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Category:Graphics incl Charts and Tables
MONTHYEARLR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N23-0050, Attachment 5: Hope Creek Pavan Output File2023-09-0606 September 2023 Attachment 5: Hope Creek Pavan Output File ML23249A2682023-09-0606 September 2023 Attachment 4: Hope Creek Pavan Input File ML23249A2672023-09-0606 September 2023 Attachment 3: Salem Pavan Output File ML23249A2662023-09-0606 September 2023 Attachment 2: Salem Pavan Input File ML23249A2652023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2021 ML23249A2642023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2020 ML23249A2632023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2019 ML17335A1182018-01-25025 January 2018 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident ML17046A2962017-01-30030 January 2017 Revision 29 to Updated Final Safety Analysis Report, Table 3.8-1 Through 3.8-11 ML17046A3072017-01-30030 January 2017 Revision 29 to Updated Final Safety Analysis Report, Table 3A-1 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3.8-1 Through 3.8-112017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3.8-1 Through 3.8-11 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3A-1 (Deleted)2017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3A-1 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 4.1-1 Through 4.1-32017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 4.1-1 Through 4.1-3 ML17046A3112017-01-30030 January 2017 Revision 29 to Updated Final Safety Analysis Report, Table 4.1-1 Through 4.1-3 LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-30030 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16320A4842016-11-15015 November 2016 Public Telecon Regarding LAR to Upgrade Power Range Neutron Monitoring System (Meeting Handout) ML16231A1102016-08-16016 August 2016 Updated Issues List for 08/16/2016 Public Telecon Regarding LAR to Upgrade Power Range Neutron Monitoring System Meeting Handout ML16116A2352016-03-15015 March 2016 Meeting Summary for Public Teleconference Between PSEG LLC and the Nuclear Regulatory Commission, Hope Creek Generating Station - Power Range Neutron Monitoring System Digital Upgrade LAR HCGS Numac Upgrade - Open Item DOC-0006-2118 Ri ML16102A2772016-03-11011 March 2016 Submittal of Annual Incidental Take Report ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15238B6552015-09-10010 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15243A5022015-09-10010 September 2015 Interim Letter Tables 1 and 2 ML15243A4472015-09-10010 September 2015 Master Report - Tables 1 and 2 ML15238B7042015-09-10010 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54 Information Request - Flood Causing Mechanism Reevaluation ML15030A3002014-09-22022 September 2014 Table 07, Unit 1 Seismic Gap Drain Tritium Analytical Results ML15030A3012014-09-22022 September 2014 Table 08, Unit 2 Seismic Gap Drain Tritium Analytical Results ML15030A2982014-09-22022 September 2014 Table 06A, Groundwater Tritium Analytical Results for Well AC ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2992014-09-22022 September 2014 Table 06B, Groundwater Analytical Results for Well AC ML15030A2502014-09-22022 September 2014 Figure 8,Salem Generating Station Hydrogeologic Cross Section D-D' ML15030A2842014-09-22022 September 2014 Table 02, Sample Collection Schedule - First & Second Quarter 2014 ML15030A2832014-09-22022 September 2014 Table 01, Well Construction Details ML15030A2822014-09-22022 September 2014 Figure 16, Salem Unit 2 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2812014-09-22022 September 2014 Figure 15, Salem Unit 1 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2802014-09-22022 September 2014 Figure 14, Historic Tritium Recovered Through Well Field Operation ML15030A2762014-09-22022 September 2014 Figure 11, Station Wind Summary - Q1 2014 ML15030A2752014-09-22022 September 2014 Figure 10, Precipitation Measurements ML15030A2512014-09-22022 September 2014 Figure 9, Salem Generating Station Hydrogeologic Cross Section E-E' ML15030A2962014-09-22022 September 2014 Table 05, Groundwater Analytical Results (1.22.2003 Through 3.31.2014) ML15030A2492014-09-22022 September 2014 Figure 7, Salem Generating Station Hydrogeologic Cross Section C-C' ML15030A2482014-09-22022 September 2014 Figure 6, Salem Generating Station Hydrogeologic Cross Section B-B' ML15030A2472014-09-22022 September 2014 Figure 5, Salem Generating Station Hydrogeologic Cross Section A-A' ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-1492012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 ML12284A4272012-10-0404 October 2012 PSEG Early Site Permit Application, Calculation of Multiplier Effects for Er Section 10.4 LR-N12-0027, Submittal of RCS Dei Graphs Report2012-03-0202 March 2012 Submittal of RCS Dei Graphs Report ML11181A1872011-06-29029 June 2011 Attendance Sheet for 06/29/2011 Public Meeting to Discuss Observations and Lessons Learned of the Pilot Application of the Nuclear Energy Institute'S 2024-04-05
[Table view] Category:Inspection Report
MONTHYEARIR 05000272/20240032024-10-30030 October 2024 Integrated Inspection Report 05000272/2024003 and 05000311/2024003 IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) IR 05000272/20240052024-08-29029 August 2024 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005) IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) IR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 IR 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 IR 05000272/20230062024-02-28028 February 2024 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006 IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 IR 05000272/20230402023-05-0202 May 2023 And Salem Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023420, 05000272/202340 and 05000311/2023420 IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) IR 05000272/20220042023-01-31031 January 2023 Integrated Inspection Report 05000272/2022004 and 05000311/2022004 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 IR 05000272/20220112023-01-0606 January 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000272/2022011 and 05000311/2022011 ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000272/20220032022-11-0909 November 2022 Integrated Inspection Report 05000272/2022003 and 05000311/2022003 IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 IR 05000354/20223012022-10-24024 October 2022 Initial Operator Licensing Examination Report 05000354/2022301 IR 05000272/20220052022-08-31031 August 2022 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022005 and 05000311/2022005) IR 05000354/20220052022-08-31031 August 2022 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2022005) IR 05000354/20220022022-08-10010 August 2022 Integrated Inspection Report 05000354/2022002 IR 05000272/20220022022-08-0808 August 2022 Integrated Inspection Report 05000272/2022002 and 05000311/2022002 2024-09-23
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Text
HOPE CREEK NRC INSPECTION FINDINGS Deficien cv Finding.
