Letter Sequence Other |
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MONTHYEARML20135F7511996-12-10010 December 1996 Forwards Request for Addl Info Re Low Level Radwaste Shredding & U Recovery Project stage: RAI ML20132G7001996-12-23023 December 1996 Requests Addl Info Re 960822 Application Requesting Rev of License SNM-1227 to Include LLRW Shredding & Uranium Recovery from LLRW in Modular Recovery Unit as Authorized Activity Project stage: Approval ML20134F7581997-01-27027 January 1997 Forwards Responses to RAI Re Low Level Radwaste Shredding & U Recovery,Discussed in Ltrs & 1223 Project stage: Response to RAI ML20210P1221997-08-22022 August 1997 Forwards Request for Addl Info Described in Encl to Ltr Re Application & Hazard Analyses & 0501, Requesting Rev of License SNM-1227 to Include low-level Radwaste Shredding & U Recovery Project stage: RAI ML20210V4421997-09-0909 September 1997 Forwards Response to Questions in Ltr & Hazard Analyses & 0501 Project stage: Other ML20217A3711997-09-10010 September 1997 Requests That Review of Operations Scrap Warehouse & UF6 Cylinder Recertification Facility Amend Applications Be Placed Ahead of Merf Application.Completion of TAC L30989 & L30997 Amends by 971030 & TAC L30896,will Support Schedules Project stage: Other ML20198Q1211998-01-15015 January 1998 Forwards Amend 9 to License SNM-1227 & Ser.Amend Authorizes Use of Operations Scrap Warehouse Project stage: Other ML20203A5031998-02-0404 February 1998 Summary of 980127 Meeting W/Siemens Power Corp Re Pending License Amendments.Meeting Agenda & List of Attendees,Encl Project stage: Meeting 1997-08-22
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J8171999-10-14014 October 1999 Responds to NRC GL-98-03,completing Portion Which Applies to Safety & Process Control Activities of Y2K Readiness Program to Assure That Computer Sys Will Not Prevent or Degrade Safety Function of Structure,Sys or Component ML20217B7511999-10-11011 October 1999 Forwards Siemens Power Corp Responses to RAI in Ltr ML20217C7671999-10-0606 October 1999 Forwards Proprietary Rev 32 EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuels Fabrication Plants, Replacing Chapters 2 & 3 of Rev 32,dtd Jul 1999. Proprietary Info Withheld,Per 10CFR2.790(d) ML20217C5651999-10-0404 October 1999 Requests Addl Info Needed Before Action Can Be Taken on Siemens Application for Amend to License SNM-1227 to Authorize Activities with SNM in Fuel Services Bldg.Info Specified in Encl Should Be Provided within 10 Days of Ltr ML20216J5381999-09-30030 September 1999 Forwards RAI Per 990721 Application Requesting Amend to License SNM-1227 to Add Process Waste Storage Area Consisting of Four Tanks & Ion Exchange Column to Ammonia Recovery Facility as Part of Wastewater Treatment Process ML20212G3631999-09-21021 September 1999 Forwards Two Sheets from R Burklin Dose Calculations for Heather & Julie ML20212A1921999-09-10010 September 1999 Submits follow-up to NRC Operations Center Rept 36030 Re Bulletin 91-001 Rept on over-batching of Waste Drums Due to Inaccurate Determinations of U Contents ML20217B5621999-09-0202 September 1999 Ack Receipt of 990806 Application for Amend to License SNM-1227.Acceptance Review Completed & Identified No Administrative Omissions or Deficiencies.Formal Review Anticipated Completion Date of Dec 1999 ML20212G1281999-08-31031 August 1999 Informs That Corporation Is Expected to Produce Approx 40,000 Gallons of Ammonium hydroxide-ammonium Nitrate Solution Per Week.Unsold Solution Will Be Processed Through Arf for Recovery of Ammonia & Then Be Sent to Sewer ML20211G1681999-08-26026 August 1999 Ack Receipt of Transmitting Application for Amend to License SNM-1227 Re Addition to Ammonium Recovery Facility.Acceptance Review Has Identified No Administrative Errors of Omissions ML20211F5791999-08-25025 August 1999 Forwards Insp Rept 70-1257/99-201 on 990802-05.No Violation Noted.Proprietary Document Enclosed ML20211B9101999-08-19019 August 1999 Forwards Insp Rept 70-1257/99-202 on 990802-05.No Violations Noted ML20210R8961999-08-12012 August 1999 Forwards Insp Rept 70-1257/99-02 on 990712-16.