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| {{#Wiki_filter:_ _ _ _ _ _ ____- - -_-_-___. _ _____-_ . _ _ _ _ . | | {{#Wiki_filter:_ _ _ _ _ _ ____- - -_-_-___. _ _____-_. |
| $. July 20, 1998 e o Mr. vV. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250
| | July 20, 1998 e |
| | o Mr. vV. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REVISION 11 OF THE RENEWAL APPLICATION -INCIDENT REPORTING - | | REVISION 11 OF THE RENEWAL APPLICATION -INCIDENT REPORTING - |
| (TAC NO. L31068) i I | | (TAC NO. L31068) i I |
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| ==Dear Mr. Goodwin:== | | ==Dear Mr. Goodwin:== |
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| This refers to your application (document NRC-98-012) dated April 3,1998, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Co!umbia, South Carolina, Fuel Fabrication Facility. | | This refers to your application (document NRC-98-012) dated April 3,1998, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Co!umbia, South Carolina, Fuel Fabrication Facility. |
| Our review of your application has identified addition information that is needed before final action can be taken on your request. The additionalinformation, specified in the enclosure, i should be provided within 45 days of the date of this letter. Please reference the above TAC No. In future correspondence related to this request. | | Our review of your application has identified addition information that is needed before final action can be taken on your request. The additionalinformation, specified in the enclosure, i |
| | should be provided within 45 days of the date of this letter. Please reference the above TAC No. In future correspondence related to this request. |
| If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV. | | If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV. |
| Sincerely, Original signed by: HFelsher for l Charles E. Gaskin, Project Manager Section 1 Licensing Branch Division of Fuel Cycle Safety , | | Sincerely, Original signed by: |
| and Safeguards, NMSS I | | HFelsher for l |
| f/5 i nse SN - 107 PY II N.UR OITV a wu a u.a w uu x _a %nn e | | Charles E. Gaskin, Project Manager Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS I |
| | f/5 i nse SN - 107 PY II N.UR OITV a wu a u.a w uu x _a %nn e |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated DISTRIBUTION with encl. (Control No. 820S) | | As stated DISTRIBUTION with encl. (Control No. 820S) |
| Docket 70-1151 PUBLIC NRC File Center Region 11 DAyres, Ril FCLB R/F FCSS R/F NMSS R/F SChotoo | | Docket 70-1151 PUBLIC NRC File Center Region 11 DAyres, Ril FCLB R/F FCSS R/F NMSS R/F SChotoo |
| 'G:\WO403RAl.98)
| | 'G:\\WO403RAl.98) |
| * See Previous Concurrence OFC FCLB E FCLB E FCLB E FCLB C NAME CGaskin | | * See Previous Concurrence OFC FCLB E |
| | FCLB E FCLB E FCLB C |
| | MAdak NAME CGaskin |
| * PShea | | * PShea |
| * HFelsher | | * HFelsher * |
| * MAdak | | ( |
| ( DATE 07/ 06/98 07/07/98 07/ 07/98 07N/98 | | DATE 07/ 06/98 07/07/98 07/ 07/98 07N/98 l |
| ~'
| | C = COVER E = COVER & ENCLOSURE N = NO COPY |
| l C = COVER E = COVER & ENCLOSURE N = NO COPY 9807310326 900720 ~'' "- 'AL RECORD COPY PDR ADOCK 07001151 l C PDR t__-___
| | ~' |
| | ~'' |
| | 9807310326 900720 |
| | "- 'AL RECORD COPY PDR ADOCK 07001151 l |
| | C PDR t__-___ |
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| e | | e p erg, t |
| ., p erg,
| | UNITED STATES |
| * t UNITED STATES
| |
| [ | | [ |
| j NUCLEAR REGULATORY COMMISSION WA8mNGToN, D.c. 20665 0001 f* July 20,1998 Mr. W. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250 | | j NUCLEAR REGULATORY COMMISSION WA8mNGToN, D.c. 20665 0001 f* |
| | July 20,1998 Mr. W. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==Dear Mr. Goodwin:== | | ==Dear Mr. Goodwin:== |
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| |
| This refers to your application (document N9C-98-012) dated April 3, ' 098, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina, Fuel Fabrication Facility. | | This refers to your application (document N9C-98-012) dated April 3, ' 098, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina, Fuel Fabrication Facility. |
| Our review of your application has identified addition information that is needed before final action can be taken on your request. The additional information, specified in the enclosure, should be provided within 45 days of the date of this letter. Please ieference the above TAC No. in future correspondence related to this request. | | Our review of your application has identified addition information that is needed before final action can be taken on your request. The additional information, specified in the enclosure, should be provided within 45 days of the date of this letter. Please ieference the above TAC No. in future correspondence related to this request. |
