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Category:LICENSE
MONTHYEARML20216J4631999-09-29029 September 1999 Amend 36 to License SNM-1168 for Framatome Cogema Fuels, Deleting License Condition S-4 ML20198F0641998-12-0202 December 1998 Amend 35 to License SNM-1168 for Framatome Cogema Fuels ML20154D5811998-09-28028 September 1998 Amend 34 to License SNM-1168,authorizing Receipt,Rod Loading,Downloading,Assembly,Storage & Shipment of Enriched Processed U with Minimum Enrichment of 2.5 percent,U-235, Containing Pu & Other Transuranic Isotopes ML20217Q0021998-02-25025 February 1998 Amend 33 to License SNM-1168,authorizing Organizational & Administrative Changes,Including Changes in Chapter 4, Nuclear Criticality Safety. Condition S-1,also Amended ML20199F9381998-01-26026 January 1998 Amend 32 to License SNM-1168,revising License Condition SG-1.1,by Incorporating Revised Fundamental Nuclear Matl Control Plan ML20149G7521997-07-16016 July 1997 Amend 31 to License SNM-1168 for Framatome Cogema Fuels ML20141D3981997-06-24024 June 1997 Amend 29 to License SNM-1168 for B&W Fuel Company,Allowing Delay of Receipt Measurements & Distribution of Doe/Nrc Form 741 on Specified Matl ML20134D8331996-10-24024 October 1996 Amend 28 to License SNM-1168 for B&W Fuel Co,Adding Condition S-10 ML20058B4471993-11-17017 November 1993 Matls Licensing Package for Amend 15 to License SNM-1168 for B & W Fuel Co,Incorporating Revised Emergency Plan, ML20059E6881993-11-0101 November 1993 Amend 14 to License SNM-1168,revising SG-1.1 Re Licensee Shall Follow Chapters 1.0 Through 8.0 of Fnmc,Submitted Per 10CFR74.31(b) ML20128E2531993-02-0404 February 1993 Amend 10 to License SNM-1168,incorporating Changes Made to Radiological Contingency Plan ML20245A0031989-06-0909 June 1989 Addendum to Safeguards Amend 1 to License SNM-1168, Clarifying License Conditions 1999-09-29
[Table view] Category:SNM & AMEND TO LICENSE (DKT 70S)
MONTHYEARML20216J4631999-09-29029 September 1999 Amend 36 to License SNM-1168 for Framatome Cogema Fuels, Deleting License Condition S-4 ML20198F0641998-12-0202 December 1998 Amend 35 to License SNM-1168 for Framatome Cogema Fuels ML20154D5811998-09-28028 September 1998 Amend 34 to License SNM-1168,authorizing Receipt,Rod Loading,Downloading,Assembly,Storage & Shipment of Enriched Processed U with Minimum Enrichment of 2.5 percent,U-235, Containing Pu & Other Transuranic Isotopes ML20217Q0021998-02-25025 February 1998 Amend 33 to License SNM-1168,authorizing Organizational & Administrative Changes,Including Changes in Chapter 4, Nuclear Criticality Safety. Condition S-1,also Amended ML20199F9381998-01-26026 January 1998 Amend 32 to License SNM-1168,revising License Condition SG-1.1,by Incorporating Revised Fundamental Nuclear Matl Control Plan ML20149G7521997-07-16016 July 1997 Amend 31 to License SNM-1168 for Framatome Cogema Fuels ML20141D3981997-06-24024 June 1997 Amend 29 to License SNM-1168 for B&W Fuel Company,Allowing Delay of Receipt Measurements & Distribution of Doe/Nrc Form 741 on Specified Matl ML20134D8331996-10-24024 October 1996 Amend 28 to License SNM-1168 for B&W Fuel Co,Adding Condition S-10 ML20058B4471993-11-17017 November 1993 Matls Licensing Package for Amend 15 to License SNM-1168 for B & W Fuel Co,Incorporating Revised Emergency Plan, ML20059E6881993-11-0101 November 1993 Amend 14 to License SNM-1168,revising SG-1.1 Re Licensee Shall Follow Chapters 1.0 Through 8.0 of Fnmc,Submitted Per 10CFR74.31(b) ML20128E2531993-02-0404 February 1993 Amend 10 to License SNM-1168,incorporating Changes Made to Radiological Contingency Plan ML20245A0031989-06-0909 June 1989 Addendum to Safeguards Amend 1 to License SNM-1168, Clarifying License Conditions 1999-09-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216J4631999-09-29029 September 1999 Amend 36 to License SNM-1168 for