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representatives Records,Interviews with Personnel & Observation of Activities in Progress ML20210T4811999-08-11011 August 1999 Informs That NRC Has Completed Acceptance Review of Application for Amend to License SNM-1227 & Have Identified No Administrative Omissions or Deficiencies.Nrc Anticipates Completing Formal Review by End of Oct 1999 ML20210U0561999-08-11011 August 1999 Responds to 990714 Correspondence,By Which Siemens Sent Revised Page Change to Table I-1.1, Authorized Activities. Since NRC Had Previously Authorized Activity Stated,Change to Application Is Administrative & No Action Is Required ML20210G0681999-07-28028 July 1999 Concludes That Proposed Additions to Chapter 15 of License Application Submitted by Listed Ltrs Demonstrate Applicant Adherence to Conditions in Part I of License Application & That No Amend to License Necessary ML20210E9551999-07-26026 July 1999 Forwards Amend 17 to License SNM-1227,allowing Storage of Moderated Uranium Compounds in sea-land Containers.Safety Condition S-1 Has Also Been Revised to Include Date of 990527.Safety Evaluation Rept,Encl ML20210F1791999-07-23023 July 1999 Forwards Proprietary Rev 32 to EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuel Fabrication Plants, Replacing All Sections of Existing Plan.Proprietary Encl Withheld ML20216D4351999-07-21021 July 1999 Provides Description of Modifications That Will Be Made to Ammonia Recovery Facility.Wastewater Flowsheet Encl ML20209H5361999-07-15015 July 1999 Ack Receipt of 990519 Application for Amend to License SNM-1227 Re Sale of Ammonium Nitrate/Ammonium Hydroxide Solution Fertilizer.Initial Review of Application Has Identified No Administrative Omissions or Deficiencies ML20209G2561999-07-12012 July 1999 Informs That Staff Has No Comments on Siemens Power Corp Ammonium Recovery Facility - Sepa Determination of non-significance in Response to ML20209D8121999-07-0606 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1257/99-01. Corrective Actions Will Be Reviewed During Future Insp to Determine That Full Compliance Has Been Achieved ML20196H0021999-06-23023 June 1999 Submits Response to NRC GL 98-03 for Y2K.Upgraded Y2K Ready Primary Control Sys Will Be Installed & Tested in July 1999 ML20196A0931999-06-15015 June 1999 Responds to NRC Re Violations Noted in Insp Rept 70-1257/99-01.Corrective Actions:Info Requested by NRC Is Fully Available in Previously Docketed Correspondence ML20209C2711999-06-11011 June 1999 Requests Review & Comment on Encl Sepa Checklist & Other Info on File with City,By 990625 ML20195F9401999-06-0707 June 1999 Concurs That 990331 Proposed Changes to Richland Facility Emergency Plan Do Not Decrease Effectiveness of Plan.Nrc Will Amend License,Within Next Six Months,To Ensure Latest Rev to Plan Is Reflected ML20207B3681999-05-21021 May 1999 Forwards Insp Rept 70-1257/99-01 on 990322-26,0514 & 21 & Nov.Three Violations Identified Involving Two Examples of Using Transport Containers Which Did Not Meet Terms & Conditions of Applicable Certificate of Compliance ML20206L5371999-05-11011 May 1999 Forwards Amend 16 to License SNM-1227,allowing Storage of Moderated Special Nuclear Matl in sea-land Containers.Ser Also Encl ML20207M0151999-03-11011 March 1999 Informs That Encl Ltr Dtd 950622,explains How NRC Staff Plans to Institute Round Robin Sample Exchange Program Administered by Nbl for Verifying Quality of Licensee U Destructive Measurement Systems.Invoice FL0236-99 Encl ML20207J7221999-02-24024 February 1999 Ack Receipt of 980121 Application for Amend to License SNM-1227.Completed Initial Review with No Administrative Omissions or Deficiencies Identified.Anticipates Technical Review Will Be Completed by First Week in April ML20203G2191999-02-16016 February 1999 Responds to Which Expressed Concerns Re USNRC Plans to Distribute 981221 SRM Re SECY-98-232 & Commission Paper to All Agreement States.Informs That NRC Does Not Plan to Delay Implementation of Actions Specified in SRM ML20202H6241999-01-29029 January 1999 Forwards Siemens Power Corp Best Estimate of Upcoming Work Which Will Require NRC Licensing Actions ML20202E4141999-01-29029 January 1999 Ack Receipt of 990122 Response to Violations Noted in Insp Rept 70-1257/98-204.Implementation of Licensee Corrective Actions Will Be Reviewed During Future Insps ML20199K9571999-01-19019 January 1999 Informs of Listed New Address,For Docket 7106851,for Siemens Power Corp,Effective 990101.Postcard with New Address,Encl ML20199F3741999-01-12012 January 1999 Responds to NRC Re Violations Noted in Insp Rept 70-1257/98-204.Corrective Actions:All Work on Line 1 Ammonium Diuranate (Adu) Project Was Stopped Until Incident Could Be Fully Investigated & Necessary Actions Implemented ML20206R9451999-01-0707 January 1999 Forwards Pages 15-159 Through 15-174 to