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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20216J4711999-09-29029 September 1999 Safety Evaluation Rept Supporting Amend 36 to License SNM-1168 for Framatome Cogema Fuels ML20198F0811998-12-0202 December 1998 Safety Evaluation Supporting Amend 35 to License SNM-1168 ML20154D5901998-09-28028 September 1998 Safety Evaluation Supporting Amend 34 to License SNM-1168 ML20217Q0061998-02-25025 February 1998 Safety Evaluation Supporting Amend 33 to License SNM-1168 ML20199F9571998-01-26026 January 1998 Safeguards Evaluation Rept Supporting Amend 32 to License SNM-1168 ML20149G7671997-07-16016 July 1997 Safeguards Evaluation Rept Granting one-time Safeguards License Condition SG-1.3 ML20141D4041997-06-24024 June 1997 Safeguards Evaluation Rept Supporting Licensee 970507 Request for Delaying Receipt Measurements & Distribution of Doe/Nrc Form 741 ML20134D8381996-10-24024 October 1996 SER Granting Licensee Request for 2-month Delay in Submitting Updated Demonstration Section by Issuing New Safety Condition S-10 ML20058B4701993-11-17017 November 1993 Safety Evaluation Supporting Amend 15 to License SNM-1168 ML20059E7041993-11-0101 November 1993 Safeguards Evaluation Rept,Supporting 930930 Application for Amend to License SNM-1168,correcting Inconsistencies in Licensee Matl Control & Accountability Program Discovered During Insp Conducted on 930517-21 ML20128E2841993-02-0404 February 1993 SER Supporting 921211 & 930114 Applications for Amend to License SNM-1168,addressing Fire Fighting Methods in Radiological Contingency Plan Re Rearrangement of Fissile Matl ML20247P0831989-05-31031 May 1989 Safety Evaluation Accepting Licensee Request Re External Radiation Contamination Action Levels for Protective Clothing ML20246B1801989-04-28028 April 1989 SER Recommending Approval of 890419 Amend Application Re Increase of Am-241 Possession Limit ML20248K0971989-03-30030 March 1989 SER Recommending Approval of 890316 Application for Amend to License,Authorizing Possession of Am-241 in Form of Sealed Sources ML20235M5731989-02-17017 February 1989 SER Supporting 890722 Amend to License SNM-1168,revising Conditions 7.K,7.L,8.K & 8.L to Increase Possession Limits of Matl to 20 Ci in Addl Field Svc Operations Equipment ML20151F0161988-07-0808 July 1988 SER Supporting Amend 12 to SNM-1168 Re Plans to Shutdown Fuel Fabrication Activities from 880709 or 0809-0909 ML20151W2571988-04-22022 April 1988 Safety Evaluation Supporting Amend to License SNM-1168 ML20236B2951987-10-19019 October 1987 SER Consenting to B&W 870903 Request for Transfer of License SNM-1168 to B&W Fuel Co ML20235Z0271987-07-22022 July 1987 SER Supporting Issuance of Amend 9 to License SNM-1168 ML20206B1281987-04-0606 April 1987 Safety Evaluation Supporting Amend 8 to License SNM-1168 Re Mod to Radiation Protection Program During Shutdown of Fuel Fabrication Activities ML20127A1481985-06-12012 June 1985 Evaluation of 840911 Application to Amend License SNM-1168 Re Authorization to Modify Plant Activities & Functions Due to Removal of Pelletizing Operation.Issuance of Amend Recommended 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20216J4711999-09-29029 September 1999 Safety Evaluation Rept Supporting Amend 36 to License SNM-1168 for Framatome Cogema Fuels ML20198F0811998-12-0202 December 1998 Safety Evaluation Supporting Amend 35 to License SNM-1168 ML20154D5901998-09-28028 September 1998 Safety Evaluation Supporting Amend 34 to License SNM-1168 ML20249A2201998-06-10010 June 1998 SER Accepting Licensing TR BAW-10221P, NEMO-K,Kinetics Solution in Nemo ML20217Q0061998-02-25025 February 1998 Safety Evaluation Supporting Amend 33 to License SNM-1168 ML20199F9571998-01-26026 January 1998 Safeguards Evaluation Rept Supporting Amend 32 to License SNM-1168 ML20149G7671997-07-16016 July 1997 Safeguards Evaluation Rept Granting one-time Safeguards License Condition SG-1.3 ML20141D4041997-06-24024 June 1997 Safeguards Evaluation Rept Supporting Licensee 970507 Request for Delaying Receipt Measurements & Distribution of Doe/Nrc Form 741 ML20134D8381996-10-24024 October 1996 SER Granting Licensee Request for 2-month Delay in Submitting Updated Demonstration Section by Issuing New Safety Condition S-10 ML20058B4701993-11-17017 November 1993 Safety Evaluation Supporting Amend 15 to License SNM-1168 ML20059E7041993-11-0101 November 1993 Safeguards Evaluation Rept,Supporting 930930 Application for Amend to License SNM-1168,correcting Inconsistencies in Licensee Matl Control & Accountability Program Discovered During Insp Conducted on 930517-21 ML20128E2841993-02-0404 February 1993 SER Supporting 921211 & 930114 Applications for Amend to License SNM-1168,addressing Fire Fighting Methods in Radiological Contingency Plan Re Rearrangement of Fissile Matl ML20247P0831989-05-31031 May 1989 Safety Evaluation Accepting Licensee Request Re External Radiation Contamination Action Levels for Protective Clothing ML20246B1801989-04-28028 April 1989 SER Recommending Approval of 890419 Amend Application Re Increase of Am-241 Possession Limit ML20248K0971989-03-30030 March 1989 SER Recommending Approval of 890316 Application for Amend to License,Authorizing Possession of Am-241 in Form of Sealed Sources ML20235M5731989-02-17017 February 1989 SER Supporting 890722 Amend to License SNM-1168,revising Conditions 7.K,7.L,8.K & 8.L to Increase Possession Limits of Matl to 20 Ci in Addl Field Svc Operations Equipment ML20151F0161988-07-0808 July 1988 SER Supporting Amend 12 to SNM-1168 Re Plans to Shutdown