ML20137G064
| ML20137G064 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 03/27/1997 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20137G022 | List: |
| References | |
| NUDOCS 9704010304 | |
| Download: ML20137G064 (9) | |
Text
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, j Pursuant to the Atomic Energy Act of 1954, as amended, the Enetp> Reorgani/ation Act of 1974 iPubbe Law 93 43M. and Title 10. Code of Q l t ! Federal Regulations. Chapter 1. Parts 30. 31. 32. 31. 34. 35. 36. 39. 40. and 70. and in reliance on statements and representations heretofore made C h bs he licensee, a license is hereby iwued authori/ing the licensee to receise. A pm eu and transfer by product, source. and special nuclear
(( material de ignated below: 10 use such material f or the purposeN and at the placeN designated below; to deiner or transfer such material to $
$l l persons authorved to receise it in accordance with the regulanons of the applicable PartN. This been e shall be deemed to contain the condition
, j specified in Section 183 of the Atomic Energy Act of 1954. as amended, and is subject to all applicable rules. regulations. and orders of the l Nuclear Regulatory Commission now or hereafter in ettect and to any conditions specified below. [;? l f ,e 9 i I k Licensee El
- 1. Westinghouse Electric Corporation 3. License Number SNM-Il07 Amendment 4 i I
B I
P.O. Box 355 !s I
E Pittsburgh, Pennsylvania 15230-0355 s lh ,~ 4. Expiration Date November 30, 2005 s :
a s C 5. Docket or 70-1151 G1 Reference No.
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- 6. ' Byproduct. Source, and/or 7. Chemical and/or Physical
- 8. Maximum Amount that Licensee May Possess at Any One Time (l
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, Special Nuclear Material Form s ,
I l Under This License ql l l c I
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i ! A. U-235 A. Any A. 0.35 kg !g I I B. U-235 B. Any, except B. 75,000 kgs l metal, enriched !g
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$l l to not more g-I'
! than 5.0 w/o 43 C. U-233 C. Any C. 5 grams 4;
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D. Pu-238, Pu-239 D. Sealed sources D. 1.5 grams 4:
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1 9. Authorized place of use: The licensee's existing facilities at Columbia, South (i al Carolina.
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% 10. This license shall be deemed to contain two sections: Safety Conditions and Ql l& Safeguards Conditions. These sections are part of the license and the licensee is 7l lh\ subject to compliance with all listed conditions in each section. j 9 fr I
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q sj E 5! FOR THE NUCLEAR REGULATORY COMMISSION ![i 8 7l t O'1' l 1 Date: 3 27 D By: Michael F. Weber O I i Division of Fuel Cycle Safety yl I i and Safeguards W, l i Washington, DC 20555 Ij
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License Number gI g . SNM-1107 Amendment 4 El p MATERIALS LICENSE omei or nererence Number g g SUPPLEMENTARY SHEET 70-1151 gj N E' y SAFETY CONDITIONS fEi
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N B SAFETY CONDITIONS lE N E I E, 1 S-1 Authorized use: For use in accordance with statements, representations, and E I conditions in the license application' dated April 30, 1995, and supplements E
, I dated May 11, 18; August 4, 25; and September 25, 1995. E
- 1 E' N S-2. The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis E y (CSAs) will define the criticality safety bases utilized throughout the plant E W and will be completed as described in Sections 6.4.1 and 6.4.2 of the license E i application for each step of the process. 'A' submittal to the NRC will be gl g made by Westinghouse.which will include information which the staff will i!
g review against the comitments listed in Section-6.2.3 of the license p g application. These submittals will not be specific comitments, but are E!
y intended as a demonstration of the adequacy of the bases of safety itemized E i
g in Section 6.2.3. The contents listed in Section 6.4.2 of the license gi y application are commitments. The demonstration will show the logic used by g' y the Columbia Fuel Fabrication Facility (CFFF) in developing the criticality y y safety bases. It is understood that this demonstration may change over time. y' g The submittal will consist of a sumary of the CSE or CSA as annotated below g!
