ML20199C592

Amend 7 to License SNM-1107 for Westinghouse Electric Corp, Correcting Frequency of Emergency Exercises from Annual to Biennially to Be Consistent W/Emergency Plan

ML20199C592
Person / Time
Site:	Westinghouse
Issue date:	10/21/1997
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20199C585	List: ML20199C581 ML20199C592 ML20199C600
References
NUDOCS 9711200065
Download: ML20199C592 (8)

Text

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g Pursuant to the Atornic I nergy Act of 1954, as amended, the EnerFy Reorganitation Act of 1974 (pubhc Lawl 9 I

1 g i ederal Regulations, Chapter I, parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance em statements and representations heretof l i by the lit enwe, a licenw is hereby issued authoriring the licensee to receise, acquire, powest., and transfer by product, source, an gj material daignated below; to use such material for the purpowN and at the place (s) designated below; to deliser or transfer such material t N j"l

% specified persons authotiied in Sectmn to reteise IN3 of the Atomic 1:nergy Actitof in accordance 1954, as amended, and with the is subject to allreFulations of the appbcable applicable rules, reFulations, and orders of the fpa

$j Nuclear Regulatory Commiuion now or hereaf ter in effect and to any conditmns specified below. jel D

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'- Westinghouse Electric Corporation 3. Ucenw Numba SNM-1107 @9 i

@g Amendment 7 P.O. Box 355 {l

2. Pittsburgh, Pennsylvania 15230-0355 .

. 4. Ihpiration Date i '

NoyembSr_JQm2005_ I l p i 5. Dodel or Q Reference No. 70-1151 ;l 4

2 6 ilypin!uct, Source, and/or 7. Chemica' and/or Physical 8. Matimum Amount that 1,icenwe h O Special Nuclear Material Form May Powen at Any One Time W

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• i A. U-235 A. Any A. 0.35 kg Il

$S B. U 235 B. Any, except B. 75,000 kgs I  !

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$ to I.ot more i l

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C. U-233 C. Any C. 5 grams $

5, D. Pu-238 D. Sealed sources D. 1.5 grams @

$ Pu-239 bl 5

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% 9. Authorized place of use: The licensee's existing facilities at Columbia, South Carolina, {d iel 5l10.

9 This license shall be deemed to contain two sections: Safety Conditions and sl l g Safeguards Conditions. These sections are part of the license and the licensee is &

I subject to compliance with all listed conditions in each section. $. ,

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4 FOR THE NUCLEAR REGULATORY COMISSION 3 S $. ,

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3AFETY CONDITIONS n g.

.W SAFETY CONDITIONS l M

I S-1 Authorized use: For use in accordance with statements, representations, and E

conditions in the license application dated April 30, 1995, and supplements 8 dated May 11 and 18, August 4 and 25, September 25, 1995; July 25 and August 11, 1997 l N

5-2. The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis l N. (CSAs) will define the criticality safety bases utilized throughout the plant Nl N and will be completed as described in Sections 6.4.1 and 6.4.2 of the license 4 N application for each step of the process. A submittal to the NRC will be made l8 N

N, by Westinghouse which will include information which the staff will review Mj against the commitments listed in Section 6.2.3 of the license application. E Wj These submittals will not be specific comitments, but are intended as a E W demonstration of the adequacy of the bases of safety itemized in Section 4 Mj 4

6.2.3. The contents listed in Section C.4.2 of the license application are N comitments. The demonstration will show the logic used by the Columbia Fuel #

4; M Fabrication Facility (CFFF) in developing the criticality safety bases. It is N WI understood that this demonstration may change over time. The submittal will #l consist of a sumary of the CSE or CSA as-annotated below for each system '{

Rf M (which shall include fault-trees for those systems for which a CSE will be E '

f done). The adequacy of the comitments in Section 6.2.3 of the license N m application will be evaluated and a reply in tha form of a letter report will E M;

j be generated and sent from the staff to Westinghouse. The submittal by the E.