I OCFR 50.63: Failure to consider design SBO coping analysis was not considered in information (SBO coping) in OD. the OD for a steam leak in HPCI room.
(Engineering) 18. Report No. 2003002 Criterion III DESIGN CONTROL Failure to ensure that EDO design specs were Failure to translate design information into translated into design documents. Report No.
design documents. (Engineering) 6. 2003004*
Non-conservative design assumptions used in Inadequate acceptance limits for HPCI HPCI surveillance test. quarterly operability surveillance testing for (Engineering) 15. pump flow.
_______________________________Report No. 2003002 Incorrect and non-conservative design Incorrect and non-conservative design informnation is translated into a procedure. information is translated into the SRV tailpipe temperature procedure. Report No. 2003006 (Engineering) 20.____________________
Criterion V Procedures: Improper cutting of Maintenance did not follow the SSWS key without procedure guidance. travelling screen procedure. Report No.
(Maintenance) 19. 2003006 Criterion XNI Corrective Actions:: Electro-hydraulic control oil leak in No. 4 Inadequate maintenance! post maint. testing combined intermediate valve results in (Maintenance)1. Not a violation, manual scram. Report No. 2003007*
Failed to initiate timely corrective actions to Minor power, pressure and level excursion transient. results in larger operational transient. Report (Operations)2. No. 2003003 Engineering performned inadequate Residual heat removal system minimum flow evaluations and corrective actions valve cycling during RI-1R pump starts. Report (Engineering)3. No. 2003007*
Uncompleted corrective actions The "B" control room chiller tripping when (Maintenance)4. placed in service. Report No. 2003007*
Untimely corrective actions Low pressure coolant injection suction relief valve was not thoroughly evaluated for extent (Engineering)5. of condition. Report No. 2003004*
Maintenance improperly repaired the EDO 3 Incorrect maintenance procedure to replace times. the A EDG intercooler pump seal. Report No.
(Maintenance)6. 2003 004*
Failed to take corrective actions on an High pressure coolant injection system observed deficient condition. lubricating oil pressures were degradled in (Engineering, System)7. multiple tests. Report No. 2003003 0 /q
Failed to provide assurance that ADHR Did not follow through on corrective actions method was in place. regarding adequate stroking of all applicable alternate decay heat removal valves .Report (Engineering/ Operations)8. No. 2003003 multiple Notifications without resolution. Failure to identify and correct problems with the HIPCI lube oil temperature monitoring..
(Maintenance) 16. Report No. 2003 002*
Criterion XI Test Control: Failed to provide Safety auxiliary cooling system heat acceptance criteria in test procedure. exchanger testing does not provide acceptance (Engineering)9. limits. Report No. 2003004*
Tech. Spec. 3.7.2: Inadequate tagging Testing of the A control room ventilation boundary.sytmmdbohteAadBcv' (Work Control) 10. inoperable. Report No. 2003003*
Tech Spec 4.5.1 Failed to include valve in Incomplete HPCI valve position verification ECCS surveillance procedure to satisfy Tech Spec requirement. Report No.
(operations)17.
Tech. Spec. 4.8.1.1.2: Failed to translate the Did not verify the fuel oil transfer pump Tech Spec requirement into surveillance transfer capability from each fuel oil storage procedure. (Operations) 11. tank. Report No. 2003004*
Failed to translate the Tech Spec requirement Inadequate testing of the EDG lockout relays.
into the surveillance procedure. (Maint.) 12. Report No. 2003002*
Tech. Spec. 6.8.1: Failure to follw~o EOP's A control room supervisor issued an order that post scram. conflicted with the emergency operating procedures for the Post scram wvater level (Operations) 13. 1control. Report No. 2003004*
Failed to adequately control the work process Ineffective work control regarding the and associated fire protection provisions, automatic fire suppression system for the C EDG resulted in the CO 2 being out of service.