Include in Chapter 15 of Siemens Power Corp License Application.Pages Provide Summary of Criticality Safety Analysis for Processes Carried Out in Lagoon U Recovery & Solids Processing ML20198P0991998-12-30030 December 1998 Submits Response to GL 98-03 Re Program Set Forth in EMF-2097, Siemens Power Corp Yr 2000 Readiness & Administered by Yr 2000 Project Team ML20198M8901998-12-23023 December 1998 Forwards Amend 15 to License SNM-1227,amended to Allow Processing of TVA Lead Test Assembly Fuel ML20198F5701998-12-15015 December 1998 Forwards Insp Rept 70-1257/98-05 on 981026-30.No Violations Noted.Areas Examined During Insp Were Operational Safety & Event Review Feedback & Mgt Organization & Controls ML20198A9651998-12-15015 December 1998 Submits Addl Info to Support Request to Amend Limit for transuranic-related Activity in Feedstock for License SNM-1227.Revised License Pages 1-5 & 1-6,correcting Inadvertent Omission of Section 1.6.12,encl ML20198B4041998-12-14014 December 1998 Forwards Insp Rept 70-1257/98-204 on 981109-13 & Notice of Violation Involving Failure to Control Decommissioning Operations So That Operators Would Verify That Disassembled Equipment Free from Visible U Deposits ML20154S1881998-10-20020 October 1998 Submits follow-up to NRC Operations Ctr Rept 34819 Bulletin 91-001 on Failure to Remove Accumulated Solids from Dismantled Ductwork ML20155A5371998-10-0909 October 1998 Informs That NRC Has Reviewed Changes to Part II of Application for License SNM-1227.Administrative Error Re Three 500 Kw Generators Was Noted.Nrc Would Like to Be Informed as to Whether Interpretation Is Correct ML20153C3091998-09-18018 September 1998 Submits Response to GL 98-03,re Year 2000 Readiness Program ML20151X0591998-09-11011 September 1998 Forwards Insp Rept 70-1257/98-04 on 980810-14.No Violations Noted.During Insp,Licensee Conduct of Activities at Siemens Facility Was Generally Characterized by Effective Implementation of Operational Safety,Maint & Surveillance ML20239A5221998-09-0202 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1257/98-03 on 980717 ML20151W9751998-09-0202 September 1998 Forwards Amend to License SNM-1227,revising to Incorporate Fundamental Nuclear Matl Control Plan.Revised License & Evaluation Rept,Encl ML20151W9951998-09-0101 September 1998 Forwards Amend 13 to License SNM-1227 to Reflect Correct Location of UF6 Cylinder Storage,Adding Filter Presses to Table I-4.1 & Sale of Ammonium Hydroxide for Fertilizer ML20237E7701998-08-26026 August 1998 Forwards Pages 15-133 Through 15-139 Which Provide Summary of Criticality Safety Analysis for Recovery of U from Pellets in Gd Scrap U Recovery Facility for Info & Inclusion in Chapter 15 of Siemens Power Corp License Application ML20237B4371998-08-13013 August 1998 Responds to NRC Re Violations Noted in Insp Rept 70-1257/98-03.Corrective Actions:Applicable SOPs Have Been Revised to Include Info on Consequences of Mixing Incompatible Wastes & to More Fully Describe Operations 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217J8171999-10-14014 October 1999 Responds to NRC GL-98-03,completing Portion Which Applies to Safety & Process Control Activities of Y2K Readiness Program to Assure That Computer Sys Will Not Prevent or Degrade Safety Function of Structure,Sys or Component ML20217B7511999-10-11011 October 1999 Forwards Siemens Power Corp Responses to RAI in Ltr ML20217C7671999-10-0606 October 1999 Forwards Proprietary Rev 32 EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuels Fabrication Plants, Replacing Chapters 2 & 3 of Rev 32,dtd Jul 1999. Proprietary Info Withheld,Per 10CFR2.790(d) ML20212G3631999-09-21021 September 1999 Forwards Two Sheets from R Burklin Dose Calculations for Heather & Julie ML20212A1921999-09-10010 September 1999 Submits follow-up to NRC Operations Center Rept 36030 Re Bulletin 91-001 Rept on over-batching of Waste Drums Due to Inaccurate Determinations of U Contents ML20212G1281999-08-31031 August 1999 Informs That Corporation Is Expected to Produce Approx 40,000 Gallons of Ammonium hydroxide-ammonium Nitrate Solution Per Week.Unsold Solution Will Be Processed Through Arf for Recovery of Ammonia & Then Be Sent to Sewer ML20210F1791999-07-23023 July 1999 Forwards Proprietary Rev 32 to EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuel Fabrication Plants, Replacing All Sections of Existing Plan.Proprietary Encl Withheld ML20216D4351999-07-21021 July 1999 Provides Description of Modifications That Will Be Made