Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML18038A323 | 30 August 1990 | Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM | Grab sample Annual Radiological Environmental Operating Report Process Control Program |
| ML17056A977 | 30 August 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm. | |
| ML18038A322 | 24 August 1990 | Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation | Emergency Lighting Job Performance Measure Fuel cladding Coast down |
| ML18038A320 | 21 August 1990 | Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components | |
| ML18038A325 | 20 August 1990 | Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed | |
| ML20058Q115 | 15 August 1990 | Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21) | |
| ML20055G526 | 18 July 1990 | Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl | |
| ML17058A584 | 27 June 1990 | Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2 | |
| ML18038A305 | 26 June 1990 | Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl | Scram Discharge Volume |
| ML20042E374 | 11 April 1990 | Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request | |
| ML20012F613 | 30 March 1990 | Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d)) | |
| ML17056A672 | 2 March 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. | Offsite Dose Calculation Manual Process Control Program |
| ML17347B588 | 1 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 | |
| ML15217A103 | 28 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 | Offsite Dose Calculation Manual Process Control Program |
| ML18094B322 | 28 February 1990 | Forwards Executed Amend 14 to Indemnity Agreement B-74 | |
| ML20011F382 | 26 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 | |
| ML20006G062 | 22 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 | |
| ML20006E144 | 16 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 | |
| ML20006E907 | 16 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 | |
| ML20006E420 | 14 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 | |
| ML20011E615 | 12 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) | |
| ML20011E499 | 6 February 1990 | Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested | |
| ML18038A707 | 5 February 1990 | Forwards Rev 5 to NMPC-QATR-1, QA Topical Rept for Nine Mile Point Nuclear Station Operations. | |
| ML20006D691 | 2 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 | |
| ML20006C566 | 31 January 1990 | Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants | Fitness for Duty |
| ML18153C095 | 29 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 | Coatings Biofouling |
| ML20006D661 | 29 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 | |
| ML20006C671 | 29 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 | Ultimate heat sink Coatings Biofouling |
| ML20006B796 | 29 January 1990 | Forwards Summaries of Latest ECCS Evaluation Model Changes | |
| ML20011E252 | 29 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) | |
| ML18153C087 | 26 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 | Shutdown Margin |
| ML18094B286 | 26 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 | Coatings Biofouling |
| ML20006D243 | 26 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 | |
| ML19354E671 | 24 January 1990 | Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 | |
| ML17347B545 | 24 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 | |
| ML19354E445 | 22 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 | |
| ML19354E446 | 22 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 | |
| ML20005G716 | 20 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 | |
| ML20006A800 | 19 January 1990 | Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) | |
| ML16152A909 | 18 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 | |
| ML18153C077 | 17 January 1990 | Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 | |
| ML20006A201 | 16 January 1990 | Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg | Anchor Darling Nondestructive Examination |
| ML18153C073 | 15 January 1990 | Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves | Anchor Darling |
| ML20005G643 | 10 January 1990 | Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood | |
| ML20006A820 | 10 January 1990 | Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River | |
| ML18038A706 | 10 January 1990 | Forwards Rev 21 to Emergency Plan,Revised Emergency Action Procedures,Including Rev 7 to S-EAP-1,Rev 11 to S-EAP-2,Rev 8 to S-EAP-3 & Epips,Including Rev 13 to S-EPP-4 & Rev 13 to S-EPP-20 | |
| ML20006B882 | 10 January 1990 | Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs | |
| ML20005G760 | 4 January 1990 | Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo | |
| ML18153C049 | 3 January 1990 | Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner | Fitness for Duty |
| ML18094B233 | 3 January 1990 | Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana | Fitness for Duty |