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Issue date | Site | Title | |
---|---|---|---|
ML15295A337 | 28 October 2015 | Results of Periodic Review of Regulatory Guide (RG)1.126 | |
ML13169A114 | 10 June 2013 | Indian Point | Official Exhibit - NYS000477-00-BD01 - CR-IP2-2012-05324, Condition Report Regarding Visual Inspection of 4' Service Water Return Line (Sept. 11, 2012) Inspection Date: 08/22/2012 |
ML13161A452 | 22 August 2012 | Indian Point | State of New York Pre-Filed Evidentiary Hearing Exhibit NYS000477, Condition Report CR-IP2-2012-05324 (Service Water Return Line), Inspection Date: 08/22/2012 |
ML13011A399 | 9 June 2012 | Indian Point | Entergy Pre-Filed Hearing Exhibit ENT000605, Gel, Laboratory Soil Analysis of IP2 Service Water and IP3 CST Soils (June 9, 2012) |
ML13039A462 | 9 June 2012 | Indian Point | Official Exhibit - ENT000605-00-BD01 - Gel, Laboratory Soil Analysis of IP2 Service Water and IP3 CST Soils (June 9, 2012) |
ML12340A756 | 31 May 2012 | Indian Point | Official Exhibit - ENT000582-00-BD01 - Gza/Theielsch Engineering Soil Resisitivity Data for IP2 & IP3 AFW Bldg, IP2 SW Line 408 (June 2012) |
ML12276A473 | 31 May 2012 | Indian Point | Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000582, Gza/Theielsch Engineering Soil Resisitivity Data for IP2 & IP3 AFW Bldg, IP2 SW Line 408 (June 2012) |
ML12130A517 | 9 May 2012 | Indian Point | Entergy Pre-Filed Evidentiary Hearing Exhibit ENTR00373 - Testimony of Applicant Witnesses Alan Cox, Ted Ivy, Nelson Azevedo, Robert Lee, Stephen Biagiotti, and Jon Cavallo Concerning NYS-5 (Buried Piping and Tasks) (Revised May 9, 2012) |
ML12090A660 | 30 March 2012 | Indian Point | Entergy Pre-Filed Hearing Exhibit ENT000375, Curriculum Vitae of Robert C. Lee |
ML12339A458 | 30 March 2012 | Indian Point | Official Exhibit - ENT000375-00-BD01 - Curriculum Vitae of Robert C. Lee |
ML12339A556 | 8 December 2011 | Indian Point | Official Exhibit - ENT000444-00-BD01 - Condition Report, CR-IP2-2011-06250 |
ML12090A780 | 8 December 2011 | Indian Point | Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000444 - Condition Report, CR-IP2-2011-06250 |
ML12090A773 | 8 December 2011 | Indian Point | Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000443 - Condition Report, CR-IP2-2011-06248 |
ML12339A550 | 8 December 2011 | Indian Point | Official Exhibit - ENT000443-00-BD01 - Condition Report, CR-IP2-2011-06248 |
ML12334A695 | 29 April 2011 | Indian Point | Official Exhibit - NYS000174-00-BD01 - SEP-UIP-IPEC, Rev. 0, Underground Components Inspection Plan (IPEC00234037) (SEP-UIP-IPEC) |
ML113530086 | 29 April 2011 | Indian Point | New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000174, SEP-UIP-IPEC, Rev. 0, Underground Components Inspection Plan (IPEC00234037) (SEP-UIP-IPEC) |
ML20093F003 | 1 January 2011 | SAND2011-0128 - Accident Source Terms for LWR NPPs Using High-Burnup or MOX Fuel | |
ML12334A707 | 30 December 2008 | Indian Point | Official Exhibit - NYS000180-00-BD01 - Entergy, Corrective Action, LO-IP3LO-2008-00151 (Dec. 30, 2008) (LO-IP3LO-2008-00151) |
ML113530099 | 30 December 2008 | Indian Point | New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000180, Entergy, Corrective Action, LO-IP3LO-2008-00151 (Dec. 30, 2008) (LO-IP3LO-2008-00151) |
ML090410051 | 1 July 2008 | Indian Point | EC 5000033794, Revision 1, Indian Point 2 Station Blackout and Appendix R Diesel Generator Set |
IR 05000003/2037094 | 1 July 2008 | Indian Point | EC 5000033794, Revision 1, Indian Point 2 Station Blackout and Appendix R Diesel Generator Set |
ML092870685 | 26 October 2004 | Indian Point | Exhibit R - Aermod: a Dispersion Model for Industrial Source Applications. Part II: Model Performance Against 17 Field Study Databases |
ML20212G319 | 30 September 1999 | Corium Dispersion in Direct Containment Heating.Separate Effect Experiments with Water and Woods Metal Simulating Core Melt for Zion Reactor Conditions | |
ML20212G328 | 30 September 1999 | Corium Dispersion in Direct Containment Heating.Theoretical Analysis of the Hydrodynamic Characteristics | |
M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function | 12 July 1999 | Braidwood | Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function |
ML20216D384 | 12 July 1999 | Braidwood | Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function |
ML20196A072 | 16 March 1999 | Braidwood | Cycle 8 COLR in ITS Format & W(Z) Function |
ML20206U908 | 17 December 1998 | Braidwood | Cycle 8 COLR in ITS Format & W(Z) Function |