| If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV. | | If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV. |
| Sincerely, Charles E. Gaskin, e Manager Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-1151 License SNM-1107 | | Sincerely, Charles E. Gaskin, e Manager Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-1151 License SNM-1107 |
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| ==Enclosure:== | | ==Enclosure:== |
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| 9 a | | 9 a |
| .e-e Request for Additional Information Application Dated April 3,1998 Westinghouse Commercial Fuel Fabrication Facility Docket 70-1151 Please provide the following information:
| | .e-e Request for Additional Information Application Dated April 3,1998 Westinghouse Commercial Fuel Fabrication Facility Docket 70-1151 Please provide the following information: |
| : 1. On page 1.12, the definition of "Significant Removable Contamination" differs significantly from the reporting requirements in 10 CFR 70.50(b)(3) which uses the term
| | 1. |
| " spreadable radioactive contamination." Your proposed radiation level is well above normal levels for release from controlled areas and exceeds the DOT limit for transporting of surface-contaminated objects. Finally, it is questionable whether or not these limits should be in the license application. (There was no scan area specified.) In this case, the Amendment Application should be modified to comply with 10 CFR 70.50(b)(3).
| | On page 1.12, the definition of "Significant Removable Contamination" differs significantly from the reporting requirements in 10 CFR 70.50(b)(3) which uses the term |
| : 2. The entire Chapter 3 is still numbered as Revision 10 instead of Revision 11.
| | " spreadable radioactive contamination." Your proposed radiation level is well above normal levels for release from controlled areas and exceeds the DOT limit for transporting of surface-contaminated objects. Finally, it is questionable whether or not these limits should be in the license application. (There was no scan area specified.) In this case, the Amendment Application should be modified to comply with 10 CFR 70.50(b)(3). |
| : 3. On page 3.18, Section 3.7.3 indicates that decisions will be made whenever the cognizant regulatory function engineer arrives at the site. How is safety assured until that person arrives onsite and how long should the onsite personnel wait before declaring that the incident " clock" has started? Further the qualified emergency coordinator should be sufficiently trained in all procedures to make " event" decisions.
| | 2. |
| | The entire Chapter 3 is still numbered as Revision 10 instead of Revision 11. |
| | 3. |
| | On page 3.18, Section 3.7.3 indicates that decisions will be made whenever the cognizant regulatory function engineer arrives at the site. How is safety assured until that person arrives onsite and how long should the onsite personnel wait before declaring that the incident " clock" has started? Further the qualified emergency coordinator should be sufficiently trained in all procedures to make " event" decisions. |
| Indeed, that person should perform the duties of a cognizant regulatory function engineer within the operating parameters of the specific procedures. | | Indeed, that person should perform the duties of a cognizant regulatory function engineer within the operating parameters of the specific procedures. |
| : 4. On page 3.20 there is a commitment for an informal notification. Informal notifications are not part of the license and should also be removed from your submittal.
| | 4. |
| : 5. On page 3.19, clarify Section 3.7.3 (c.4) regarding what is damaged and/or breached.
| | On page 3.20 there is a commitment for an informal notification. Informal notifications are not part of the license and should also be removed from your submittal. |
| | 5. |
| | On page 3.19, clarify Section 3.7.3 (c.4) regarding what is damaged and/or breached. |
| The License Application should be modified to comply with 10 CFR 70.50(b)(4). | | The License Application should be modified to comply with 10 CFR 70.50(b)(4). |
| : 6. Revision 10 also modifies pages in Chapter 3. These pages need to be addressed in the changes to the License Application in Revision 10 or Revision 11.
