ML20207D342
From kanterella
Jump to navigation
Jump to search
| ML20207D342 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 02/22/1999 |
| From: | Goodwin W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20207D344 | List: |
| References | |
| CON-NRC-99-007, CON-NRC-99-7 NUDOCS 9903090307 | |
| Download: ML20207D342 (1) | |
Similar Documents at Westinghouse | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J1721999-10-13013 October 1999
[Table view]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 Category:INCOMING CORRESPONDENCE MONTHYEARML20216J7131999-10-0202 October 1999
[Table view]Forwards Response to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness Programs 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 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 ML20209C9201999-07-0808 July 1999 Forwards Response to NRC GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness Programs 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 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) 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 ML20206S8911999-05-0606 May 1999 Informs That Wl Goodwin Has Reviewed Encl Special Nuclear Matl Inventory Rept & Concurs with Authorizing Signature of RA Williams 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 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 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 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 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 ML20207D3421999-02-22022 February 1999 Forwards Gaseous Effluent Discharges, Jul-Dec 1998. Detailed Summary Liquid Discharge Rept Is Provided as Attachment B ML20203G3781999-02-12012 February 1999 Submits Proposed Rev 15.0 of Page V and Page 1.4 from Chapter 1.0 for Application for Renewal of SNM-1107 for Commercial Nuclear Fuel Div at Columbia,Sc Fuel Fabrication Facility ML20203C2001999-02-0202 February 1999 Provides 30-day follow-up Rept,Per Requirements of 10CFR70.50(c)(2).Event Involved Ventilation Hood 704,which Serves Drying Oven of Flouride Stripping Platform in URRS Area ML20202F0941999-01-29029 January 1999 Submits Response to Violations Noted in Insp Rept 70-1151/98-10.Corrective Actions:Specific Conservatisms in Analyses for Rack Identified That More than Compensated for Small Amounts of Matl from Polypaks Being Stored Anywhere ML20199J5631999-01-18018 January 1999 Forwards Copies of All Procedures Which Have Been Revised Since Last Major Rewrite of July 1996 of W Emergency Response Manuals.Revised Index Encl ML20199C5911999-01-11011 January 1999 Forward Proprietary Copies of Section 1, Process Description, & Section 5, Safety Analysis, of Integrated SA for Adu Process Bulk Powder Blending Sys,In Response to NRC Rai.Proprietary Info Withheld,Per Encl Affidavit ML20199C6101999-01-0707 January 1999 Requests That Encl Info Re Columbia Plant Criticality Safety Evaluations Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-99-5820, Requests That Encl Proprietary Info Re Columbia Plant Criticality Safety Evaluation,Be Withheld from Public Disclosure,Per 10CFR9.17(a)(4)1999-01-0707 January 1999 Requests That Encl Proprietary Info Re Columbia Plant Criticality Safety Evaluation,Be Withheld from Public Disclosure,Per 10CFR9.17(a)(4) ML20198P1631998-12-29029 December 1998 Forwards W Response to RAI Re License Rev 10.0, Criticality Safety ML20198F0911998-12-17017 December 1998 Forwards Year 2000 Project Plant Update for W Columbia Fuel Fabrication Facility,Per Response to NRC GL 98-03, NMSS Licensees & Certificate Holders Year 2000 Readiness Programs ML20196E5951998-12-0101 December 1998 Forwards Proprietary Rev 29 to Fundamental Nuclear Matl Control Plan for Columbia Fuel Fabrication Facility. Proprietary Encl Withheld (Ref 10CFR2.790(d)) ML20195F3811998-11-16016 November 1998 Refers to CBS Corp Ltr Concerning Application for Transfer & Amend of License SNM-1107.Ltr Encl as Addl Matl Pertaining to Application ML20195F3891998-11-11011 November 1998 Submits Listed Statements & Representations Re 980929 Applications for Transfers & Amends of Matls Licenses,Qa Program Approvals & Cocs,As Provided by NRC Regulations & Info Notice 89-25,rev 1 ML20198A5921998-10-29029 October 1998 Requests That Proprietary Info on Columbia Plant Criticality SEs Be Withheld from Public Disclosure,Per 10CFR2.790 ML20154S6041998-10-21021 October 1998 Responds to NRC Requesting Specific Reasons for Exempting from Public Disclosure,Certain Info