g for each system (which shall include fault trees for those systems for which g g a CSE will be done). The adequacy of the comitments in Section 6.2.3 of the E y
license application will be evaluated and a reply in the form of a letter g y report will be generated and sent from the staff to Westinghouse. The ,
y submittal by the CFFF will be provided according to the following schedule: ,
5 UN tanks - summary of CSE -10/95 3
- URR!, Dissolver - sumary of CSE - 10/95 l
5 - Solvent Extraction - sumary of CSE - TBD* I 5 - URR!. Scrap Processing: g 5 - Low-level Waste Processing System - summary of CSA - 9/96 ,
5 Hop Water System Equipment - summary of CSA - 9/96 ,
5 Incinerator System - sumary of CSE - 9/96 I 5 Ash Recovery System - summary of CSE - 9/96 ,
5 Liquid Honing System - summary of CSE - 9/96 I 5 Ultrasonic Cleaning System - sumary of CSE - 9/96 I 5 Shredder System - sumary of CSE - 9/96 I 5 - URRS Waste Treatment - summary of CSA - 11/95 I
5 - IDR Conversion - summary of CSE - Prior to Restart I
B - ADU Conversion - summary of CSE - 4/96 I
N - ADU Pelleting - sumary of CSE - 6/n6 I N - Powder Blending - summary of CSE - 1/96 I
B. - Miscellarmous:
I N Ventilation Systems (Geometry Controlled) -
I N- sumary of CSE - 12/97** I N
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g . License Number g SNM-1107 Amendment 4 p ,
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$ MATERIALS LICENSE Docket or Reference Number g SUPPLEMENTARY SHEET 70-1151 i R
SAFETY CONDITIONS lE g p ,
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N E N Ventilation Systems (Moderation Controlled) - E j W sumary of CSE - 12/97** E a
i Scrubber Systems - sumary of CSE - 12/97** E q Hoods & Containment - summary of CSA - 9/96 E p Laboratories - sumary of CSA - 9/96 g g - IFBA - summary of CSA - 3/96 i; a W - Storage Pad - NCS is based on DOE reports K-1920 and K-1663 E W - Rods - sumary of CSA - 3/96 E g - Storage - summary of CSE - 4/97 g i Final Assembly. - sumary of CSE - 6/97 g
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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 g g schedule of this CSE at this time. p,
S-3 Plan, dated April 30, 1990, and revisions dated March 31, and September 30, 1992; ljl E
g March 25, August 15, and September 30, 1994; January 9, February 17, August 17, and ,
y October 23, 1995; or as further revised by the licensee consistent with ,
y 10 CFR 70.32(i). ,
I N
S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external I
N surfaces of packaged radioactive material receipts for radioactive contamination, N the licensee is exempted from such requirement relative to flatbed trailer i N shipments of fuel assemblies received from the General Electric Company for interim I N storage purposes only, provided the constreints, conditions and controls committed i E to in the licensee's letter, dated November 30, 1993, (identification # NRC E N 036), are satisfied; and further provided that the total number of such fuel .E N assemblies stored at the licensee's site at any given time does not exceed 250. lE R E N i N E 6 i B i
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,g , E y . SNM-1107 Amendment 4 g g MATERIALS LICENSE oockes or sererence Number .[
g SUPPLEMENTARY SHEET 70-1151 g SAFEGUARDS CONDITIONS l -
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N !E N SAFEGUARDS CONDITIONS 's N E N E g
N SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTING W E W SG-1.1 The licensee shall follow Chapters 1.0 through 9.0 of its " Fundamental y y Nuclear Material Control Plan for the Coiumbia Fuel Fabrication Facility," E g with all pages identified as "Rev. No. 25.0" and dated "07AUG96." This Plan E y may be revised in accordance with, and pursuant to, either 10 CFR 70.32(c) or g g 70.34. g N E y SG-1.2 Operations involving special nuclear materials which are not referenced in y y the Plan identified in Condition SG-1.1 shall not be initiated until an y y appropriate safeguards plan has been approved by the Nuclear Regulatory g g Commission. E SG-1.3 In lieu of the requirenants 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 l
g 9
g provided all information required by the latest printed instructions for ,
y completing the particular form is included. ,
l SG-1.4 In lieu of the requirements contained in CFR 70.54 and 74.15 to use the DOE /NRC Form-741, the licensee may use computer generated forms provided all l!