| | 6. |
| | Revision 10 also modifies pages in Chapter 3. These pages need to be addressed in the changes to the License Application in Revision 10 or Revision 11. |
| ENCLOSURE l________________________________________._____.}} | | ENCLOSURE l________________________________________._____.}} |
Letter Sequence RAI |
|---|
|
|
MONTHYEARML20236V1421998-07-20020 July 1998
Forwards RAI Which Has to Be Completed Before Final Action Can Be Taken on Request for Amend to Matls License SNM-1107 for Chapters 1.0 & 3.0 of Application for Renewal for SNM License
Project stage: RAI
ML20154D7781998-09-30030 September 1998
Responds to 980720 RAI Re Rev 11 of Renewal Application.Encl Details Answers to Six Questions Raised by NRC Staff
Project stage: Other
ML20154S6581998-10-21021 October 1998
Forwards Changes to Proposed Rev 11.0 of Pages IV & Chapters 1.0 & 3.0 for Application for Renewal of Special Nuclear Matls License for Commercial Nuclear Fuel Div at Columbia, Sc Fuel Fabrication Facility
Project stage: Request
ML20155E8321998-10-30030 October 1998
Application for Renewal of License SNM-1107,changing Proposed Rev 11.0 of Chapter 3.0 for Commercial Nuclear Fuel Div at Columbia
Project stage: Request
ML20198E8291998-12-17017 December 1998
Forwards Amend 16 to License SNM-1107,revising Pages 3.18 Through 3.20 of License Application.Safety Condition S-1 Revised to Include Dates of 980403,1021 & 30.SER Including Categorical Exclusion Determination Encl
Project stage: Other
1998-12-17
[Table View] |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J1721999-10-13013 October 1999
Forwards Insp Rept 70-1151/99-05 on 990920-21.No Violations Noted
ML20216J7131999-10-0202 October 1999
Forwards Response to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness Programs
ML20216J5321999-09-28028 September 1999
Ack Receipt of ,Which Transmitted Application for Amend to License SNM-1107 Re Rev 30 to Fnmc Plan.Staff Has Completed Acceptance Review & No Administrative Omissions or Deficiencies Were Identified
ML20212G4171999-09-24024 September 1999
Informs That NRC Has Completed Acceptance Review of License Amend Application & Have Identified No Administrative Omissions or Deficiencies.Nrc Anticipates Completing Technical Review by End of Dec 1999
ML20212G3351999-09-24024 September 1999
Informs That NRC Has Completed Initial Review of License Annex Submitted for Adu Pelleting Sys,Rev 1 with No Administrative Omissions or Deficiencies Identified. Submittal Has Been Assigned TAC L31240
ML20212G4221999-09-24024 September 1999
Informs That NRC Has Completed Initial Review of License Annex Submittal for Storage of U Bearing Metals with No Administrative Omissions or Deficiencies Identified.Nrc Anticipates Completing Technical Review by 991029
ML20216G0581999-09-20020 September 1999
Forwards Proprietary Rev 30 Proposed Changes to 10CFR74 Fundamental Nuclear Matl Control Plan for Columbia Fuel Fabrication Facility. Explanation of Changes Incorporated within Revised Plan,Included.Proprietary Encl Withheld
ML20217C7171999-09-15015 September 1999
Ack Receipt of W ,Transmitting Rev 27 to W Physical Security Plan.Nrc Review of Rev Has Found It to Be Acceptable for Inclusion Into Plan.Encl Withheld,Per 10CFR2.790
ML20217M2361999-08-31031 August 1999
Forwards Description of Complete Scenario,Controller Assignments,Simulation Data & Messages That Will Be Used for 990921 Full Scale Emergency Exercise
ML20211K8071999-08-31031 August 1999
Forwards Rev 1 to Criticality Safety Evaluation (Cse) License Annex Pelleting, Replacing Adu Pelleting Cse Summary Previously Submitted on 960628
ML20211J1871999-08-27027 August 1999
Submits Proposed Rev 16.0 of Page V & Pages from Chapters 1.0,2.0,3.0,10.0 & 11.0 of Application for Renewal of License SNM-1107.Changes Are Identified by Marginal Lines
ML20211J8611999-08-27027 August 1999
Informs That Listed Rept Fulfills Regulatory Requirements as Listed in 10CFR70.59 Effluent Monitoring Requirements, for six-month Period Jan-June 1999.Detailed Summary Rept by Stack Is Provided as Attachment a
ML20210R4401999-08-0303 August 1999