Hj CFFF will be provided according to the following schedule: ,

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UN tanks - summary of CSE -10/95 URRS Dissolver - sumary of CSE - 10/95 lkW j l i

l . Solvent Extraction - sumary of CSE - TBD* l l g! . URRS Scrap Processing: H g' . Low-Level Waste Processing System - sumary of CSA - 9/96 jn '

g)I g Hop Pater System Equipment - summary of CSA - 9/96 El Incinerator System - summary of CSE - 9/96 jE g!

g Ash Recovery System - sumary of CSE - 9/96 :E Liquid Honing System - sumary of CSE - 9/96 W  !

g(! Ultrasonic Cleaning System - sumary of CSE - 9/96 El g Shredder System - summary of CSE - 9/96 E URRS Waste Treatment - sumary of CSA - 11/95 I y .

g . IDR Ccaversion sumary of CSE - Prior to Restart (E l p . ADU Conversion - sumary of CSE - 4/96 .

l l . ADU Pelleting - summary of CSE - 6/96 p'

. Powder Blending - sumary of CSE - 1/96 lE j

ll n! . Miscellaneous: >W gl q Ventilation Systems (Geometry Controlled) - lj l

g sumary of CSE - 12/97**

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ia Ventilation Systems (Moderation Controlled) -

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!g Scrubber Systems - summary of CSE 12/97**

Hoods & Containment - sumary of CSA 9/96 (E Laboratories - summary of CSA - 9/96 i8 u

. IFBA - summary of CSA - 3/96 t

. Storage Pad - NCS is based on DOE reports K-1920 and K-1643 lEA Rods - sumary of CSA - 3/96 i

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+ Final Assembly - su.amary of CSE - 6/97 j - UF, Cylindar Washing - sumary of CSE - 12/95 j{N '

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• The Cfff has performed a CSA upgrade and does not have a specific date for schedule  !

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h; ** These systems are to be coupled with the Columbia Plant Risk Management Program t

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(RMP) to be done for the EPA. ,e The licensee shall maintain and execute the response measures in the Site Emergency l#

phl S-3 N Plan, dated April 30, 1990, and revisions dated March 31, and September 30, 1992; j#

E p March 15. August 15, and September 30, 1994; January 9, February 17 August 17, and  :

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October 23, 1995; or as further revised by the licensee consistent with lW l p 10 CFR 70.32(1). jW Nl -

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p!S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external jE p' surfaces of packaged radioactive material receipts for radioactive contamination, i N

pl the licensee is exempted from such requirement relative to flatbed trailer shipments ju p'

of fuel assemblies received from the General Electric Company for interim storage jn' purposesonly,providedtheconstraints,conditionsandcontrolscommittedtointhejEl, p

l licensee's letter, dated November 30,1993, (identification # NRC-93 036), are I jW WI satisfied; and further provided that the total number of such fuel assemblies stored pl at the licensee's site at any given time does not exceed 250. jt-l

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% SECTION 1.0 . MA1ERI AL CONTROL AND AC[DidHE F

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4lSG-1.1 9 The licensee shall follow pages i through xvii and Chapters 1.0 through 9.0 of $

% its " fundamental Nuclear Material Control Plan for the Columbia fuel #

fabrication facility," with all pages identified as Revision 27 (dated f May 23, 1997). Any further revisions to this Plan shall be made only in fj

% accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34, &

w 4lSG-1.2

1. Operations involving special nuc b .r material which are not referenced in the kjCf Plan identified in Condition SG-1.1 shall not be initiated until an

% appropriate safeguards plan has been approved by the Nuclear Regulatory f Commission, f 4

In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use f$l k SG-1.3 the forms DOE /NRC-742 and 742C, the licensee may use computer generated forms f#

provided all information required by the latest printed instructions for completing the particular form is included. i ,

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$ In lieu of the requirements contained in CFR 70.54 and 74.15 to use the j i

% SG-1.4 DOE /NRC form 741, the licensee may use computer generated forms provided all

% f informatlon required by the latest printed instructions for completing the R

% particular form is included.

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d; SG-1.5 Deleted Per Amendment 3, August 1996 Commitment now contained in licensee's fundamental Nuclear Material Control Plan. [y 4 '

% SG-1,6 liotwithstanding the requirements of the FNMC Plan identified in License ]

Condition SG-1.1, the licensee may use (1) a single standard for measurement  ;

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d, control (including daily control limit monitoring and bias corrections) for la any linear-response tube or rod scales, in any initially demonstrated to be hl 4 linear over its range of use within the discrimination of the scale by  ; l 4

calculating a bias at four levels across the range of use and demonstrating d ' '

d that the four results are not statistically different, and (L') that the d continued linearity of response of the scales is verified by monthly E calibration against at least four traceable standards covering the range of Vlpj dl 4

t use.

k Notw;thstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the V' d SG-1.7 4

licensee'sfundamentalNuclearMaterialControlPlan,thelicenseeisexemptedl l d from physical inventory requirements relative to the material identified in l d Condition S-4; provided the conditions and commitments contained in the  ! l k licensee's November 30, 1993, letter (identification # NRC-93-036) are  %

