ML20212A137

Amend 6 to License SNM-1107 for Westinghouse Electric Corp

ML20212A137
Person / Time
Site:	Westinghouse
Issue date:	10/16/1997
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20212A128	List: ML20212A124 ML20212A137 ML20212A157
References
NUDOCS 9710230168
Download: ML20212A137 (8)

Text

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, g NRC FORM 374 U.S. NUCLE AR REIULATORY COMMISSION

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' g' hlNI'ERI A1.S I.lCENSE n %yl gl g i ederat ReFulations, Chapter I, l' arts 30.11,32,33,34,33,36,39,40, and 70, and in teltance on l b) the licensee, a hcenw in hereby luued authorising the licensee to reccis e, a(quire, pouco, and transfer by prmiuct, sourte, and special nuclear ii Nl runterial designated below; to use auth material for the purposeth) and at the place (si designated below; to deliger or transfer such material t i

% spe(ified personin > suthoriteti Section 110 of the to rescine Atomic it in I netF) Act anordance of 1934, with at amended, and lithe regulaimns subject ofrulen, to all applicable theregulations, apphcable Part(s) and ortlers of the1his beenw sha

% Nuclear Regulatory Cornminion ruiu or hereaf tet in clicci and to any (onditions specified below.

I A>E Licensee V 4i.

Westinghouse Electric Corporation 3. ucenw Nuniber glg g jg7

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P.O. Box 355 P 2-Pittsburgh, Pennsylv:lia 15230-0355 mp;,,, ion 9,,, if November 30, 2005 i;l

5. DocLet or l gll Reference Na 70 1151 i;i!l 4

gI 6. liyproduu, Source, and/or 7, Chernical and/or t'hysical 8. Maumum Amount timt Licenwe $l l Special Nuclear Material 1 orm May Poweu at Any One Time g V y Under This License ip i

o A. U-?35 A. Any A. 0.35 kg &

• $ j B. U-235 B. Any, except B. 75,000 kgs &

Nj metal, enriched f si to not more &

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C. U 233 than 5.0 w/o s

% C. Any C. 5 grams $

D. Pu 238, D. Sealed sources D. 1.5 grams &

s% i Pu-239 F

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

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% 10. This license shall be deemed to contain two sections: Safety Conditions and rl

% Safeguards Conditions. These sections are part of the license and the licensee is &

% subject to compliance with all listed conditions in each section. yj

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FOR THE NUCLEAR REGULATORY COMMISSION g ,

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AYfWk Date: '

By: Michael F. Weber h

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= = = uuuuuusr = = = wouuuuuuont.uw= = = uuustw, RE!ULAfoM PAGE _2 OF 8 PAGES g kenw Numtet g SNM-1107 Amendment 6 g MATERIALS LICENSE Luket w Refereme Numtet g

. SUPPLEMENTARY SHEET 70-1151 g u,

SAFETY CONDITIONS gl t

W W N N l SAFETY CONDITIONS l

N N N U S1 Authorized use: For use in accordance with statements, representations, and N

conditions in the license application dated April 30, 1995, and supplements dated May 11 and 18, August 4 and 25, September 25, 1995; and July 25, 1997. y N S 2. TheCriticalitySafetyEvaluations(CSEs)andCriticalitySafetyAnalysis N (CSAs) will define the criticality: safety bases utilized throughout the plant N and will be completed as described in Sections 6.4.1 and 6.4.2 of the license application for each step of the process. AsubmitttitotheNRCwillbemade! -

by Westinghouse which will include information which the staff will review N against the commitments listed in Section 6.2.3 of the license application. E These submittals will not be specific commitments, but are intended as a N' demonstration of the adequacy of the bases of safety itemized in Section N l 6.2.3. The contents listed in Section 6.4.2 of the license a) plication are E N commitments. The demonstration will show the logic used by tie Columbia Fuel E

1. Fabrication Facility (CFFF) in developing the criticality safety bases. It is .h N understood that this demonstration may chnge over time. The submittal will N 8{ consist of a summary of the CSE or CSA as annotated below for each system W Bj (which shall include fault trees for those systems for which a CSE will be N 4; done). The adequacy of the commitments in Section 6.2.3 of the license W W; application will be evaluated and a reply in the form of a letter report will 8 W! be generated and sent from the staff to Westinghouse. The submittal by the N N CFFF will be provided according to the following schedule: W E

. UN tanks - summary of CSE -10/95 m

. URRS Dissolver - summary of CSE - 10/95 E

. Solvent Extraction summiary of CSE - TBD*

. URRS Scrap Processing:

W . Low-level Waste Processing System - summary of CSA - 9/96 4 Mop Water System Equipment - summary of CSA - 9/96 m Incinerator System - summary of CSE - 9/96 jE I

Ash Recovery System - sunmary of CSE - 9/96 W Wl W Liquid Honing System - summary of CSE - 9/96 h 5 Ultrasonic Cleaning System - summary of CSE - 9/96 ;W W Shredder System - suneary of CSE - 9/96 N N . URRS Waste Treatment - summary of CSA - 11/95 E a . IDR Conversion - summary of CSE - Prior to Restart h p . ADU Conversion - sunnary of CSE - 4/96 W m; .

