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

I 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 1

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

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% persons authotiied to reteise it in accordance with the reFulations of the appbcable pa specified in Sectmn IN3 of the Atomic 1:nergy Act of 1954, as amended, and is subject to all applicable rules, reFulations, and orders of the f

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

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i Westinghouse Electric Corporation

3. Ucenw Numba SNM-1107

@g Amendment 7 P.O. Box 355

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Pittsburgh, Pennsylvania 15230-0355 i

. 4. Ihpiration Date NoyembSr_JQm2005_

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5. Dodel or Q

p Reference No.

70-1151

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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 I l B. U 235 B.

Any, except B.

75,000 kgs I

S metal, enriched i

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to I.ot more i

l than 5.0 w/o d

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Any C.

5 grams 5,

D. Pu-238 D.

Sealed sources D.

1.5 grams Pu-239 bl 5

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

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

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4 FOR THE NUCLEAR REGULATORY COMISSION 3

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• lDate: 6ekAc 2/' / 7 7 7-p By: Michael F. Weber i

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SAFETY CONDITIONS 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

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5-2.

The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis l

Nl (CSAs) will define the criticality safety bases utilized throughout the plant 4

N and will be completed as described in Sections 6.4.1 and 6.4.2 of the license 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 E

M against the commitments listed in Section 6.2.3 of the license application.

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Wj These submittals will not be specific comitments, but are intended as a W

demonstration of the adequacy of the bases of safety itemized in Section 4

Mj 6.2.3.

The contents listed in Section C.4.2 of the license application are N

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comitments. The demonstration will show the logic used by the Columbia Fuel 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

1. l Rf consist of a sumary of the CSE or CSA as-annotated below for each system

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

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

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

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UN tanks - summary of CSE -10/95 a!

URRS Dissolver - sumary of CSE - 10/95 j

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Solvent Extraction - sumary of CSE - TBD*

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URRS Scrap Processing:

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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!

Ash Recovery System - sumary of CSE - 9/96

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Shredder System - summary of CSE - 9/96 I

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lp' ADU Pelleting - summary of CSE - 6/96 j ll Powder Blending - sumary of CSE - 1/96 n!

Miscellaneous:

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Ventilation Systems (Geometry Controlled) -

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g sumary of CSE - 12/97**

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Rods - sumary of CSA - 3/96 i

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

of this CSE at this time.

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• • These systems are to be coupled with the Columbia Plant Risk Management Program h

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(RMP) to be done for the EPA.

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,e phl S-3 The licensee shall maintain and execute the response measures in the Site Emergency l#

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Plan, dated April 30, 1990, and revisions dated March 31, and September 30, 1992; j#

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

October 23, 1995; or as further revised by the licensee consistent with lW l

p 10 CFR 70.32(1).

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p!S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external jE N

p' surfaces of packaged radioactive material receipts for radioactive contamination, i

pl the licensee is exempted from such requirement relative to flatbed trailer shipments ju of fuel assemblies received from the General Electric Company for interim storage jn' p'

purposesonly,providedtheconstraints,conditionsandcontrolscommittedtointhejEl, l

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licensee's letter, dated November 30,1993, (identification # NRC-93 036), are j

I 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.

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

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

9 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 Operations involving special nuc b.r material which are not referenced in the k fjC 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

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k SG-1.3 In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use

$l 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.

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% SG-1.4 In lieu of the requirements contained in CFR 70.54 and 74.15 to use the j

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

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

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

control (including daily control limit monitoring and bias corrections) for 4

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

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

Vlpj calibration against at least four traceable standards covering the range of dl 4

use.

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

t licensee'sfundamentalNuclearMaterialControlPlan,thelicenseeisexemptedl l

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from physical inventory requirements relative to the material identified in l

d Condition S-4; provided the conditions and commitments contained in the

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licensee's November 30, 1993, letter (identification # NRC-93-036) are

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satisfied.

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8 6 SG 1.8 Notwithstanding the requirement of Section 6.2.l(a).5 of the licensee's 8

W fundamental Nuclear Material Control Plan to unpackage and perform an item i

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

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

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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 scrap receipts (following recovery processing) within 60 days of receipt, the 8

i 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 741) is used to book such receipts.

