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Category:Letter type:LR
MONTHYEARLR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022 2022 Annual 10 CFR 50.46 Report LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022 Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021 Corrected Hope Creek 10 CFR 50.46 Reports LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021 2021 Annual 10 CFR 50.46 Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021 Emergency Plan Document Revisions Implemented August 10, 2021 LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021 In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021 Correction to Prior Spent Fuel Cask Registration Letter LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021 Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021 Deviation from EPRI Document 33002012244 Inspection Requirements LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication 2023-09-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARLR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements LR-N20-0051, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2020-07-21021 July 2020 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-11-25025 November 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors LR-N19-0064, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer2019-07-29029 July 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer LR-N19-0065, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements2019-07-0808 July 2019 License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements LR-N19-0060, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-18018 June 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program LR-N19-0038, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2019-04-22022 April 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR LR-N19-0004, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2019-04-18018 April 2019 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0098, License Amendment Request: Remote Shutdown System2018-10-30030 October 2018 License Amendment Request: Remote Shutdown System LR-N18-0086, Supplemental Information to License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or 82018-09-26026 September 2018 Supplemental Information to License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or 8 LR-N18-0059, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2018-06-29029 June 2018 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules LR-N18-0032, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension2018-04-13013 April 2018 License Amendment Request: Inverter Allowed Outage Time (AOT) Extension LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0032, License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-03-27027 March 2017 License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report LR-N17-0060, Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2017-03-27027 March 2017 Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. LR-N16-0175, License Amendment Request - Administrative Controls2016-10-17017 October 2016 License Amendment Request - Administrative Controls LR-N16-0156, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-0707 October 2016 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N16-0103, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using Consolidated Line Item Improvement Process2016-07-20020 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using Consolidated Line Item Improvement Process LR-N16-0066, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-06-17017 June 2016 License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N16-0092, Supplemental Information - License Amendment Request - Digital Power Range Neutron Monitoring (Prnm) System Upgrade2016-06-17017 June 2016 Supplemental Information - License Amendment Request - Digital Power Range Neutron Monitoring (Prnm) System Upgrade ML16181A1932016-06-0808 June 2016 Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change LR-N16-0099, Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2016-06-0808 June 2016 Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change LR-N16-0002, License Amendment Request to Amend Technical Specifications (TS) to Delete Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves (Srvs)2016-05-11011 May 2016 License Amendment Request to Amend Technical Specifications (TS) to Delete Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves (Srvs) ML15265A2242015-09-21021 September 2015 License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade2015-09-21021 September 2015 Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0147, License Renewal Commitment Implementation2015-07-22022 July 2015 License Renewal Commitment Implementation LR-N14-0224, License Amendment Request to Update Appendix B to the Renewed Facility Operating License2014-12-0909 December 2014 License Amendment Request to Update Appendix B to the Renewed Facility Operating License LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process LR-N13-0265, License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule2013-12-24024 December 2013 License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N12-0200, for License Amendment Request - Cyber Security Plan Implementation Schedule Milestones2012-07-26026 July 2012 for License Amendment Request - Cyber Security Plan Implementation Schedule Milestones LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012 License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0343, License Amendment Request - Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out-of-Service2010-09-22022 September 2010 License Amendment Request - Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out-of-Service ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1021500732010-07-20020 July 2010 License Amendment Request H09-02 to Relocate the Reactor Recirculation System Motor-Generator (MG) Set Scoop Tune Stop Setting Surveillance ML1021500922010-07-20020 July 2010 License Amendment Requests H10-02 & S10-02: Proposed Revision to Technical Specifications - Removal of Reactor Coolant System Structural Integrity Requirements. 2023-09-08
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 FOL 2.C. (27)
LR-N15-0147 JUL 2 2 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
License Renewal Commitment Implementation
References:
(1) LR-N12-0212, "License Renewal Commitment Implementation,"
dated July 19, 2012 The Renewed Operating License No. NPF-57 for Hope Creek Generating Station (HCGS) was issued on July 20, 2011. The renewed license included several license conditions related to the ASME Section XI, Subsection IWE aging management program and, in particular, to the Hope Creek drywell air gap drains. In accordance with License Condition 2.C. (27) c, this letter transmits a report summarizing the results of the ultrasonic thickness (UT) measurements taken during Refueling Outage 19.
