ML20137G437
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7171999-10-26026 October 1999
[Table view]Informs That Effective 991026,SW Holmes Will Be NRC Inspector for Facility at Dow Chemical Co,Due to Retirement of Previously Assigned Inspector ML20210P9881999-08-10010 August 1999 Forwards Insp Rept 50-264/99-201 on 990712-15.No Violations Noted.Insp Consisted of Selected Exams of Procedures & Representative Records,Interview with Personnel & Observations of Activities in Progress ML20210N3311999-08-0202 August 1999 Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20203L1271998-02-26026 February 1998 Forwards Request for Addl Info Re Emergency Plan Submitted on 960708,as Supplemented on 980115.Responses Requested to Be Provided within 30 Days of Date of Ltr ML20203A0561998-02-11011 February 1998 Forwards Amend 8 to License R-108.Amend Increases Amount of Time from 30 to 60 Days That Temporary Radiation Monitor May Be Used in Place of Area Monitor ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20198B4181997-12-18018 December 1997 Forwards Insp Rept 50-264/97-201 on 971202-03.No Violations or Deviations Identified.Annual Emergency Plant Drill Acceptable Demonstration of Ability to Respond & to Mitigate Consequences of Reactor Event ML20217P3201997-08-22022 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Nrr.All Related Repts, Correspondence & Inquires W/Docket Number Specified Should Be Directed to Listed Address ML20210R0971997-08-19019 August 1997 Forwards Amend 7 to License R-108 & Safety Evaluation.Amend Deletes Requirement for Scram Function on Min Reactor Period,Changes Periodic Insp of Reactor Fuel Schedule, & Modifies Facility Organizational Structure ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20140E5471997-04-23023 April 1997 Forwards Insp Rept 50-264/97-01 on 970407-11.No Violations Noted ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20132D2781996-12-17017 December 1996 Forwards Request for Addl Info Re License Triga Research Reactor ML20132D5511996-12-16016 December 1996 Ack Receipt of Ltr Dtd 961030,transmitting Changes to Physical Security Plan for Dow Triga Research Reactor Submitted,Per 10CFR50.54(p) ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20129H1331996-10-0202 October 1996 Requests Addl Info Re Dow Triga Research Reactor Emergency Plan Submitted on 960708 Before Review Can Be Complete ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20058N4841990-08-0101 August 1990 Forwards Insp Rept 50-264/90-01 on 900709-11.No Violations or Deviations Identified ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes 1999-08-02 Category:INCOMING CORRESPONDENCE MONTHYEARML20210N3311999-08-0202 August 1999
[Table view]Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo 1999-08-02 Category:VENDOR/MANUFACTURER TO NRC MONTHYEARML20055F6901990-07-0101 July 1990
[Table view]Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML19327A8441989-10-11011 October 1989 Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities ML19327B2491989-10-0606 October 1989 Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. ML19327A8511989-10-0505 October 1989 Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed ML20247F4121989-08-31031 August 1989 Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided ML20246B1671989-08-0808 August 1989 Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged ML20247Q5521989-05-24024 May 1989 Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected ML20247P8071989-04-0404 April 1989 Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed ML20247G4991989-03-30030 March 1989 Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) ML19324C3151989-02-20020 February 1989 Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies ML20235M8971989-02-10010 February 1989 Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 ML20206D6241988-11-11011 November 1988 Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve ML20205Q6331988-11-0202 November 1988 Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected ML20205P9511988-11-0101 November 1988 Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d)) ML20195E4291988-10-31031 October 1988 Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page ML20205N3301988-10-27027 October 1988 Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations ML20195B6091988-10-21021 October 1988 Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W ML20154K3841988-09-12012 September 1988 Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production ML20154E6451988-08-31031 August 1988 Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d)) ML20207L7651988-08-30030 August 1988 Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151H9381988-07-25025 July 1988 Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants ML20151L3321988-07-20020 July 1988 Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal ML20151M9211988-07-20020 July 1988 Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50% ML20151G9761988-07-14014 July 1988 Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790) ML20150F1561988-07-0808 July 1988 Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting ML20207C7931988-06-29029 June 1988 Advises That Jj Havel Replaced Mb Gibbs as Chair of Reactor Operations Committee,Effective 880623 ML20155F4441988-05-0404 May 1988 Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104 ML20154C2651988-04-29029 April 1988 Forwards Mods to Suppl Application for Renewal of License R-108,per a Adams Request ML20151F7661988-03-29029 March 1988 Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld ML20234C2231987-12-28028 December 1987 Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld ML20234D1101987-12-14014 December 1987 Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld ML20237C3611987-11-24024 November 1987 Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4)) ML20236C0261987-10-22022 October 1987 Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) ML20236B0621987-10-0505 October 1987 Informs That 870925 Audit of Triga Research Reactor Showed Two Tasks Involving Surveillance Required by Tech Specs Not Done Per Scheduled Weekly Checklist for Wk of 870713.Failure to Complete Tasks Did Not Violate Tech Specs LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request ML20238A0461987-08-14014 August 1987 Forwards Supplementary Info Re Renewal of License R-108 for Dow Triga Research Reactor ML20237L4351987-08-14014 August 1987 Forwards Licensed Operator Requalification Program for Facility.Program Reflects Changes Made Following Guidance of Hn Berkow ,Ansi/Ans 15.1-1977 & Changes in 10CFR55 Effective 870526 ML20238A3091987-08-13013 August 1987 Forwards Answers to Questions Posed Following Submittal of May 1987 Formal Answers,Including More Detailed Info Re fire-fighting Equipment in Reactor Room & Nearby Areas & Detailed Analysis of Temp Rise Expected in Fuel Element ML20236H4971987-07-29029 July 1987 Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid ML20236H1311987-07-28028 July 1987 Forwards Revised Security Plan,Per RA Erickson 870526 Request.Rev Withheld (Ref 10CFR2.790) ML20236B4141987-07-13013 July 1987 Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid ML20196K1621987-07-0909 July 1987 Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12 ML20215L0591987-06-22022 June 1987 Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl ML20214T0611987-06-0202 June 1987 Forwards ALARA Policy Statement,Revised Requalification Program & Tech Specs & Addl Info in Support of Application for Renewal of License R-108,per a Adams Request ML20215D4081987-05-15015 May 1987 FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1 ML20213G8111987-05-13013 May 1987 Forwards Endorsement 60 to Nelia Policy NF-160 ML20237D2761987-04-27027 April 1987 Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl ML20212R4711987-04-15015 April 1987 Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987 Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days 1990-07-01 |
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> THE DOW CMEMICAL COMPANY MIDLAN D. MICHIG AN 48840 April 30,1971
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/ Division of Reactor Licensing D_ IUl) [
i U.S. Atomic Energy Commission dE_b_ E M . P 'I O Washington, D. C. 20545 E_l__..Z__.
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jQt Gentlemen:
ffte M _P'N gWj guyu With reference to our communicatiois of February 9,1971, Docket b 50-264-R108, I would like to send you the enclosed copy of a descrip-i tion of the Nuclear Reactor Flux Regulator and Multirange Pico-
/ ammeter Channel which we are purchasing from the manufacturer of our Dow TRIGA Reactor to modernize the control circuitry.
I We are assured by Gulf General Atomics that the design and circuits k have been incorporated as standard equipment in the more modern consoles installed since 1967 and have proven themselves very
- reliable and requiring but littic maintenance. The new c1cetronics is to replace older tube-type components presently performing the same functions, so that no change in the specifications are intended.
The control rod to be employed for the flux controller has a nominal reactivity valye of $3. in our reactor. The enclosed specifications for the flux controller NFC-3 list a maximum control rod velocity of 0.43 in/sec. for a $4. rod. The latter resulting in a maximum reactivity insertion rate of $.16/sec, which is equivalent to .11*/o sik/k/sec. , a value falling within our Technical Specifications. i 1
We are planning to install the new equipment sometime after May 25, at which time we shall carry out detailed testing of the new circuitry before using it on a routine basis.
We would appreciate hearing froin you any comments you wish to make so that we can proceed with this modernization as soon as the equipment is delivered. .
Very truly yours, Lt4S C Dr. Harold Hoyle Chairman Radiation Safety Committee 1701 Building 1 YY rir enc 1.
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B508270299 850712 \
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