to Ammonia Recovery Facility.Wastewater Flowsheet Encl ML20196H0021999-06-23023 June 1999 Submits Response to NRC GL 98-03 for Y2K.Upgraded Y2K Ready Primary Control Sys Will Be Installed & Tested in July 1999 ML20196A0931999-06-15015 June 1999 Responds to NRC Re Violations Noted in Insp Rept 70-1257/99-01.Corrective Actions:Info Requested by NRC Is Fully Available in Previously Docketed Correspondence ML20209C2711999-06-11011 June 1999 Requests Review & Comment on Encl Sepa Checklist & Other Info on File with City,By 990625 ML20202H6241999-01-29029 January 1999 Forwards Siemens Power Corp Best Estimate of Upcoming Work Which Will Require NRC Licensing Actions ML20199K9571999-01-19019 January 1999 Informs of Listed New Address,For Docket 7106851,for Siemens Power Corp,Effective 990101.Postcard with New Address,Encl ML20199F3741999-01-12012 January 1999 Responds to NRC Re Violations Noted in Insp Rept 70-1257/98-204.Corrective Actions:All Work on Line 1 Ammonium Diuranate (Adu) Project Was Stopped Until Incident Could Be Fully Investigated & Necessary Actions Implemented ML20206R9451999-01-0707 January 1999 Forwards Pages 15-159 Through 15-174 to Include in Chapter 15 of Siemens Power Corp License Application.Pages Provide Summary of Criticality Safety Analysis for Processes Carried Out in Lagoon U Recovery & Solids Processing ML20198P0991998-12-30030 December 1998 Submits Response to GL 98-03 Re Program Set Forth in EMF-2097, Siemens Power Corp Yr 2000 Readiness & Administered by Yr 2000 Project Team ML20198A9651998-12-15015 December 1998 Submits Addl Info to Support Request to Amend Limit for transuranic-related Activity in Feedstock for License SNM-1227.Revised License Pages 1-5 & 1-6,correcting Inadvertent Omission of Section 1.6.12,encl ML20154S1881998-10-20020 October 1998 Submits follow-up to NRC Operations Ctr Rept 34819 Bulletin 91-001 on Failure to Remove Accumulated Solids from Dismantled Ductwork ML20153C3091998-09-18018 September 1998 Submits Response to GL 98-03,re Year 2000 Readiness Program ML20237E7701998-08-26026 August 1998 Forwards Pages 15-133 Through 15-139 Which Provide Summary of Criticality Safety Analysis for Recovery of U from Pellets in Gd Scrap U Recovery Facility for Info & Inclusion in Chapter 15 of Siemens Power Corp License Application ML20237B4371998-08-13013 August 1998 Responds to NRC Re Violations Noted in Insp Rept 70-1257/98-03.Corrective Actions:Applicable SOPs Have Been Revised to Include Info on Consequences of Mixing Incompatible Wastes & to More Fully Describe Operations ML20236R4341998-07-14014 July 1998 Forwards Rev 31 to EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuels & Fabrication Plants, Dtd 980630.Encl Replaces Rev Dtd Jan 1998,entirely.Proprietary Info Withheld,Per 10CFR2.790(d) ML20236N6771998-07-0808 July 1998 Informs of Listed Changes to Part II of License Application. Revised Effective Pages Forwarded ML20249C3081998-06-23023 June 1998 Forwards Incident Investigation Board Rept & Suppl Thereto on 980415 Fire in Siemens Power Corp UO2 Bldg Waste Handling Area,Per Request of P Lain ML20248H1001998-06-0101 June 1998 Responds to NRC Re Violations Noted in Insp Rept 70-1257/98-202.Corrective Actions:Item Listing in Rodss Was Promptly Updated to Accurately Account for Bundles in Question ML20248L9301998-05-29029 May 1998 Forwards Proprietary NRC Form 327,which Repts Results of Matl Balance Accounting & Seid Calculations for Period 980319-0413.Encl Withheld (Ref 10CFR2.790(d)) ML20247K3031998-05-14014 May 1998 Responds to 980504 Telcon RAI Re Criticality Safety Info for Spf.Licensee Provides Summary of Listed Items ML20217Q6561998-03-25025 March 1998 Submits 10CFR71.95(c) Rept Re Instance in Which Conditions of Approval in Coc for Licensed Shipping Container Were Not Observed in Making Shipment.Licensee Currently Evaluating Compliance of All Fissile Matl Containers,Per CAL-98-8-02 ML20216J7921998-03-19019 March 1998 Forwards Revised Affidavit & non-proprietary Version of Response to NRC RAI W/Info Licensee Considers Proprietary Blanked Out.Previous Affidavit Was Not Adequate for NRC to Judge Whether to Withhold Info in Response ML20203J8101998-02-13013 February 1998 Requests That Ref Table Be Substituted W/Encl Corrected Table Due to Minor Errors Discovered in Gaseous Effluent Table ML20203C5371998-02-13013 February 1998 Requests That Gaseous Effluent Table Be Substituted W/Corrected Table.Emitted Uci Quantity for Stack 10 Should Be 0.66 Instead of 2.66 & for