Framatome Cogema Fuels, Deleting License Condition S-4 ML20212A9211999-09-10010 September 1999 Application for Amend to License SNM-1168,to Delete Safety Condition S-4,as License Does Not Expire Until Sept 30,2000 & Pending Changes to 10CFR70 ML20198F0641998-12-0202 December 1998 Amend 35 to License SNM-1168 for Framatome Cogema Fuels ML20154G4051998-10-0505 October 1998 Application for Amend to License SNM-1168,reflecting Recent Organizational Changes at Lynchburg,Va Mfg Facility ML20154D5811998-09-28028 September 1998 Amend 34 to License SNM-1168,authorizing Receipt,Rod Loading,Downloading,Assembly,Storage & Shipment of Enriched Processed U with Minimum Enrichment of 2.5 percent,U-235, Containing Pu & Other Transuranic Isotopes ML20236F9441998-06-25025 June 1998 Application for Amend to License SNM-1168,revising Safety Condition S-9 to Be Consistent W/Section 1.4.11 of Chapter 1 of License Conditions.Deletion of Safety Conditon S-6, Requested,As Well ML20217Q0021998-02-25025 February 1998 Amend 33 to License SNM-1168,authorizing Organizational & Administrative Changes,Including Changes in Chapter 4, Nuclear Criticality Safety. Condition S-1,also Amended ML20199F9381998-01-26026 January 1998 Amend 32 to License SNM-1168,revising License Condition SG-1.1,by Incorporating Revised Fundamental Nuclear Matl Control Plan ML20149G7521997-07-16016 July 1997 Amend 31 to License SNM-1168 for Framatome Cogema Fuels ML20141D3981997-06-24024 June 1997 Amend 29 to License SNM-1168 for B&W Fuel Company,Allowing Delay of Receipt Measurements & Distribution of Doe/Nrc Form 741 on Specified Matl ML20134D8331996-10-24024 October 1996 Amend 28 to License SNM-1168 for B&W Fuel Co,Adding Condition S-10 ML20058B4471993-11-17017 November 1993 Matls Licensing Package for Amend 15 to License SNM-1168 for B & W Fuel Co,Incorporating Revised Emergency Plan, ML20059E6881993-11-0101 November 1993 Amend 14 to License SNM-1168,revising SG-1.1 Re Licensee Shall Follow Chapters 1.0 Through 8.0 of Fnmc,Submitted Per 10CFR74.31(b) ML20059F5781993-11-0101 November 1993 Application for Amend to License SNM-1168,authorizing Use & Possesion of 1 Uci of Standard Samples of Atomic Number 1-96 ML20056C3351993-05-0707 May 1993 Application for Amend to License SNM-1168,permiting Higher Education to Reduce Experience Requirements ML20128E2531993-02-0404 February 1993 Amend 10 to License SNM-1168,incorporating Changes Made to Radiological Contingency Plan ML20217C3351991-07-0202 July 1991 Application for Amend to License SNM-1168,to Authorize U Enrichment to Increase from 4.1% to 5.1%.Evaluation Supporting Proposed Increase Encl ML20058A9781990-10-24024 October 1990 Application for Amend to License SNM-1168,reflecting Organizational Changes ML20246D6111989-06-21021 June 1989 Application for Renewal of License SNM-1168 for 10-yr Period ML20245A0031989-06-0909 June 1989 Addendum to Safeguards Amend 1 to License SNM-1168, Clarifying License Conditions ML20246J8721989-04-27027 April 1989 Application for Amend to License SNM-1168,increasing beta-gamma Contamination on Protective Clothing Since Protective Clothing Cannot Be Effectively Smear Surveyed to Measure Removable Contamination ML20246L6831989-04-19019 April 1989 Application for Amend to License SNM-1168,authorizing Possession of 5 Ci Am-241,contained in One or More Sealed Sources.Fee Paid ML20248D6911989-03-16016 March 1989 Application for Amend to License SNM-1168,authorizing Possession of 2 Ci Am-241,contained in One or More Sealed Sources.Fee Paid ML20150D8031988-06-29029 June 1988 Revised Application for Amend to License SNM-1168 to Accommodate Temporary Shutdown in Fuel Fabrication Activities in Summer 1988.Attachment I of 880531 Application Modified ML20151R9991988-04-11011 April 1988 Application for Renewal of License SNM-1168 for 10-yr Period ML20149L5031988-02-16016 