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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 | |
ML20154L667 | 20 May 1988 | Responds to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in Plant. Formal Program That Complies W/Nrc Generic Ltr 88-05 Will Be Implemented by 891231 | Exelon Tiernan J | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
IR 05000317/1988014 | 21 July 1988 | Insp Rept 50-317/88-14 on 880613-24.No Violations Noted. Major Areas Inspected:Inservice Insp & Steam Generator Insp Activities to Ascertain Whether Licensee Activities Conducted in Compliance W/Applicable ASME Code | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Strosnider J Mcbrearty R Winters R | |
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 | |
ML20247P661 | 18 September 1989 | Requests Addl Info Re Generic Ltr 88-05, Boric Acid Corrossion of Carbon Steel Reactor Pressure Boundary.... NRC Should Be Notified of Full Implementation of Program within 30 Days Following Implementation | Office of Nuclear Reactor Regulation Mcneil S | Exelon Creel G |
ML20006B511 | 25 January 1990 | Forwards Info Re Commitment Implementation Assessment Project Objectively Assessing How Effectively Util Historically Identified,Implemented & Maintained Commitments Made to NRC | Exelon Creel G | NRC Russell W |
ML20011E132 | 30 January 1990 | Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Formal Program to Ensure That Boric Acid Corrosion Does Not Lead to Increase in Abnormal Leakage Implemented | Exelon Creel G | Office of Information Resources Management |
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 | |
ML20059F890 | 15 October 1993 | Nonproprietary Version of Calvert Cliffs Nuclear Power Plant,Unit 1 & 2 Pressurizer Inconel 600 Sleeve Nozzle SAR for Alternative Roll/Plug Repairs | INC. MPR ASSOCIATES | |
ML20065M470 | 15 April 1994 | Summarizes Telcon W/Nrc on 940401 to Discuss Unit 2 Operability Re Accelerated Boric Acid Attack Observed on Unit 1 Incore Instrumentation Flange Assembly | Exelon Cruse C | Office of Information Resources Management |
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 | |
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 | |
ML20196J486 | 30 July 1997 | Forwards Integrated Plant Assessment (IPA) Sys Rept on RPV & Control Element Drive Mechanisms/Electrical Sys for Review & Approval | Exelon Cruse C | Office of Information Resources Management |
ML20199C807 | 14 November 1997 | Forwards Integrated Plant Assessment Sys & Commodity Repts for Review & Approval IAW 10CFR54,license Renewal Rule. Amends Will Be Submitted That Identify Any Changes to Current Licensing Basis Per 10CFR54.21(b) | Exelon Cruse C | Office of Information Resources Management |
ML20197D224 | 17 December 1997 | Forwards Integrated Plant Assessment Sys Repts for Review & Approval IAW 10CFR54,license Renewal Rule.Info Accurate as of Dates of Refs Listed Therein.Amend or Amends Will Be Submitted That Identify Any Changes | Exelon Cruse C | Office of Information Resources Management |
ML20199A111 | 21 January 1998 | Forwards Integrated Plant Assessment (IPA) Commodity & Sys Repts for Review & Approval IAW 10CFR54 | Exelon Cruse C | Office of Information Resources Management |
ML20151X751 | 3 September 1998 | Forwards RAI Re Plant,Units 1 & 2 Integrated Plant Assessment Technical Rept for Rcs,Section 4.1.Response Requested within 30 Days of Receipt of Ltr | NRC (Affiliation Not Assigned) Dave Solorio | Exelon Cruse C |
ML20155H253 | 4 November 1998 | Provides Response to RAI for Review of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 Integrated Plant Assessment Rept for Safety Injection Sys | Exelon Cruse C | Office of Information Resources Management |
ML20195D556 | 13 November 1998 | Forwards Revised RAI Re Result of Bge Comments Provided to NRC,980928.Specifically RAI Numbers 5.10.6 & 4.2.8 Are Being Clarified by This Ltr | NRC (Affiliation Not Assigned) Dave Solorio | Exelon Cruse C |
ML20195J039 | 16 November 1998 | Summary of 980928 Meeting with Util in Rockville,Md Re License Renewal Activities for Plant,Units 1 & 2 & to Provide Rept Card for Both NRC & Util | NRC (Affiliation Not Assigned) Dave Solorio | NRC (Affiliation Not Assigned) |
ML20195J618 | 19 November 1998 | Forwards Responses to 980903 RAI for Review of Ccnpp,Units 1 & 2 Integrated Plant Assessment Rept for Rcs,Per License Renewal Application | Exelon Cruse C | Office of Information Resources Management |
ML20207F026 | 1 June 1999 | Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2 | Exelon | |
ML020950022 | 2 April 2002 | 15-Day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | Exelon Cruse C | Office of Nuclear Reactor Regulation Document Control Desk |
ML022630288 | 17 September 2002 | Inservice Inspection Report | Exelon Katz P | Office of Nuclear Reactor Regulation Document Control Desk |
ML023230447 | 19 November 2002 | Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Request for Additional Information | NRC/NRR/DLPM/LPD1 Skay D | Calvert Cliffs Katz P |
IR 05000317/2003002 | 7 May 2003 | IR 05000317-03-002, 05000318-03-002; Calvert Cliffs Nuclear Plant, Inc.; on 12/29/2002 -3/29/2003; Calvert Cliffs Nuclear Power Plant, Units 1 & 2; Drill Evaluation and Event Follow-up | James Trapp Reactor Projects Region 1 Branch 1 | Constellation Generation Group Katz P |
ML21278A302 | 7 September 2021 | 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.5, References | Exelon | Office of Nuclear Reactor Regulation |