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 Issue dateTitleFromTo
NRC Generic Letter 1988-0517 March 1988NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR PlantsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1988-077 April 1988NRC 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
ML20154P89227 May 1988Responds 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 Specification2 August 1988NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical SpecificationsMiraglia F
Office of Nuclear Reactor Regulation
ML20153C85730 August 1988Advises That 880527 Response to Generic Ltr 88-05 Describing Commitment to Boric Acid Leakage Monitoring & Preventative Program Fulfills RequirementAlexion T
Office of Nuclear Reactor Regulation
Ameren
Schnell D
NRC Generic Letter 1991-1717 October 1991NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants.Partlow J
Office of Nuclear Reactor Regulation
ML20076F98812 October 1994Rev 0 to Second 10-Yr Interval ISI Plan for Callaway Nuclear Power PlantAmeren
Kulat S
Mccraken S
Potter H
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion.5 January 1995Degradation 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 1995Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion.Grimes B
Office of Nuclear Reactor Regulation
ML20117D07719 August 1996Informs 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 RequestedAmeren
Schnell D
Office of Information Resources Management
ML20129G8943 October 1996Safety Evaluation Re Second 10-yr Interval Insp Program Plan Revised Request for Relief ISI-07BNRC (Affiliation Not Assigned)
ML20217F31824 March 1998SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp ProgramNRC (Affiliation Not Assigned)
ML20210H65330 July 1999SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1NRC (Affiliation Not Assigned)
ML0209401711 April 2002Amerenue'S Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary IntegrityAmerenUE
Affolter R
Office of Nuclear Reactor Regulation
Document Control Desk
ML02326014821 November 2002RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 15-Day & 60-Day ResponsesNRC/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 2003Response 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 Integrity19 November 2003Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary IntegrityAmerenUE
Keith Young
Office of Nuclear Reactor Regulation
Document Control Desk
ULNRC-05425, Facility Operating License NPF-030 Cycle 15 Commitment Change Summary16 July 2007Facility Operating License NPF-030 Cycle 15 Commitment Change SummaryAmerenUE
Graessle L
Office of Nuclear Reactor Regulation
Document Control Desk
ULNRC-05920, Enclosure 2 to ULNRC-05920, Amendment 13, LRA Changes from RAI Responses24 October 2012Enclosure 2 to ULNRC-05920, Amendment 13, LRA Changes from RAI ResponsesUnion Electric Co
Ameren Missouri
Office of Nuclear Reactor Regulation
ML20209A04413 November 2019Rev. OL-24 to Final Safety Analysis Report, Chapter 19, License Renewal SupplementUnion Electric Co
Ameren Missouri
Office of Nuclear Reactor Regulation
ML21193A20822 June 2021Revision OL-25 to Final Safety Analysis Report, Chapter 19, License Renewal SupplementAmeren MissouriOffice 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 2022Enclosure 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
ML22220A13221 October 2022Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed ApproachMahesh Chawla
Plant Licensing Branch IV
Ameren Missouri
Diya F
ML23062A62429 December 2022Revision OL-26 to Final Safety Analysis Report, Chapter 19, License Renewal SupplementUnion Electric Co
Ameren Missouri
Office of Nuclear Reactor Regulation