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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y y 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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i I-Westinghouse Electric Corporation 3 l *'" N ""d'e' SNM-1107 Amendment 5

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$ P.O. Box 355 5

• l 2. Pittsburgh. Pennsylvania 15230-0355 .

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

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5. Docket or y

,I Reference No. 70-1151 y 6.113product. Source, and/or 7. Chemical and/or Phpical K. Masimum Amount that I icensee %l g)l Special Nuclear Material 1:orm May Poweu at Any one Time Q il l'nder This 1.icen se ip p

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• ! A. U 235 A. Any A. 0.35 kg 5 5 B. U-235 Any. except

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metal, enriched B. 75.000 kgs 5

, t 5 9 to not more nl h than 5.0 w/o #l h C. U-233 C. Any C. 5 grams $

% D. Pu 238. D. Sealed sources D. 1.5 grams $l Pu-239 $.j h,l s 9. Authorized place of use: The licensee's existing facilities at Columbia, South h

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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

$i is subject to compliance with all listed conditions in each section. yl s .

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% R 5; #l t FOR THE NUCLEAR REGULATORY COMMISSION Y g,d . [M l>

% Date: fc-l4 /Y' I1 W By: Michael F Weber F

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sj S1 Authorized use: For use in accordance with statements, representations.

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

l tj license application for each step of the process. A submittal to the NRC '

l  % will be made by Westinghouse which will include information which the staff I Bl 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 !g 4 in Section 6.2.3. The contents listed in Section 6.4.2 of the license W a) plication are commitments. The demonstration will show the logic used by 9 Ml M t1e Columbia Fuel Fabrication Facility (CFFF) in developt.g the criticality safety bases. It is understood that this demonstration may change over V Wj W time. The submittal will consist of a summary of the CSE or CSA as f 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 I

g following schedule:

N g e UN tanks - summary of CSE -10/95  %(ll e URRS Dissolver summary of CSE - 10/95 r4 g

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Solvent Extraction - summary of CSE - TBD*

URRS Scrap Processing:

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

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Mop Water System Equipment - summary of CSA - 9/96  ! l g Incinerator System - summary of CSE - 9/96 i l g Ash Recovery System - summary of CSE - 9/96 i l Liquid Honing System - summary of CSE - 9/96 !T

@y Ultrasonic Cleaning System - summary of CSE - 9/96  ?

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

g e URRS Waste Treatment - summary of CSA - 11/95 e

A g IDR Conversion - summary of 3E - Prior to Restart l g

• ADU Conversion - summary of LSE - 4/96 i

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g e ADU Pelleting - summary of CSE - 6/96 g

e Powder Blending - summary of CSE - 1/96 n e hiscellaneous: {lI nl gf Ventilation Systems (Geometry Controlled) - ?l summary of CSE - 12/97**

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j{ 5A5555amCausCKw5 i5AEwC55m5AAEA555A5AKKwfiC NRC FORM 374A U.S. NUCLE AR REGULATSRY COMMISSION Lkenw Numtcre PAGE 3 or 9 Pacts SNM-1107, Amendment 5 (g ,

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• N summaryofCSf-12/97**

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

• 8 Hoods & Containment - sumary of CSA - 9/96 8

1 Laboratories - sumary of CSA - 9/96 l i,

8]1 e IFBA - summary of CSA - 3/96 U 8 i e Storage Pad - NCS is based on DOE reports K-1920 and K-1663 E

El e Rods - summary of CSA - 3/96 Nj 8j e

e Storage - summary of CSE - 4/97 Final Assembly summary of CSE - 6/97 l ly e UF6 Cylinder Washing - summary of CSE - 12/95 8l

• 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*

(RMP) to be done for the EPA.

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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

%j 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). $

pl: S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external W l4;

% 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 interim storage purposes only. provided the constraints. conditions and controls f '

% jE committed to in the licensee's letter. dated November 30,1993. (identification f Wl.

4 # NRC-93-036), are satisfied; and further provided that the total number of such fuel assemblies stored at the licensee's site at any given time does not exceed fj

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SAFEGUARDS CONDITIONS q N

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SAFEGUARDS CONDIT10NS l

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

SG-1.1 h 9.0 N ThelicenseeshallfollowpagesithroughxviiandChapters1.0throu!1 of its " Fundamental Nuclear Material Control Plan for the Columbia Fu .N I N Fabrication Facility." with all pages identified as Revision 27 (dated N

May 23, 1997). Any further revisions to this Plan shall be made only in l 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 b appropriate safeguards plan has been approved by the Nuclear Regulatory l Commission.

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Nj SG-1.3 In lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to i use the Forms DOE /NRC-742 and 742C the licensee may use computer generated A

q forms provided all inforiaation required by the latest printed instructions N{ for completing the particular form is included.

SG-1.4 In lieu of the re #

DOE /NRC Form-741,quirements the licensee may contained use computer in CFR 70.54 forms generated and 74.15 to use the provided W all information required by the latest printed instructions for completing 8 the particular form is included. I' s W

1. 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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SG-1,6 Notwithstanding the requirements of the FNhC Plan identified in License t' W Condition SG-1.1. the licensee may use (1) a single standard for l#

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 I E

gj the range of use, N E

l W; SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of I l i

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the licensee's Fundamental Nuclear Material Control Plan, the licensee is j ;

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

4, identified in Condition S-4: provided the conditions and commitments contained in the licensee's November 30, 1993. letter (identification

1. NRC-93-036) are satisfied.

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

N I Fundamental Nuclear Material Control Plan to un j#

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count upon receipt of special nuclear material,the package licenseeand perform an item is exempted I N