ADO Pelleting - sunmary of CSE - 6/96 N.

. Powder Blending - sunmary of CSE - 1/96 N  ;

P.iscellaneous: W Ventilation Systems (Geometry Controlled) - 5 summary of CSE - 12/97** n W

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SUPPLEMENTARY SHEET 70-1151 g SAFETY CONDITIONS l

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s VentilationSystems(ModerationControlled)- U N I susunary of CSE - 12/97**

N Scrubber Systems - susunary of CSE 12/97**

I N Hoods & Containment - susunary of CSA - 9/96 I Laboratories - sununary of CSA - 9/96 I

. IFBA - sununary of CSA - 3/96 8

. Storage Pad - NCS is based on DOE reports K-1920 and K-1663 8 N . Rods - summary of CSA - 3/96 N N . Storage - sununary of CSE - 4/97 . l E

N . Final Assembly - summary of CSE~- 6/97 4

. UF, Cylinder Washing - summary of CSE - 12/95, l

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• The CFFF has performed a CSA upgrade and does not have a specific date for schedule n N of this CSE at this time.' 4 W N R ** 7hese systems are to be coupled with the Columbia Plant Risk Management Program N R

(RMP)tobedonefortheEPA. N N N W S-3 The licensee shall maintain and execute the response measures in the Site Emergency 4 N Plan, dated April 30, 1990, and revisions dated March 31. and September 30, 1992; N N March 25 August 15, and September 30, 1994; January 9, February 17, August 17, and N N October 23, 19951 or as further revised by the licensee consistent with N N 10CFR70.32(1). N R N N S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external N R surfaces of packaged radioactive material receipts for radioactive contamination, N the licensee is exempted from such requirement relative to flatbed trailer shipments N of fuel assemblies received from the General Electric Company for interim storage N purposes only, provided the constraints, conditions and controls committed to in the lN licensee's letter, dated November 30, 1993, (identification # NRC 93 036), are a satisfied; and further provided that the total number of such fuel assemblies stored N at the licensee's site at any given time does not exceed 250. N N N i > N N N I

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SUPPLEMENTARY SHEET 70-1151 W g SAFEGUARDS CONDITIONS lI SAFEGUARDS CONDITIONS l

N N SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTlhG l

Ni SG 1.1 The licensee shall follow pages i through xvit and Chapters 1.0 through 9.0 of -8 N N its " Fundamental Nuclear Material Control Plan for the Columbia Fuel N

Fabrication Facility," with all pages identified as Revision 27 (dated I N

N May23,1997). Any further revisions to this Plan shall be made only in N accordancewith,andpursuantto,either10CFR70.32(c)or70.34.

l l Bj SG 1.2 Operations involving special nuclear material which are not rr Terenced in the N N

i Plan identified in Condition SG-1.1 shall not be initiated until an N Nl appropriate safeguards plan has been approved by the Nuclear Regulatory N N; Commission. N l Ri 4 N in lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use Nl j SG 1.3 the Forms DOE /NRC-742 and 742C, the licensee may use computer generated forms .

Ej provided all information required by the latest printed instructions for N

i completing the particular form is included.

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N SG-1.4 In lieu of the requirements contained in CFR 70.54 and 74.15 to use the N Nj 00E/NRC form-741, the licensee may use computer generated forms provided all N N{ information required by the latest printed instructions for completing the W N

i particular form is included. N N N N SG-1.5 Deleted Per Amendment 3, August 1996 Cosmiitment now contained in licensee's N N Fundamental Nuclear Material Control Plan. N N N N SG-1.6 Notwithstanding the requirements of the FNMC Plan identified in License N N Condition SG 1.1, the licensee may use (1) a single standard for measurement N control (includingdailycontrollimitmonitoringandbiascorrections)for N 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 Nl N calculating a bias at four levels across the range of use and demonstrating la j

N I

that the four results are not statistically different, and (2) that the W N continued linearity of response of the scales is verified by monthly I N

I calibration against at least four traceable standards covering the range of W use. N N

N SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the W licensee'sFundamentalNuclearMaterialControlPlan,thelicenseeisexempt p!

