Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20210N3312 August 1999Forwards 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
ML20153B54514 September 1998Forwards 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
ML20151Z43927 July 1998Informs 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
ML20198P78215 January 1998Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRCFuel cladding
ML20141C29316 June 1997Forwards 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
ML20135C72524 February 1997Forwards 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
ML20133G3159 December 1996Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs
ML20129B5958 October 1996Forwards Response to RAI Re 960912 Amend Request for License R-108
ML20115E6678 July 1996Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text
ML20113C36618 June 1996Responds to Request for Addl Info Re Amend Request for FOL R-108
ML20101H62818 March 1996Forwards Annual Rept for Triga Facility for 1995
ML20087E4017 August 1995Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108
ML20078M1378 February 1995Forwards Response to RAI Re 941221 Application for Amend to License R-108
ML20069J1656 June 1994Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922
ML20065B22328 March 1994Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108)
ML20057D45130 September 1993Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor
ML20072Q91114 March 1991Advises 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
ML20062F74119 November 1990Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108
ML20055F6901 July 1990Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected
ML17347B5881 March 1990Responds 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
ML15217A10328 February 1990Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation ManualsOffsite Dose Calculation Manual
Process Control Program
ML18094B32228 February 1990Forwards Executed Amend 14 to Indemnity Agreement B-74
ML20011F38226 February 1990Confirms 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
ML20006G06222 February 1990Forwards 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
ML20006E58820 February 1990Forwards 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)
ML20006E14416 February 1990Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals
ML20006E90716 February 1990Discusses 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
ML20006E42014 February 1990Requests 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
ML20011E61512 February 1990Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21)
ML20011E5578 February 1990Forwards 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
ML20011E4996 February 1990Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested
ML20011E5985 February 1990Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj
ML20006D6912 February 1990Provides 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
ML20006C56631 January 1990Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at PlantsFitness for Duty
ML20011E25229 January 1990Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790)
ML20006D66129 January 1990Advises 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
ML20006C67129 January 1990Responds 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 BiofoulingUltimate heat sink
Coatings
Biofouling
ML20006B79629 January 1990Forwards Summaries of Latest ECCS Evaluation Model Changes
ML18153C09529 January 1990Forwards 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 NotedCoatings
Biofouling
ML20006D24326 January 1990Provides 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
ML18094B28626 January 1990Forwards 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 IssuanceCoatings
Biofouling
ML18153C08726 January 1990Responds 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 OutageShutdown Margin
ML19354E41925 January 1990Comments 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
ML17347B54524 January 1990Informs 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
ML19354E67124 January 1990Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226
ML19354E44622 January 1990Forwards 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
ML19354E44522 January 1990Submits 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
ML20005G71620 January 1990Forwards 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
ML20006A80019 January 1990Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21)
ML16152A90918 January 1990Forwards 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
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:INCOMING-20CORRESPONDENCE-5D-5D-20-5B-5BSite::Dow-20Chemical-20Company-7C-7C05000000-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"