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 Issue dateSiteTitle
ML22194A93314 July 2022Charter for the Working Group on Assessing the NRC Telework Policy and Implementation
ML22143A93620 May 2022Nuclear Energy InstituteMay 13, 2022, Public Meeting on Draft Regulatory Issue Summary Operational Leakage, 87 Fed. Reg. 2361 (Jan. 14, 2022) (Docket Id NRC-2021-0173)
ML17228A17711 August 2017Clinch RiverFEMA - Review of an Early Site Permit Application for the Clinch River
ML17178A17726 June 2017Nuclear Energy InstituteComment (36) of the Nuclear Energy Institute on PR-50, 52 - Emergency Preparedness for Small Modular Reactors
ML17164A21612 June 2017Fort CalhounFEMA Letter (J. Hoyes) to NRC Dated June 12, 2017: Proposed Commission Paper Language for the Fort Calhoun Station Emergency Plan Decommissioning Exemption Request
ML17164A20612 June 2017Clinch RiverFEMA Letter (J. Hoyes) to NRC Dated June 12, 2017: FEMA Review of an Early Site Permit Application for the TVA Clinch River Nuclear Site
ML16286A23712 October 2016BrunswickFEMA Assessment of Offsite Plans and Preparedness Post-Hurricane Matthew (October 2016)
ML16285A5009 October 2016Robinson(Fema/Nrc Email) H.B. Robinson: FEMA Assessment of Offsite Plans and Preparedness Post-Hurricane Matthew (Oct 2016 Hurricane Matthew-FEMA Review of Offsite Plans and Preparedness)
ML16285A4557 October 2016Saint Lucie(Oct 2016 Hurricane Matthew-FEMA Notification of Intent to Review Offsite Plans and Preparedness)
ML07354005320 December 2007BellefonteResults of Acceptance Review for the Bellefonte Nuclear Plant, Units 3 & 4 Combined License Application
ML07243012920 July 2007Nine Mile Point
Fermi
Susquehanna
River Bend
05200006
PROJ0740
05200011
from: Brent Clayton, Subj: Pre-app Readiness Assessment
ML0627900135 October 2006VogtleRequest for Additional Information (RAI) for the Vogtle Early Site Permit Application Section 2.4
ML0624902196 September 2006Vogtle
PROJ0737
Acceptance Review Results for the Vogtle Early Site Permit Application (Section 13.6)
ML05158033219 April 2005MillstoneAlert Declared at Millstone Unit 3 on Sunday
ML05146028919 April 2005MillstoneE-mail Alert Declared at Millstone Unit 3 on Sunday
ML05145054019 April 2005MillstoneAlert Declared at Millstone Unit 3 on Sunday
ML0434800343 January 2005Public Version of the January 2005 Director'S Quarterly Status Report
ML04203018521 July 2004Surry
North Anna
Notice of Meeting with Virginia Electric & Power Company (VEPCO) to Discuss Vepco'S Proposed plant-specific Topical Report That Implements VIPRE-D Code
ML04198012216 July 2004Oconee
Mcguire
Catawba
McGuire
Notice of Meeting with Duke Energy Corporation to Discuss Proposed Amendment 33 to the Duke Energy Corporation Topical Report, Duke-1A
ML0419100161 July 2004CatawbaSummary of April 22, 2004, Conference Call Regarding Duke Power Company'S Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, for Catawba, Unit 1
ML04190016428 June 2004Oconee
Mcguire
Catawba
McGuire
Summary of June 1, 2004, Conference Call Regarding Duke Power Company'S Request to Modify Quality Assurance Program for Catawba, McGuire and Oconee Nuclear Stations
ML0415302091 June 2004Hatch
Vogtle
Farley
Docketing of Questions and Responses Transmitted Electronically or by Facsimile
ML0412805107 May 2004CatawbaNotice of Meeting with Duke Energy Corporation to Discuss Information Needed to Review the Issues in the Nuclear Regulatory Commission Staff'S Letter Dated April 30, 2004, Regarding the Use of Mixed Oxide Fuel at the Catawba Nuclear Station
ML05332044926 April 2004Vermont YankeeE-Mail from Marsh to Elliot, Vermont Yankee Revised Talking Points on Reactor Vessel Clad Cracking
ML03087028120 September 2002Davis BesseE-mail J. Hopkins, NRR, to C. Stephanie, Fwd: Sample Plan Phase 3
ML03086029615 July 2002Davis BesseE-mail D. Pickett, NRR, to A. Mendiola, NRR, Et Al, Fwd: Sample Plan Phase 3
ML02161019410 June 2002Indian PointSite Visit Trip Report
ML03153036924 May 2002Davis BesseE-mail from W. Norris to A. Hiser Et Al., Regarding NRC Questions on Safety Significance Assessment
ML03105003020 May 2002Davis BesseE-mail from J Grobe to a Hiser Et Al., Responses to Two NRC Questions Following the Root Cause Analysis Presentation
ML03085072015 May 2002Davis BesseSerial 1-1274 - Supplemental Information in Response to NRC Question Number 24 on the Preliminary Probable Cause Summary Report Dated March 22, 2002
ML03085061315 May 2002Davis BesseMeeting on Davis-Besse Risk Assessment
ML0308505776 May 2002Davis BesseMessage for Davis-Besse Root Cause Meeting
ML03153039915 April 2002Davis BesseE-mail from S. Long to A. Hiser Et Al., Regarding Items for Today 2:00 Pm Davis Besse Call
ML02099005410 April 2002Davis BesseSummary of Meeting Held on March 19, 2002, with NEI and EPRI Material Reliability Program to Discuss the Generic Implications of the Davis-Besse Reactor Vessel Heal Degradation
ML02099000810 April 2002Davis Besse
Nuclear Energy Institute
Summary of March 13, 2002 Telephone Conversation on the Davis-Besse Reactor Vessel Head Degradation Follow-up