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	Issue date	Site	Title
ML23271A073	28 September 2023		NRR E-mail Capture - Action: Opportunity to Review and Comment on an NRC Information Collection, 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (3150-0151)
ML23269A213	26 September 2023		NRR E-mail Capture - Action: Opportunity to Review and Comment on an NRC Information Collection, 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (3150-0151)
ML23269A125	25 September 2023		NRR E-mail Capture - Action: Opportunity to Review and Comment on an NRC Information Collection, 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (3150-0151)
ML22179A056	27 June 2022		Email to Holtec Regarding Transmission of Safeguards Information
ML20219A411	10 August 2020	NuScale	Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851
ML20113F081	22 April 2020		NRR E-mail Capture - Opportunity to Review and Comment on an NRC Proposed Information Collection NRC CUI Program Challenge Request Process
ML20062F726	5 March 2020	NuScale	Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public
ML19226A234	14 August 2019	NuScale	Request for Withholding Information from Public Disclosure for NuScale Power, LLC
ML19154A575	5 June 2019	NuScale	Request for Withholding Information from Public Disclosure for Nuscale Power, LLC
ML19108A453	22 April 2019	NuScale	Request for Withholding Information from Public Disclosure for NuScale Power, LLC
ML18201A226	7 December 2018	NuScale	LLC, Design Certification Application - Safety Evaluation with Open Items for Chapter 2, Site Characteristics and Site Parameters.
ML18323A445	20 November 2018	NuScale	Audit Plan for the Regulatory Audit of NuScale Power, LLC Topical Report TR-0516-49416, Non-Loss-Of-Coolant Accident Analysis Methodology, Revision 1 - Memo
ML18157A255	14 June 2018	NuScale	Summary of the Category 1 Public Teleconference with NuScale Power, LLC - Meeting to Discuss the NuScale Power Initial Test Program Review
ML081270079	6 May 2008	Palo Verde	Safety Evaluation for License Amendment Request, Change in Refueling Water Tank Level Requirement
ML052850300	5 October 2005	Oyster Creek	Audit and Review Plan for Plant Aging Management Reviews and Programs at the Oyster Creek Generating Station (Tac No. MC7624)
ML060740471	23 September 2005	Oyster Creek	E-mail: Oyster Creek Questions for AMP Audit (PD)
ML051250308	4 May 2005	Browns Ferry	Memo, Audit and Review Report for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plant
ML043210577	15 November 2004	Cook	Audit and Review Report for Plant Aging Management Reviews and Programs at the Donald C. Cook Nuclear Power Plant, Units 1 and 2
ML042300153	1 September 2004	Arkansas Nuclear	Section 3.5, Aging Management of Structures and Component Supports - ANO-2 SER Final W/Open and Confirmatory Items
ML042300068	1 September 2004	Arkansas Nuclear	Section 3.0, Aging Management Reviews Results - ANO-2 SER Final Draft W/Open and Confirmatory Items
ML042300091	1 September 2004	Arkansas Nuclear	Section 3.1, Aging Management of Reactor Vessel, Internals, and Reactor Coolant System - ANO-2 SER Final W/Open and Confirmatory Items
ML042300128	1 September 2004	Arkansas Nuclear	Section 3.2, Aging Management of Engineered Safety Features Systems - ANO-2 SER Final W/Open and Confirmatory Items
ML042300134	1 September 2004	Arkansas Nuclear	Section 3.3, Aging Management of Auxiliary Systems - ANO-2 SER Final W/Open and Confirmatory Items
ML042300148	1 September 2004	Arkansas Nuclear	Section 3.4, Aging Management of Steam and Power Conversion Systems - ANO-2 SER Final W/Open and Confirmatory Items
ML042300157	1 September 2004	Arkansas Nuclear	Section 3.6, Aging Management of Electrical and Instrumentation and Controls - ANO-2 SER Final W/Open and Confirmatory Items
ML042240274	19 August 2004	Arkansas Nuclear	Audit and Review Report for Plant Aging Management Reviews and Programs at the Arkansas Nuclear One Nuclear Power Plant, Unit 2
ML042240255	10 August 2004	Browns Ferry	Audit and Review Plan for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plants, Units 1, 2 and 3
ML042110488	27 July 2004	Arkansas Nuclear	Audit and Review Plan for Plant Aging Management Reviews and Programs at the Arkansas Nuclear One Nuclear Power Plant, Units 2
ML041950100	10 June 2004	Browns Ferry	Audit and Review Plan for Plant Aging Management Programs and Reviews - Browns Ferry Nuclear Plant, Units 1, 2 and 3
ML18101B140	21 December 1995	Salem	LER 95-014-00:on 951211,SI Throttle Valve Was Inoperable. Caused by Inadequate Deficiency.Installed Orifice in Cold Leg Branch Lines Prior to startup.W/951221 Ltr
ML18101B141	18 December 1995	Salem	LER 95-012-00:during Nov 1995,TDAFWP Encl Not Matching as- Built Conditions of 761211.Caused by Inadequate Verification of as-build Design Deficiency Calculations.Helb Calculations reviewed.W/951218 Ltr
ML20236B749	23 September 1987	Rancho Seco	Rev 1 to D-0050, Engineering Action Plan
ML20214H064	17 April 1987	Rancho Seco	Rev 0 to D-0050, Engineering Action Plan for Rancho Seco Nuclear Generating Station
ML19326B541	1 December 1973	Arkansas Nuclear	Reactor Containment Bldg Integrated Leak Rate Test.
ML20027A708	1 November 1972	Sequoyah	Rev 1 to Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants.

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