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Issue date | Title | Topic | |
---|---|---|---|
ML20210M825 | 3 August 1999 | Draft License Termination/Amend Plan for Maine Yankee Atomic Power Co | Boric Acid High Radiation Area Offsite Dose Calculation Manual Coatings Temporary Modification Feedwater Heater Process Control Program Fire Protection Program |
ML20206D798 | 10 November 1998 | Revised Maine Yankee Odcm | |
ML20237D067 | 19 August 1998 | Rev 1 to Maine Yankee Certified Fuel Handler Training & Retraining Program | |
ML20236T478 | 14 July 1998 | Proposed Tech Specs Revising Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing 10CFR20.1302 Requirements | |
ML20216F895 | 13 April 1998 | Proposed Tech Specs Re Fuel Storage Pool Water Level | |
ML20216E184 | 10 March 1998 | Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry | Offsite Dose Calculation Manual Fire Protection Program |
ML20202H504 | 10 February 1998 | Proposed Tech Specs Page 5-8,including Specification Re Cold Weather Operations | Fire Protection Program |
ML20212A621 | 20 October 1997 | Proposed Tech Specs Re Permanently Defueled Status of Plant | Time of Discovery High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Fire Protection Program |
ML20210M587 | 15 August 1997 | Proposed Tech Specs Revising Facility Staffing & Training Requirements | Annual Radioactive Effluent Release Report Process Control Program Fire Protection Program |
ML20210L960 | 15 August 1997 | Certified Fuel Handler Training & Retraining Program | |
ML20137S889 | 8 April 1997 | Proposed Tech Specs Reducing RCS Flow | |
ML20135F726 | 7 March 1997 | Restart Readiness Plan | Fitness for Duty Post Accident Monitoring Temporary Modification High Energy Line Break Eddy Current Testing Overexposure |
ML20136B526 | 5 March 1997 | Proposed Tech Specs,Requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant | Operating Basis Earthquake Stress corrosion cracking Eddy-Current Testing |
ML20134J664 | 7 February 1997 | Proposed Tech Specs Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements | |
ML20134J631 | 7 February 1997 | Proposed Tech Specs 4.10.C.2 Re SG Tube Surveillance Requirements | Operating Basis Earthquake |
ML20133N047 | 15 January 1997 | Proposed Tech Specs 4.4 Re Containment Testing | |
ML20133G328 | 23 December 1996 | Cycle 15 Startup Test Rept Suppl 5 | |
ML20133A713 | 19 December 1996 | Proposed Tech Specs 3.13 Re Refueling & Fuel Consolidation Operations & Table 4.2-1 Re Minimum Frequencies for Sampling Tests | Power change |
ML20129F883 | 25 September 1996 | Proposed Tech Specs Re Organization Change Affecting Nuclear Safety Audit & Review Committee | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20138F403 | 11 April 1996 | Revised Maine Yankee Odcm | Grab sample Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Power change |
ML20148C658 | 31 December 1994 | Guidelines for Diagnostic Evaluation,Dec 1994,Rev 4 | |
ML20148C651 | 31 December 1994 | Diagnostic Evaluation Team Managers Handbook,Dec 1994, Rev 1 | Systematic Assessment of Licensee Performance Backfit |
ML20128D676 | 28 January 1993 | Co ISI Program for Third ISI Interval 921228-021228 | Boric Acid Reactor Vessel Water Level Packing leak Hydrostatic Nondestructive Examination VT-2 High Energy Line Break Stress corrosion cracking Eddy Current Testing Liquid penetrant Dissimilar Metal Weld Scaffolding |
ML20127P247 | 25 January 1993 | Proposed Tech Specs Change 177 Re Main Yankee Spent Fuel Pool Reracking | Shutdown Margin Earthquake |
ML20126B691 | 15 December 1992 | Proposed TS 3.19 Re Position Restrictions on Loop Isolation Valves,Safety Injection Header Isolation Valves & Safety Injection Tank Isolation Valves | |
ML20198D077 | 8 May 1992 | Proposed Tech Spec 1.4.D, Containment Purge Sys | |
ML20141M118 | 24 March 1992 | Proposed TS Spec 1.3 Re Fuel Enrichment Limit in Reactor Core | Boric Acid |
ML20062D285 | 5 November 1990 | Proposed Tech Specs Re Removal of cycle-specific Operating Limits | |
ML20058B607 | 15 October 1990 | Proposed Tech Specs Modifying 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns | |
ML20059N767 | 1 October 1990 | Cycle 12 Startup Test Rept | |
ML20058L931 | 30 July 1990 | Proposed Tech Spec Page 5.2-2 Re Manager Qualification for Operations | |
ML20055G312 | 10 July 1990 | Proposed Tech Specs Consisting of Proposed Change 155 Re Safety Injection Actuation Sys | |
ML20055E098 | 5 July 1990 | Proposed Tech Specs Re Qualification Requirements for Operations Manager | |
ML20055D465 | 20 February 1990 | Rev 3 to Procedure 0-07-1, Matl Receipt | |
ML20055D469 | 15 August 1989 | Rev 4 to Procedure 0-15-1, Nonconformance Repts (Ncr) | |
ML20235H558 | 15 February 1989 | Proposed Tech Specs,Adding Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability & Surveillance Requirements to Sections 3.9 & 4.1 | |
ML20196B530 | 22 November 1988 | Proposed Tech Specs Supporting Change 134 Re Main Steam Excess Flow Check Valve & Turbine Valve Testing Frequency | Liquid penetrant |
ML20206F234 | 8 November 1988 | Proposed Tech Spec 1.1, Fuel Storage | Earthquake |
ML20246H528 | 31 October 1988 | Reactor Containment Bldg Integrated Leak Rate Test for Oct 1988 | |
ML20206C290 | 26 October 1988 | Proposed Tech Specs,Deleting Offsite & Facility Organization Charts,Figures 5.2-1 & 5.2-2 | Safe Shutdown |
ML20205M975 | 18 October 1988 | Proposed Tech Specs,Modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test Frequency,Per C-E STS | Liquid penetrant |
ML20204G119 | 31 August 1988 | Rev 1 to Procedure 26.1, Offsite Dose Calculation Manual | Grab sample Offsite Dose Calculation Manual |
ML20207E261 | 2 August 1988 | Errata to Proposed Tech Specs Figure 3.10-4,showing Allowable Unrodded Radial Peak as Function of Cycle Average Burnup for Cycle 11 Operation | |
ML20150E902 | 30 June 1988 | Proposed Tech Specs,Consisting of Proposed Change 141,to Reflect Operating Parameters for Cycle 11 | Shutdown Margin Anticipated operational occurrence Fuel cladding |
ML20150G053 | 28 March 1988 | Proposed Tech Specs,Increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235 | Boric Acid |
ML20147G901 | 1 March 1988 | Proposed Tech Specs Reflecting Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure | |
ML20155D380 | 1 February 1988 | Rev 3 to Procedure 18-340-1, Maine Yankee Simulator Work Order | |
ML20235A832 | 6 January 1988 | Proposed Tech Specs,Revising Offsite & Facility Organizational Charts | |
ML20237G219 | 10 August 1987 | Co Simulator Certification Test Plan | Stroke time |
ML20236G511 | 30 July 1987 | Proposed Tech Specs,Consisting of Proposed Change 132, Replacing Page 3.10-4 Re Incore Monitoring Sys |