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Issue date | Title | |
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ML23334A182 | 30 November 2023 | Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 |
NRC-2015-0070, Comment (044) from Mary Lampert of Pilgrim Watch on PR-20, 26, 50, 51, 52, 72, 73 and 140 - Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning | 22 August 2022 | Comment (044) from Mary Lampert of Pilgrim Watch on PR-20, 26, 50, 51, 52, 72, 73 and 140 - Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning |
ML19142A043 | 18 December 2019 | Letter and Safety Evaluation, Exemption to Allow Reduced Emergency Planning Requirements; Revise Radiological Emergency Response Plan Consistent with Permanently Defueled Reactor |
ML19088A050 | 25 March 2019 | (PNPS) - Request for Exemption from Portions of 10 CFR 50.54(w)(1) |
ML19088A127 | 25 March 2019 | (PNPS) - Request for Exemption from 10 CFR 140.11 (a)(4) |
ML19051A019 | 20 February 2019 | Watch Petition to Intervene and Hearing Request |
ML18218A174 | 1 August 2018 | Revised the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition |
CNRO-2018-00031, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E | 3 July 2018 | Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E |
ML16278A313 | 17 April 2017 | NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding External Events |
ML16187A325 | 24 June 2016 | Request for Extension to Comply with NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions |
ML15069A112 | 17 April 2015 | G20110563 - Licensee Letter Regarding Draft Director'S Decision to Licensee'S with Mark I and II Containment Design |
ML12215A314 | 17 April 2015 | Proposed Director'S Decision - 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs |
ML12215A283 | 17 April 2015 | G20110563 - LTR to Lochbaum -- Draft Director'S Decision Re 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs |
ML15043A754 | 24 March 2015 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) |
ML14188B731 | 30 June 2014 | Phase 1 Overall Integrated Plan in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) |
ML14003A046 | 12 December 2013 | FSAR Update Revision 29, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Regulatory Commitment Changes |
ML13063A096 | 28 February 2013 | Overall Integrated Plan for Reliable Hardened Containment Vents |
ML12122A071 | 14 May 2012 | Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 |
ML11326A153 | 9 November 2011 | FSAR Update Revision 28, Technical Specifications Bases Changes, 10 CFR 50.59(d) Report, and Commitment Changes |
ML11178A379 | 27 June 2011 | Exhibit 4, Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety - the Accident at Tepco'S Fukushima Nuclear Power Stations |
ML11178A383 | 27 June 2011 | Exhibit 4, Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety - the Accident at Tepco'S Fukushima Nuclear Power Stations |
ENOC-11-00010, Comments Opposing NRC Acceptance of Petition for Emergency Enforcement Action for GE Boiling Water Reactors Utilizing Mark I Primary Containment Systems and Without Dedicated Class E1 Power for Cooling Elevated Irradiated Used Fuel Sto | 24 May 2011 | Comments Opposing NRC Acceptance of Petition for Emergency Enforcement Action for GE Boiling Water Reactors Utilizing Mark I Primary Containment Systems and Without Dedicated Class E1 Power for Cooling Elevated Irradiated Used Fuel Storage |
NRC-2010-0131, Brief of Nuclear Energy Institute as Amicus Curiae in Opposition to the Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions | 2 May 2011 | Brief of Nuclear Energy Institute as Amicus Curiae in Opposition to the Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions |
ML110420305 | 31 January 2011 | Entergy - Response to NRC Request for Additional Information Dated January 10, 2011, to Support the Review of Setpoint and Setpoint Tolerance Increases for Safety Relief Valves (SRV) and Spring Safety Valves (SSV) |
ML083050631 | 31 October 2008 | Concurring Opinion of Administrative Judge Ann Marshall Young to Initial Decision Issued October 30, 2008 (LBP-08-22) |