There are no regulatory commitments contained in this letter.
If you have any questions or require additional information, please do not hesitate to contact Mr. Philip J. Duca at 856-339-1640.
Sincerely,
\.CU Paul J. Davison Site Vice President - Hope Creek pj d '
Attachment - Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19
NRG Document Control Desk LR-N15 -0147 Page 2 cc: Mr. D. Dorman, Administrator, Region I Nuclear Regulatory Commission Ms. Carlene Parker - Project Manager Hope Creek USNRC Mr. Justin Hawkins - NRG Senior Resident Inspector - Hope Creek (X24)
Mr. Thomas MacEwen - Hope Creek Commitment Coordinator (H02)
Mr. Lee Marabella - Corporate Commitment Coordinator (N21)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering New Jersey Department of Environmental Protection PO Box 420 Trenton, New Jersey 08625
LR-N15-0147 Attachment Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19
LR-N15-0147 Attachment Page 1 of 5 Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19
Background:
Renewed Operating License No. NPF-57 for Hope Creek Generating Station was issued on July 20, 2011. The renewed license contains several license conditions related to License Renewal and, in particular, to the Hope Creek drywell air gap drains.
Some portions of these License Conditions were included in the Refueling Outage (RF) 17 scope and were worked during the outage that began on April 13, 2012, and ended on May 9, 2012. Continued investigations and changes were included in RF 18 scope and were worked during the outage that began on October 11, 2013, and ended November 10, 2013. Monitoring of air gap leakage and performance of drywell shell UT thickness measurements were included in the RF 19 scope and were worked during the outage that began on April 10, 2015, and ended May 13, 2015.
The relevant license conditions are contained in Section 2.C of the renewed license.
Specifically, Section 2.C.(27) delineates those activities required to be performed following the establishment of drainage capability from the drywell air gap (that is, following completion of license condition 2.C.(26)) and reads as follows:
(27) After drainage has been established from the bottom of the air gap in all four quadrants, the licensee will:
- a. Submit a report to the NRG staff in accordance with 10 CFR 50.4 describing the final drain line configuration and summarizing the testing results that demonstrate drainage has been established for all four quadrants.
- b. Monitor penetration sleeve J13 daily for water leakage when the reactor cavity is flooded up. In addition, perform a walk-down of the torus room to detect any leakage from other drywell penetrations. These actions shall continue until corrective actions are taken to prevent leakage through J13 or through the four air gap drains.
- c. Perform UT measurements of the drywell shell between elevation 86'-11" (floor of the drywell concrete) and elevation 93'-0" (bottom of penetration J13) below penetration J13 area during the next three refueling outages. In addition, UT measurements shall be performed around the full 360 degree circumference of the drywell between elevations 86'-11" and 88'-0" (underside of the torus down comer vent piping penetrations). The results of the UT measurements will be used to identify drywell surfaces requiring augmented inspections in accordance with IWE requirements for the period of extended operation, establish a corrosion rate, and demonstrate that the effects of aging will be adequately managed such that the drywell can perform its intended function until April 11, 2046. Within 90 days of completion of each refueling outage, submit a report to the NRG staff in accordance with 10 CFR
LR-N15-0147 Attachment Page 2 of 5 Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19 50.4 summarizing the results from the UT measurements and if appropriate, corrective action.