,i g
information required by the latest printed instructions for completing the particular form is included. l N Deleted Per Amendment 3, Augoic 1996 --- Commitment now contained in i SG-1.5 E licensee's Fundamental Nuclear Material Control Plan. I l, 5 E1 Notwithstanding the requirements of the FNMC Plan identified in License I' N SG-1.6 N Condition SG-1.1, the licensee may use a single standard for measurement E i
N control (including daily control limit monitoring and bias corrections) for 8l N any linear-response tube or rod scales, in any initially demonstrated to be E N linear over its range of'use within the discrimination of the scale by i N calculating a bias at four levels across the range of use and demonstrating E' N that the four results are not statistically different. and (2) that the E N continued linearity of response of the scales is verdied by monthly E N calibration against at least four traceable standards covering the range of j i'
N use. {EE N
N SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the E N licensee's Fundamental Nuclear Material Control Plan, the licensee is E N exempted from physical inventory requirements relative to the material E N identified in Condition S-4; provided the conditions and commitments jE N contained in the licensee's November 30, 1993, letter (identification # NRC- lE
'E N 93-036) are satisfied. E N
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> N SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's i N Fundamental Nuclear Material Control Plan to unpackage and perform an item i
. N count upon receipt of special nuclear material, the licensee is exempted from i N such requirement relative to the material identified in Condition S-4; i MI provided the conditions and commitments contained in the licensee's E
$ November 30, 1993, letter (identification # NRC-93-036) are satisfied. E E
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SG-1.9 Notwithstanding the requirement of Section II.A.7, block U, of NUREG/BR-0006, E N which is incorporated via 10 CFR 74.15, to complete receiver's neasurements E W of scrap receipts (following recovery processing) within 60 days of receipt, E N the licensee shall not be' subject to any time limit relative to recovering E p and measuring received UF, heels when the block U action code (of DOE /NRC E g Form 741) is used'to book such receipts. E N i g SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, E g " allowed number" within the phrase " allowed number of defects" is hereby p g specified as being: g N E i (i) up to two defects when each item within a batch of items has an assigned 5 g value equal to or less than 50 grams U-235; E
' N E y (ii) no more than one defect when each item within a batch of items has an g g assigned value of less than 500 grams U-235, but one or more items has an ,
y assigned value in excess of 50 grams U-235; and j l (iii) zero defect when any item within a batch of items ~contains 500 or more l g grams U-235. ,
! SG-1.11 Notwithstanding the first paragraph of Section 7.1 of the Plan identified by l Condition SG-1.1, the licensee shall conduct shipper-receiver comparisons on l
- all SNM materials received (regardless of whether booked on the basis of receiver's or shipper's values), except for those materials identified in l Section 7.1 of NUREG-1065 (Rev. 2) as being exempted from shipper-receiver g
g comparisons. ,
SECTION 2.0 -- PHYSICAL PROTECTION 0F SNM 0F LOW STRATEGIC SIGNIFICANCE l
N SG-2.1 The licensee shall follow the " Site Physical Security Plan - Westinghouse E N Electric Corporation, Columbia, S.C.." dated March 1980; Revision 10.0 dated jE N October 1, 1987; the " Revision Record" contained in the approved Physical lE N Security Plan (current to October 1, 1994); and as may be revised in E N accordance with the provisions of 10 CFR 70.32(e). {I N E N E N E W<
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License Number SNM-1107 Amendment 4 lgg y ,
MATERIALS LICENSE oncket or Reference Number !g y
g SUPPLEMENTARY SHEET 70-1151 g l SAFEGUARDS CONDITIONS f 3 EI 3 lE
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y g SECTION 3.0 -- INTERNATIONAL SAFEGUARDS 3 Ei g SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility E g Attachment No. 5A dated August 31, 1988, to the US/IAEA Safeguards Agreement. g 3
Such Transitional Facility Attachment shall be interpreted in accordance with 8 3
Conditions SG-3.1.1 through SG-3.1.7. E; M
y SG-3.1.1 With respect to Transitional Facility Attachment Code 2: El E
3 E'
y The reference design information is that dated by the licensee on October 14, g!
