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 Issue dateTitleTopic
ML23335A11215 December 2023Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers
LR-N21-0007, Report of Changes, Tests, and Experiments28 January 2021Report 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 Conditions25 July 2018Report 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 ConditionsHigh 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 6.9.1.19 February 2017Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1Shutdown Margin
LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 207 February 2017License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20Aging Management
LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal29 December 2016Flood Hazards Mitigating Strategies Assessment (MSA) Report SubmittalHigh winds
Ultimate heat sink
Hydrostatic
FLEX
Fukushima Dai-Ichi
ML16256A64112 September 2016NUREG-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 2016NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.
ML16256A64031 August 2016Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment
LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment31 August 2016Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment
ML16256A64318 July 2016ISG-06 Enclosure B Roadmap, Phase 2 Documents.
LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.18 July 2016ISG-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 2016GNF-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
ML16049A60929 February 2016Staff 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 ClosureSafe 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 2014Response 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 71-923311 August 2014CFR 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 Station25 April 2014CFR 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 2014PSEG 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
ML13266A29718 November 2013Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant AccidentUnanalyzed Condition
Hydrostatic
Fukushima Dai-Ichi
Earthquake
ML13052A67528 November 2012Attachment 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) Summary28 November 2012Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary
ML12220A25010 August 2012Closeout of Bulletin 2011-01, Mitigating StrategiesB.5.b Mitigating Strategies
ML12159A3558 June 2012Review 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 AccidentFukushima Dai-Ichi
Earthquake
ML11270006926 September 2011Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 PlantsShutdown Margin
Anticipated operational occurrence
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Channel-control blade interference
Scram Discharge Volume
Earthquake
ML11203A07813 July 2011Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6Non-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 Stations8 April 20112010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations
ML11061A00530 March 2011Ncsa Hope Creek Observations Rev. 4
LR-N10-0355, Salem, EAL Technical Bases Supporting Documents14 October 2010Salem, EAL Technical Bases Supporting DocumentsEarthquake
ML11006023914 October 2010Salem, EAL Technical Bases Supporting DocumentsEarthquake
ML11263A03020 September 2010E-mail with Attachment from B. Pham, NRR to L. Perkins, NRR, on Forward Salem/Hope Creek Chapter 5 SAMA InputSafe Shutdown
High winds
Fire Barrier
Internal Flooding
B.5.b
License Renewal
Earthquake
Power Uprate
ML11263A02816 September 2010E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal MemoSafe 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'S10 August 201050.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'SIncorporated by reference
Fuel cladding
Fire Protection Program
Power Uprate
Affidavit
LR-N09-0206, Special Report - North Plant Vent Radiation Monitoring System (Rms)24 August 2009Special 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 Affidavit31 October 2008Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and AffidavitMELLLA
Power change
ML08310082731 October 2008Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and AffidavitMELLLA
Power change
LR-N08-0247, Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action30 October 2008Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action
ML0826005732 September 2008NFS-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
ML0732300969 November 2007Discharge Confirmation Report - Retraction of Reported Discharge to the Delaware RiverHigh winds
NJPDES
HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error23 May 2007Notice of Noncompliance and Affirmative Defense of Laboratory ErrorNJPDES
LR-N07-0040, Special Report - North Plant Vent Radiation Monitoring System (Rms)20 February 2007Special 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 Models28 September 2006Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models
ML0626900641 September 2006Attachment 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
ML06228055627 July 2006Groundwater 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 Report4 May 2006Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment ReportFitness for Duty
Coatings
ML0607204377 March 2006Redacted Response to Request for Information Regarding Executive Review Board Commitments; PSEGDownpower
ML0606703017 February 2006PSEG-News Document Detailing Chris Bakken Will Succeed Anderson as President and CNO of PSEG Nuclear
ML0605801621 February 2006Performance 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 CStroke time
Fire impairment
Biofouling
Fire Watch
Downpower
ML05249015831 August 2005Allegation Receipt Report Regarding Facility: Hope Creek
ML05263022723 August 2005Communication Plan & Notification Sequence Regarding Receipt & Docketing of PSEG Assessment Reports
ML05318037630 April 2005NEDO-33186, Revision 1, MELLLA Tracg Divom Evaluation for Hope Creek at Cppu Conditions.Minimum Critical Power Ratio
MELLLA