. I e URRS Waste Treatment - summary of CSA - 11/95 g
i e IDR Conversion - summary of CSE - Prior to Restart g I e- ADU Conversion - summary of CSE- 4/96 g i e ADU Pelletag - summary of CSE - 6/96 g i e Powder Blending - summary of CSE - 1/96 g 1
i e Miscellaneous: g l Ventilation Systems (Geometry Controlled) - g l - summary of CSE - 3/98" g i VentNetion Systems (Moderation Controlled) - g l summary of CSE - 3/98" g i Scrubber Systems - summary of CSE - 12/97" g i Hoods & Containment - summary of CSA - 9/96 g4 Laboratories - summary of CSA- 9/96 g i
i e IFBA - summary of CSA - 3/96 g e Storage Pad - NCS is based on DOE reports K-1920 and K-1663 l
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SNM-1107 Amendment 9 g
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SUPPLEMENTARY SHEET q l SAFETY CONDITIONS l
b e Rods - summary of CSA- 3/96 g I e Storage - summary of CSE - 4/97 g y e Final Assembly summary of CSE - 6/97 g I
- UFe Cylinder Washing - summary of CSE - 12/95 g N N
- The CFFF has performed a CSA upgrade and does not have a specrtic date forschedule of this CSE at p k
R this time. l 4
" These systems are to be coupled with the Columbia Plant Risk Management Program (RMP) to be done R
> for the EPA 5 I E b S-3 The licensee shall maintain and execute then~ sponse measures in the Site Emergency Plan, dated N I April 30,1990, and revisions dated March'31, and'9ehkMntiet 30,1992; March 25, August 15, and 4 b September 30,1994; January 9,-Februcry 17, August 17, and October 23,1995; or as further revised by 5 I the licensee consistent with 10 CFR 70.32(l). 1/ s E
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'. N N S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the extemal surfaces of packaged -E N radioactive material receipts for radioactive contamination, the licensee is exempted from such E N requirement relative to flatbed traile_r shipments of fuel assemblies received from the General Electric E N Company for interim storage purposes only, provided the constraints, conditions and controls committed E N to in the licensee's letter, dated November 30,1993, (identification # NRC 93-036), are satisfied; and ll N further provided that the total number of such fuel assemblies stored at the licensee's site at any given W N time does not exceed 250. E N E N u El y c .,
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MATERIALS LICENSE
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l onckei or nevennee sumter l SUPPLEMENTARY SHEET 70-1151
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E l SAFEGUARDS CONDITIONS t
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, I h l SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING l I l SG-1.1 The licensee shall follow pages i through xvil and Chapters 1.0 through 9.0 of its " Fundamental F l Nuclear Material Control Plan for the Columbia Fuel Fabncahon Facildy," with all pages identified I l as Rev6sion 27 (dated May 23,1997). Any further revisions to this Plan shall be made only in [ '
l accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34. [--
4 l SG 1.2 - Operations involving special nuclear potene[ are not referenced in the Plan identitled in Condition SG 1,1 shall not bos initisted 6ntitan safeguards plan has been approved l '
g by the Nuclear Regulatory Commission. //
l <b" 4,
, p SG-1.3 in lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use the Forms l DOE /NRC-742 and 742C, the licensee may use computer generated forms provided all
. g information required by the latest printed instructions for completing the particular form is g included. 6 s i r,
-x 3 l p' SG-1.4 in lieu of the requirements' contained in CFR 70.54 and 74.15 to use the DOE /NRC Form-741, l g the licensee may use computer generated forms provided all ink,6C Mrequired by the latest g printed instructions for completing the particular form is included. O '"'
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- W SG-1.5 Deleted Per Ar.nondment 3, August 1996 Commitment now contained in licensee's Fundamental
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Nuclear Matonal Control Plan.
y p yh ; e' l SG-1.6 Notwithstanding the requwements of the FNMC Plan identified in License Condition SG-1,1, the -
p licensee may use (1) a single standerd for measurement control (includeg daily control limi' g monitoting and bias corrections) for any linear-response tube or rod scales, in any initially g demonstrated to'be knear over its range of use within the discnminshon of the scale by g calculating a bias at four levels across the range of use and demonstrating that the four results y are not statistically different, and (2) that the continued kneanty of response of the scales is y venfled by monthly calibration against at least four traceable' standards covering the range of r I
g use. ,
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L g SG-1.7 Notwithstandmg the requirements contamed in Sections 5.2.2 and 5.2.3 of the licensee's g Fundamental Nuclear Matenal Control Plan, the licensee is exempted from physical inventory f requirements relative to the material identified in Condition S-4; provided the conditions and k p
p tommitments contained in the licensee's November 30,1993, letter (identification # NRC 93-036) E E
g are satisfied.
g I g SG-1.8 Notwithstanding the requwement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear g Material Control Plan to unpackage and perform an item count upon receipt of special nucisar matenal, the licensee is exempted from such requirement relative to the material identified in F p
F g Condition S-4; provided the conditions and commitments contamed in the licensee's l- p November 30,1993, letter (identification # NRC-93-036) are satisfied.