g 1985. "Information on the Facility" also includes other facility information gl 3
submitted via Concise Notes in accordance with 10 CFR 75.11(c). g SG-3.1.2 With respect to Transitional Facility Attachment Code 2.2: l E
Substantive changes to the information provided in the Columbia Plant Design l Information Questionnaire (DIQ) means those changes requiring amendment of g !g g
the Transitional Facility Attachment. Such changes shall be provided by g; letter to the NRC Office of Nuclear Material Safety and Safeguards at least I, l y
g 70-days in advance of implementation. I 5 Non-substantive changes to the information provided in the DIQ means those 5
l changos not requiring amendment of the Transitional Facility Attachment.
Such changes shall be provided by Concise Note (Form DOE /NRC-740M) as part of the routine quarterly update of the DIQ,
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i 3j The types of modifications with respect to which information is required jf under 10 CFR 75.11, (to be submitted in advance), are those items e ed in 3l i 3j Code 2.2, specifically:
3 lE 3 "Any change in the purpose of type of facility" means: if (a) !E 3
3' Any deviation from the described activities involving special nuclear i 3 material and any change to the maximum enrichment and/or quantities of j i
3 U-235 currently authorized by License No. SNM-1107, and/or as described li ti 3;j in "Iragraph 5 of the Design Information Questionnaire (DIQ) dated October 14, 1985, or as modified in accordance with 10 CFR 75.11(c). !
3j Included also is any deviation from the described special nuclear i 3l material (SNM) production activities described in paragraph 6 of the 1 3
3 DIQ dated October 14, 1985, or as modified in accordance with 10 CFR E I
75.11(c). f 5l 3
3 (b) "Any changes in the layout of the facility which affects safeguards i l; implementation of the provisions of the Protocol" means: E i
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y SNM-1107 Amendment 4 g p MATERIALS LICENSE Docket or Reference Number fg y SUPPLEMENTARY SHEET. 70-1151 Ig SAFEGUARDS CONDITIONS l b !!
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N Any change in the existing facility and/or site layout or new addition l l N affecting any activity involving SNM as described in Paragraph 10 and El N 11 (per the referenced attachments of the DIQ dated October 14, 1985, EI I or as modified in accordance with 10 CFR 75.11(c). Included also is Ei I any. modification to, or deviation from, the data provided in Paragraph E1 N 13 and 14 (per the referenced attachments) of the DIQ dated October 14, E i
b 1985, or as modified in accordance with 10 CFR 75.11(c). E E
1
- W (c) "Any change that makes the selected Key Measurement Points (KMPs) (as p p' described in Code;3.1'2) inadequate for the Agency's accounting E
- p purpose" means: g E :;
N . .
