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| Issue date | Title | |
|---|---|---|
| IR 05000309/1986013 | 19 September 1986 | Insp Rept 50-309/86-13 on 860729-0910.Insp Results:One Plant Trip Occurred Caused by Inverter Failure,Personnel Error During Recovery Caused Momentary Loss of One Emergency Bus & Contaminated Sand Released in Controlled Area |
| Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing | 26 June 1986 | Improper Installation of Heat Shrinkable Tubing |
| Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System | 2 February 1987 | Miswiring in a Westinghouse Rod Control System |
| Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 |
| Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 |
| Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break | 30 June 1989 | Degradation of Containment Isolation Capability by a High-Energy Line Break |
| Information Notice 1991-38, Thermal Stratification in Feedwater System Piping | 13 June 1991 | Thermal Stratification in Feedwater System Piping |
| Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures | 9 July 1997 | Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability |
| ML063110627 | 7 October 1996 | Independent Safety Assessment of Maine Yankee Atomic Power Company |
| ML18043B161 | 26 March 2018 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident |
| ML20132B453 | 5 December 1996 | Responds to 960904,13,25 & 1007 & 14 Ltrs Re Concerns at Plant About Conformance W/Tmi Action Plan Items II.K.3.30 & II.K.3.31,competence & Integrity Questions About Nonconformance W/Items |
| ML20148C615 | 16 May 1997 | Responds to Recipient Concerns Expressed in Senator SM Collins to Chairman Jackson Re Safety of Plant & Adequacy of NRC Oversight of Facility.Forwards Encl Documents Currently Available from AEOD |
| ML20148C644 | 30 June 1996 | Review of Operating Experience for Maine Yankee from Jan 1993 - Mar 1996 |
| ML20205D401 | 26 March 1999 | Responds to Sent to Lj Callan Re Emergency Preparedness & Financial Protection Exemption Requests Made by Util & Requests Meeting Scheduled at NRC Headquarters Be Rescheduled & Held in Vicinity of Myaps |
| ML20236F483 | 30 April 1998 | Expresses Appreciation for Prompt Response to Ltr Requesting NRC Consider Moving April 23rd Predecisional Enforcement Conference from Ofc in PA to Wiscasset,Maine.Disappointed That NRC Opted to Proceed W/Meeting in PA |
| ML20236H271 | 26 October 1987 | Responds to Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Procedures Will Be Developed for Lowering Coolant Level in Reactor Vessel Below Top of Loop Piping. W/One Oversize Drawing |
| NRC Generic Letter 1983-43 | 19 December 1983 | NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications |
| NRC Generic Letter 1987-12 | 9 July 1987 | NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled |
| NRC Generic Letter 1992-02 | 6 March 1992 | NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown. |