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g SNM-1107 Amendment 9 !q g MATERIAI,S LICENSE Docket or Reference Number g l SUPPLEMENTARY SHEET 70-1151 g I N g SAFEGUARDS CONDITIONS g N
N p' SG-1.9 Notwithstanding the requirement of Section ll.A.7, block U, of NUREG/BR-0006, which is y p incorporated via 10 CFR 74.15, to complete receiver's measurements of sxap receipts (following g g recovery processing) within 60 days of receipt, the licensee shall not be subject to any time limit g a
relative to recovering and measuring received UF, heels when the block U action code (of g g DODNRC Form 741) is used to book such receipts. g N N GG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, " allowed number" g N
within the phrase "a# owed number of defects'is hereby specifed as being: y
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N N (i) up to two defects when each item within 6 batch of items has an assigned value equal to or g less than 50 grams U-235; y c: [. Eo,4,. a N (ii) no more than one defect when each item within a batch of items has an assigned value of g g less than 500 grams U-235, but one or more items has an assigned value in excess of 50 grams g U-235; and g
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7 N - . E g (iii) zero defect when any item within a batch of items contains 500 or more grams U-235. g i N! .
N g SG-1.11 Notwithstandirsg the first paragraph of Section 7.1 of the Plan identified by Condition SG-1.1, the y l y W licensee shall conduct shipper-receiver comparisons on all SNM materials received (regardless p of whether booked on the basis of receiver's or shipper's values), except for those materials g
! ( identified in Section 7.1 of NUREG-1065 (Rev. 2) as being exempted from shipper-receiver g
g j g comparisons.
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E p SECTION 2.0 - PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE g y w. , a g SG 2.1 The licensee shall follow the " Site Physical Secunty Plan - Westinghouse Electric Corporation, g g Columbia, S.C.; dated March 1980; Revision 10.0 dated October 1,11987; the " Revision Record" g g contained in the, approved Physical Secunty Plan (current to Ociober 1,1994); and as may be g g revised in accordance with the provisions of 10 CFR 70.32(e). g N N g SECTION 3.0 - INTERNATIONAL SAFEGUARDS g l
N 't g SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility Attachment No. SA dated g g August 31,1988, to the US/lAEA Safeguards Agreement. Such Transitional Facility Attachment y g shall be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7. g
- N N i g SG-3.1.1 With respect to Transitional Facility Attcchment Code 2: g W W g The reference design information is that dated by the licensee on October 14,1985. "Information g g on the Facility" also includes other facility information submitted via Concise Notes in accordance y g with 10 CFR 75.11(c). g N E N n N. E W
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FOfue374A U.s. NUCLEAR REoOLAToRY CCWassKW MGE b OF 0 GES g Lkenne !dumhet g l :.-- SNM-1107 Amendment 9 y l
MATERIALS LICENSE y l gegejerence Numter l SUPPt.EMENTARY SHEET l l SAFEGUARDS CONDITIONS l
l 8 G 3.1.2 With respect to Transthonal Facility Attachment Code 2.2: I l I ,
( Substantive changes to the information provxiod in the Columbia Plant Design informahon g l
I Questionnaire (DlQ) means those changes requiring amendment of the Transitional Facility ,
1 Attachmerd. Such changes shall be provided by letter to the NRC Office of Nucisar Material N I Safety and Safeguards at least 70-days in advance of implementation. W I l 1 1 - Non-substantive changes to the information in the DlQ means those changes not requiring l I amendment of the Transitional Facility Attachment. Such changes shall be provided by Concise W '
I Note (From DOFJNRC 740M) within 30 days of receivmg notdication from the NRC that the - l I facility has been identified under Article 39(b) of the US/lAEA Safeguards Agreement l The types of modifications with're to b is required under 10 CFR 75.11, (to I be submitted in advance), are those items stated in Code 2.2, specificalty: l I
I (a) "Any change in'the purpose of type of facility" means:
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l I Any deviation from the described activities involving special nuclear material and any change to l I the maximum cnrichmerd and/or quantities of U-235 currently authorized by License No. SNM- l N 1107, and/or as desenbod in Paragraph 5 of the Design Information Questionnaire (DlQ) dated N N October 14,1985, or as modified in accordance with 10 CFR 75.11(c). included also is any 8
, N deviation from the described special nuclear material (SNM) production activities described in l N paragraph 6 of the D'Q dated October 14,1985, or as modified in accordance with 10 CFR N
' N N 75.11(c).