Ack Receipt of NRC Ltr & Insp Rept Dtd 990611,pertaining to Insp of Facility Preparedness & Radiation Protection Programs by a Gooden on 990510-0514
ML20210L6091999-07-29029 July 1999
Responds to Providing Update to Site Emergency Plan Emergency Procedure A-01 (Rev 3).No Amend to License Necessary,Since No Change to Plan Was Made
ML20210F4601999-07-22022 July 1999
Forwards Insp Rept 70-1151/99-201 on 990628-0702.No Violations Noted
ML20209J4131999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for URRS Waste Treatment Sys,Transmitted by .Anticipates Completion of Review by 990830
ML20209H6131999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Adu Conversion Sys (Rev 1),trasmitted by .Staff Has Completed Initial Review with No Administrative Omissions or Deficiencies Identified
ML20209J3881999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Scrap U Recovery Processing Sys,Transmitted by . Anticipates Completion of Review by 990830
ML20209J4031999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Solvent Extraction Sys,Transmitted by .Anticipates Completion of Review by 990830
ML20210A0021999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Adu Bulk Powder Bldg Sys (Rev 1),transmitted by . Anticipates Completion of Review by 990830
ML20209J3781999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Un Bulk Storage Sys,Rev 1,transmitted by .Anticipates Completion of Review by 990830
ML20209D5311999-07-0909 July 1999
Provides Ack Ltr Which Closes Out TAC L31180,which Was Rev 2 of License Annex Submittal for Plant Ventilation Sys
ML20209C9201999-07-0808 July 1999
Forwards Response to NRC GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness Programs
ML20209E0121999-07-0606 July 1999
Ack Receipt of License Annex Submittal for Chemicals Receipt,Handling & Storage Sys at W Plant Transmitted by Ltr Dtd 990430.NRC Has Completed Initial Review of License Annex with No Adminstrative Omissions or Deficiencies Identified
ML20209C2421999-06-30030 June 1999
Forwards Rev 0 to Cse License Annex,Solvent Extraction Re Commitment to Submit Upgraded Csa/Cse Summaries in Format of License Annex
ML20209C0251999-06-29029 June 1999
Ack Receipt of License Annex Submittal for Rev 1 to Hood & Containment Sys,Transmitted by .Initial Review of Submittal Has Been Completed & Staff Anticipates Completing Review of Annexes by 990830.Ltr Closes Out TAC L31164
ML20209E3661999-06-25025 June 1999
Ack Receipt of NRC Ltr & Insp Rept 70-1151/99-03,dtd 990611. Insp Was Conducted on 990510-14 on Facility Emergency Response & Radiation Protection Programs
ML20196H2601999-06-18018 June 1999
Forwards Rev 3 to Site Emergency Administrative Procedure A-01, Emergency Response Organization, in Accordance with Provisions of 10CFR70.32(i)
ML20196A3841999-06-11011 June 1999
Forwards Insp Rept 70-1151/99-03 on 990510-14.No Violations Noted.Conduct of Activities at Facility Was Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices
ML20196K5701999-06-0303 June 1999
Submits Intent to Change License Annex for Columbia Plant Ventilation Sys
ML20206S6981999-05-14014 May 1999
Forwards Rev 1 to Cse License Annex Hoods & Containments. Submittal Is Upgrade to Replace the Criticality Safety Evaluation Summary Submitted on 990228
ML20206L5271999-05-10010 May 1999
Forwards Proprietary Insp Rept 70-1151/99-202 on 990419-23. No Violations Noted.Details of Insp Rept Withheld,Per 10CFR2.790(d)
ML20206S9491999-05-0606 May 1999
Forwards One NRC Form 327, Special Nuclear Matl (SNM) Physical Inventory Summary Rept, for Matl Balance Period Ending 990407 at Columbia Fuel Fabrication Facility (Cfff). Final Values for Items 1-9 Included
ML20206S8911999-05-0606 May 1999
Informs That Wl Goodwin Has Reviewed Encl Special Nuclear Matl Inventory Rept & Concurs with Authorizing Signature of RA Williams
ML20206R3091999-05-0505 May 1999
Ack Receipt of NRC Ltr & Insp Rept 70-1151/99-02 Dtd 990429, Pertaining to Insp of Facility Fire Safety Program on 990405-08
ML20206H4221999-05-0404 May 1999
Forwards Amend 19 to License SNM-1107,incorporating Revised Fundamental Nuclear Matl Control Plan & Safeguards Evaluation Rept,Which Includes Revs of 981201 & 990302 to Read as Listed