Summary of Commitment Implementation:
The action required by License Condition 2.C. (27) a. was completed and the results submitted to the NRC in PSEG Letter No. LR-N12-0212 dated July 19, 2012. In accordance with License Condition 2.C. (27), this report discusses the actions taken by PSEG during Hope Creek Refueling Outage 19 (RF19) to satisfy license condition 2.C.
(27) b. and 2.C. (27) c., above. The specific license conditions addressed and/or resolved during RF19 are as follows:
A Monitoring of J13 Penetration Sleeve (License Condition 2.C. (27) b.)
During RF19, the J13 penetration sleeve was monitored daily for leakage while the reactor cavity was flooded up (April 13, 2015 through April 30, 2015).
Further, the penetrations adjacent to penetration J13 (J19, J14, J29, J24, and J37, specified here as the "J13 penetration group") and the air gap drains were monitored daily for water leakage. In addition, a full walk-down of the torus room was performed to confirm there was no leakage from any other penetrations.
Walk-downs were performed daily while the reactor cavity was flooded by Operations in accordance with Operating Procedure HC.OP-IO. ZZ-0005, COLD SHUTDOWN TO REFUELING, and by Engineering. During the walk-downs following reactor cavity flood-up and continuing until reactor cavity drain down, water was observed at the 225 degree azimuth from the J13 penetration group (specifically the J19 penetration) as well as the excavated access tunnel located at 250 degree azimuth (credited air gap drain).
On April 17, 2015, leakage was identified from penetration sleeve J19 at a leak rate of approximately 42 drops per minute. Note that penetrations J13 and J19 are at the same elevation and are separated by approximately 25 inches. No water was noted leaking from any other areas within the torus room. The leak rate from the J19 penetration remained at or around 42 drops per minute through April 20, 2015. On April 20, 2015 leakage was also observed coming out of the excavated access tunnel at 250 degree azimuth. The leakage from the 250 degree azimuth tunnel was estimated to be approximately 10 drops per minute.
On April 21, 2015 the 250 degree azimuth tunnel leakage remained at approximately 10 drops per minute while the penetration J19 leakage dropped to approximately 20 drops per minute. On April 22, 2015 the leakage from the 250 degree azimuth tunnel ceased and the leakage from the penetration J19 diminished to approximately 2 drops per minute. The leakage form the 250 degree azimuth tunnel never returned and the penetration J19 leakage continued
LR-N15-0147 Attachment Page 3 of 5 Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19 to diminish over the next several days. The last leakage was recorded on April 25, 2015 from the penetration J19 at a rate of approximately 1 drop per minute.
It is likely that the leakage observed April 22 through 25, 2015 was residual leakage. Note that the cavity remained flooded through April 30, 2015. The chart below represents a comparison of the RF19 leakage to that of the RF18 leakage where the X-axis represents days following flood up and the Y-axis represents cumulative gallons leaked.
18.00 16.00 14.00 12.00 10.00 too 6.00 RF19 4.00 2.00 0,00 1 2 3 4 s 6 7 8 9 10 11 12 13 14 15 16 17 Note that the time from flood up to first observation of leakage during RF19 was four days versus two days during RF18. In addition, the leakage during RF19 lasted only five days versus fourteen days during RF18. The RF19 total leakage was less than 25% of that collected during RF18. The characteristic deltas between the observed leakage from RF18 to RF19 will be taken into consideration when developing leak investigation efforts for RF20.
From the monitoring conducted during RF19 it can be concluded that the source of the leakage has not degraded from RF18 to RF19. No leakage was observed from any other air gap penetration sleeves and there was no sign of leakage from the end of the other three drywell air gap drains (at 80, 160 and 340 degree azimuths) or from the excavated tunnels at 290, 155 and 115 degree azimuths.
The Reactor Cavity to Drywell Seal Rupture Drain Alarm (HC.OP-AR.ZZ-0024, Alarm point 03837) did not actuate. All leakage stopped before draining of the reactor cavity.