(Work control) 14. -Report No. 2003005*
SALEM I NRC INSPECTION FINDINGS Criterion III, Design Control Increased likelihood of a loss of offsite power due to inadequacies during plant modifications, set point changes and revisions of calculations associated with the 4160 volt power systems. Report No. 2003008 Failed to include the appropriate steps in the procedure for a modification of the Unit 1 /2 chemical and volume control system. Report No. 2003008 Temporary modifications to the 22 auxiliary feedwater pump and the 13 A-FW pump skids were not properly evaluated. Report No.
___ ___ ___ ___ ___ ___ 2003003 Criterion V, Procedures Failure to follow the FME procedure allowed a bolt to jam the feedwater regulating valve
______________________________making it inoperable. Report No. 2003009 Criterion XVI, Corrective Actions Failed to implement adequate corrective actions to address design issues following the July 29,2003 loss of offsite power. Report No. 2003008 Salem Units 1/ 2 experienced a control air transient as a result of an incomplete control air preventive maintenance item and inadequate corrective actions. Report No.
___ __ ___ ___ ___ ___ __ 2003003 Failure to take effective corrective action for corrosion products in the control air system resulted in the Unit 2 chilled water
______________________________compressor tripping. Report No. 2003009 Service water pump strainer tripped due to ineffective corrective actions. Report No.
2003009 Failure to promptly identify and correct a leak from the spent fuel pool. Report No. 2003006 Failure to correct a service water valve air actuator leak. Report No. 2003005 Failure to promptly identify a throttled auxiliary feedwater flow control valve air
________________________________supply. Report No. 2003005
Inadequate maintenance practices resulted in recurrence of a service water valve motor operator failure. Report No. 2003005 Criterion XVI, Corrective Actions (cont.) Failure to identify emergency diesel generator room roof leaks. Report No. 2003003 The emergency diesel generator tripped due to a known electrical connector problem and inadequate interim corrective actions. Report
_______________________________ No. 2003003 Failure to implement corrective actions for wires located in the control room panels from an over cur-rent condition and a degraded component cooling water system pipe support.
Report No. 2003004 Failure to implement corrective actions for repetitive fuel oil leaks on the emergency
______________________________diesel generators. Report No 2002010 Ineffective corrective actions led to recurrence of the emergency diesel generator turbocharger failure. Report No. 2002010 Tech Spec. 4.0.5 Failure to establish stroke time reference values for the containment fan coil units.
Report No. 2003005 Tech. Spec. 6.8.1 Failure to perform maintenance in accordance with the procedure for the 13 auxiliary feedwater pump causing a trip. Report No.
___ __ ___ ___ ___ ___ __ 2003007
- 21. Failure to follow the test procedure for the
_______________________________PORV. Report No. 2003005 Failure to properly perform maintenance on the component cooling cross connect valve
___ __ __ ___ __ __ ___ __ _ CCI7
SALEM 2 NRC INSPECTION FINDINGS Criterion III, Design Control Increased likelihood of a loss of offsite power due to inadequacies during plant modifications, set point changes and revisions of calculations associated with the 4160 volt
________________________________power systems. Report No. 2003008 Failed to include the appropriate steps in the procedure for a modification of the Unit 1 /2 chemical and volume control system. Report
___ ___ ___ ___ ___ __ No. 2003008 Temporary modifications to the 22 auxiliary feedwater pump and the 13 AFW pump skids were not properly evaluated. Report No.
2003003 Criterion XVI, Corrective Actions Deferral of a vendor recommended design change on the control rod drive mechanisms led to a manual reactor trip due to dropped
_______________________________control rod. Report No. 2003003 Failed to implement adequate corrective actions to address design issues following the July 29,2003 loss of offsite power. Report No. 2003008 Salem Units 1/ 2 experienced a control air transient as a result of an incomplete control air preventive maintenance item and inadequate corrective actions. Report No.
___ __ ___ ___ ___ ___ __ 2003003 A compressor air leak on the starting air system for the A EDG was not properly evaluated before removing the other compressor from service for maintenance.
Report No. 2003009 Ineffective problem evaluation of air pockets in the residual heat removal system resulted in a waterharnuer on the RHR and CS systems.
________________________________Report No. 2003009 Delayed corrective actions from 5/02 to 11/03 for the water hammer on the RI-R system.
Report No. 2003009
The emergency diesel generator tripped due to a known electrical connector problem and inadequate interim corrective actions. Report 4
No. 2003003 Failure to implement corrective actions for wires located in the control room panels from an over current condition and a degraded component cooling water system pipe support.
Report No. 2003004 Tech. Spec. 6.8.1 Failure to follow a testing procedure for the pressurizer spray valve 2PS3. Report No.
___ ______ ___ ____ ___ ___ 2003005 Untimely placement of identified steam generator tube plug deficiencies into the corrective action program. Report No.
___ ___ ___ ___ ___ __ 12003009