ML20206P3971999-04-29029 April 1999
Forwards Insp Rept 70-1151/99-02 on 990405-08.No Violations Noted
ML20206B2631999-04-22022 April 1999
Ack Receipt of Which Transmitted License Annex Re LLRW Processing Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Subject Info by 990630
ML20206B2531999-04-22022 April 1999
Ack Receipt of Which Transmitted Revised License Annex for Plant Ventilation Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Previous License Annexes by 990630
ML20205S9321999-04-14014 April 1999
Submits Comments on RAI for Emergency Response Technical Manual Supplements.Licensee Is Confident That NRC Will Concur That Info in Environ Evaluation Rept & in Licensee Annex Provides Sufficient Detail for Intent of Supplements
ML20205H2481999-03-31031 March 1999
Forwards Rev 0 to Cse License Annex LLRW Processing Sys, Which Covers low-level Radwaste Processing Sys
ML20205M4091999-03-18018 March 1999
Ack Receipt of License Annex Submittal for Adu Pelleting Sys at Plant Transmitted by Ltr
ML20205M4191999-03-18018 March 1999
Ack Receipt of License Annex Submittal for Hoods & Containment Sys at Plant Transmitted by Ltr
ML20205A3921999-03-15015 March 1999
Ack Receipt of 990129 Response to NOV Issued on 981231 Re Activities Conducted at Columbia Nuclear Fuel Plant. Response Meets Requirements of 10CFR2.201
ML20207J7671999-03-0404 March 1999
Forwards Amend 17 to License SNM-1107 & Ser.Amend Changes Pages V & 1.4 of License Application to Rev 15.0.Safety Condition S-1 Has Been Revised to Include Date of 990212 & License Conditions 6E,7E & 8E Have Been Added as Listed
ML20207E5961999-03-0202 March 1999
Forwards Proprietary Rev 29 to Fundamental Nuclear Matl Control Plan, for Commercial Nuclear Fuel Division Fuel Mfg Plant in Columbia,Sc.Rev Includes Addl Info Re Determination of Nominal %U for UF6 Receipts.Proprietary Info Withheld
ML20204E7481999-03-0202 March 1999
Ack Receipt of NRC Insp Rept 70-1151/99-01 Re Insp of Facility Operational Safety & Environ Programs
ML20204E0001999-03-0101 March 1999
Forwards Certificate of Compliance 6400,rev 25 for Model 6400 Package,As Requested in 980928 Application
ML20207B0251999-02-28028 February 1999
Forwards Rev 0 to Criticality Safety Evaluation License Annex Hoods & Containments. Tenth Such Submittal Presented in Format of License Annex
ML20207D3601999-02-26026 February 1999
Forwards Insp Rept 70-1151/99-01 on 990201-05 at Columbia Nuclear Fuel Plant.No Violations or Deviations Were Cited
1999-09-28
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J1721999-10-13013 October 1999
Forwards Insp Rept 70-1151/99-05 on 990920-21.No Violations Noted
ML20216J5321999-09-28028 September 1999
Ack Receipt of ,Which Transmitted Application for Amend to License SNM-1107 Re Rev 30 to Fnmc Plan.Staff Has Completed Acceptance Review & No Administrative Omissions or Deficiencies Were Identified
ML20212G4221999-09-24024 September 1999
Informs That NRC Has Completed Initial Review of License Annex Submittal for Storage of U Bearing Metals with No Administrative Omissions or Deficiencies Identified.Nrc Anticipates Completing Technical Review by 991029
ML20212G4171999-09-24024 September 1999
Informs That NRC Has Completed Acceptance Review of License Amend Application & Have Identified No Administrative Omissions or Deficiencies.Nrc Anticipates Completing Technical Review by End of Dec 1999
ML20212G3351999-09-24024 September 1999
Informs That NRC Has Completed Initial Review of License Annex Submitted for Adu Pelleting Sys,Rev 1 with No Administrative Omissions or Deficiencies Identified. Submittal Has Been Assigned TAC L31240
ML20217C7171999-09-15015 September 1999
Ack Receipt of W ,Transmitting Rev 27 to W Physical Security Plan.Nrc Review of Rev Has Found It to Be Acceptable for Inclusion Into Plan.Encl Withheld,Per 10CFR2.790
ML20210L6091999-07-29029 July 1999
Responds to Providing Update to Site Emergency Plan Emergency Procedure A-01 (Rev 3).No Amend to License Necessary,Since No Change to Plan Was Made
ML20210F4601999-07-22022 July 1999
