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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML20094S316 + (Revised Personnel Exposure Rept for 1990)
- ML20091A018 + (Revised Personnel Exposure Rept for 1991, Consisting of Tabulation of Number of Station,Util & Other Personnel Receiving Exposure of More than 100 Mrem/Yr)
- ML20154G893 + (Revised Personnel Whole Body Exposures for CY87 & Personnel Monitoring Rept & Notification Summary for 1987,per Reg Guide 1.16)
- NOC-AE-13003004, Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights + (Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights)
- ML13182A021 + (Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights)
- ML052580162 + (Revised Physical Security Plan)
- L-2003-258, Revised Physical Security Plan + (Revised Physical Security Plan)
- ML060740412 + (Revised Physical Security Plan (PSP))
- ML12032A135 + (Revised Pilgrim Relief Request (PRR)-21, Revision 3, Contingency Repair Plan for Reactor Pressure Vessel (RPV) Standby Liquid Control Nozzle Weld, RPV-N14-1)
- ML12128A152 + (Revised Pilgrim Relief Request (PRR)-21, Revision 4, Contingency Repair Plan for Reactor Pressure Vessel (RPV) Standby Liquid Control Nozzle Weld, RPV-N14-1)
- ML20073F941 + (Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1)
- ML20073F950 + (Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station)
- ML20205G693 + (Revised Plant Emergency Procedures,Including Rev 15 to Procedure Pep 02.1, Initial Emergency Actions, Rev 8 to Procedure Pep 02.2, Emergency Control - Unusual Event & Rev 8 to Procedure Pep 02.3, Emergency Control - Alert)
- ML18019A589 + (Revised Plant Emergency Procedures,Including Rev 2 to PEP-223, Radiological Control Manager & Rev 1 to PEP-103, Site Emergency Coordinator - Technical Support Ctr. W/One Oversize Drawing)
- ML20235G524 + (Revised Plant Emergency Procedures,Including Rev 2 to Change 5 to PEP-101, Emergency Classification & Initial Emergency Actions, & Rev 2 to PEP-221, Technical Analysis Manager. W/One Oversize Drawing)
- ML18018B768 + (Revised Plant Emergency Procedures,Including 1.0 Re Emergency Classifications & Control Procedures & 2.0 Re Emergency Mgt Guides.Three Oversize Figures Encl.Aperture Cards Available in PDR)
- ML20090H838 + (Revised Plant Procedure Indexes,Including Administrative Procedure,Chemistry Procedures,Emergency Plan Implementing Procedure,Environ Test Procedures & General Maint Procedure. W/840713 Transmittal Ltr)
- ML17284A643 + (Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package)
- ML17289A781 + (Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties)
- ML17286A738 + (Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15)
- IR 05000382/1996099 + (Revised Plant Support Section of SALP Rept 50-382/96-99)
- L-2019-130, Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results + (Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results)
- ML20062D105 + (Revised Portion of QA Program for Design & Const Phase, Revision 1.Description of Qa/Qc Program to Be Implemented Upon Bechtel Assumption of Ae Responsibilities Will Be Submitted by 811211)
- ML20037D199 + (Revised Portions of Monthly Operating Rept for Mar 1981 Re Unit Shutdowns & Power Reductions)
- ML20217K123 + (Revised Positions for DBNPS & PNPP QA Program)
- ML20155G633 + (Revised Post-Accident Sampling Sys Evaluation Rept)
- ML20215L380 + (Revised Post-Remedial-Action Radiological Survey Rept for Pu Facility of Bmi - Columbus Div West Jefferson Complex West Jefferson,Oh Apr 1980 - June 1982)
- ML102090071 + (Revised Power Reactor Security Rule)
- ML102080224 + (Revised Power Reactor Security Rule)
- ML102080325 + (Revised Power Reactor Security Rule)
- ML102070404 + (Revised Power Reactor Security Rule Letter)
- ML20137Q790 + (Revised Power Sys Mgt Business Dept Plan for Qualifying Class 1E Devices)
- IR 05000528/1994035 + (Revised Pp 2 & 14 to Insp Rept 50-528/94-35,50-529/94-35 & 50-530/94-35,correcting Any Ambiguity Re Submittal of TS Limits for Plant by Util)
- ML20134J414 + (Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2)
- ML102510015 + (Revised Prairie Island Indian Communitys Rebuttal Statement of Position on the Safety Culture Contention)
- ML102510008 + (Revised Prairie Island Indian Communitys Rebuttal Statement of Position on the Safety Culture Contention)
- ML102510007 + (Revised Prairie Island Indian Communitys Initial Statement of Position on Safety Culture Contention)
- ML20067B721 + (Revised Prairie Island Large Break LOCA Calculation Using WCAP-10924,Vol 1,Addenda 4 Model Changes)
- IR 05000282/2015004 + (Revised Prairie Island Nuclear Generating Plant, Units 1 and 2, NRC Integrated Inspection Report 05000282/2015004; 05000306/2015004, October 1, 2015 Through December 31, 2015)
- ML19165A078 + (Revised Pre-Application Meeting for the Model No. TN-32 Transportation Package with Tn Americas LLC)
- ND-18-1243, Revised Preliminary Amendment Request (Par): Passive Core Cooling System (Pxs) Gutter Drain Line Vents (PAR-18-022R1) + (Revised Preliminary Amendment Request (Par): Passive Core Cooling System (Pxs) Gutter Drain Line Vents (PAR-18-022R1))
- ML20154K244 + (Revised Preliminary Assessment of United Nuclear Corp Wood River Junction,Ri)
- ML20202E098 + (Revised Preliminary Evaluation of Us DOE Approach to Performance Assessment at West Valley Demonstration Project)
- ML20236G811 + (Revised Preservice Insp Plan for Nuclear Piping Sys & Component Supports)
- ML20236G816 + (Revised Preservice Insp Plan for Nuclear Piping Sys & Reactor Pressure Vessel)
- ML20247B199 + (Revised Pressure Temp Limits Rept for Byron Unit 2)
- ML21285A281 + (Revised Pressure and Temperature Limits Report)
- ML17313A128 + (Revised Pressure and Temperature Limits Report (PTLR))
- WBL-19-026, Revised Pressure and Temperature Limits Report (PTLR) + (Revised Pressure and Temperature Limits Report (PTLR))
- WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR) + (Revised Pressure and Temperature Limits Report (PTLR))
- WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR) + (Revised Pressure and Temperature Limits Report (PTLR))