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8 6 SG 1.8 Notwithstanding the requirement of Section 6.2.l(a).5 of the licensee's 8 Wi fundamental Nuclear Material Control Plan to unpackage and perform an item I 5 count upon receipt of special nuclear material, the licensee is exempted from 8

! such requirement relative to the material identified in Condition S-4; .d i

provided the conditions and commitments contained in the licensee's i

November 30, 1993, letter (identification # NRC-93 036) are satisfied. l 3

lSG-1.9 Notwithstanding the requirement of Section II.A.7 block U, of NUREG/BR 0006, 8

which is incorporated via 10 CTR 74.15, to complete receiver's measurements of #

i scrap receipts (following recovery processing) within 60 days of receipt, the 8 licensee shall not be subject to any time limit relative to recovering and 8 measuring received UF, heels when the block U action code (of DOE /NRC form i

741) is used to book such receipts. j fSG-1.30 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 n N

i specified as being: N W

(1) 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; l

W (11) no more than one defect when each ites within a batch of items has an assigned value of less than 500 grams U-235, but one or more items has an I assigned value in excess of 50 grams U-235 and W E

I (iii) zero defect when any item within a batch of items contains 500 or more W grams U-235. 4 q n Notwithstanding the first paragraph of Section 7.1 of the Plan identified by N nlSG-1.ll W

Condition SG-1.1, the licensee shall conduct shipper-receiver comparisons on ;il

% all SNM materials received (regardless of whether booked on the basis of W, jt receiver's or shipper's values), except for those materials identified in W d'

I Section 7.1 of NUREG-1065 (Rev. 2) as being exempted from shipper-receiver (

g comparisons. #

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W SECTION 2.0 -- PflYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE q N

K' SG;2.1 The licensee shall follow the " Site Physical Security Plan - Westinghouse .g g'

p Electric Corporation, Columbia, S.C.," dated March 1980; Revision 10.0 dated La e' October 1, 1987;_the ' Revision Record" contained in the approved Physical lg I

p! Security Plan (current to October 1, 1994); and as may be revised in pl accordance with the provisions of 10 CFR 70.32(e). lta;a tj 3 g-5:

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SAFEGUARDS CONDITIONS s l l $ECT10N 3.0 -- INTERNATIONAL SAFEGUARDS l 8

SG-3.1- The licensee shall follow Codes 1 through 6 of Transitional Facility I Attachment No. SA dated August 31, 1988, to the US/XAEA Safeguards Agreement. 8 Such Transitional Facility Attachment shall be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7. l 8

SG-3.1.1 With respect to Transitional Facility Attachment Code 2: ,

8 The reference design information is that dated by the licensee on October 14, I l 1985. "Information on the Facility" also includes other facility information 8 submittedviaConciseNotesinacco{dancewith10CFR75."(c). E E

I SG-3.1.2 With respect to Transitional Facility Attachment Code 2.2: d i

SubstantivechangestotheinformationprovidedintheColumbiaPlantDesign N information Questionnaire (DIQ) means those changes requiring amendment of the I  !

Transitional Facility Attachment. Such changes shall be provided by letter to I the NRC Office of Nuclear Material Safety and Safeguards at least 70-days in d N

advance of implementation.

N Non-substant a changes to the information in the DIQ means those changes not E i

' requiring amendment of the Transitional-Facility Attachment. Such changes I shall be provided by Concise Note (From DOE /NRC-740M) within 30 days of. I I -receiving notification from the NRC that the facility has been identified E 1 under Article 39(b) of the US/IAEA Safeguards Agreement. N 4

1 lj 1he types of modifications with respect to which information is required under N 10 CFR 75.11 (to be submitted in advance), are those items stated in Code 4 2.2, specifically: E Il l

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l- (a) "Any change in the purpose of type of facility" means: E 4

I Any deviation from the described activities involving special nuclear material q i J I and any change to the maximum enrichment and/or quantities of U-235 currently a authorized by Licease No. SNM-1107, and/or as described in Paragraph 5 of the t  :

DesignInformationQuestionnaire(DIQ)datedOctober 14, 1985, or as modified u inaccordancewith10CFR75.11(c). Included also is any deviation from the a described special nuclear material (SNM) production activities described in g i

paragraph 6 of the DlQ dated October 14, 1985, or es modified in accordance a with 10 CFR 75.ll(c). a ,

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'(b)."Any changes in the-layout of the facility which affects safeguards a ,

implementation of the provisions of the Protocol" means: a ,

4 Any change in the existing facility and/or site layout or new addition a ,

affecting any-activity involving SNM as described in Paragraphs 10 and ll. g a (per the-referenced attachments of the DlQ dated October 14, 1985, or as e i modified in accordance with 10 CFR 75.11(c). Included also is any.