Forwards Insp Rept 70-1151/99-201 on 990628-0702.No Violations Noted
ML20210A0021999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Adu Bulk Powder Bldg Sys (Rev 1),transmitted by . Anticipates Completion of Review by 990830
ML20209J4131999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for URRS Waste Treatment Sys,Transmitted by .Anticipates Completion of Review by 990830
ML20209J4031999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Solvent Extraction Sys,Transmitted by .Anticipates Completion of Review by 990830
ML20209J3881999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Scrap U Recovery Processing Sys,Transmitted by . Anticipates Completion of Review by 990830
ML20209J3781999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Un Bulk Storage Sys,Rev 1,transmitted by .Anticipates Completion of Review by 990830
ML20209H6131999-07-16016 July 1999
Ack Receipt of Revised License Annex Submittal for Adu Conversion Sys (Rev 1),trasmitted by .Staff Has Completed Initial Review with No Administrative Omissions or Deficiencies Identified
ML20209D5311999-07-0909 July 1999
Provides Ack Ltr Which Closes Out TAC L31180,which Was Rev 2 of License Annex Submittal for Plant Ventilation Sys
ML20209E0121999-07-0606 July 1999
Ack Receipt of License Annex Submittal for Chemicals Receipt,Handling & Storage Sys at W Plant Transmitted by Ltr Dtd 990430.NRC Has Completed Initial Review of License Annex with No Adminstrative Omissions or Deficiencies Identified
ML20209C0251999-06-29029 June 1999
Ack Receipt of License Annex Submittal for Rev 1 to Hood & Containment Sys,Transmitted by .Initial Review of Submittal Has Been Completed & Staff Anticipates Completing Review of Annexes by 990830.Ltr Closes Out TAC L31164
ML20196A3841999-06-11011 June 1999
Forwards Insp Rept 70-1151/99-03 on 990510-14.No Violations Noted.Conduct of Activities at Facility Was Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices
ML20206L5271999-05-10010 May 1999
Forwards Proprietary Insp Rept 70-1151/99-202 on 990419-23. No Violations Noted.Details of Insp Rept Withheld,Per 10CFR2.790(d)
ML20206H4221999-05-0404 May 1999
Forwards Amend 19 to License SNM-1107,incorporating Revised Fundamental Nuclear Matl Control Plan & Safeguards Evaluation Rept,Which Includes Revs of 981201 & 990302 to Read as Listed
ML20206P3971999-04-29029 April 1999
Forwards Insp Rept 70-1151/99-02 on 990405-08.No Violations Noted
ML20206B2631999-04-22022 April 1999
Ack Receipt of Which Transmitted License Annex Re LLRW Processing Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Subject Info by 990630
ML20206B2531999-04-22022 April 1999
Ack Receipt of Which Transmitted Revised License Annex for Plant Ventilation Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Previous License Annexes by 990630
ML20205M4191999-03-18018 March 1999
Ack Receipt of License Annex Submittal for Hoods & Containment Sys at Plant Transmitted by Ltr
ML20205M4091999-03-18018 March 1999
Ack Receipt of License Annex Submittal for Adu Pelleting Sys at Plant Transmitted by Ltr
ML20205A3921999-03-15015 March 1999
Ack Receipt of 990129 Response to NOV Issued on 981231 Re Activities Conducted at Columbia Nuclear Fuel Plant. Response Meets Requirements of 10CFR2.201
ML20207J7671999-03-0404 March 1999
Forwards Amend 17 to License SNM-1107 & Ser.Amend Changes Pages V & 1.4 of License Application to Rev 15.0.Safety Condition S-1 Has Been Revised to Include Date of 990212 & License Conditions 6E,7E & 8E Have Been Added as Listed
ML20204E0001999-03-0101 March 1999
Forwards Certificate of Compliance 6400,rev 25 for Model 6400 Package,As Requested in 980928 Application
ML20207J8101999-02-26026 February 1999
Informs That NRC Has Received License Submittal for Adu Bulk Powder Blending Sys at Plant Transmitted by Ltr Dtd 981231.Submittal Has Been Assigned TAC Number L31155
ML20207D3601999-02-26026 February 1999
Forwards Insp Rept 70-1151/99-01 on 990201-05 at Columbia Nuclear Fuel Plant.No Violations or Deviations Were Cited
ML20207J8871999-02-22022 February 1999