Stack 31 Should Be 0.58 Instead of 1.58 ML20202H9521998-02-13013 February 1998 Forwards Response to Violations Noted in Insp Rept 70-1257/97-07.Corrective Actions:Violation Discovered by Licensee & Reported Both on 971218 to NRC Inspector on Plant at Time & by Telcon to NRC Headquarters Next Day ML20202J8401998-02-10010 February 1998 Forwards Discharges of Radioactive Matls in Effluents from Nuclear Fuels Fabrication Plant in Richland,Wa.Data from Jul-Dec 1997,reported in Attached Tables ML20202G3271998-02-0606 February 1998 Forwards Page 1-11 of License SNM-1227,per 980206 Telcon. Inclusion of Page Is to Conclude License Amend Process to Add Modular Extraction/Recovery Facility to Siemens Power Corp License ML20203C9471998-02-0505 February 1998 Forwards Proprietary Changes Constituting Rev 31 to EMF-12, Nuclear Matls Safeguards Procedures Description for Fuel Fabrication Plants. Encl Withheld ML20202C0121998-02-0505 February 1998 Forwards Proprietary Rev 31 to EMF-12(P), Nuclear Matls Safeguards Procedures Description for Fuels Fabrication Plants. Encl Withheld (Ref 10CFR2.790(d)) ML20202D0681998-02-0202 February 1998 Provides Attached Info Re Planned Storage of Hydrogen Peroxide Used in Merf Process.Licensee Does Not Intend to Process Alcohol Rags Until Further Data on Any Possible Reactions W/Nitric Acid Is Obtained ML20199K8991998-01-28028 January 1998 Forwards Changes to Part II of License SNM-1227.Main Changes Are to Chapter 11 Associated W/Amends 5 & 7 Issued 970829 & 971003,respectively.Revised Pages Include 9-1,9-6,9-7 & 11-1 Through 11-50,14-9 & 1-10.W/document Rev Instruction Sheet ML20199B5371998-01-22022 January 1998 Forwards Proprietary Rev 15 to EMF-538(P), Physical Protection Plan for SNM of Low Strategic Significance. Encl Which Does Not Decrease Effectiveness of Plan,Submitted Under Provisions of 10CFR70.32(e).Encl Withheld ML20198R2841998-01-12012 January 1998 Provides Relevant Assumptions Re Criticality Safety Calculations for Operations Scrap Warehouse Per 980109 Telcon ML20198G7761998-01-0505 January 1998 Informs NRC That Actions Requested in Item 3 of NRC Bulletin 97-002, Puncture Testing of Shipping Packages Under 10CFR71, Not Required ML20198K8091997-12-30030 December 1997 Forwards Number of Questions & Responses During 971223 Telcon,Per Review of Licensee Request for License Amend for Operations Scrap Warehouse.Tables Revised to Include Powder Density Along W/Container Loading Info,Encl ML20198E0551997-12-29029 December 1997 Responds to Violations Noted in Insp Rept 70-1257/97-07 on 971218.Corrective Actions:Licensee Will Submit Amend Request Authorizing Storage of Wider Range of U Bearing Compounds in Temporary Storage ML20198K8621997-12-29029 December 1997 Submits Annual Update to Financial Assurance Instruments of Decommissioning Funding Plan ML20198K5551997-12-22022 December 1997 Forwards Requested Info Re Temporary Storage in Planar Arrays as Reported During 971219 Telcon W/M Adams & H Felsher ML20198K7421997-12-16016 December 1997 Submits Revised Schedule for Completion of Category III Criticality Safety Analyses Updates ML20203K0081997-12-10010 December 1997 Informs That Licensee Intends to Use Operations Scrap Warehouse as Temporary Storage Facility as Described in Table 1.1.1 in License Application ML20203K0451997-12-0808 December 1997 Forwards Pages 15-35 Through 15-37d from Siemens Power Corp Informational Submittal of 970415,per 971201 Request ML20202G9431997-12-0505 December 1997 Responds to NRC Re Violations Noted in Insp Rept 70-1257/97-202.Corrective Actions:Dry Conversion Pilot Program Will Remain in Shutdown Condition Until Required Engineered Barriers Are Installed ML20203H2001997-12-0303 December 1997 Provides Addl Info Needed to Complete Review & Approval of 970714 Request for Amend to License,To Add Operations Scrap Warehouse to Table I-1.1 as Specific Location of Authorized Activity 1999-09-21
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P # k o l>$
SIEMENS:
September 9,1997 JBE:97:146
. U.S. Nuclear Regulatory Commission Attn: Mr. M.F. Weber, Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Washington, DC 20555
Dear Mr. Weber:
Subject:
- NRC RAI (TAC No. L30896)
Ref.:
Letter, K.J. Hardin to L.J. Maas, " Request for Additional Information, Amendment Application dated August 22,1996 and the Hazard Analyses dated March 3 and May 1, 'i 997 (TAC No. L30896)".
~ Attached are Siemens Power Corporation's (SPC's) response to the questions in the referenced letter.