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d N (b) "Any changes in the layout of the facility which affects safeguards implementation of the '
i N .
provisions of the, Protocol" means: y N N -
j 4 g N Any changeln the existing facility ar%#or site layout or new addihon affecting any activity l N involving SNM as described in Paragraphs 10 and 11 (per the referenced attachments of l N the DlQ dated October 14,1985, or as modified in accordance 'with 10 CFR 75.11(c). g included also is any modification to, or deviation from, the data provided in Paragraphs 13 g L I N and 14 (per the referenced attachments) of the OlQ dated October 14,1985, or as q 3
I modified in accordance with 10 CFR 75.11(c). y 5 i N J Jg ? I
- N (c) "Any change that makes the selected Key Measurement Points (KMPs) (as described in l N Code 3.1.2) inadequate for the Agency's accounhng purpose" means
- 5 N g I Any change to the KMPs as described in Code 3.1.2 of the Westinghouse-Columbia l N Transitional Facdoty Attachment to the US/lAEA Safegual. is Agreement, or as modified in l N accordance with 10 CFR 75,11(c), that results in any KMP alteration affectog the purpose l N of KMPs as stipulated by 10 CFR 75.4(m) W N N N (d) "Any change in the physical inventory procedures that would adversely affect the inventory l N taking for the Agencys accounting purposes" means: 5 .
N q r N Any change to the description data contained in Paragraph 34 (per the referenced l
. I attachments) of the OlQ dated October 14,1985, or as mo4 fled in accordance with 10 CFR q N 75.11(c), that would not permit the Agency to conclude an SNM material balance for the d
' N Westinghouse-Columbia facility. 5 I l i I N I I IKumana mm m mm m m m m m m m m , m m m m m m m m m , m m m m m m m m m m m m m m m mM
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FORM 374A . U.S. NUCLEAR REOULAToRY Cotham PAGE 7 or 8 PAGES- ij
.- Licerne Number g l
. l SNM-1107 Amendment 9 i
! I MATERIALS LICENSE thirt or Reference Number i l , $UPPt.EMENTAFW SHEET 70-1151 g 1 l l
SAFEGUARDS CONDITIONS ,
I (e) " Introduction of a signmcenpy less accurate ana'ytical method for sooounting purposes" g I means: g I g\
l Any recalculation of the " Relative Enors-Random and Systematic" as listed in Attachment g.
I 38.2 referenced in Paragraph 36 of the DlQ dated October 14,1985, or as modilled in gl l accordance with 10 CFR 75.11(c), that results in the estimates of the random and - gi l r,:::Tf: errors being affected by a factor of two or more, u, 11 g-l (f) "Docrease in the frequency of calibrating measuring equipment if it significantly decreases g I the accuracy of the materials accounting system" means: g i u i Any change that results in the estimates of the 3,2:If: error being affected by a factor of g p p !W M t G- [1; i two or more. g i a
( (g) "Any change in the statistical procedures used to combirie individual measurement error g
, i estimates to obtain limits of error for shipper / receiver (S/R,) differences and material g unaccounted for (MUF)" means: , g l 3
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'A g) i e Any deviabon from (or moddication of) the equations and/or ch=hons g I
outlined in Attachments 37.1, 37.2, and 37.3 referenced in Paragraph 37 of g I the DlQ dated October 14,1985, or as moddeed in accordance with 10 CFR g g
l 75.11(c).
- I .
- l g'
l SG-3.1.3 With respect to Transitional Facility Attachment Code 3,1.2:
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<, q q KMP* - This is a KMPMwhich all shipper receiver ddleren:es (SRDs).must be recorded and g I reported even if numerically zero. SRDs are computed and reported by the Nuclear Materials y
- I " 7,ep,T, erd and Safeguards System upon receipt of the receiver's measurement results, g j 1 @ l7 .
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l SG-3.1.4 With respect to Transitional Facility Attachment Code 4: -
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The licensee shall use the material compoedion codr.s documerYted in the DlO dated October 14, g l
l 1985, and as modified b Concise Notes. Further, notwithstanding any other requirements for g
, I advance notWication and/or reporting, the licor. sos may add or delete ce.Tvesition codes for y I nuclear material routmely processed and on inventory'st CFFF immediately upon telephone g I notdication to the Office of Nuclear Material Sids4y and Safeguards Follow-up documentation, in g l the form of a Concise Note accompensed by appropnate changes to Table 1 of Attachment 34.8 - g, I to the DlQ shall be submitted w6 thin three regular workdays of the telephone notecahon. I I u
< q SG-3.t5 With respect to Transitional Facility Attachment Code 4.1: g
' g f
l Measured discards should be reported as an SN (Shipment to non-safogaards facility) when g, I shipped off-site to an authorized bunal ground (The IAEA system will not process measured g I discards as loss / disposal (LDs) when they are shipped off-site). g p I I l l c I t
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SAFEGUARDS CONDITIONS g g ~BG-3.1.5 WilhTeTMI5Tritis~iti668TT&51itTAttRhlMbhTC606 5.1.i: g N E y For inventory changes, time of recording, "upon" means: No later than the next regular workday g y (Monday through Friday). g W E gi For those occasions where natural or depleted uranium is inadvertently enriched above 0.711 y p
I percent through commingling with residual enriched uranium in process equipment, the resultant g I product shall be considered as being produced through a blending operation and the material y category change shall be recorded upon obtaining measurement confirmation that a material g category change has occurred. g E E SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2: g W
g < Pt M. M h (.) / . g gi For Concise Notes describing the anticipated operational programme, " anticipated operational y y programme" means: Anticipated physicalinventory schedule / , g W. E E
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