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Issue date | Title | Topic | |
---|---|---|---|
ML20059K195 | 18 September 1990 | Clarifies Auxiliary Feedwater Sys Commitments Concerning Ability of Sys to Prevent Total Loss of Feedwater Following Various Pipe Breaks & Component Failures | |
ML20064A747 | 18 September 1990 | Discusses Response to Generic Ltr 88-17, Loss of Dhr. Development of Appropriate Tech Spec Changes for Reducing Cooling Flow Rate in Process.Changes Will Provide Increased Margin to Vortexing Conditions | |
ML18057A481 | 17 September 1990 | Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant | |
LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions | 17 September 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions | |
LIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl | 17 September 1990 | Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl | |
LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls | 13 September 1990 | Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls | Job Performance Measure Generic Fundamentals Examination |
LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 | 13 September 1990 | Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 | |
LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits | 12 September 1990 | Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits | Safe Shutdown Temporary Modification |
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 | |
ML20064A807 | 11 September 1990 | Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d | |
LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets | 7 September 1990 | Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets | |
ML20059F476 | 7 September 1990 | Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld | |
ML20059H281 | 7 September 1990 | Forwards Rev 4 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Rev Creates Std Format for Action Plans Which States Scope, Deliverables & Overall Objectives of Action Plan | |
ML20059H424 | 7 September 1990 | Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900905 | New Project Manager |
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 | |
ML18057A455 | 6 September 1990 | Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6)) | |
LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes | 6 September 1990 | Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes | |
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 |
ML18057A452 | 4 September 1990 | Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated | |
IR 05000255/1990010 | 4 September 1990 | Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated | |
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 |
LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529 | 4 September 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529 | |
LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990 | 31 August 1990 | Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990 | Fitness for Duty |
ML18057A437 | 31 August 1990 | Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment | Fire Protection Program |
ML18057A438 | 31 August 1990 | Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place | |
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 |
ML20059E000 | 29 August 1990 | Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 | |
LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations | 27 August 1990 | Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations | Systematic Assessment of Licensee Performance |
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 |
05000317/LER-1989-023, Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture | 24 August 1990 | Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture | |
ML18057A420 | 24 August 1990 | Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting | |
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 | |
ML18057A402 | 22 August 1990 | Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E | |
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 | |
LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection | 22 August 1990 | Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection | |
LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl | 22 August 1990 | Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl | |
LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 1990 | 22 August 1990 | Forwards Fort Calhoun Station Performance Indicators for Jul 1990 | |
LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution | 22 August 1990 | Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution | Boric Acid Temporary Modification |
ML20059B748 | 21 August 1990 | Forwards fitness-for-duty Program Performance Data for Jan-June 1990 | Fitness for Duty |
ML18057A407 | 21 August 1990 | Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable | Hydrostatic |
ML18057A412 | 21 August 1990 | Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level | |
ML18057A418 | 21 August 1990 | Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff | Minimum staff |
ML18057A424 | 21 August 1990 | Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test | |
ML18057A384 | 17 August 1990 | Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr | Safe Shutdown |
ML18057A385 | 17 August 1990 | Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon | Exemption Request |
ML18057A391 | 17 August 1990 | Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program. | |
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 | |
ML18057A382 | 14 August 1990 | Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1)) |