N from physical inventory requirements relative to the material identified in 'N N Condition S 4; provided the conditions and commitments contained in the W N licensee's November 30, 1993, letter (identification # NRC-93-036) are N! satisfied.

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SNM-1107 Amendment 6 Ig g g gI MATERIALS LICENSE thaci er Refceriwe Numter u g

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. SUPPLEMENTARY SHEET 70-1151 g SAFEGUARDS CONDITIONS Nl N E

N l SG-1.8 NotwithstandingtherequirementofSection6.2.1(a).5ofthelicensee's l i 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.

SG-1.9 Notwithstanding the requirement of Section II.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 N licensee shall not be subject to any time limit relative to recovering and E

measuring rece%ed UF, heels when the block V action code (of DOE /NRC Form 741) is used to book such receipts. g R SG-1.10 With re', pact to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, E Nf "allowt.d number" within the phrase " allowed number of defects" is hereby R N; specified as being: 8 W W i

, (i) up to two defects w'..en each item within a batch of items has an assigned lE Nl E value equal to or less than 50 grams U-235; 'E

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b; (ii) no more than one defect when each item within a batch of items has an E R assigned value of less than 500 grams U-235, but one or more items has an 4 assigned value in excess of 50 grams U 235; and W W

(iii) zero defect when any item within a batch of items contains 500 or more E grams U-235. f .

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SG-1,11 Notwithstanding the first paragraph of Section 7.1 of the Plan identified by jW Condition SG-1.1, the licensee shall conduct shipper-receiver comparisons on iM all SNN materials received (regardless of whether booked on the basis of receiver's or sF'.iper's values), except for those materials identified in lE N;j Section 7.1 of ..AEG-1065 (Rev. 2) as being exempted from shipper-receiver g comparisons.

Nli p SECTION 2.0 -- PHYSl{AL PROTECTION OF.JNM OF LOW STRATEGIC SIGNIFIC MCE

p. ,t SG-2.1 The licensee shall follow the " Site Pnysical Security Plan - Westinghouse !E Electric Corporation, Columbia, S.C.," dated March 1980; Revision 10.0 dated !W October 1, 1987; the " Revision Record" contained 'n the approved Physical u Security Plan (current to October 1, 1994); and as may be revised in g gj accordance with the provisions of 10 CFR 70.32(e). t Ni E I

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, y SNM-1107 Amendment 6 l l MATERIALS LICENSE IMet nt Reference Numter j g SUPPLEMENTARY SHEET 70-1151 l SAFEGUARDS CONDITIONS g I SECTION 3.0 -- INTERNATIONAL SAFEGUARDS  !

I I I SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility E I: Attachment No. 5A dated August 31, 1988, to the US/IAEA Safeguards Agreement. I N Such Transitional Facility Attachment shall be interpreted in accordance with i N Conditions SG 3.1.1 through SG-3.1.7. I N I 4 SG-3.1.1 With respect to Transitional Facility Attachment Code 2: H M t B The reference design information is that dated by the licensee on October 14, E

$ 1985. "Information on the Facility" also includes other facility information E N submitted via C9ncise Notes ,in:accordance-with 10 CFR 75.ll(c). E M . G Ai t 4

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p SG-3.1.2 With respect to Transitional Facility Attachannt Code 2.2: g g s s; aj . g N Substantive changes)to the information )rovided in' tfie Columbia Plant Design (-

M Information Questionnaire (DIQ) means tiose changes requiring amendment of the g p Transitional Facility Attachment. Such changes shall be provided by letter to g u the NRC Office.of Nuclear Material Safety and Safeguards at least 70 days in g i advance of imp kmentation.- ,~ ~"

g p !s g-p Non-substantive changes to the information.infthe DlQ means those changes not t

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( requiring amendment of the Transitional Facility Attachment) Such changes g g shall be provided by Concise Note-(from. DOE /NRC 740M) within 30 days of g g receiving notification from the NRC that the facility hastbeen identified g.

p underArticle39(b):of.theUS/IAEASafeguardsAgreement.] g f

g Thetypesof$modificationswithirespecttowhichinformationisrequiredunder 10 CFR 75.11,;(to be submitted'in advance), are those items stated in Code f g

y 2.2, specifically: -

g (a) "Any change in the purpose of type of facility" mans:

l h Any deviation from the described activities involving special nuclear material I g{ and any change to the maximum enrichment and/or quantities of U 235 currently I authorized by License No. SNM-1107,'and/or as described in Paragraph 5 of the I ljl Design Information Questionnaire (DlQ) dated October 14, 1985, or as modified I y in accordance with 10 CFR 75.ll(c). Included also is any deviation from the I g described special nuclear material (SNM) production activities described in I. -

paragraph 6 of the DlQ dated October 14, 1985, or as modified in accordance I h with 10 CFR 75.11(c).