ML20196B371 | 8 September 1998 | Braidwood | Cycle 8 Operating Limits Rept (Olr) |
ML20134K080 | 26 August 1996 | Summary of 960819-20 Meeting at Fauske & Associates,Inc in Burr Ridge,Il Re Review of SCDAP/RELAP5 Code Modeling of Natural Circulation Under Severe Accident Conditions | |
ML20127L171 | 31 December 1992 | 07100200 | Notifies That Licensee No Longer Wishes to Participate in QA Program |
ML20151G277 | 28 May 1988 | 07109033 07109032 | Advises That Listed Equipment Authorized for Radiography on Board Uss Dixon,Permit 59-20132-A1NP |
ML20148K637 | 29 February 1988 | THERMAL-HYDRAULIC Research Plan for Babcock and Wilcox Plants | |
ML20197D665 | 16 October 1987 | Notification of 871020 Meeting W/B&W Owners Group & EPRI in Bethesda,Md to Discuss Technical Issues & Data Needs to Further Understanding of once-through-steam Generator Behavior Under Transient & Accident Conditions | |
ML20237J623 | 24 August 1987 | Revised Agenda for 870826 Meeting W/B&W Owners Group in Bethesda,Md to Discuss Thermal Hydraulic Testing for B&W Plants | |
IR 05000313/1987022 | 11 August 1987 | Arkansas Nuclear | Insp Repts 50-313/87-22 & 50-368/87-22 on 870701-31. Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance,Followup on Previously Identified Items,Lers & Plant Safety Committee |
ML20236J028 | 31 July 1987 | Arkansas Nuclear | Forwards Draft Safety Evaluation of Auxiliary Feedwater Sys (Generic Issue 124) Re ANO-2.Preliminary Findings Discussed at 870610 Public Meeting,Still Being Reviewed |
ML20235Y032 | 21 July 1987 | Arkansas Nuclear | Forwards Request for Addl Info Supporting Util 831105,850527 & 0726 Responses to Item 2.2 (Part 2) of Generic Ltr 83-28, Vendor Interface (Programs for All Safety-Related Components). Response Requested by 60 Days of Ltr Receipt |
ML20235F016 | 1 July 1987 | Arkansas Nuclear | Summary of 870610 Meeting W/Util in Bethesda,Md Re Reliability of Plant Emergency Feedwater Sys.List of Meeting Attendees Encl |
ML20214S881 | 3 June 1987 | Arkansas Nuclear | Notification of 870609 Meeting W/Util in Bethesda,Md to Discuss Emergency Feedwater Sys Reliability |
ML20209F011 | 20 April 1987 | Arkansas Nuclear | Requests Assistance in Making Arrangements for Bnwl 870427 Site Visit to Gather Info for NRC Nuclear Plant Aging Research Program & Review Emergency Operating Procedures |
ML20206B625 | 8 April 1987 | Satsop | Forwards from Energy Facility Site Evaluation Council of State of Wa Advising That C Eschels Replaced Nd Lewis as Council Chairman.Distribution Lists for Future Amends to FSAR & Environ Repts Should Be Revised |
ML20206B544 | 7 April 1987 | Satsop | Requests Addl Info Re Facility Soil Structure interaction- Deconvolution Issue within 90 Days of Ltr Receipt,Per Encl List |
ML20207S216 | 9 March 1987 | Arkansas Nuclear | Forwards Request for Addl Info Re Items 2.1 & 2.2.1 of Generic Ltr 83-28 & Description of Vendor Interface Program. Response to Addl Info Due within 60 Days of Ltr |
ML20212K292 | 2 March 1987 | Arkansas Nuclear | Provides Info Re Implementation Schedules.Due to Delays Incurred in Preparation of QA Guidance (Generic Ltr 85-06) & Extensive Time & Effort Resolving Complex Issues,Deadline Extended to No Later than 840724 |
ML20213H007 | 13 November 1986 | Arkansas Nuclear | Advises That Site Visit Scheduled for 861202-05 to Review Design,Maint,Surveillance Testing & Reliability of Emergency Feedwater Sys.Assistance in Making Necessary Arrangements Requested.Agenda Will Be Provided by 861117 |
ML20215L608 | 24 October 1986 | Arkansas Nuclear | Forwards SAIC-86/3070, Technical Evaluation of Dcrdr, Arkansas Nuclear One,Unit 1, & SAIC-86/3067, Technical Evaluation of Dcrdr,Arkansas Nuclear One,Unit 2, Technical Evaluation Repts.Open Items & Need for Addl Info Noted |
ML20211G281 | 23 October 1986 | Arkansas Nuclear | Informs That NRC Will Be Conducting post-accreditation Review of Facilities Training Programs Beginning 861104.Exit Briefing Will Be Held 861106.Cwalina 861020 Memo Providing Specific Info Encl |
ML20211G109 | 23 October 1986 | Arkansas Nuclear | Forwards Safety Evaluation Re Util 840413 & 850701 Responses to Reg Guide 1.97, Emergency Response Capability. Responses Acceptable.Requests Addl Info Re Instrument Range of RCS Pressure Instrumentation within 60 Days |
ML20211D494 | 16 October 1986 | Arkansas Nuclear | Approves Util 840830 Request to Withhold Proprietary R-84-011-P, Final Rept for Phase 1 of Arkansas Power & Light Co Inadequate Core Cooling..., from Public Disclosure (Ref 10CFR2.790) |