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Issue date | Title | Topic | |
---|---|---|---|
ML23335A112 | 15 December 2023 | Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers | |
LR-N21-0007, Report of Changes, Tests, and Experiments | 28 January 2021 | Report of Changes, Tests, and Experiments | |
LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 25 July 2018 | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | High winds High Radiation Area Stroke time FLEX Tornado Missile Protection Design basis earthquake Foreign Material Exclusion Severe Accident Management Guideline Containment Hardened Vent Battery sizing Hardened vent |
LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 | 9 February 2017 | Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 | Shutdown Margin |
LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | 7 February 2017 | License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | Aging Management |
LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | 29 December 2016 | Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | High winds Ultimate heat sink Hydrostatic FLEX Fukushima Dai-Ichi |
ML16256A641 | 12 September 2016 | NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | |
LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | 12 September 2016 | NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | |
ML16256A640 | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
ML16256A643 | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents. | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. | 31 May 2016 | GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. | Minimum Critical Power Ratio Fuel cladding |
ML16049A609 | 29 February 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. | 9 December 2014 | Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. | Safe Shutdown High winds High Radiation Area Ultimate heat sink FLEX Fukushima Dai-Ichi Severe Accident Management Guideline |
LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 | 11 August 2014 | CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 | |
LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station | 25 April 2014 | CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station | |
LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... | 28 March 2014 | PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... | Safe Shutdown High winds Safe Shutdown Earthquake Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Earthquake Seismic Walkdown Report |
ML13266A297 | 18 November 2013 | Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident | Unanalyzed Condition Hydrostatic Fukushima Dai-Ichi Earthquake |
ML13052A675 | 28 November 2012 | Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary | |
LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary | 28 November 2012 | Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary | |
ML12220A250 | 10 August 2012 | Closeout of Bulletin 2011-01, Mitigating Strategies | B.5.b Mitigating Strategies |
ML12159A355 | 8 June 2012 | Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident | Fukushima Dai-Ichi Earthquake |
ML112700069 | 26 September 2011 | Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants | Shutdown Margin Anticipated operational occurrence Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Channel-control blade interference Scram Discharge Volume Earthquake |
ML11203A078 | 13 July 2011 | Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6 | Non-Destructive Examination Offsite Dose Calculation Manual Fire Barrier Tornado Missile Safe Shutdown Earthquake Enforcement Discretion Incorporated by reference Tornado Missile Protection Annual Radioactive Effluent Release Report Design basis earthquake Annual Radiological Effluent Release Report Earthquake Control of Heavy Loads Fuel cladding Fire Protection Program |
LR-N11-0090, 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations | 8 April 2011 | 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations | |
ML11061A005 | 30 March 2011 | Ncsa Hope Creek Observations Rev. 4 | |
LR-N10-0355, Salem, EAL Technical Bases Supporting Documents | 14 October 2010 | Salem, EAL Technical Bases Supporting Documents | Earthquake |
ML110060239 | 14 October 2010 | Salem, EAL Technical Bases Supporting Documents | Earthquake |
ML11263A030 | 20 September 2010 | E-mail with Attachment from B. Pham, NRR to L. Perkins, NRR, on Forward Salem/Hope Creek Chapter 5 SAMA Input | Safe Shutdown High winds Fire Barrier Internal Flooding B.5.b License Renewal Earthquake Power Uprate |
ML11263A028 | 16 September 2010 | E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo | Safe Shutdown High winds Fire Barrier Internal Flooding Probabilistic Risk Assessment Met Tower Severe Accident Management Guideline B.5.b Mitigating Strategies Earthquake |
LR-N10-0306, 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S | 10 August 2010 | 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S | Incorporated by reference Fuel cladding Fire Protection Program Power Uprate Affidavit |
LR-N09-0206, Special Report - North Plant Vent Radiation Monitoring System (Rms) | 24 August 2009 | Special Report - North Plant Vent Radiation Monitoring System (Rms) | |
LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit | 31 October 2008 | Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit | MELLLA Power change |
ML083100827 | 31 October 2008 | Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit | MELLLA Power change |
LR-N08-0247, Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action | 30 October 2008 | Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action | |
ML082600573 | 2 September 2008 | NFS-0255, Revision 0, Hope Creek Generating Station - Initial Implementation of WCAP-15942-P-A (Formerly CENO-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement to CENP-287, Evaluation of Control Blade I | |
ML073230096 | 9 November 2007 | Discharge Confirmation Report - Retraction of Reported Discharge to the Delaware River | High winds NJPDES |
HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error | 23 May 2007 | Notice of Noncompliance and Affirmative Defense of Laboratory Error | NJPDES |
LR-N07-0040, Special Report - North Plant Vent Radiation Monitoring System (Rms) | 20 February 2007 | Special Report - North Plant Vent Radiation Monitoring System (Rms) | |
LR-N06-0401, Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models | 28 September 2006 | Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models | |
ML062690064 | 1 September 2006 | Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. | Finite Element Analysis Flow Induced Vibration |
ML062280556 | 27 July 2006 | Groundwater Protection - Data Collection Questionnaire | |
LR-N06-0216, Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report | 4 May 2006 | Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report | Fitness for Duty Coatings |
ML060720437 | 7 March 2006 | Redacted Response to Request for Information Regarding Executive Review Board Commitments; PSEG | Downpower |
ML060670301 | 7 February 2006 | PSEG-News Document Detailing Chris Bakken Will Succeed Anderson as President and CNO of PSEG Nuclear | |
ML060580162 | 1 February 2006 | Performance Themes for Use After Inspection Exits (Regarding Poor Equipment Reliability, Corrective Action Ineffectiveness) and Organizational Issues (Regarding Engineering, Maintenance & Work Control, Operations, and Licensing/Regulatory C | Stroke time Fire impairment Biofouling Fire Watch Downpower |
ML052490158 | 31 August 2005 | Allegation Receipt Report Regarding Facility: Hope Creek | |
ML052630227 | 23 August 2005 | Communication Plan & Notification Sequence Regarding Receipt & Docketing of PSEG Assessment Reports | |
ML053180376 | 30 April 2005 | NEDO-33186, Revision 1, MELLLA Tracg Divom Evaluation for Hope Creek at Cppu Conditions. | Minimum Critical Power Ratio MELLLA |