ML20212A070

Amend 5 to License SNM-1107 for Westinghouse Electric Corp

ML20212A070
Person / Time
Site:	Westinghouse
Issue date:	10/14/1997
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20212A033	List: ML20212A030 ML20212A070 ML20212A099
References
NUDOCS 9710230147
Download: ML20212A070 (9)

Text

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Putsuant to the Atomic 1:ncrr) Ast of 1954, as amended, the 1.ncry) Rrotranitation Att of 1974 tpublie 1.aw 93 44), and Title 10. Cate of g gl I ederal kryulations Charter 1. Parts 3n. 31,32,3% 34,35. 36,39. 4n. and 70, and in rehan(e on statements and representations heretotore made Q by the licensee, a hiense is hereby inued at.thoriting the bienser to tetene acquite. pouen and transfer byprodust. sourtc. and speaal nutlear g

! nw il designated below; to use sus h snatcrial for the purpose (s) and at the platcN designated below; to deiner or transfer sus h material to Li fi petsons authorited to tr6cne at in a(cordance with the scpulatioin of the apphiable PattN. lhis biense shall be dermed to tontain the conditions $

5; speofied in Nection IN3 of the Atomic 1.ncry) Act of 1934. as amended, and is subjett to all upphcable rules, regulations and orders of the

%, Nuticar Regulatory Comminion now of hereaf ter in effect and to an> tonditions specihed below.

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Westinghouse Electric Corporation SNM-1107 il l

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P.O. Box 355 5

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Pittsburgh. Pennsylvania 15230-0355

4. l.apiration t>aie November 30m 2005 y

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5. Docket or y

,I Reference No.

70-1151 y

g)l 6.11 product. Source, and/or

7. Chemical and/or Phpical K. Masimum Amount that I icensee

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Special Nuclear Material 1:orm May Poweu at Any one Time Q

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A. U 235 A.

Any A.

0.35 kg 5

5 B. U-235 B.

Any. except B.

75.000 kgs 5

t metal, enriched 5

9 to not more nl h

than 5.0 w/o

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C. U-233 C.

Any C.

5 grams D. Pu 238.

D.

Sealed sources D.

1.5 grams

$l h,l Pu-239

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9.

Authorized place of use:

The licensee's existing facilities at Columbia, South h

Carolina.

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10.

This license shall be deemed to contain two sections:

Safety Conditions and n

Safeguards Conditions.

These sections are part of the license and the licensee s

is subject to compliance with all listed conditions in each section.

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FOR THE NUCLEAR REGULATORY COMMISSION Y

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Date:

By: Michael F Weber

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SAFELY CONDITIONS

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lE Wi lE sj S1 Authorized use:

For use in accordance with statements, representations.

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i and conditions in the license application dated April 30. 1995 and lE Wi supplements dated May 11. 18: August 4. 25: and September 25. 1995.

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4 S-2.

The Criticality Safety Evaluations (CSEs) and Criticality Safet Anal sis

$l (CSAs) will define the criticality safety bases utilized "Troug out t e Wj plant and will be completed as described in Sections 6.4.1 and 6.4.2 of the M(

tj license application for each step of the process.

A submittal to the NRC l

l Bl will be made by Westinghouse which will include information which the staff I

j will review against the commitments listed in Section 6.2.3 of the license Wi application.

These submittals will not be specific commitments, but are

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4 intended as a demonstration of the adequacy of the bases of safety itemized

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in Section 6.2.3.

The contents listed in Section 6.4.2 of the license W

Ml a) plication are commitments.

The demonstration will show the logic used by 9

M t1e Columbia Fuel Fabrication Facility (CFFF) in developt.g the criticality V

Wj safety bases.

It is understood that this demonstration may change over f

W time.

The submittal will consist of a summary of the CSE or CSA as M

annotated below for each system (which shall include fault trees for those (y

systems for which a CSE will be done).

The adequacy of the commitments in k

k Section G.2.3 of the license 'pplication will be evaluated and a reply in g

e the form of a letter report will be generated and sent from the staff to d

Westinghouse.