/
Very truly yours, 8{B. Edgar Jam Staff Engineer, Licensing
/pg Enclosures s\\
toe *EENEdI l!!ElElR.IEEjH.iB.
c Siemens Power Corporation Nuclear Division 2101 Horn Rapids Road Teh (509) 375 8100 Engineering & Manufacturing P.o. Box 130 Fax:
(509) 375 8402 Richland, WA 9S352 0130
$1. F. Web:r Attachment September 9,1997 Page 1 Attachment
- 1) NRC Reouest Drawing FOO3, sheet 2 of 2, dated 4/23/96, indicates that precipitated uranium will be pumped through a filter.
a) What safety devices are in place to prevent operators from being sprayed with uranium solution if a leak occurs in piping, connections, or the filter?
SPC Responso Most of the piping throughout the facility is either welded, fused or solvent cemented.
Mechanical fittings are minimized. Splash guards will be installed on all flanged fittings on pipes which carry corrosive liquids. Safety shields will be instdlied on rotameters. Filtration by the Oberlin Filter is achieved automatically within a stainless steel enclosure, inspection of the piping prior to startup will evaluate any add.tional requirements to protect the worker from being sprayed with process solutions. Daily inspection of the facility for leaks and spills is required. The operator will notify supervision any time there is a leak in the piping, connections or the tiher. Operations will not proceed until the leak has been fixed.
Additionally, the operators are required to wear safety glasses in the facility. When changing out chemical drums / totes in the Raw Material Storage Area, the operator is required to wear eye, hand, body and foot protection that is resistant to the chemical being handled.
b) How are these safety devices maintained and tested, to ensure that they remain in place and will function if needed?
SPC Resoonse Safety shields and splash guards will be inspected for correct installation. They will not be removed without approval from the supervisor and then they must be replaced before operations can begin. Periodic safety inspections will check that these protective devices are in place and in a fu!!y functional condition.
- 2) NRC Reouest Drawing G003, sheet 1 of 1, dated 11/12/96, indicates the Raw Material Storage Area contains nitric acid, sodium hydroxide, hydrogen peroxide, and a propane fired boiler which is within 6 feet of the heating ventilation and air conditioning (HVAC) skid.
a) Has the possibility of a chemical release or propane release from the Raw Material Storage Area, being drawn into the HVAC air intake, been analyzed?
$1. I'. Wsbir Attachment September 9,1997 Page 2 SPC Responsa These scenarios have not formally been analyzed but are considered very unlikely. In the I
caso of propane, it assumes that a major propane leak occurs, the propane gas detector has failed, and that there is a breach in the walls of the Raw Materials Storage Area, it should be noted thbt the propane storage tank is remote from the f acility and the lines from the tank to the facility are underground. Scenarios related to the process chemicals are similarly unlikely, l.a., requiring chemical container leakage and breaching of the walls of the Raw Material
' Storage Area, b) What effect would this type of release have on operators in the modular extractionhecovery f acility (MERF)?
SPC Response As discussed above, the likelihood of any of these chemicals reaching the MERF operations -
area, via the postulated accident scenario, is very low. The risks are further mitigated by a number of factors, including good physiological warning properties via smell or sensory irritation (propane, nitric acid vapor, sodicm nydroxide, hydrogen peroxide), very low volatility i
(sodium hydroxide) or toxicologicalinertness (propane), if any of these chemicals were detected in unocceptable concentrations in the MERF operating areas, the operator would 3'
investigate the source and initiate corrective action. Operations would cease until the source was eliminated. The presence of high concentrations, albeit highly unlikely, would necessitate evacuation until the situation could be corrected.
- 3) NRC Reauest
-Drawing F003, sheet 2 of 2, dated 4/23/96, indicates that the hydrogen peroxide concentration is'5 percent higher than the concentration in the material safety data sheet (MSDS). Also, drawing FOO3, sheet 1 of 2, dated 4/23/96,-indicates that the nitric acid concentration is 9 percent lower than the concentration !isted in the Hazards Analysis, page 6, Section 2.10.
a) Please confirm the concantration that will be used in the MERF.
SPC Resoonse The actual concentrations for the respective chemicals used in the MERF facility are as i
follows:
t 30% Hydrogen Peroxide 50% Sodium Hydroxide 68% Nitric Acid Originally the concentration of hydrogen peroxide was to be 35%. However, it was felt that the 30% concentration would be safer to handle. Nitric acid, at a concentration of 57%, was
4
$1. F') absr Attachmsnt September 9,1997 Page 3 3
to be downloaded from SPC's bulk tank, but our chemical supplier was able to supply nitric acid (68%) in stainless steel totes at a price that could not justify the cost of building a new downloading station. By receiving full totes of nitric acid from the supplier, instead of filling i
totes from our bulk tank, we feel that the added safety from reduced handling more than offsets the danger due to higher concentration, in both cases, the drawings were not i-updated to reflect the change in concentrations. The sodium hydroxide concentration (50%)
has not been changed.
