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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20064A807 | 11 September 1990 | Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d | |
| A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access | 11 September 1990 | Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access | |
| B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel | 7 September 1990 | Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel | |
| B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon | 5 September 1990 | Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon | Safe Shutdown |
| A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage | 4 September 1990 | Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage | Hardened vent |
| B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility | 31 August 1990 | Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility | |
| B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed | 31 August 1990 | Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed | Internal Flooding Probabilistic Risk Assessment |
| B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 | 24 August 1990 | Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 | Safe Shutdown |
| ML20059C206 | 23 August 1990 | Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents | |
| A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided | 22 August 1990 | Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided | |
| B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps | 15 August 1990 | Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps | |
| B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 | 14 August 1990 | Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 | |
| B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 | 10 August 1990 | Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 | |
| A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision | 8 August 1990 | Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision | Backfit |
| ML20058N218 | 7 August 1990 | Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 | |
| ML20058M832 | 7 August 1990 | Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples | |
| B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise | 1 August 1990 | Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise | |
| A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event | 31 July 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event | |
| B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) | 30 July 1990 | Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) | |
| ML20055J462 | 27 July 1990 | Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 | |
| A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities | 26 July 1990 | Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities | |
| B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys | 26 July 1990 | Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys | |
| B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent | 24 July 1990 | Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent | Backfit |
| ML20063P979 | 23 July 1990 | Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util | |
| B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage | 20 July 1990 | Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage | |
| B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety | 20 July 1990 | Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety | |
| ML20055G533 | 18 July 1990 | Forwards Decommissioning Financial Assurance Certification Rept | |
| A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 | 18 July 1990 | Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 | |
| B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged | 18 July 1990 | Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged | |
| B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components | 16 July 1990 | Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components | |
| ML20055D346 | 3 July 1990 | Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility | Operability Determination |
| ML20055D348 | 29 June 1990 | Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action | |
| ML20055D719 | 29 June 1990 | Amends 900604 Rev 13 to QA Program | |
| B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 3 | 29 June 1990 | Forwards Rev 3 to Updated FSAR for Millstone Unit 3 | |
| B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl | 27 June 1990 | Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl | |
| B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys | 26 June 1990 | Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys | |
| ML20043F872 | 11 June 1990 | Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp | |
| ML20043H016 | 8 June 1990 | Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested | Exemption Request Backfit |
| ML20043E883 | 5 June 1990 | Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant | |
| ML20043D045 | 30 May 1990 | Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr | |
| ML20042H031 | 9 May 1990 | Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified | |
| ML20042F094 | 30 April 1990 | Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request | |
| ML20042F066 | 30 April 1990 | Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs | |
| ML20042E833 | 27 April 1990 | Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. | |
| ML20012E268 | 23 March 1990 | Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel | |
| ML20012C314 | 13 March 1990 | Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr | |
| ML20012B411 | 2 March 1990 | Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator | |
| B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably | 26 February 1990 | Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably | Systematic Assessment of Licensee Performance |
| ML20011F754 | 26 February 1990 | Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 | |
| ML20006G158 | 21 February 1990 | Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms | Enforcement Discretion Missed surveillance Job Performance Measure Systematic Assessment of Licensee Performance Fire Protection Program |