The submittal by the CFFF will be provided according to the (q

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following schedule:

Ng UN tanks - summary of CSE -10/95 e

URRS Dissolver summary of CSE - 10/95 r4 g)g e

Solvent Extraction - summary of CSE - TBD*

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URRS Scrap Processing:

e g) low-level Waste Processing System - summary of CSA - 9/96

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e Mop Water System Equipment - summary of CSA - 9/96

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Incinerator System - summary of CSE - 9/96 i

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Ash Recovery System - summary of CSE - 9/96 i

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@y Liquid Honing System - summary of CSE - 9/96

! T Ultrasonic Cleaning System - summary of CSE - 9/96

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g Shredder System - summary of CSE - 9/96 g

URRS Waste Treatment - summary of CSA - 11/95 A

e IDR Conversion - summary of 3E - Prior to Restart g

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l ADU Conversion - summary of LSE - 4/96 g

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ADU Pelleting - summary of CSE - 6/96 g

e Powder Blending - summary of CSE - 1/96

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Ventilation Systems (Geometry Controlled) -

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summary of CSE - 12/97**

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n Ventilation S stems (Moderation Controlled) -

i summaryofCSf-12/97**

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

81 Hoods & Containment - sumary of CSA - 9/96 l

8 Laboratories - sumary of CSA - 9/96 8]1 e

IFBA - summary of CSA - 3/96 i,

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Storage Pad - NCS is based on DOE reports K-1920 and K-1663 E

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Rods - summary of CSA - 3/96 e

Storage - summary of CSE - 4/97 l

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Final Assembly summary of CSE - 6/97 ly UF Cylinder Washing - summary of CSE - 12/95 e

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• The CFFF has performed a CSA upgrade and does not have a specific date for i8 schedule of this CSE at this time.

• • These systems are to be coupled with the Coluabia Plant Risk Managcment Program l*

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(RMP) to be done for the EPA.

W S-3 The licensee shall maintt,and execute the response measures in the Site N

Emergency Plan. dated Apr 30, 1990, and revisions dated March 31. and September W

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30. 1992: March 25. August

5. and September 30, 1994: January 9. February 17.

9 August 17. and October 23, 4995: or as further revised by the licensee consistent Pj with 10 CFR 70.32(1).

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W S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external surfaces of packaged radioactive material receipts for radioactive contamination.

[. l the licensee is exempted from such requirement relative to flatbed trailer j

Bj shipments of fuel assemblies received from the General Electric Company for f

interim storage purposes only. provided the constraints. conditions and controls jE committed to in the licensee's letter. dated November 30,1993. (identification f

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1. NRC-93-036), are satisfied; and further provided that the total number of such f

4 fuel assemblies stored at the licensee's site at any given time does not exceed j

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SUPPL.EMENTARY SHEET 70-1151 4

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I SAFEGUARDS CONDITIONS q

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SAFEGUARDS CONDIT10NS l

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SECTION 1.0 -- M',TERIAL CONTROL AND ACCOUNilNG l

N SG-1.1 ThelicenseeshallfollowpagesithroughxviiandChapters1.0throu!1 h 9.0 of its " Fundamental Nuclear Material Control Plan for the Columbia Fu

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I Fabrication Facility." with all pages identified as Revision 27 (dated l

N May 23, 1997). Any further revisions to this Plan shall be made only in lli l

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

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N SG-1.2 0)erations involving special nuclear materials which are not referenced in N

N t ie Plan identified in Condition SG-1.1 shall not be initiated until an U

N appropriate safeguards plan has been approved by the Nuclear Regulatory b

l Commission.

l Nj In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to N

SG-1.3 i

use the Forms DOE /NRC-742 and 742C the licensee may use computer generated A

forms provided all inforiaation required by the latest printed instructions q

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for completing the particular form is included.

SG-1.4 In lieu of the re DOE /NRC Form-741,quirements contained in CFR 70.54 and 74.15 to use the the licensee may use computer generated forms provided W

all information required by the latest printed instructions for completing 8

the particular form is included.

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W SG-1.5 Deleted Per Amendment 3. August 1996 Commitment now contained in licensee's N

Fundamental Nuclear Material Control Plan.

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t' SG-1,6 Notwithstanding the requirements of the FNhC Plan identified in License W

Condition SG-1.1. the licensee may use (1) a single standard for measurement control (including daily control limit monitoring and bias W

corrections) for any linear-response tube or rod scales, in any initially N

demonstrated to be linear over its range of use within the discrimination ju of the scale by calculating a bias at four levels across the range of use h

and demonstrating that the four results are not Statistically different.

W and (2) that the continued linearity of response of the scales is verified W

by monthly calibration against at least four traceable standards covering IE gj the range of use, N

ElW; SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of I

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t the licensee's Fundamental Nuclear Material Control Plan, the licensee is I

j Dl exempted from physical inventory requirements relative to the material j j 4

identified in Condition S-4: provided the conditions and commitments 4,

contained in the licensee's November 30, 1993. letter (identification

1. NRC-93-036) are satisfied.

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SAFEEVMDS CONDITIONS N

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SG-1.8 Notwithstanding the requirement of Section 6.2.1(a) 5 of the licensee's N

count upon receipt of special nuclear material, package and perform an item j#

Fundamental Nuclear Material Control Plan to un I

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the licensee is exempted I

i Ni from such requirement relative to the material identified in Condition S-4:

{N Nl 3rovided the conditions and commitments contained in the licensee's

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lovember 30, 1993. letter ' identification #NRC 93 036) are satisfied.