ML081830650 | 23 June 2008 | Pilgrim Watch Rebuttal to NRC Staff Proposed Findings of Fact Conclusions of Law, and Order in the Form of an Initial Decision |
ML081610820 | 9 June 2008 | Pilgrim - NRC Staff Proposed Findings of Fact and Conclusions of Law, and Order in the Form of an Initial Decision |
ML081070329 | 10 April 2008 | Official Transcript of Pilgrim Evidentiary Hearing Held in Plymouth, Ma; Pp. 557-874 |
ML081090245 | 6 March 2008 | Pilgrim April 2008 Evidentiary Hearing - Applicant Exhibit B, Rebuttal Testimony of A. Cox, B. Sullivan, S. Woods, W. Spataro on Pilgrim Watch Contention 1, Regarding Adequacy of Aging Management Program for Buried Pipes and Tanks and ... |
ML080740276 | 6 March 2008 | Rebuttal Testimony of Alan Cox, Brian Sullivan, Steve Woods, and William Spataro on Pilgrim Watch Contention 1, Regarding Adequacy of Aging Management Program for Buried Pipes and Tanks and Potential Need for Monitoring Wells To... |
ML062850366 | 10 October 2006 | Part 21 Notification - BWR Core Shroud Tie Rod Upper Support Cracking |
ML062080589 | 21 July 2006 | Pilgrim - Entergy'S Brief on New and Significant Information in Response to Licensing Board Order of July 14, 2006 |
ML062020795 | 21 July 2006 | Pilgrim - NRC Staff'S Response to July 14, 2006 Licensing Board Order |
ML061940179 | 6 July 2006 | 2006/07/06- Pilgrim - Official Transcript of Oral Arguments on Contentions for the Pilgrim Nuclear Power Station License Renewal Proceeding |
ML061930418 | 5 July 2006 | 2006/07/05-Pilgrim, License Renewal Application Amendment 4: Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives |
ML061870225 | 29 June 2006 | Pilgrim - Massachusett'S Attorney General'S Reply to Entergy'S and NRC Staff'S Responses to Hearing Request and Petition to Intervene |
ML061840216 | 26 June 2006 | Pilgrim - Entergy'S Answer to the Request for Hearing and Petition to Intervene by Pilgrim Watch and Notice of Adoption of Contention |
ML061790134 | 22 June 2006 | Pilgrim - Entergy'S Answer to Massachusetts Attorney General'S Request for a Hearing, Petition for Leave to Intervene, and Petition for Backfit Order |
ML072500130 | 26 May 2006 | Commonwealth of Massachusetts V. USNRC; Nos. 07-1482 and 07-1483; Joint Appendix |
ML20128G562 | 30 September 1996 | Seismic Evaluation Rept for Resolution of USI A-46 |
ML20128G536 | 30 September 1996 | Safe Shutdown Equipment List Rept for Resolution of USI A-46 |
BECO-LTR-94-117, Forwards Response to 941019 RAI Re Reactor Core Shroud at Plant.Proprietary Response to Question 4 Also Encl. Proprietary Response Withheld | 28 October 1994 | Forwards Response to 941019 RAI Re Reactor Core Shroud at Plant.Proprietary Response to Question 4 Also Encl. Proprietary Response Withheld |
ML20062B393 | 12 October 1990 | Comments on NRC Draft Generic Ltr 88-20,Suppl 4, Individual Plant Exam of External Events for Severe Accident Vulnerabilities - 10CFR50.54(f). Endorses NUMARC 901010 Comments |
IR 07100022/2011004 | 12 November 1987 | Forwards Facility Biweekly Status Rept for 871022-1104 |
ML20205E325 | 19 March 1987 | Insp Rept 50-293/87-03 on 870101-0220.Violations Noted: Failure to Properly Control High Radiation Area Keys,Failure to Initiate Failure & Malfunction Rept & Failure to Comply W/Fire Protection Sys Tech Specs |
ML20087L093 | 31 August 1983 | Safety Review of Pilgrim Nuclear Power Station,Unit 1 at Core Flow Conditions Above Rated Flow Throughout Cycle 6 |
ML19347C958 | 4 March 1981 | Forwards Addl Info Re Containment Vent & Purge Valve Operability,In Response to 801210 Ltr |
ML19309D518 | 4 April 1980 | Forwards Methods of Implementation for Category a Items Re 791030 Discussions of Lessons Learned Task Force short-term Requirements.Conformance Necessary Prior to Next Operating Cycle |
ML19254F562 | 15 October 1979 | Comments on IE Bulletin 79-02,Suppl 1,Revision 1, Pipe Supports Base Plate Designs Using Concrete Expansion Anchor Bolts. Interim Threshold Anchor Bolt Safety Factor Too Conservative |
ML20204B400 | 5 October 1978 | Responds to NRC 780807 Request for Evaluation of Reactor Protection Sys Power Supply.Ge Will Rept on Failure Modes & Effects by mid-Nov |