Fuel Fabrication Activities from 880709 or 0809-0909 ML20151W2571988-04-22022 April 1988 Safety Evaluation Supporting Amend to License SNM-1168 ML20236B2951987-10-19019 October 1987 SER Consenting to B&W 870903 Request for Transfer of License SNM-1168 to B&W Fuel Co ML20235Z0271987-07-22022 July 1987 SER Supporting Issuance of Amend 9 to License SNM-1168 ML20206B1281987-04-0606 April 1987 Safety Evaluation Supporting Amend 8 to License SNM-1168 Re Mod to Radiation Protection Program During Shutdown of Fuel Fabrication Activities ML20127A1481985-06-12012 June 1985 Evaluation of 840911 Application to Amend License SNM-1168 Re Authorization to Modify Plant Activities & Functions Due to Removal of Pelletizing Operation.Issuance of Amend Recommended ML20198G7741978-02-15015 February 1978 Rev 2 to Decommissioning Plan for License SNM-1168 1999-09-29
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g 1 UNITED STATES lr E NUCLEAR REGULATORY COMMISSION f' WASHINGTON, D.C. 20555 4001
%***,+# September 28, 1998' l DOCKET: 70-1201 LICENSEE: Framateme Cogema Fuels (Framatome)
Lynchburg Manufacturing Facility Lynchburg, Virginia
SUBJECT:
3AFETY EVALUATION REPORT: APPLICATION DATED JUNE 25,1998, REQUEST TO REVISE SAFETY CONDITION S-9 l i BACKGROUND ,
By application dated June 25,1998, and letters dated August 14, and September 14,1998, the ]
licensee requested Materials License SNM-1168 be amended to change Safety Condition S-9 l and Section 1.4.11 to allow the receipt, rod loading, downloading, assembly, storage, and shipment of processed uranium containing plutonium and other transuranic isotopes up to 50 i bequerels (Bq) per gram of uranium. In addition, the licensee requested the deletion of Safety _
Condition S-6 and correction of minor editorial and typographical errors found in the license.
DISCUSSION The modifications proposed by Framatome are as follows: ;
- 1. Change Safety Condition S-9 and Section 1.4.11 of the license application to allow the receipt, rod loading, downloading, assembly, storage, and shipment of enriched processed uranium containing plutonium and other transuranic isotopes up to 50 Bq per gram of uranium. This material will only be used for loading Tennessee Valley Authority (TVA) fuel assemblies, and the licensee will ensure that WA obtains all necessary NRC approvals prior to shipping the processed fuel to WA reactor sites.
I Framatome is currently limited to 3.3 Bq of alpha activity from plutonium and neptunium per gram of uranium. This value was taken from Section 4," Safety, Health, and Criticality Requirements," of ASTM C996-90," Standard Specnications of Uranium Hexafluoride Enriched to Less than 5% 23sU." The staff has determined that loading and using the pellets containing up to 50 Bq per gram of plutonium and other transuranic isotopes willincrease the specific activity of the pellets by less than 0.1 percent and accordingly have no significant impact on the radiation dose to workers or the public and is acceptable.
l In addition, in order to ensure that Framatome's use of processed uranium does not l meet the definition of production facility in 10 CFR 50.2, the staff is requiring that the enrichment of the processed uranium be at least 2.5 percent U-235.
9810070270 990928 PDR ADOCK 07001201 C PDR _
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- 2. Delete Safety Condition S-6, which states:
l -S-6. The incumbent, Manager, Fuel Manufacturing, identified in the amendment l application dated September 25,1991, is deemed to satisfy the education l
l requirements for the position because of the incumbent's experience in the 1 l position since 1985 and his nuclear plant experience since 1970.
l Because the new Manager, Fuel Manufacturing satisfies the education and experience requirements set forth in Section 2.1.2 of the license application, Safety Condition S-6 is no longer necessary. This is an administrative change and is acceptable. ,
- 3. Correct minor editorial and typographical errors throughout the license application to 1 improve consistency. The modifications were the following: (1) in the Table of
{
Contents, changed revision and date of Chapter 1 to Revision 16 dated June 25,1998, '
and changed the last page for Chapter 11 from 11-32 to 11-21 (typographical error);
- l. (2) in Section 1.2, changed Babcock and Wilcox NNFD and Nuclear Technology Center to BWX Technology; and (3) in Section 1.7.1, changed 20.1904(e) to 20.1904(:)
(typographical error). These are administrative changes and are acceptable.
ENVIRONMENTAL REVIEW
- This amendment constitutes a change in process operations that meet the following provisions
1 (i) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, (ii) there is no significant increase in individual or cumulative occupational radiation l exposure, (iii) there is no significant construction impact, (iv) there is no significant increase in the potential for or consequences from radiological accidents.
Therefore, in accordance with 10 CFR 51.22(c)(11), neither an environmental assessment nor an environmental impact statement is warranted for the proposed action.
CONCLUSIOfJ/ RECOMMENDATION The staff concludes that the amendment meets the requirements of 10 CFR Part 20 and can be issued without undue risk to workers, the public, or the environment. Therefore, approval of the amendment is recommended.
The Region ll Principal Inspector has no objection to this proposed action.
Princioal Contributors:
i Harry Felsher
- Michael Lamastra g M p,tch 9/,//9/
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