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SG-1.9 Notwithstanding the requirement of Section II.A.7. block U. of NUREG/

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BR.0006, which is incorporated via 10 CFR 74.15, to complete receiver's N

N measurements of scrap receipts'(following recovery processing) within 60 N

N days of receipt. the liceasee shall not be subject to any time limit N

Ni relative to recovering and measuring received UF hee N

action code (of DOE /NRC Form 741) is used to book suc!s when h receipts.

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Nl SG 1.10 N

With respect to Section 5.1.4 (b) of the Plan identified by Condition N

N; SG-1.1. " allowed nuaber" within the phrase " allowed number of defects" is l0 Bj hereby specified as being:

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(i) up to two defects when each item within a batch of items has an 4

N assigned value equal to or less than 50 grams U-235:

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(ii) no more than one defect when each item within a batch of items has an 4

gj assigned value of less than 500 grams U-235. but one or more items has an

.N gj assigned value in excess of 50 grams U-235: and W

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M (iii) zero defect when any item within a' batch of items contains 500 or E

d more grams U 35.

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SG-1.11-Notwithstanding the first paragraph of Section 7.1 of the Plan identified

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by Condition SG-1.1. the licensee shall conduct shipper-receiver E

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comparisons on all SNM materials received (regardless of whether booked on E

M the basis of receiver's or shiner's values), except for those materials t

1. l identified in Section 7.1 of NREG-1065 (Rev. 2) as being exempted from E

p shipper-receiver comparisons, n

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p SECTION 2.0 -- PHYSICAL PROTECTION OF SNM 0F LOW STRATEGIC SIGNIFICANCE n

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SG-2.1

-The licensee shall follow the " Site Physical Security Plan - Westinghouse g

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

g dated October 1. 1987; the " Revision Record" contained in the ap3 roved a

mi Physical Security Plan (current to October 1. 1994); and as may 3e revised d;

in accordance with the provisions of 10 CFR 70.32(e).

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FORM M4A U.S. NUCLEAR REOULATORY COMMISSION PAGE 6 0F g pao g

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SNM-1107; Amendment 5 I

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SAFEUARDS CON 0lIl0NS 4

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N SECTION 3.0 - INTERNATIONAL SAFEGQA@S l

I SG-3.1 The licensee shall fo!10w Lodes 1 through 6 of Transitional Facility N

Attachment No. 5A dated August 31. 1988, to the US/lAEA Safeguards I

Agreement.

Such Transitional Facility Attachment shall be interpreted in accordance with Conditions SG 3.1.1 through SG 3.1.7.

SG-3.1.1 With resper.t to Transitional Facility Attachment Code 2:

ll The reference design information is that dated by the licensee on October 14. 1985.

"Information on the Facility" also includes other h

N facility information submitted via Concise Notes in accordance with 10 CFR 8

N 75.11(c).

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

l Substantive changes to the information provided in the Columbia Plant 8

Design Information Questionnaire (010) means those changes requiring E

amendment of the Transitional Facility Attachment.

Such changes shall be provided by letter to the NRC Office of Nuclear Material Safety and jh N

Safeguards at leest 70-days in advance of implementation.

I Nj N

Nj Non-substantive changes to the information provided in the DIO means those d

changes not requiring amendment of the Transitional Facility Attachment.

i Such changes shall be provided by Concise Note (Form DOE /NRC-740M) as part jW of the routine quarterly update of the DIO.

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The types of modifications with respect to which information is required jE E

under 10 CFR 75.11. (to be submitted in advance), are those items stated in j g

Code 2.2, specifically:

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

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Any deviation from the f.escribed activities involving special nuclear jE lp material and any change to the maximum enrichment and/or quantities of U-jh I

p 235 currently authorized by License No. SNM-1107, and/or as described in lE ip Paragraph 5 of the Design Information Questionnaire (D10) dated October 14 H

3 1985. or as modified in accordance with 10 CFR 75.11(c).