41 NRC Reouest Reference Modular Extraction / Recovery Facility (MERF):. Hazard Analysis, EMF 1946, Revision 0, page 2, Sections 2.1.4 and 2.1.5..There is a discussion about wet wastes and alcohol contaminated rags. The Fire Hazard Analysis (FHA) for the MERF, dated 2/12/97, page 1, discusses waste containing small amounts of tributyi phosphate (TBP), dodecane, lubricating oils and greases (organics). Also on page 1 is the statement that bench-scale tests were conducted on three of four waste types anticipated in the MERF, and at that time, alcohol rags had not been defined as a waste stream that would be treated in the MERF.
a) Did the bench scale tests discussed above confirm that incompatible reactions between the organics, including alcohol, and oxidizers (nitric acid and hydrogen peroxide) are not going to occur and operators can safely perform the washing / extracting and precipitation steps without the potential of an incompatible reaction occurO gJ SPC Respongg Bench scale tests evaluated HEPA filter media, prefilters and wet wastes. The wet wastes,
-_ containing organics, did not result in an incompatible reaction. -The alcohol rags were not tested. However, once in the washer / extractor, a pre-rinse cycle will be run to remove most of the alcohol prior to the addition of nitric acid. Incompatible reactions with very low residual concentrations of alcohol are not expected. Only three batches (50,30-gallon drums) of alcohol rags will be run.
- 5) NRC Reauest Attachment A, page 13 of the Modular Extraction / Recovery Facility (MERF): Hazard Analysis, EMF-1946, Revision 0, states there _is a potential explosion hazard if ammonium nitrate accumulates in the f acility, a)-Has the compatibility of dodecane, lubricating oils, nitric acid and hydrogen peroxide with ammonium nitrate been considered and documented?
SPC Resoonse The explosion hazard referenced in the hazard analysis was due to postulated accumulation of ammonium nitrate solids in the ductwork followed by welding of the ductwork without
i
- 4.
e j
M. P. Wabsr Attachment
- September 9,1997 Page 4 f
inspection and removal of these solids, it was not related to incompatible chemical reactions associated with dodecane, lubricating oils, nitric acid and hydrogen peroxide. However, bench-scale testing did not exhibit incompatible reactions with these chemicals due to ammonium nitrate.
b) What measures have been taken to promote worker safety and prevent these potential incompatible reactions from occurring?
SPC Rergpngt Low concentrations of ammonium nitrate are expected in the process solutions. We do not anticipate, nor did bench-scale tests demonstrate any significant incompatible reactions.
Significant quantitles of white solids on any of the waste materials will require, by procedure, a pre-rinse cycle in the washer / extractor to significantly reduce the ammonium nitrate concentration prior to the addition of nitric acid.
6)' NRC Reauest The washer / extractor will be heated by injecting saturated steam at (100 psig and 334 degrees Fahrenheit) into the washer / extractor drum to maintain a temperature in excess of 100 degrees Fahrenheit.
a) What measures or controls are provided to prevent an operator from opening the washer door during injection of 334 degree saturated steam into the nitric acid solution?
_SPC Resoonse The washer / extractor's control syatem program will not allow the access doors to be opened during operation. A1 operator cannot access the washer unless the program has been terminated. With the door open, the solenoid valve for injecting steam into the washer will not open, b) is there a device that prevents opening the door until the temperature has cooled sufficiently to prevent injury to the operator?
SPC Resoonse Access to the washer / extractor under normal operating conditions is intended to occur at the end of the cycle, following a cold water (70 F) rinse step. The washer / extractor's microprocessor is the device that ensures that this cold water rinse occurs and that solenoid valves controlling steam and chemical addition remain closed to prevent injury to the operator during loading and unloading operations c) Are safety controls tested to ensure that they will perform as expected at startup and during operations?.
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. F. Webir Attachmsnt September 9,1997 Page 5 SPC Resoonse
-The safety features for the washer / extractor will be tested in a formal Acceptance Test Procedure (ATP). The door interlocks and the solenoid valves for chemical ard steam
_ addition will be specifically tested to ensure that the operator cannot gain access until it is safe to enter. Daily operation of the washer / extractor and its control system will then be closely monitored. Any problem or malfunction will require immediate resolution before operations can continue.
d) How will these controls be tested?
SPC Resoonse The washer extractor will be operated with c!ean waste materials prior to startup. All of the safety controls and interlocks will be evaluated at that time, per the ATP, to ensure they are functioning properly,
- 7) NRC Reauest Reference the MERF Hazards Analysis, EMF-1946, Revision 0, Attachment A, page 12. The safeguards for the What if scenario where the temperature control valve fails on the steam line to the washar and UNH tank are: (1) High temperature indication, (2) Operator will be attending the machine during operation, and (3) Routine calibration, a) If the temperature sensing device fails, what happens with the temperature control valve?
SPC Response The temperature control valve will close to shut down the flow of steam if the temperature sensor fails, b) is the temperature sensing device loses power, would the high temperature indicator still
- operate?