. p Any change to the KMPs as described in Code 3"1.2 of the Westinghouse-
. El g Columbia Jransitional Facility Attachment to the US/IAEA Safeguards El I g Agreement, or as modified in accordance with 10 CFR 75.11(c), that g y results in any KMP alteration affecting the purpose of KMPt as g g stipulated by 10 CFR 75.4(m) E E1 4
N y (d) "Any change in the physical inventory procedures that would adversely y; y affect the inventory taking for the Agency's accounting purposes" gj g means: gl Any change to the description data contained in Paragraph 34 (per the l l referenced attachments) of the DIQ dated October 14, 1985, or as ,
g y
modified in accordance with 10 CFR 75.11(c), that would not permit the ,
y Agency to conclude an SNM material balance for the Westinghouse- ,,
y Columbia facility. ,l i
N (e) " Introduction of a significantly less accurate analytical method for 4
l accounting purposes" means: ll i
N Any recalculation of the " Relative Errors-Random and Systematic" as N listed in Attachment 36.2 referenced in Paragraph 36 of the DIQ dated E E ,i 8 October 14, 1985, or as modified in accordance with 10 CFR 75.11(c),
N that results in the estimates of the random and systematic errors being il affected by a factor of two or more. l
" Decrease in the frequency of calibrating measuring equipment if it i N. (f) i, E significantly decreases the accuracy of the materials accounting N system" means: I l ,
N Any change that results in the estimates of the systematic error being E' N' affected by a factor of two or more. Ei il p
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,, g , License Number g y .
. SNM-1107 Amendment 4 g g MATERIALS LICENSE Docket or Reference Number g g SUPPLEMENTARY SHEET 70-1151 ,
SAFEGUARDS CONDITIONS l N E1 N E N E, N (g) "Any change in the statistical procedures used to combine individual E N measurement error estimates to obtain limits of error for- E N shipper / receiver (S/R) differences and material unaccounted for (MUF)" E W means: E N E N Any deviation from'(or modification of) the equations and/or =1 W calculations outlined in Attachments 37.1, 37.2, and 37.3 referenced in E1 g Paragraph 37 of the DIQ dated October 14, 1985, or as modified in I W accordance with 10 CFR 75.11(c). ^
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N . . . El W SG-3.1.3 With respect to Transitional Facility Attachment Code 3.1.2: gl N E' g KMP* -- This is a KMP in which all shipper receiver differences (SRDs) must EI g be recorded and reported even if numerically zero. SRDs are computed and E l
g reported by the Nuclear Materials Management and Safeguards System upon , l g receipt of the receiver's measurement results. E' l SG-3.1.4 With respect to Transitional Facility Attachment Code 4: ll The licensee shall use the material composition codes documented in the DIQ g y, y dated October 14, 1985, and as modified by Concise Notes. Further, E y notwithstanding any other requirements for advance notification and/or g g
reporting, the licensee may add or delete composition codes for nuclear ,,
g material routinely processed and on inventory at CFFF immediately upon y y
telephone notification to the Office of Nuclear Material Safety and ,4 Safeguards. Follow-up documentation, in the form of a Concise Note , ,
E accompanied by appropriate changes to Table 1 of Attachment 34.8 to the DIQ I U shall be submitted within three regular workdays of the telephone I
!s notification. i SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1: E E
U Measured discards should be reported as an SN (Shipment to non-safeguards N facility) when shipped off-site to an authorized burial ground. (The IAEA E
E E system will not process measured discards as loss / disposal (LDs) when they 5 are shipped off-site). E N E E
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- E y . SNM-1107 Amendment 4 E p MATERIALS LICENSE Dockt or Reference Number g g SUPPLEMENTARY SHEET 70-1151 g B E g, SAFEGUARDS CONDITIONS E II lE Nj E b E N SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1: E ;
N E N For inventory changes, time of recording, "upon" means: No later than the E W next regular workday (Monday through Friday). E N E N For those occasions where natural or depleted uranium is inadvertently E R enriched above 0.711 percent througn i.ommingling with residual enriched E N uranium in process equipment, the resultant product shall be considered as E ;
W being produced through a blending operation and the material category change g W shall be recorded upon obtaining measurement confirmation that a material y g category change has occurred. E E
y SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2: y ,
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