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fSG-1.30 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, n

" allowed number" within the phrase " allowed number of defects" is hereby N

specified as being:

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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; lW (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 IW (iii) zero defect when any item within a batch of items contains 500 or more 4

q grams U-235.

n nlSG-1.ll Notwithstanding the first paragraph of Section 7.1 of the Plan identified by N

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

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all SNM materials received (regardless of whether booked on the basis of jt d'

receiver's or shipper's values), except for those materials identified in W

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

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comparisons.

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

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

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Electric Corporation, Columbia, S.C.," dated March 1980; Revision 10.0 dated La p

e' October 1, 1987;_the ' Revision Record" contained in the approved Physical lg I

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Security Plan (current to October 1, 1994); and as may be revised in lt pl accordance with the provisions of 10 CFR 70.32(e).

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$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.

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

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The reference design information is that dated by the licensee on October 14, I

1985.

"Information on the Facility" also includes other facility information 8

submittedviaConciseNotesinacco{dancewith10CFR75."(c).

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

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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

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' requiring amendment of the Transitional-Facility Attachment.

Such changes I

shall be provided by Concise Note (From DOE /NRC-740M) within 30 days of.

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-receiving notification from the NRC that the facility has been identified E

1 under Article 39(b) of the US/IAEA Safeguards Agreement.

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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

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2.2, specifically:

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

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J Any deviation from the described activities involving special nuclear material q

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).

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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:

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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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Wli modification to, or deviation from, the data provided in Paragraphs 13 and 8 W

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14 (per the referenced attachments) of the D10 dated October 14, 1985, or as modified in accordance with 10 CFR 75.ll(c).

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(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

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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

[e 10 CFR 75.4(m) j E

I (d) "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's accounting purposes" means:

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4l Any change to the description data contained in Paragraph 34 (per the

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

l (e) " Introduction of a significantly less accurate analytical method for

a accounting purposes" means

K Wl Anyrecalculationofthe'RelativeErrors-RandomandSystematic"aslistedl l 4

in Attachment 36.2 referenced in Paragraph 36 of the DIQ dated October 14. j )l 1985, or as modified in accordance with 10 CFR 75.ll(c), that results in E

lg the estimates of the random and systematic errors being affected by a W i l

factor of two or more, e

4 (f) " Decrease in the frequency of calibrating measuring equipment if it

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significantly decreases the accuracy of the materials accounting system"

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Any change that results in the estimates of the systematic error being s

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affected by a factor of two or more.

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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 '

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

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4l Any deviation from (or modification of) the equations and/or calculations l

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

e the DIQ dated October 14, 1985, or at modified in accordance with 10 CFR V

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75.ll(c).

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

KMP* -- This is a KMP in which all chipper receiver differ d

i recorded and reported even if numerically zero.

SRDs are computed and reported by the Nuclear Materials Managc'ent and Safeguards System upon i

receipt of the receiver's measurement results.

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

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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 notwithstanding any other requirements for advance notification :nd/or ji j

4, reporting, tne licensee may add or delete conmosition codes for nuclear jl i!

material routinely processed and on inventory at CFFF immediately upon N;

telephone notification to the Office of Nuclear Material Safety and f

Safeguards.

Follow-up documentation, in the form of a Concise Note H

accompanied by appropriate changes to Table 1 of Attachment 34.8 to the D10 it; k

shall be submitted within three regular workdays of the telephone j

notification, f

4 i l SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1:

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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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% SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1:

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Ml For inventory changes, time of recording, "upon" means: No later than the E

next regular workday (Monday through Friday).

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for those occastors where natural or depleted uranium is inadvertently w

enriched above 0.711 percent through commingling with residual enriched lEl uranium in process equipment, the resultant product shall be considered as E.

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

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shall be recorded upon obtaining measu:ement confirmation that a m;terial category change has occurred.

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SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2:

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s for Concise Notes describing the anticipated operational programe, S

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" anticipated operational prograrane" means: Anticipated physical inventory M

schedule.

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