SPC Resoonse The high temperature indicator would not operate if the sensor loses power.
c) Are there separate temperature sensing devices for the temperature control valve and the temperature indicator?- Are there redundant temperature sensing devices?
SPC Resoonse There is only one sensor that provides the input to the indicator and the control valve. There are no redundant temperature sensing devices.
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fA.12. Web:r Attcchm:nt September 9,1997 Page 6 d) If the MERF facility loses electrical power, does the temperature control valve fall in a safe position,' i.e., closed?
SPC Resoonse In the event of a power failure, the temperature control va!ve will fail in the closed position and shut off the flow of steam._
e) Does routine calibration, described in (3) above, involve a functional test where a high temperature is simulated and the temperature control valve is verified to close?
~ SPC Response l
Routine calibration means that the temperature sensor will be tested to ensure that the accuracy of the reading is within allowable tolerances. ' Additionally, a functional test will evaluate the operation of the temperature control valve by inputting a high temperature signal into the controller. This testing will be conducted annually, f) Are'there separate temperature sensing devices for the UNH Hold Tank and Washer /kxtractor temperature control valve?
SPC Resoonse There are separate temperature control devices for the UNH Hold Tank and _the washer / extractor.
- 8) NRC Reauest Reference the MERF Hazards Analysis, EMF-1946, Revision 0, page 28, Attachment D, Material Safety Data Sheet 30% Hydrogen Peroxide, Section 7-Handling and Storage. The MSDS recommends the fol.owing for hydrogen peroxide storage: store in a cool, dry, well ventilated area: do not store near heat or flame; and, store below 100 degrees Fahrenheit. According to drawing G003, sheet 1'of 1, dated'11/12/96, hydrogen peroxide will be stored in the Raw Material / Storage Area Weatherport Enclosure, which includes the steam boiler, a) Will the storage conditions recommended in the MSDS be met.
SPC Resoonse The hydrogen peroxide will not be stored in direct proximity to the boiler.- However, storage of chemicals in the Weatherport enclosure is subject to ambient conditions. Therefore, the temperature may exceed 100* F in the summer. All other conditions will be met.
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Attachment September 9,1997-Page 7 b) How will these storage conditions be maintained? If they can not be maintained, have the consequences and associated risks with hydrogen peroxide thermal decomposition been considered?
SPC Response The temperature in the Raw Material Storage' Area will not be maintained. However, the manufacturer of hydrogen peroxide has been contacted regarding storage at temperatures greater than 100* F (weather conditions for the Richland area). They indicated that the rate of thormal decomposition is very slow and should not pose a problem. Also, each chemical tote or drum will be stored on individual containment basins to prevent intermingling of chemicals as a result c8 a spill or leak.
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_9) NRC Reauest Prior to opening drums at the Sortir.g Station, are they checked for bulging or other signs of -
4 pressure build-up? If a drum is suspected to be pressurized, what measures are being used to relieve the pressure? Is a check for pressure in the drum required by procedure or covered curing operator training classes?
i SPC Response The plastic drums containing wet waste are the only ones likely to be pressurized and then mainly in hot weather. They will be visually inspected for bulging. Every drum will be opened and vented in the glovebox. The operators will be made aware in training sessions that the drums can be pressurized and to use caution when opening.
10)NRC Reauest -
The MERF Hazards Analysis, EMF 1946, Revision 0, Section 9.10, Nitric Acid Supply System, page 6, and the Siemens RAI response to Question 1.3, datea 1/27/97, states tMt concentrated nitric acid is pumped via a metering pump through a flow totalize, to a hold tank where the nitric acid solution is made up, a) How is the concentration of the nitric acid solution controlled and verified?
SPC Response Water will be added to the UNH Hold Tank to a preset level. The nitric acid flow controller will be set for the specified volume of nitric acid. The operator will confirm that nitric acid is flowing and that the desired volume has been delivered. A check of the tank level (level gauge)_will confirm that the correct arr, sunt of acid is added.
. M. F. Webtr Attachmsnt September 9,1997 Page 8 b) If the flow totalizer fails or pumps the incorrect amount, what is the highest nitric acid solution concentration that could be achieved in the washer / extractor? If a higher nitric acid concentration was obtained, would this result in incompatible reactions between the nitric acid (oxidizer) and organic (lubricating oils greases, dodecane, alcohol) co'itaminants? What controls are in place to prevent this?
SPC Response The highest concentration of nitric acid that can be achieved for u e in the washer extractor would be approximately 6 molar. To achieve this concentration requires the addition of excess nitric acid to the point of overflowir:g the tank.
Bench-scale tests were conducted with nitric acid concentrations as high as 5 molar without any observable incompatible reactions with the organic contaminants. Therefore, it is not expected that at 6 molar, these reactions would occur.
A flow controller is used to ensure the correct addition of nitric acid into the UNH Hold Tank.
Additionally, an operator would be at the tank, by procedure, to ensure that the nitric acid volume does not exceed the preset level (pec the level gauge) for making a 3 molar solution.
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