Requests That Info Re Nuclear Fuel Mfg Process Descriptions & Corresponding Nuclear Safety Analyses Conducted for W Columbia,Sc,Plant Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4)
ML20199E0441999-01-0404 January 1999
Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool
ML20199F2281998-12-31031 December 1998
Forwards Insp Rept 70-1151/98-10 on 981207-11 & NOV Re Failure to Ensure Physical Condition of Radioactive Matl Shipping Containers & Failure to Follow Operating Procedures
ML20199E0161998-12-31031 December 1998
Responds to Ltrs & 30,with Attached Affidavit ,requesting That Info Re Nuclear Fuel Manufacturing Process Descriptions & Corresponding Nuclear Safety Analyses Conducted for W,Columbia,Sc Plant,Be Withheld
ML20198M8511998-12-18018 December 1998
Ack Receipt of License Annex Submittal for URRS Dissolver Sys,Dtd 981030.Initial Review of License Annex Has Been Completed with No Administrative Omissions.Projection of Technical Review Schedule Will Be Provided
ML20198E8291998-12-17017 December 1998
Forwards Amend 16 to License SNM-1107,revising Pages 3.18 Through 3.20 of License Application.Safety Condition S-1 Revised to Include Dates of 980403,1021 & 30.SER Including Categorical Exclusion Determination Encl
ML20198A8341998-12-0303 December 1998
Forwards Insp Rept 70-1151/98-09 on 981109-13.No Violations Noted.Purpose of Insp Was to Determine Whether Activities Authorized by License Were Conducted Safely & in Accordance with NRC Requirements
ML20196B0421998-11-23023 November 1998
Informs That NRC Has Received License Annex Submittals for Several Operating Sys at W Plant.List of Submittals NRC Has Received,Dates of Documents & Assigned TAC Numbers,Listed. TAC Numbers Should Be Used on Associated Correspondence
ML20195J1831998-11-18018 November 1998
Forwards Partially Withheld Insp Rept 70-1151/98-205 on 981019-23.Violations Noted.Rept Details Withheld (Ref 10CFR2.790)
ML20195B9681998-11-12012 November 1998
Responds to & Affidavit ,requesting That Info Concerning Nuclear Fuel Manufacturing Process Be Withheld Per 10CFR2.790(b)(4).Determined That Info Sought to Be Withheld Contains Proprietay Info & Will Be Withheld
ML20195B7701998-10-29029 October 1998
Requests Addl Info on 980331 Application for Amend to License SNM-1107 for Changes to Chapters 3.0 & 6.0 Re Criticality Safety.Addl Info Needed Specified in Encl
ML20155A9431998-10-13013 October 1998
Forwards Insp Rept 70-1151/98-07 on 980921-25.No Violations Noted
ML20155C4821998-10-0707 October 1998
Forwards Amend 15 to License SNM-1107,revising Chapters 1,2, 3,4,5 & 8 & Revising Safety Conditions S-1 & S-2.Safety Evaluation Rept,Including Categorical Exclusion Determination,Encl
ML20154D4921998-09-25025 September 1998
Responds to Requesting Certain Info Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4).Not All of Six Reasons Apply to Subject Document.Licensee Has Thirty Days from Date of Ltr to Submit Properly Marked Document
ML20153C4751998-09-18018 September 1998
Ack Receipt of Licensee Response to Violations Noted in Insp Rept 70-1151/98-203.Staff Determined That Corrective Actions Meet Requirements of 10CFR2.201 & Implementation of Corrective Actions Will Be Reviewed During Future Insps
ML20153F1101998-09-0909 September 1998
Ack Receipt of Transmitting Rev 26 to Physical Security Plan,Reflecting Current Organization Names & Documenting W Annual Review of Security Program.Rev Acceptable for Inclusion Into Plan
ML20151T0621998-08-26026 August 1998
Forwards Insp Rept 70-1151/98-06 on 980803-07 & Notice of Violation.Violation Involved Three Individuals,Not Adequately Instructed in General Safety Info Required by 10CFR19.12
ML20151S9101998-08-21021 August 1998
Ack Receipt of Transmitting Rev 25 to Physical Security Plan.Rev Has Been Found to Be Acceptable
ML20239A4051998-08-21021 August 1998
Forwards Insp Rept 70-1151/98-05 on 980727-31.No Violations Noted.Purpose of Insp,To Determine Whether Activities Authorized by License Conducted Safely & in Accordance W/Nrc Requirements
ML20237D7941998-08-21021 August 1998
Forwards Insp Rept 70-1151/98-204 on 980810-13.No Violations Noted
1999-09-28
[Table view] |
Text
_ _ _ _ _ _ ____- - -_-_-___. _ _____-_.