February 1988 Supplemental Application for Amend to License SNM-1201, Correcting Pages to 880210 Request,Concerning Increase in Allowed Enrichment from 4.05 to 4.1% ML20196A5801988-01-13013 January 1988 Application for Amend to License SNM-1168,changing Company Name as Result of New Business Arrangement.Fee Paid ML20235F7051987-06-0808 June 1987 Application for Amend to License SNM-1168,accommodating Changes Needed on Byproduct Possession Authorization.Fee Paid ML20205F1641987-03-17017 March 1987 Rev 1 to Page 72 to 870204 Application for Amend to License SNM-1168,addressing Soong Concerns Re Failed Fuel Rod Detection Sys ML20207T0561987-03-0606 March 1987 Application for Amend to License SNM-1168,authorizing Listed Exemptions for 870615-0831 Shutdown,Including Retraining of Radiation Workers & Monthly Audit of Plant Status Re Nuclear Radiological Safety.Fee Paid ML20212E7271987-02-0404 February 1987 Application for Amend to License SNM-1168,authorizing Organizational & Operational Changes.Withdrawal of 860210 & 0819 Requests for Amend to License Requested.Subj Amend Incorporates Changes from Previous Requests.Fee Paid ML20213D9591986-09-0909 September 1986 Supplemental Application for Amend to License SNM-1168, Authorizing Storage of U3O8 Drums Outside of Presently Authorized Containers.Page 40 of Section V,Originally Submitted on 860814,modified Re Monthly Visual Insp ML20212N1861986-08-14014 August 1986 Application for Amend to License SNM-1168,allowing Natural U3O8 Drums to Be Stored Outside Presently Authorized Freight Containers.Background Info on U Storage Area & Justification for Proposed Change Encl.Fee Paid ML20142A1691986-02-10010 February 1986 Application for Amend to License SNM-1168,accommodating Changes in Organizational Structure & Allowing Routine Localized Operations Involving Pellets Outside Controlled Area ML20128E7221985-05-28028 May 1985 Application for Amend to License SNM-1168,authorizing Changes Needed to Accommodate Storage of Unirradiated, Naturally Enriched U in Form of U-308.Fee Paid ML20125D0711985-05-0707 May 1985 Application for Amend to License SNM-1168,allowing Storage & Maint of Failed Fuel Rod Detection Sys Used at Reactor Sites 1999-09-29
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i ADDENDUM TO SAFEGUARDS AMENDMENT SG-1
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BABC0CK & WILCOX-COMMERCIAL NUCLEAR FUEL PLANT l o LICENSE NO. SNM-1168 I' L US/IAEA SAFEGUARDS AGREEMENT Fcr purposes of this license amendment, the Facility Attachment referenced in L.C. 3.1 shall be interpreted in accordance with the following: !
Facility Attachment Code 2.2 Substantive changes to the information provided in the B&W - CNFP Design _
Information Questionnaire (D1Q) means tt.ose changes requiring amendment of the .
Facility Attachment. Such changes shall be provided by letter to the NRC I Office of Nuclear Material Safety and Safeguards at least 70 days in advance !
of implementation. )
1 Non-substantive changes to the information provided in the DIQ means those changes not requiring amendment of the Facility Attachment. Such changes shall be provided by Concise Note (FORM DOE /NRC-740M) as part of the routine update of the DIQ. ,
The types of modifications with' respect to which information is required, !ll under 10 CFR 75.11, to be submitted in advance are those items stated in Code 2.2.
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- 1. "Any change in the purpose or type of the facility" means:
Any deviction from the described activities involving source or special nuclear material and any change to the maximum enrichment and/or quantities of U-235 currently authorized by License No. SNM-1168, and/or as described in Paragraph 5 of the Design Information Questionnaire (DIQ) dated l January 26, 1989, orasmodifiedinaccordancewith10CFR75.11(c).
