Letter Sequence Other |
---|
|
|
MONTHYEARML20199B9671997-11-0707 November 1997 Refers to 970714 Application Requesting Amend to License SNM-1107,to Release Industrial Waste Treatment Products (Primarily Calcium Fluoride) to Cement Manufacturers.Addl Info Needed Before Final Action Can Be Taken Project stage: Other ML20202D2271997-11-17017 November 1997 Forwards Response to RAI Re Licensee Request for Amend to Release Industrial Waste Treatment Product to Cement Mfgs Project stage: Response to RAI ML20203C3151997-12-0909 December 1997 Forwards Amend 8 to License SNM-1107 & Ser.Amend Authorizes Release of Industrial Waste Treatment Products to Cement Mfgs Project stage: Other 1997-11-07
[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 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 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 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 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 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 ML20209J4031999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Solvent Extraction 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 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 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 ML20204E7481999-03-0202 March 1999 Ack Receipt of NRC Insp Rept 70-1151/99-01 Re Insp of Facility Operational Safety & Environ Programs 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 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 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 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 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 ML20209J4031999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Solvent Extraction Sys,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 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 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 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 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 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 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 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 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 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 ML20151S9101998-08-21021 August 1998 Ack Receipt of Transmitting Rev 25 to Physical Security Plan.Rev Has Been Found to Be Acceptable ML20237D7941998-08-21021 August 1998 Forwards Insp Rept 70-1151/98-204 on 980810-13.No Violations Noted 1999-09-28
[Table view] |
Text
_. __- _ ._ __ __ . _ _ _ . _ , . _ _ . _ . . _ _. _
,.. November 7, 1997 l Mr. Robert A. Williams
. Safeguards Coordinator Westinghouse Electric Corporation ,
Commercial Nuclear fuel Division -
' Drawer R Columbia. South Carolina 29250
SUBJECT:
- AMENDMENT REQUEST TO RELEASE INDUSTRIAL WASTE TREATMENT PRODUCTS i
TO CEMENT MANUFACTURERS (TAC NO. L31003)
Dear Mr. W1111ams:
This refers to your application dated July 14. 1997 requesting an amendment to i Materials License SNM 1107 to release industrial waste treatment products (primarily l calcium fluoride) to cement manufacturers. :
Our review of your application has identified additional information that is needed :
before final action can be taken on your request. The additional information. I specified in the enclosure. should be provided within 30 days of the date of this letter. Please reference the above TAC No. in future correspondence related to this
-request, if you have any questions regarding this matter, please contact me at (301) 415 8116. ,
Sincerely.
1
/s Charles Gaskin l Licensing Section 1
- Licensing Branch i Division of Fuel Cycle Safety and Safeguards. NMSS ;
Docket 70-1151 License SNM 1107
Enclosure:
As stated.
Distribution: w/ enc 1. (Control No. 7EOS) [ PARTIAL]
Docket 70 1151 PUBLIC NRC File Center Region 11
'FCLB R/F FCSS R/F NMSS R/F DAyres Ril 8
-Schotoo AIF05 , s
[c:\chotoo\westhse\caf.rai) 0FC- FCLB E FCLp,f, FCLB (5 FCLB h FCLB y d.
NAME Schotoo 600. CGaIki$ PShea g ' Mdl)Jlhy ' HAdams%h !
DATE 11/ .3 /97 11/[( /97 11/ y' /97 IN e( /97 11/ 7 /97 m, c ,, ,
l M ,
_ - _ =
r ,
i Request for Additional Information
- Application Dated July 14, 1997 .
Westinghouse Electric Corporation i Docket 70 1151 ,
Please provide the following information:
- 1. Indicate the chemical form of the uranium present in the industrial waste products at the time of transfer. Al e indicate the amount of variability in this assessment.
- 2. Provide co,servative concentrations of any radionuclides other than l uranium in the waste treatment products, i
- 3. Conmit to notifying each recipient of waste products in writing of the radionuclide concentration in each batch.
- 4. Describe how the waste treatment products are expected to be used by the cement manufacturers.
- 5. Provide 6 conservative dose assessment for use of the waste treatment products by cement manufactures. When the material is released from your control, the NRC can no longer place restrictions on its use to reduce potential doses. Therefore, your dose assessment should consider the most conservative circunstances that may occur. For example, you should consider uranium exposure due to dust inhalation by a worker for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week. 50 weeks per year, while engaged in moderate to heavy activity. The airborne dust concentration should be assumed to be equal to tho Occupational Safety and Health Administration exposure limit, and the airborne uranium concentration should be assumed to be proportional to the maximum concentration in the waste treatment products. Justify use of less conservative parameters.
l
November 7,1997 l
Gr. Robert A. Williams Safeguards Coordinator Westinghouse Electric Corporation
, Comercial Nuclear fuel Division Drawer R Columbia. South Carolina 29250
SUBJECT:
AMENDMENT REQUEST TO RELEASE INDUSTRIAL WASTE TREATMENT PRDDUCTS TO CEMENT MANUFACTURERS (TAC ND. L31003)
Dear Mr. Williams:
1his refers to your application dated July 14. 1997. requesting an amendment to Materials License SNM 1107 to release industrial waste treatment products (primarily calcium fluoride) to cement manufacturers.
Our review of your application has identified additional informati5n that is r.eeded before final action can be taken on your request. The additional information, specified in the enclosure, should be provided within 30 days of the date of this letter. Please reference the above TAC No in future correspondence related to this request.
If you have any questions regarding this matter. please contact me at (301) 415-8116.
Sincerely.
Charles Gaskin Licensing Section 1 Licensing Branch Division of Fuel Cycle Safety and Safeguards. NMSS Docket 70 1151 License SNM-1107
Enclosure:
As stated.
Distrioution: w/ encl. (Control No. 7EOS) [ PARTIAL]
Docket 70-1151 PUBLIC NRC File Center Region 11 FCLB R/F FCSS R/F NMSS R/F DAyres, Ril Schotoo
[c:\chotoo\westhse\caf.rai) 0FC FCLB E FCLp,ff FCLB C FCLB j FCLB (,.
NAME SChotoo $O0. CGaIki$ PShea g M6hjbf$y MAdamsfjj}
DATE 11/ J /97 11/ Q /97 11/ L/ /97 11/ /97 11/ 7 /97
Request for Additional Information Application Dated July 14. 1997 Westinghouse Electric Corporation Docket 70 1151 Please pr? vide the following information:
- 1. Indicate the chemical form of the uranium present in the industrial waste products at the time of transfer. Also indicate the amount of variability in this assessment.
- 2. Provide conservative concentrations of any radionuclides other than uranium in the waste treatment products.
- 3. Commit to notifying each recipient of waste products in writing of the radionuclide concentration in each batch.
- 4. Describe how the waste treatment products are expected to be used by the cement manuf.cturers.
- 5. Provide a conservative dose assessment for use of the waste treatment products by cement manufactures. When the material is released from your control, the NRC can no longer place restrictions on its use to reduce potential doses. Therefore. your dose assessment should consider the most conservative circumstances that may occur. For example, you should consider uranium exposure due to dust inhalation by a worker for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week. 50 weeks per year, while engaged in moderate to heavy activity. The airborne dust concentration should be assumed to be equal to the Occupational Safety and Health Administration exposure limit and the airborne uranium concentration should be assumed to be proportionel to the maximum concentration in the waste treatment products. Justi fy use of less conservative parameters.
L. .