July 20, 1998 e
o Mr. vV. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250
SUBJECT:
REVISION 11 OF THE RENEWAL APPLICATION -INCIDENT REPORTING -
(TAC NO. L31068) i I
Dear Mr. Goodwin:
This refers to your application (document NRC-98-012) dated April 3,1998, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Co!umbia, South Carolina, Fuel Fabrication Facility.
Our review of your application has identified addition information that is needed before final action can be taken on your request. The additionalinformation, specified in the enclosure, i
should be provided within 45 days of the date of this letter. Please reference the above TAC No. In future correspondence related to this request.
If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV.
Sincerely, Original signed by:
HFelsher for l
Charles E. Gaskin, Project Manager Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS I
f/5 i nse SN - 107 PY II N.UR OITV a wu a u.a w uu x _a %nn e
Enclosure:
As stated DISTRIBUTION with encl. (Control No. 820S)
Docket 70-1151 PUBLIC NRC File Center Region 11 DAyres, Ril FCLB R/F FCSS R/F NMSS R/F SChotoo
'G:\\WO403RAl.98)
- See Previous Concurrence OFC FCLB E
FCLB E FCLB E FCLB C
MAdak NAME CGaskin
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DATE 07/ 06/98 07/07/98 07/ 07/98 07N/98 l
C = COVER E = COVER & ENCLOSURE N = NO COPY
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WA8mNGToN, D.c. 20665 0001 f*
July 20,1998 Mr. W. L. Goodwin Project Manager Westinghouse Electric Corporation Commercial Nuclear Fuel Division Drawer R Columbia, South Carolina 29250
SUBJECT:
REVISION 11 OF THE RENEWAL APPLICATION -INCIDENT REPORTING -
(TAC NO. L31068)
Dear Mr. Goodwin:
This refers to your application (document N9C-98-012) dated April 3, ' 098, requesting an amendment to Materials License SNM-1107 for Chapters 1.0 and 3.0 of the Application for Renewal for a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina, Fuel Fabrication Facility.
Our review of your application has identified addition information that is needed before final action can be taken on your request. The additional information, specified in the enclosure, should be provided within 45 days of the date of this letter. Please ieference the above TAC No. in future correspondence related to this request.
If you have questions regarding this matter, please contact me at (301) 415-8116 or E-mail CEG1@NRC. GOV.
Sincerely, Charles E. Gaskin, e Manager Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-1151 License SNM-1107
Enclosure:
As stated
9 a
.e-e Request for Additional Information Application Dated April 3,1998 Westinghouse Commercial Fuel Fabrication Facility Docket 70-1151 Please provide the following information:
1.
On page 1.12, the definition of "Significant Removable Contamination" differs significantly from the reporting requirements in 10 CFR 70.50(b)(3) which uses the term
" spreadable radioactive contamination." Your proposed radiation level is well above normal levels for release from controlled areas and exceeds the DOT limit for transporting of surface-contaminated objects. Finally, it is questionable whether or not these limits should be in the license application. (There was no scan area specified.) In this case, the Amendment Application should be modified to comply with 10 CFR 70.50(b)(3).
2.
The entire Chapter 3 is still numbered as Revision 10 instead of Revision 11.
3.
On page 3.18, Section 3.7.3 indicates that decisions will be made whenever the cognizant regulatory function engineer arrives at the site. How is safety assured until that person arrives onsite and how long should the onsite personnel wait before declaring that the incident " clock" has started? Further the qualified emergency coordinator should be sufficiently trained in all procedures to make " event" decisions.
Indeed, that person should perform the duties of a cognizant regulatory function engineer within the operating parameters of the specific procedures.
4.
On page 3.20 there is a commitment for an informal notification. Informal notifications are not part of the license and should also be removed from your submittal.
5.
On page 3.19, clarify Section 3.7.3 (c.4) regarding what is damaged and/or breached.
The License Application should be modified to comply with 10 CFR 70.50(b)(4).
6.
Revision 10 also modifies pages in Chapter 3. These pages need to be addressed in the changes to the License Application in Revision 10 or Revision 11.
ENCLOSURE l________________________________________._____.