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

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

Nl N SG 1.10 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: ;E N: W N (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: N N

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gj (ii) no more than one defect when each item within a batch of items has an assigned value of less than 500 grams U-235. but one or more items has an 4

.N gj assigned value in excess of 50 grams U-235: and W W W M (iii) zero defect when any item within a' batch of items contains 500 or E d more grams U 35. W d n R SG-1.11- Notwithstanding the first paragraph of Section 7.1 of the Plan identified 'h E by Condition SG-1.1. the licensee shall conduct shipper-receiver E I

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

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R shipper-receiver comparisons, n p SECTION 2.0 -- PHYSICAL PROTECTION OF SNM 0F LOW STRATEGIC SIGNIFICANCE I>n

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p 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 0F g pao PAGE 6 g LArnw Number l SNM-1107; Amendment 5 I l M ATERI Al,S 1,1 CENSE twet w ncrrrente Numter

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SUPPLEMENTARY SHEET 70-1151 I(t R

gli N SAFEUARDS CON 0lIl0NS lg4 0 ll N. N SECTION 3.0 - INTERNATIONAL SAFEGQA@S l

SG-3.1 The licensee shall fo!10w Lodes 1 through 6 of Transitional Facility I Attachment No. 5A dated August 31. 1988, to the US/lAEA Safeguards N Agreement. Such Transitional Facility Attachment shall be interpreted in I l accordance with Conditions SG 3.1.1 through SG 3.1.7.

l SG-3.1.1 With resper.t to Transitional Facility Attachment Code 2: I ll The reference design information is that dated by the licensee on !h October 14. 1985. "Information on the Facility" also includes other N facility information submitted via Concise Notes in accordance with 10 CFR 8 N 75.11(c). 8 1

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

% Safeguards at leest 70-days in advance of implementation. I N

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

% changes not requiring amendment of the Transitional Facility Attachment. i d

% Such changes shall be provided by Concise Note (Form DOE /NRC-740M) as part jW

% of the routine quarterly update of the DIO. i N iN M The types of modifications with respect to which information is required jE under 10 CFR 75.11. (to be submitted in advance), are those items stated in jE Nll g

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Code 2.2, specifically: ;W jE p!

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

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Any deviation from the f.escribed activities involving special nuclear jE pl material and any change to the maximum enrichment and/or quantities of U- jh pI 235 currently authorized by License No. SNM-1107, and/or as described in pi Paragraph 5 of the Design Information Questionnaire (D10) dated October 14 3 1985. or as modified in accordance with 10 CFR 75.11(c). Included also is lE H E

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

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

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

Ni i 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: l i !

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SAFE 0llAMjLC.0DIT10NS N N

N Any change in the existing facility and/or site layout or new addition affecting any activity involving SNM as described in Paragraphs 10 and ly

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

y or as modified in accordance with 10 CFR 75.11(c). Included also is 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 described in Code 3.1.-2) inadequate for the Agency's accounting I

N gl purpose" means:

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

N l 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) N t N

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: l4 l

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

4 referenced attachments) of the D10 dated October 14, 1985. or as N modified in accordance with 10 CFR 75.11(c), that would not permit the N b}

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- Agency to conclude an SNM material balance for the Westinghouse-Columbia facility.

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R. (e) " Introduction of a significantly less accurate analytical method for f N p! 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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p! of calibrating measuring equipment if it i p (f) "significantly Decreasedecreases in the frequencfe t accuracy of the materials accounting p system" means; lN jW Any change that results in the estimates of the systematic error being lN I g affected by a factor of two or more. jN l t u M{ i l

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A (g) "Any change in the statistical procedures used to corabine individual h l measurement error estimates to obtain limits of error for shipper / receiver (S/R) differences and material unaccounted for (MUF)"

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N i Any deviation from (or modification of) the equations and/or N N calculations outlined in Attachments 37.1, 37.2. and 37.3 referenced in 1 8 N Paragraph 37 of the DIO dated October 14. 1985. or as modified in i8 acc:,cdance wito 10 CFR 75.11(c). l B

SG 3.1.3 With respect to Transitional Facility Attachment Code 3.1.2:

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

1. recorded and-reported even if numerically zero. SR0s are computed and ju Nj reported by the Nuclear Materials Management and Safeguards System upon lN receipt of the receiver's measurement results.

Bj SG-3.1.4 With respect to Transitional Facility Attachment Code 4: l g- N.

8 The licensee shall use the material composition codes documented in the DIO E bj dated October 14, 1985, and as modified by Concise Notes. Further. lE Nj notwithstanding any other requirements for advance notification and/or N Nj reporting, the licensee may add or delete composition codes for nuclear lW N material routinely processed and on inventory at CFFF immediately upon lW W telephone notification to the Office of Nuclear Material Safety and it R

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Safeguards. Follow-up o cumentation. in the form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.8 to the D10 jW f

W shall be submitted within three regular workdays of the telephone '

Nj noti fication.

W E! 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

! facility) when shipped off-site to an authorized burial ground. (The IAEA ,n g! system will not process measured discards as loss / disposal (LDs) when they n g!

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pl SAFEGUARDS CONDITIONS Nl pf W N N l 8 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 next regular workday (Monday through friday). l 8

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For those occasions where natural or depleted uranium is inadvertently enriched above 0.711 percent through commingling with residual enriched N

i uranium in process equipment, the resultant product shall be considered as l being produced through a blending operation and the material category (1 change shall be recorded upon obtaining measJrement confirmation that a l material category change has occurred. I, l! ,

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

M For Concise Notes describing the anticipated operational 3rogramme. N

" anticipated operational programme" means: Anticipated p1ysical inventory 8 W{ schedule. I N

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