Included also is E

g any deviation from the described special nuclear material (SNM) production t

i activities described in paragraph 6 of the DIO dated October 14, 1985. or u

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

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i Nj (b) "Any changes in the layout of the facility which affects safeguards j l p,

implementation of the provisions of the Protocol" means:

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or 9 PAGts Lkene Numtxt SNM-1107, Amendment 5 N

M ATERI ALS 1.lCENSE tu tei m ncrcicna Numwr N-SUPPLEMENTARY SHEET 70-1151 N

N' SAFE 0llAMjLC.0DIT10NS N

N N

Any change in the existing facility and/or site layout or new addition l

affecting any activity involving SNM as described in Paragraphs 10 and y

.i 11 (per the referenced attachments of the D10 dated October 14. 1985.

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

Included also is y

any modification to. or deviation from, the data provided in Paragraphs 3

13 and 14 (per the referenced attachments) of the D10 dated October 14, 8

1985 or as modified in accordance with 10 CFR 75.11(c).

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(c) "Any change that makes the selected Key Measurement Points (KMPs) (as 8

N described in Code 3.1.-2) inadequate for the Agency's accounting I

gl purpose" means:

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N Any change to the KMPs as described in Code 3.1.2 of the Westinghouse-l N

Columbia Transitional Facility Attachment to the US/lAEA Safeguards W

Agreement, or as modified in accordance with 10 CFR 75.11(c). that N

results in any KMP alteration affecting the purpose of KMPs as R,

stipulated by 10 CFR 75.4(m)

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1. f (d) "Any change in the physical inventory procedures that would adversely N

hj affect the inventory taking for the Agency's accounting purposes" W

D means:

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

W referenced attachments) of the D10 dated October 14, 1985. or as N

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modified in accordance with 10 CFR 75.11(c), that would not permit the N

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Agency to conclude an SNM material balance for the Westinghouse-jN 4

Columbia facility.

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

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accounting purposes" means:

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N Any recalculation of the " Relative Errors-Random and Systematic" as N

listed in Attachment 36.2 referenced in Paragraph 36 of the D10 dated

,8 October 14. 1985. or as modified in accordance with 10 CFR 75.11(c).

E that results in the estimates of the random and systematic errors being N

affected by a factor of two or more.

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(f) " Decrease in the frequencfe accuracy of the materials accounting of calibrating measuring equipment if it i

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significantly decreases t lN p

p system" means; jW Any change that results in the estimates of the systematic error being lN I

g affected by a factor of two or more.

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(g) "Any change in the statistical procedures used to corabine individual ll l

measurement error estimates to obtain limits of error for lt shipper / receiver (S/R) differences and material unaccounted for (MUF)"

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means:

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i Any deviation from (or modification of) the equations and/or N

calculations outlined in Attachments 37.1, 37.2. and 37.3 referenced in 18 N

Paragraph 37 of the DIO dated October 14. 1985. or as modified in i8 acc:,cdance wito 10 CFR 75.11(c).

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SG 3.1.3 With respect to Transitional Facility Attachment Code 3.1.2:

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i KMP* inis is a KMP in which all shipper receiver differences (SRDs) must be E

u recorded and-reported even if numerically zero. SR0s are computed and j

N reported by the Nuclear Materials Management and Safeguards System upon lN j

receipt of the receiver's measurement results.

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

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8 The licensee shall use the material composition codes documented in the DIO E

b dated October 14, 1985, and as modified by Concise Notes.

Further.

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notwithstanding any other requirements for advance notification and/or lW j

Nj reporting, the licensee may add or delete composition codes for nuclear lW N

material routinely processed and on inventory at CFFF immediately upon W

telephone notification to the Office of Nuclear Material Safety and it R

Safeguards.

Follow-up o cumentation. in the form of a Concise Note f

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accompanied by appropriate changes to Table 1 of Attachment 34.8 to the D10 jW W

shall be submitted within three regular workdays of the telephone Nj noti fication.

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SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1; I

B MI Measured discards should be reported as an SN (Shipment to non-safeguards g!

facility) when shipped off-site to an authorized burial ground.

(The IAEA

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system will not process measured discards as loss / disposal (LDs) when they n

are 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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For inventory changes, time of recording. "upon" means:

No later than the l

next regular workday (Monday through friday).

l For those occasions where natural or depleted uranium is inadvertently 8

N enriched above 0.711 percent through commingling with residual enriched l

N i

uranium in process equipment, the resultant product shall be considered as (1

being produced through a blending operation and the material category l

change shall be recorded upon obtaining measJrement confirmation that a l!

material category change has occurred.

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

M For Concise Notes describing the anticipated operational 3rogramme.

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" anticipated operational programme" means:

Anticipated p1ysical inventory 8

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