Included also is any deviation from the described source and special nuclear i material (SNM) production activities described in Paragraph 6 of the DIQ j dated January 26, 1989, or as modified in accordance with 10 CFR 75.11(c). !
- 2. "Any change in the layout of the facility which affects the implementation of safeguards" means:
Any change in the existing facility and/or site layout or new addition )
affecting any activity involving source material or SNM as described in Paragraphs 10 and 11 of the DIQ dated January 26, 1989, 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 13 and 14 of the DIQ dated :
January 26, 1989, or as modified in accordance with 10 CFR 75.11(c). !
I 8906210031 890609 PDR ADOCK 07001201
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- 3. "Ary change that makes the selected KMP's (as described in Code 3.1.2) inadequate for the Agency's accounting purpose" means:
1 Any change to Key Measurement Points (KMP's) as described in Code 3.1.2 of the B&W-CNFP Facility Attachment to the US/IAEA Safeguards Agreement, or as modified in accordance with 10 CFR 75.11(c), that results in any KMP l alteration affecting the purpose of KMP's as stipulated by 10 CFR 75.4(m).
- 4. "Any change in the physical inventory procedures that would adversely affect the inventory taking for the Agency's accounting purposes" means:
Any datedchange January to26,the description 1989, dataincontained or as modified accordanceinwith Paragraph 34 of the DIQ ),
10 CFR 75.11(c that would not permit the Agency to conclude an SNM material balance for B&W-CNFP.
- 5. "Any change that adversely affects the accuracy of measurements at any KMP (as described in Code 3.1.2) by a factor of 2 or more" (as applied to the standarddeviation)means:
Any planned change in a measurement system that results in the estimates of the random hnd systematic errors being affected by a factor of 2 or more from the estimates listed in Table 36-2, " Relative Errors-Random and Systematic," referenced in Paragraph 36 of the DIQ dated January 26, 1989.
- 6. "Any change in the statistical procedures used to combine individual measurement error estimates to obtain limits of error for S/R differences and MUF" means:
Any deviation from (or modification of) the equations and/or calculations outlined in Paragraph 37 of the DIQ dated January 26, 1989, or as modified in accordance with 10 CFR 75.11(c).
- 7. Facility Attachment 3.1.2 KMP * - This is a KMP in which all S/R differences must be recorded and reported even if numerically zero. This means that the operator must record S/R differences and that the U.S. Government must calculate and report the S/R differences to the IAEA.
- 8. Facility Attachment Code 3.1.3
" Declared values of total element and total isotope for the items in each stratum" means:
The uranium and uranium-235 values assigned to nuclear material items at the time of the inventory cut-off. The assigned values may or may not be final, but shall be adequate for agency sampling plan calculations.
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- 9. Facility Attachment Code 3.4
" Measured discards as pertains to the 0.3 effective kilogram threshold established by the Agency for a six month period" means:
The total of liquid and gaseous effluents from the facility for a 6-month period.
- 10. Facility Attachment Code 4 With respect to advance notification requirements as they pertain to
-additions or deletions of material composition code, the licensee may add or delete composition codes for nuclear materials routinely processed and on inventory immediately upon telephone notification to the Office of Nuclear Material Safety and Safeguards. Follow-up documentation, in the form of a Concise Note, shall be submitted to the International Safeguards Branch, Division of Safeguards and Transportation, NMSS within three regular workdays of the telephone notification.
- 11. Facility Attachment Code 4.1 MeasureddiscardsshouldberecordedasanSN(Shipmenttonon-safeguarded facility) when shipped off-site to an authorized buriel ground. The IAEA systems will not process measured discards as LD's when they are shipped off-site.
- 12. Facility Attachment Code 4.1 (KMP-3)
With respect to uranium blending, measurement accuracy and precision estimates are not appropriate in the case of material category changes (i.e., natural uranium to the enriched uranium account) since uranium and uranium-235 measurements are not performed.
- 13. Facility Attachment Code 5.1.1 For inventory changes, time of recording, "upon" means: j No later than the next regular workday (Monday through Friday).
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- 14. Facility Attachment Code 6.2.2 For concise notes describing the anticipated operational programme,
" anticipated operational programme" means:
Anticipated physical inventory schedule.
For the Nuclear Regulatory Commission 0C Donald J. ,as n, Acting Chief Domestic Safeguards and Regional Oversight Branch Division of Safeguards f
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