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 Issue dateTitle
ML21042B89611 January 2021Independent Spent Fuel Storage Installation, Biennial Update of the Defueled Safety Analysis Report
ML17025A10112 January 2017Independent Spent Fuel Storage Installation - Biennial Update of Defueled Safety Analysis Report
ML15029A20412 January 2015Defueled Safety Analysis Report, Revision 27, Enclosure 2 to OMY-15-001
ML15029A20312 January 2015Defueled Safety Analysis Report, Revision 26, Enclosure 1 to OMY-15-001
ML13031A07224 January 2013Submittal of the Maine Yankee Defueled Safety Analysis Report Revisions 24 and 25
ML11256A0519 September 2011Application for Consent to Proposed License Transfers: Request for Threshold Determination
ML11033017824 January 2011Submittal of the Defueled Safety Analysis Report Rev. 23
RA-05-008, Response to NRC Rai'S on FSS Final Report Nos. 1 and 216 February 2005Response to NRC Rai'S on FSS Final Report Nos. 1 and 2
ML20195H19115 June 1999Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests.Requests That Commission Consent to Two Indirect Transfers of Control & Direct Transfer
IR 05000306/19960098 October 1998Discusses Results of Several NRC Insp Repts 50-306/96-09, 50-309/96-10,50-309/96-11,50-309/96-16 & 50-309/97-01, Conducted Between 960715 & 970315,three Investigations Repts 1-95-050,1-96-025 & 1-96-043 & Forwards Notice of Violation
ML20154J4518 October 1998Responds to Which Replied to NRC DFI Issued 971219 to Yaec & Duke Engineering & Services,Inc.Nrc Staff Completed Review of Responses of Yaec & Duke Engineering & Services Inc & 2 Individuals
ML20154J8458 October 1998Responds to Which Forwarded Response to NRC Demand for Info Issued on 971219 Re OI Rept 1-95-050. Related Ltr Also Issued to Maine Yankee Identifying Apparent Violations
ML20236X1683 August 1998Forwards Revs 15 & 16 to Maine Yankee Defueled SAR, Per Requirements of 10CFR50.71 & 10CFR50.4
ML20247D3456 May 1998Rev 15 to Defueled SAR, Replacing List of Effective Pages
ML20217J94413 April 1998Requests That Enforcement Conference Currently Scheduled for 980423 Be Moved to Wiscasset,Maine & Response to List of Questions That Have Been Raised Re Meeting & Process Involved
ML20217N3723 April 1998Provides Response to Re Apparent Violations Stemming from OI Repts 1-95-025,1-96-050 & 1-96-043.Factual Record Underlying Apparent Violations Does Not Support Conclusion That Personnel Disregarded NRC Requirements
ML20210J63911 August 1997Forwards Response to Violations Noted in Insp Rept 50-309/97-05.Corrective actions:mis-positioned Mechanical Stop - Learning Bank Entry 97-02640 Written & Evaluation of Event Performed
ML20210L08111 July 1997Notice of Violation from Insp on 970414-0608.Violation Noted:Ist Requirements of 10CFR50.55a(f) Were Implemented Without Authorization of Director of NRR as Listed
NRC Generic Letter 1996-0331 January 1996NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
Information Notice 1991-14, Recent Safety-Related Incidents at Large Irradiators5 March 1991Recent Safety-Related Incidents at Large Irradiators
Information Notice 1989-82, Recent Safety-Related Incidents at Large Irradiators7 December 1989Recent Safety-Related Incidents at Large Irradiators
NRC Generic Letter 1989-098 May 1989NRC Generic Letter 1989-009: ASME Section III Component Replacements
ML20244D01914 April 1989Forwards Sec Form 10K Re Annual Rept for FY88
Information Notice 1988-53, Licensee Violations of NRC Regulations, Which Led to Medical Diagnostic Misadministrations28 July 1988Licensee Violations of NRC Regulations, Which Led to Medical Diagnostic Misadministrations
ML20151E5087 April 1988Forwards 1987 Annual Financial Rept for Main Yankee Atomic Power Co,Per 10CFR50.71(b).Original Rept on File W/ Securities & Exchange Commission
NRC Generic Letter 1983-4319 December 1983NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications
ML16148A42322 May 1981Comments on Encl B&W Rept Ltr Rept on Reactor Vessel Brittle Fracture Concerns in B&W Operating Plants. Addl plant-specific Info in Support of Subj Rept Provided.Util Will Complete Analysis to Resolve Generic Concerns