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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 | |
ML20154P892 | 27 May 1988 | Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants, Per 10CFR50.54(f) | Ameren Schnell D | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
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 | |
ML20153C857 | 30 August 1988 | Advises That 880527 Response to Generic Ltr 88-05 Describing Commitment to Boric Acid Leakage Monitoring & Preventative Program Fulfills Requirement | Alexion T Office of Nuclear Reactor Regulation | Ameren Schnell D |
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 | |
ML20076F988 | 12 October 1994 | Rev 0 to Second 10-Yr Interval ISI Plan for Callaway Nuclear Power Plant | Ameren Kulat S Mccraken S Potter H | |
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 | |
ML20117D077 | 19 August 1996 | Informs That ISI-07A Revised & Resubmitted as ISI-07B,per 10CFR50.55a(a)(3).Addl Component Specific Info,Supports Alternative Exam,Included in Attachment to Ltr.Nrc Approval Requested | Ameren Schnell D | Office of Information Resources Management |
ML20129G894 | 3 October 1996 | Safety Evaluation Re Second 10-yr Interval Insp Program Plan Revised Request for Relief ISI-07B | NRC (Affiliation Not Assigned) | |
ML20217F318 | 24 March 1998 | SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program | NRC (Affiliation Not Assigned) | |
ML20210H653 | 30 July 1999 | SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 | NRC (Affiliation Not Assigned) | |
ML020940171 | 1 April 2002 | Amerenue'S Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | AmerenUE Affolter R | Office of Nuclear Reactor Regulation Document Control Desk |
ML023260148 | 21 November 2002 | RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 15-Day & 60-Day Responses | NRC/NRR/DLPM/LPD4 Donohew J | Union Electric Co Randolph G |
ULNRC-04799, Response to Request for Additional Information - NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity. | 30 January 2003 | Response to Request for Additional Information - NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity. | AmerenUE Blosser J | Office of Nuclear Reactor Regulation Document Control Desk |
ULNRC-04920, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity | 19 November 2003 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity | AmerenUE Keith Young | Office of Nuclear Reactor Regulation Document Control Desk |
ULNRC-05425, Facility Operating License NPF-030 Cycle 15 Commitment Change Summary | 16 July 2007 | Facility Operating License NPF-030 Cycle 15 Commitment Change Summary | AmerenUE Graessle L | Office of Nuclear Reactor Regulation Document Control Desk |
ULNRC-05920, Enclosure 2 to ULNRC-05920, Amendment 13, LRA Changes from RAI Responses | 24 October 2012 | Enclosure 2 to ULNRC-05920, Amendment 13, LRA Changes from RAI Responses | Union Electric Co Ameren Missouri | Office of Nuclear Reactor Regulation |
ML20209A044 | 13 November 2019 | Rev. OL-24 to Final Safety Analysis Report, Chapter 19, License Renewal Supplement | Union Electric Co Ameren Missouri | Office of Nuclear Reactor Regulation |
ML21193A208 | 22 June 2021 | Revision OL-25 to Final Safety Analysis Report, Chapter 19, License Renewal Supplement | Ameren Missouri | Office of Nuclear Reactor Regulation |
ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138) | 27 January 2022 | Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138) | Union Electric Co Ameren Missouri | Office of Nuclear Reactor Regulation |
ML22220A132 | 21 October 2022 | Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach | Mahesh Chawla Plant Licensing Branch IV | Ameren Missouri Diya F |
ML23062A624 | 29 December 2022 | Revision OL-26 to Final Safety Analysis Report, Chapter 19, License Renewal Supplement | Union Electric Co Ameren Missouri | Office of Nuclear Reactor Regulation |