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W Wli modification to, or deviation from, the data provided in Paragraphs 13 and 8 14 (per the referenced attachments) of the D10 dated October 14, 1985, or l

% as modified in accordance with 10 CFR 75.ll(c). $lE Rl i

% (c) "Any change that makes the selected Key Measurement Points (KMPs) (as j l

% described in Code 3.1.2) inadequate for the Agency's accounting purpose" i l

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% Any c hnge to the KMPs as described in Codt, 3.1.2 of the Westinghouse- fi Columbia Transitional Facility Attachment to the US/IAEA Safeguards 4l WL Agreement, or as modified in accordance with 10 CFR 75.11( ), that esults El in any KMP alteration affecting the purpose of KMP:; as shpulated by 10 CFR 75.4(m)

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% (d) "Any change in the physical inventory procedures that would adversely  %

affect the inventory taking for the Agency's accounting purposes" means: flE Any change to the description data contained in Paragraph 34 (per the 'E 4l W

referenced attachments) of the DIQ dated October 14, 1985, or as modified l Wi in accordance with 10 CFR 75.ll(c), that would not permit the Agency to ll conclude an SNM material balance for the Westinghouse-Columbia facility. ,  ;

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% (e) " Introduction of a significantly less accurate analytical method for ;a accounting purposes" means: K Anyrecalculationofthe'RelativeErrors-RandomandSystematic"aslistedl l Wl 4

in Attachment 36.2 referenced in Paragraph 36 of the DIQ dated October 14. j 1985, or as modified in accordance with 10 CFR 75.ll(c), that results in E )l the estimates of the random and systematic errors being affected by a W i l

factor of two or more, lg e

i (f) " Decrease in the frequency of calibrating measuring equipment if it 'gll 4 significantly decreases the accuracy of the materials accounting system" !s means:

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Any change that results in the estimates of the systematic error being !gls 4' affected by a factor of two or more. i

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(! (g) "Any change in the statistical procedures used to combine individual  !

l gl measurement error estimates to obtain limits of error for shipper / receiver ' l g (S/R) differences and material unaccounted for (MUF)" means: l l i

Any deviation from (or modification of) the equations and/or calculations l l

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4 outlined in Attachments 37.1, 37.2, and 37.3 referenced in Paragraph 37 of I

.l L e l the DIQ dated October 14, 1985, or at modified in accordance with 10 CFR V 75.ll(c). V l k t m-

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l SAFEGUAPDS CONDITIONS !l SG-3.1.3 With respect to Transitional Facility Attachment Code 3.1.2:

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recorded and -- This reportedis a even ifKMP in numerically which zero. SRDs reported by the Nuclear Materials Managc'ent and Safeguards System upon all chipper receiver differ are computed and receipt of the receiver's measurement results. F 4

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d!SG-3.1.4 With respect to Transitional Facility Attachment Code 4: {

k The licensee shall use the material composition codes documented in the DIQ f

% dated October 14, 1985, and as modified by Concise Notes. Further, f d

j notwithstanding any other requirements for advance notification :nd/or ji 4, reporting, tne licensee may add or delete conmosition codes for nuclear jl material routinely processed and on inventory at CFFF immediately upon i!

N; telephone notification to the Office of Nuclear Material Safety and Safeguards. Follow-up documentation, in the form of a Concise Note fH accompanied by appropriate changes to Table 1 of Attachment 34.8 to the D10 it;

% jk shall be submitted within three regular workdays of the telephone notification, f 4 il SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1: i!

Measured disca-is should be reported as an SN (Shipment to non-safeguards b facil".y) when shipped off-site to an authorized burial ground. (The IAEA p system will not process measured discards as loss / disposal (LDs) when they are j '

shipped off-site). ,

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% With respect to Transitional Facility Attachment Code 5.1.1:

% SG-3.1.6 f i Ml 4 For inventory changes, time of recording, "upon" means: No later than the ltE next regular workday (Monday through Friday). l ;l 4 i l 4 for those occastors where natural or depleted uranium is inadvertently w

1. enriched above 0.711 percent through commingling with residual enriched lEl

$! uranium in process equipment, the resultant product shall be considered as E.

1. being produced through a blending operation and the material category change H I

shall be recorded upon obtaining measu:ement confirmation that a m;terial l

1. ' category change has occurred.

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H E SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2: k 4 I 4' for Concise Notes describing the anticipated operational programe, S

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/ " anticipated operational prograrane" means: Anticipated physical inventory schedule.

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