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| Issue date | Title | From | To | |
|---|---|---|---|---|
| NRC Generic Letter 1988-05 | 17 March 1988 | NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants | Miraglia F Office of Nuclear Reactor Regulation | |
| NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
| A07141, Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Source of RCS Leakage Determined by Insp to Be at Reactor Vessel Head O-Ring | 27 May 1988 | Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Source of RCS Leakage Determined by Insp to Be at Reactor Vessel Head O-Ring | NORTHEAST UTILITIES Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO. Northeast Nuclear Energy | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| A07137, Responds to SALP Repts 50-245/86-99 & 50-336/86-99 for June 1986 - Dec 1987.Util Responding W/Particular Emphasis on Board Recommendations for Individual Evaluation Categories | 27 May 1988 | Responds to SALP Repts 50-245/86-99 & 50-336/86-99 for June 1986 - Dec 1987.Util Responding W/Particular Emphasis on Board Recommendations for Individual Evaluation Categories | NORTHEAST UTILITIES Mroczka E Northeast Nuclear Energy | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| IR 05000336/1988013 | 6 July 1988 | Insp Rept 50-336/88-13 on 880503-0613.No Unsafe Conditions Noted.Major Areas Inspected:Plant Operations,Surveillance, Maint,Radiation Protection,Physical Security,Outage Activities,Allegations,Lers & Committee Activities | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Mccabe E | |
| NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification | 2 August 1988 | NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical Specifications | Miraglia F Office of Nuclear Reactor Regulation | |
| ML20154G035 | 13 September 1988 | Informs That 880527 Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants Acceptable | Wang A Office of Nuclear Reactor Regulation | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO. Northeast Nuclear Energy |
| ML19332G147 | 7 July 1989 | Forwards Trip Rept for Joint Nrc/Bnl Site Visit to Plant in June 1989 to Satisfy Requirements of Task Order 4 of FIN A-3871 | Brookhaven National Laboratory Czajkowski C | Bernard Grenier Office of Nuclear Reactor Regulation |
| NRC Generic Letter 1991-17 | 17 October 1991 | NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants. | Partlow J Office of Nuclear Reactor Regulation | |
| Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | Grimes B K Office of Nuclear Reactor Regulation | |
| Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | Grimes B Office of Nuclear Reactor Regulation | |
| B16601, Provides Response to GL 97-01, Degradation of CR Drive Mechanism (CRDM) Nozzle & Other Vessel Closure Head Penetrations. Prior to Issuance of GL Technical Issues, Causal Factors & Relative Importance Were Identified | 28 July 1997 | Provides Response to GL 97-01, Degradation of CR Drive Mechanism (CRDM) Nozzle & Other Vessel Closure Head Penetrations. Prior to Issuance of GL Technical Issues, Causal Factors & Relative Importance Were Identified | Brothers M Northeast Nuclear Energy | Office of Information Resources Management |
| ML020730271 | 22 March 2002 | Safety Evaluation of Relief Request RR-89-35, Temporary Installation of Mechanical Seal Assemblies on Preesurizer Heater Penetration Nozzles (Tac No. MB4039) | Clifford J NRC/NRR/DLPM/LPD1 | Dominion Nuclear Connecticut Price J Danni Smith |
| ML021050375 | 2 April 2002 | Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | Dominion Nuclear Connecticut Price J | Office of Nuclear Reactor Regulation Document Control Desk |
| ML023230322 | 19 November 2002 | Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response | Richard Ennis NRC/NRR/DLPM/LPD1 | Dominion Nuclear Connecticut Price J Danni Smith |
| ML030090398 | 27 December 2002 | Comment of S.P. Sarver on Behalf of Virginia Electric & Power Co., and Dominion Nuclear Connecticut on Third Year Implementation of the Reactor Oversight Process | Dominion Dominion Nuclear Connecticut Sarver S | Lesar M NRC/ADM/DAS/RDB |
| ML030280169 | 24 January 2003 | Mechanical Nozzle Seal Assembly Type 2 Code Replacement Request for Relief from 10 CFR 50.55a | Southern California Edison Scherer A | Office of Nuclear Reactor Regulation Document Control Desk |
| ML050750469 | 5 April 2005 | Relief Request RR-89-35, Temporary Installation of Mechanical Nozzle Seal Assemblies on Pressurizer Heater Penetration Nozzles | Darrell Roberts NRC/NRR/DLPM/LPD1 | Dominion Nuclear Connecticut Christian D |
| ML061070659 | 17 April 2006 | IR 05000336-06-006, IR 05000423-06-006; 2/13/06 - 3/3/06; Millstone Nuclear Plant, Units 2 and 3; Biennial Baseline Inspection of the Identification and Resolution of Problems. Violations Were Identified in the Areas of Effectiveness of Pro | Paul Krohn NRC/RGN-I/DRP/PB6 | Dominion Resources Christian D |
| ML13218A260 | 31 July 2013 | Information in Support of License Renewal Commitment #14 Program Description for Alloy 600 Aging Management Program | Dominion Dominion Nuclear Connecticut Stoddard D | Office of Nuclear Reactor Regulation Document Control Desk |
| IR 05000245/2016009 | 2 September 2016 | Millstone Power Station - NRC Problem Identification and Resolution Inspection Report 05000336/2016009 and 05000423/2016009 | Dentel G T Reactor Projects Region 1 Branch 2 | Dominion Resources Heacock D |
| ML23324A430 | 20 November 2023 | Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 | James Holloway Dominion Energy Nuclear Connecticut | Office of Nuclear Reactor Regulation Document Control Desk |