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Category:Letter type:LR
MONTHYEARLR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-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-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges LR-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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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-N23-0010, 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-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) 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-N22-0019, 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-N22-0016, 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-N22-0011, 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 2024-09-30
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N15-0230 NOV 1 U 2015 Mr. Daniel Dorman, Regional Administrator - Region I United States Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Summary of Courtesy Notification for "Completeness and Accuracy of Information."
On October 15, 2015, notification was made to the NRC Region I staff that information previously supplied by PSEG to the NRC was not accurate in accordance with 10 CFR 50.9(a). The inaccurate information had been supplied in support of License Change Request (LCR) H05-01, Extended Power Uprate (EPU). A courtesy notification to the NRC was made via a phone call between Mr. William Kopchick, Hope Creek Engineering Director, and Mr. Ray Lorson, DRS Division Director, NRC Region I. As discussed during that phone call, PSEG is providing this follow-up letter to that notification.
PSEG's application for an EPU included a steam dryer stress analysis. The analysis was performed by Continuum Dynamics, Inc. (CDI). The results of the CDI analysis were included in the PSEG submittals that supported EPU.
CDI contacted PSEG via letter in January 2014, to report a discrepancy found in the software used for calculating the acoustic pressure loads on the Hope Creek steam dryer. The error was characterized as "not significant" as it reduced the minimum alternating stress ratio at EPU conditions from 2.36 to 2.23. PSEG put this information in the Corrective Action Program.
In August 2015, as part of a Measurement Uncertainty Recapture (MUR) uprate feasibility study, PSEG requested CDI to complete an evaluation of the impact on the available steam dryer margin. Through this review, CDI has determined that the calculation error is larger than originally thought. In October 2015, PSEG received preliminary information from CDI which indicated the minimum alternating stress ratio had been reduced from 2.36 to 1.05.
LRN-15-0230 Mr. Daniel Dorman Page 2 of 2 The issue has been entered into the Hope Creek Corrective Action Program. The condition was screened as functional based on stress on the steam dryer being below the ASME code limit, as well as the absence of physical parameter changes. Immediate reporting criteria were reviewed for applicability. This issue does not meet the threshold for reporting under 10 CFR 50. 72.
The CDI calculation contains conservatisms that can be reduced to raise the calculated minimum alternating stress ratio margins. These conservatisms are being reviewed to determine if additional margin can be credited. As a condition of the EPU license amendment, Hope Creek has performed post-EPU inspections of the steam dryer. The steam dryer inspections have not identified any issues related to EPU. Hope Creek also monitors moisture carryover as part of an on-going assessment of steam dryer material condition. Hope Creek has not observed adverse changes in moisture carryover.
There are no regulatory commitments contained in this letter.
Should you have any questions or require additional information, please contact Thomas MacEwen at (856) 339-1097.
Sincerely, Paul J. Davison Site Vice President Hope Creek Generating Station ttm cc: Mr. Ray Lorson, Division Director for DRS - NRC Region I Mr. Thomas Wengert, Project Manager - USNRC USNRC Senior Resident Inspector - Hope Creek Mr. Patrick Mulligan, Manager IV, NJBNE Mr. William Kopchick, Hope Creek Director of Engineering.
Mr. Lee Marabella, Corporate Commitment Tracking Coordinator Mr. Thomas MacEwen, Hope Creek Commitment Tracking Coordinator
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N15-0230 NOV 1 U 2015 Mr. Daniel Dorman, Regional Administrator - Region I United States Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Summary of Courtesy Notification for "Completeness and Accuracy of Information."
On October 15, 2015, notification was made to the NRC Region I staff that information previously supplied by PSEG to the NRC was not accurate in accordance with 10 CFR 50.9(a). The inaccurate information had been supplied in support of License Change Request (LCR) H05-01, Extended Power Uprate (EPU). A courtesy notification to the NRC was made via a phone call between Mr. William Kopchick, Hope Creek Engineering Director, and Mr. Ray Lorson, DRS Division Director, NRC Region I. As discussed during that phone call, PSEG is providing this follow-up letter to that notification.
PSEG's application for an EPU included a steam dryer stress analysis. The analysis was performed by Continuum Dynamics, Inc. (CDI). The results of the CDI analysis were included in the PSEG submittals that supported EPU.
CDI contacted PSEG via letter in January 2014, to report a discrepancy found in the software used for calculating the acoustic pressure loads on the Hope Creek steam dryer. The error was characterized as "not significant" as it reduced the minimum alternating stress ratio at EPU conditions from 2.36 to 2.23. PSEG put this information in the Corrective Action Program.
In August 2015, as part of a Measurement Uncertainty Recapture (MUR) uprate feasibility study, PSEG requested CDI to complete an evaluation of the impact on the available steam dryer margin. Through this review, CDI has determined that the calculation error is larger than originally thought. In October 2015, PSEG received preliminary information from CDI which indicated the minimum alternating stress ratio had been reduced from 2.36 to 1.05.
LRN-15-0230 Mr. Daniel Dorman Page 2 of 2 The issue has been entered into the Hope Creek Corrective Action Program. The condition was screened as functional based on stress on the steam dryer being below the ASME code limit, as well as the absence of physical parameter changes. Immediate reporting criteria were reviewed for applicability. This issue does not meet the threshold for reporting under 10 CFR 50. 72.
The CDI calculation contains conservatisms that can be reduced to raise the calculated minimum alternating stress ratio margins. These conservatisms are being reviewed to determine if additional margin can be credited. As a condition of the EPU license amendment, Hope Creek has performed post-EPU inspections of the steam dryer. The steam dryer inspections have not identified any issues related to EPU. Hope Creek also monitors moisture carryover as part of an on-going assessment of steam dryer material condition. Hope Creek has not observed adverse changes in moisture carryover.
There are no regulatory commitments contained in this letter.
Should you have any questions or require additional information, please contact Thomas MacEwen at (856) 339-1097.
Sincerely, Paul J. Davison Site Vice President Hope Creek Generating Station ttm cc: Mr. Ray Lorson, Division Director for DRS - NRC Region I Mr. Thomas Wengert, Project Manager - USNRC USNRC Senior Resident Inspector - Hope Creek Mr. Patrick Mulligan, Manager IV, NJBNE Mr. William Kopchick, Hope Creek Director of Engineering.
Mr. Lee Marabella, Corporate Commitment Tracking Coordinator Mr. Thomas MacEwen, Hope Creek Commitment Tracking Coordinator