LR-N15-0147 Attachment Page 4 of 5 Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19 B. UT Measurements (License Condition 2.C. (27) c. )
The Ultrasonic Thickness (UT) measurements prescribed by license condition 2.C. (27) c. were performed during RF19. Based on the consistency of the UT measurements with those taken in previous outages, PSEG has concluded that no corrosion is occurring on the drywell shell.
UT measurements were performed on the drywell shell at the 225 degree azimuth between 86'-11" and 93'-0" elevation (below the J13 penetration group).
The lowest UT measurements occurred on a plate below the J13 penetration group and measured 1.475" in RF16, 1.470" in RF17, 1.477" in RF18, and, 1.490" in RF19. Note that these readings were not at the same measurement point but were the lowest of all recorded readings taken during the respective outages.
Comparing the lowest reading of 1.470" (from RF17) to the analysis limit of 1.4375" proves that at least 32.5 mils thickness margin remains. Further, the consistency of the thickness measurements proves that no corrosion to the drywell shell is occurring below the J13 penetration group. It should be noted that during development of the Hope Creek license renewal application, PSEG concluded that the cause of the lower readings on this plate were due to the plate's construction tolerances being at the lower end, but acceptable for use.
UT measurements were also performed for the full circumference of the drywell shell between elevations 86'-11" and 88'-0". The bottom of the drywell air gap is on the outside of the drywell shell between these elevations. The lowest UT measurements at the bottom of the drywell were 1.480" in RF16, 1. 477" in RF17, 1.471" in RF18, and 1.475" in RF19. Note that these readings were not at the same measurement point but were the lowest of all recorded readings taken during the respective outages. Comparing the lowest reading of 1.471" (from RF18) to the analysis limit of 1.4375" shows that 33.5 mils thickness margin remains. Based on the consistency of these UT measurements, PSEG has concluded that no corrosion is occurring in the drywell shell at the bottom of the drywell air gap. Nevertheless, even if a very conservative corrosion rate of 6 mils per cycle were to be assumed, the analysis limit of 1.4375 would not be reached for at least 5 cycles. The UT measurements will be taken again during the RF20 outage to confirm that no corrosion is occurring in the drywell shell.
The UT measurement activities required to be completed during RF19 by license condition 2.C. (27) c. were completed as described above. License condition 2.C. (27) c. requires these UT measurement activities for the three refueling outages following establishment of drainage capability from the bottom of the drywell air gap. RF19 is the second of these outages. Therefore, these UT measurement activities will be performed during the next outage. The results of
LR-N15-0147 Attachment Page 5 of 5 Hope Creek Generating Station License Renewal Commitment Implementation 90-Day Report for Refueling Outage 19 the RF20 UT measurement activities will be compared to the previous UT measurement results to determine if any corrosion is occurring and to determine a corrosion rate if corrosion is identified. Should a significant corrosion rate be detected, the condition will be entered into the corrective action process for resolution.
C. Corrective Actions The reactor cavity leakage is currently an ongoing investigation. Additional investigatory actions will be defined for RF20 since the leakage only occurs while the reactor cavity is flooded. While the reactor cavity leakage continues to exist, the actions prescribed by License Condition 2.C. (27) and UFSAR Section A.5, Commitment No 28; Sub-commitment 10 (Pages A-70 & 71) will be performed.
There were no additional corrective actions as a result of the activities in RF19.
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Conclusion:==
Activities associated with the Hope Creek renewed operating license condition 2.C. (27) that were required to be completed during the RF19 refueling outage were completed.
License Condition 2.C. (27) a. was satisfied through submittal of PSEG Letter No. LR N12-0212 on July 19, 2012. License conditions 2.C. (27) b. and 2.C. (27) c were satisfied during RF18 as documented in LR-N14-0029, and for RF19 as discussed above. This report satisfies the reporting requirements of 2.C. (27) c. The results of the UT measurements demonstrate there are currently no drywell surfaces requiring augmented inspections in accordance with IWE requirements.