N (b) "Any changes in the layout of the facility which affects safeguards i implementation of the provisions of the Protocol" mans: j E

Any change in the existing facility and/or site layout' or new addition Ni 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 W modified in accordance with 10 CFR 75.11(c). Included also is any E W

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( modification to, or deviation from, the data provided in Paragraphs 13 and (

N 14 (per the referenced attachments) of the DIQ dated October 14, 1985, or (

as modified in accordance with 10 CFR 75.11(c). g

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N E N "Any change that makes the selected Key Measurement Points (KMPs) (as (c) described in Code 3.1.2) inadequate for the Agency's accounting purpose"

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N E N Any change to the KMPs as described in, Code 3.1.2 of the Westinghouse- g W Columbia Transitional-Facility Attachmeqt to the US/IAEA Safeguards y p Agreement,oras,modifiedinaccordancewith10CFR75.11(c),thatresults g y in any KMP alteration affecting the purpose of/KMPs as stipulated by g g 10 CfR 75.4(m)f *( g lg (d)"Anychanheinthephysicalinventoryproceduresthatwouldadversely affect th inventory taking for the Agency's accounting purposes" means: fg 4

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Any change to the ' description data contained in Paragraph 34 (per the ,

a referenced attachments) of the DIQ dated October 14, 1985, or as modified ,

j 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.

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E (e)"Introductionofasignificantly3ess'accurateanalytihalmethodfor1 g

accounting purposes" meanst- ,

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E N Anyrecalculationofthe"Relativ'eEfrors-Randomand: Systematic"aslisted E N in Attachment 36.2 referenced-in Paragraph 36 of the DIQ dated October 14, N 1985, or as modified in accordance with 10 CFR 75~.ll(c that results in N N

i the estimates of the random and systematic errors being),affected by a E E

factor of two or more.

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N (f) " Decrease in the frequency of calibrating measuring equipment if it E Ri significantly decreases the accuracy of the materials accounting system" E

means:

N Any change that results in the estimates of the systematic error being E affected by a factor of two or more. E R (g) "Any change in the statistical procedures used to combine individual E N measurement error estimates to obtain limits of error for shipper / receiver E E

4 (S/R) differences and material unaccounted for (MUF)" means: E N

Any deviation from (or modification of) the equations and/or calculations E outlined in Attachments 37.1, 37.2, and 37.3 referenced in Paragraph 37 of E Nl n

b; the DIQ dated October 14, 1985, or as modified in accordance with 10 CFR E E<

$j 75.ll(c). E n;

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SAFE 0VARDS CONDITIONS h 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 i I recorded and reported even if numerically zero. SRDs are computed and "I I reported by the Nuclear Materials Management and Safeguards System upon '

' receipt of the receiver's measurement results. E SG 3.1.4 With respect to Transitional Facility Attachment Code 4: F l

4 The licensee shall use the material composition codes documented in the DIQ 8 8 dated October 14, 1985, and as modified by Concise Notes. Further, "

8 notwithstanding any other requirements for advance notification and/or I E reporting, the licensee may add or delett esaposition codes for nuclear r I material routinely processed and on inventory at CFFF immediately upon 3 3 telephone notification to the Office of Nuclear Material Safety and I Safeguards. Follow up documentation, in the form of a Concise Note 8 accompanied by appropriate changes to Table 1 of Attachment 34.8 to the OlQ f shall be submitted within three regular workdays of the telephone I notification. E s t i SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1: I a t I Measured discards should be reported as an SN (Shipment to non-safeguards I ,

I facility) when shipped off-site to an authorized burial ground. (TheIAEA E 1 system will_not process measured discards as loss / disposal (l.Ds) when they are E 1 shipped off site). t I t 1 SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1: r 1 r I For inventory changes, time of recording, "upon" means: No later than the F 1 next regular workday (Monday through Friday). E 1 E 1 For those occasions where natural or depleted uranium is inadvertently E 1 enriched above 0.711 percent through commingling with residual enriched t 1, uranium in process equipment, the resultant product shall be considered as E 1 being aroduced through a blending operatior, and the material category change r '

I shall )e recorded upon obtaining measurement confirmation that a material r a category change has occurred, t 1 t I SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2: r I r t for Concise Notes describing the anticipated operational )rogramme, t I l

" anticipated operational programme" means: Anticipated p1ysical inventory L I schedule. t i ;C -

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