Encl with Licensee & Affidavit.Exemption Requested IAW Paragraph 4(ii)(a),(c) & (F) of Attached Affidavit 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 ML20196D1361998-10-16016 October 1998 Ack Receipt of & Insp Rept 70-1151/98-07 on 980921-25 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 ML20154D6891998-09-28028 September 1998 Forwards Application for Transfers & Amends of Certain Matls Licenses,For Filing Necessitated by Sale of Assets of Nuclear & Government Operations Business of CBS Corp, Formerly W,To Consortium of Listed Purchasers ML20154A7011998-09-28028 September 1998 Forwards Application for Transfers & Amends of Certain Matls Licenses,Listed on Exhibit a to Encl Application ML20153C5221998-09-16016 September 1998 Forwards Yr 2000 Project Plan for Westinghouse Columbia Fuel Fabrication Facility,In Response to GL 98-03 ML20153C7461998-09-15015 September 1998 Forwards Rev 1 to Criticality SE for License Annex for Integral Fuel Burnable Absorber Fuel Rod Mfg, Submitted to NRC on 980731 ML20153G1151998-09-0101 September 1998 Ack Receipt of & Insp Rept 70-1151/98-06 on 980803-07 ML20151U0441998-08-31031 August 1998 Forwards Upgrade of Criticality Safety Evaluation License Annex,Cylinder Washing, to Replace Cylinder Washing Criticality SE Summary Previously Submitted on 951222 ML20153F3291998-08-28028 August 1998 Ack Receipt of NRC Ltr & Insp Rept Re Insp of Facility Radiation Protection Program by MR Gooden on 980727-31 ML20238E7421998-08-25025 August 1998 Forwards Effluent Monitoring Requirements for Jan-June 1998, Fulfilling Regulatory Requirements as Listed in 10CFR40.65 & 10CFR70.59.Detailed Summary Liquid Discharge Rept Provided as Attachment B ML20237E8581998-08-24024 August 1998 Forwards Sections 1 & 5 Re Process Description & Safety Analysis,Respectively of Criticality Safety Evaluations for Both Adu Conversion Process & Un Bulk Storage Sys,Per NRC 980626 Request.Encl Subj Sections Withheld ML20237E8671998-08-14014 August 1998 Requests That Proprietary Info on Columbia Plant Criticality Safety Evaluations Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-98-5758, Forwards Info Pertaining to Criticality SEs Conducted for W Cnfd - Columbia Plant.W Copyright Notice,Proprietary Info Notice,Application for Withholding & Affidavit Attached,Per 10CFR9.17(a)(4)1998-08-14014 August 1998 Forwards Info Pertaining to Criticality SEs Conducted for W Cnfd - Columbia Plant.W Copyright Notice,Proprietary Info Notice,Application for Withholding & Affidavit Attached,Per 10CFR9.17(a)(4) 1999-09-20 |
Text
-
e f3
/
\\
1
\\
G v)
Westinghouse Commercial Nuclear Drawer R Dectric Corporation Fuel Division
$"f/3 2gcar iina 292so s
NRC-99-007 February 22,1999 U. S. Nuclear Regulatory Commission ATTN: Regional Administrator, RIl Region 11 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303
Dear Sir:
Subject:
SNM-Il07/70-Il51 The following report fulfills regulatory requirements as listed in 10CFR 40.65 and 10CFR 70.59
- Effluent Monitoring Requirements." For the six-month period July 1,1998 through December 31, 1998, the following quantities of radionuclides were released to the unrestricted area by the Westinghouse Electric Company's Columbia, South Carolina Commercial Nuclear Fuel Division plant:
A. Gaseous 292.5 uCi Uranium (Analped as gross alpha)
B. Liquid Effluent 18,500.2 uCi - U-234 902.4 uCi - U-235 3,158.6 uCi - U-238 Gaseous effluent results were obtained from point source gross alpha analysis of stack gas effluent, and the individual radionuclide composition is inferred from the calculated average enrichment (82.0% U-234,4.0% U-235, and 14.0% U-238). A detailed summary report by stack is provided as Attachment "A."
Liquid effluent vahies were obtained by analysis of composite proportional samples prior to discharge to the Congaree River and basing the activity on the calculated average enrichment. All liquid discharges are routed through a single discharge line to Congaree River. A detailed summary liquid discharge report is provided as Attachment "B."
Sincerely, WESTINGHOUSE ELECTRIC COMPANY c
~S W. L. Goodwin, Manager b
Regulatory Affairs 9903090307 990222~
/
/
PDR ADOCK 07001151 alhfety and Safeguards A N 1m i Wra of Nulear M forsyth Sneet SW. Sune 23T85 U.S. Nulcar Regulamry Cummismani llama, G4 30303 Washmgum. DC 20S55 The KVstmphouse CommercolNuclearFue/Divkida - M'kmerofIhe 1988Malcolm Baldnpe Natibna/Oua/HyAward
Retrieved from "https://kanterella.com/w/index.php?title=ML20207D342&oldid=4040048"