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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:Licensee 30-Day Written Event Report
MONTHYEARLR-N16-0234, 30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change2016-12-12012 December 2016 30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change LR-N10-0353, Submittal of Report Changes in Application of Emergency Core Cooling System Evaluation Models2010-09-16016 September 2010 Submittal of Report Changes in Application of Emergency Core Cooling System Evaluation Models LR-N08-0164, Special Report - Safety Relief Valve (SRV) Acoustic Monitor2008-08-0505 August 2008 Special Report - Safety Relief Valve (SRV) Acoustic Monitor LR-N08-0053, Submittal of Special Report - North Plant Vent Radiation Monitoring System (Rms)2008-03-12012 March 2008 Submittal of Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N07-0148, Special Report Regarding Auxiliary Boiler Emission Test Failure2007-06-18018 June 2007 Special Report Regarding Auxiliary Boiler Emission Test Failure LR-N05-0421, Special Report 354/05-006-00 for Hope Creek Generating Station Re South Plant Vent Radiation Monitoring System Being Inoperable for Greater than 72 Hours2005-08-16016 August 2005 Special Report 354/05-006-00 for Hope Creek Generating Station Re South Plant Vent Radiation Monitoring System Being Inoperable for Greater than 72 Hours LR-N05-0143, Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration2005-03-31031 March 2005 Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration LR-N04-0594, Special Report 04-013-002005-01-0707 January 2005 Special Report 04-013-00 2016-12-12
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N16-0234 DEC 1 2 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354 1 1 SEG Nuclear LLC 10 CFR 50.46
Subject:
30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change Pursuant to the requirements of 10 CFR 50.46, PSEG Nuclear LLC (PSEG) hereby reports a change in the application of the Emergency Core Cooling System (ECCS) evaluation models for the Hope Creek Generating Station (HCGS). In accordance with 10 CFR 50.46(a)(3)(ii), licensees are required to provide a 30 day report when a change to evaluation models used for calculating ECCS performance results in a significant Peak Cladding Temperature (PCT) change. This letter and its attachments satisfy the 30 day reporting requirement.
HCGS has started to transition to the GNF2 fuel design. The introduction of the GNF2 fuel design was a planned activity implemented during the fall 2016 refueling outage. The Licensing Basis Peak Cladding Temperature (PCT) for the GNF2 fuel design is more than 50 °F greater than the GE14 Licensing Basis PCT including consideration of previously reported 10 CFR 50.46 Notifications (GNF2 Licensing Basis PCT = 1610 °F, GE14 Licensing Basis PCT plus all previously reported 10 CFR 50.46 Notifications
= 1485 °F). HCGS will complete transition from a full core of the GE14 fuel design to full cores of GNF2 over the next several operating cycles. For the current operating cycle, the HCGS core consists of 212 GNF2 fuel assemblies and 552 GE14 fuel assemblies.
There are no regulatory commitments in this correspondence.
If you have any questions regarding this submittal, please contact Mr. Frank Safin at (856) 339-1937.
Sincerely,
.. Edward T Casulli Plant Manager -Hope Creek ttm Attachment 1: Hope Creek Generating Station 10 CFR 50.46 Report-Peak Cladding Temperature Rack-up Sheet Attachment 2: Hope Creek Generating Station 10 CFR 50.46 Report-Assessment Notes LR-N16-0234 Document Control Desk Page 2 cc: Mr. Daniel H. Dorman, Regional Administrator-US NRC Region I Ms. Carleen Parker, USNRC Project Manager-Hope Creek Mr. Justin Hawkins, USNRC Senior Resident Inspector-Hope Creek (X24) Mr. Patrick Mulligan, Manager IV, NJ Bureau of Nuclear Engineering Mr. Thomas MacEwen, Hope Creek Commitment Coordinator (H02) Mr. Lee Marabella, Corporate Commitment Coordinator (N21)
LR-N16-0234 Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet Page 1 of 1 PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: Hope Creek Generating Station SAFER/GESTR-PRIME 12/08/2016 CURRENT OPERATING CYCLE: 21 ANALYSIS OF RECORD Evaluation Model: 1. The GESTR-LOCA and SAFER Models for the Evaluation of the of-Coolant Accident, Volume Ill, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984. 2. Licensing Topical Report, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Part 1 -Technical Bases, NEDC-Revision 1, Part 2 -Qualification, NEDC-33257P-A, Revision 1, and Part 3 -Application Methodology, NEDC-33258P-A, Revision 1, September 2010. (See Assessment Note 1) Calculations:
Hope Creek Generating Station GNF2 ECCS-LOCA Evaluation, 002N5176-RO, Revision 0, August 2016. Fuel: GNF2 Limiting Fuel Type-Licensing Basis PCT: GNF2 Limiting Single Failure: Battery Limiting Break Size and Location:
Double-Ended Guillotine in a Recirculation Suction Pipe I Fuel Type: GNF2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GNF2 None (see Assessment Note 2)
= 0°F Net PCT 1610 °F B. CURRENT LOCA MODEL ASSESSMENTS GNF2 None. (see Assessment Note 2) Total PCT change from current assessments 2::
= ooF Cumulative PCT change for current assessments L I I = oo F Net PCT 1610 °F LR-N16-0234
- 1. Evaluation Model Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes Page 1 of 1 The GESTR fuel rod thermal mechanical models described in Evaluation Model Reference 1 were replaced by the PRIME fuel rod thermal mechanical models described in Evaluation Model Reference
- 2. 2. Prior and Current LOCA Model Assessments There are no prior or current LOCA Model Assessments.
This report is being provide to document the Peak Cladding Temperature (PCT) resulting from the planned introduction of the GNF2 fuel design for Hope Creek Cycle 21 operation in accordance with 10 CFR 50.46. Hope Creek will transition from a full core of the GE14 fuel design to full cores of GNF2 over the next several operating cycles. All information reported to the NRC in accordance with 10 CFR 50.46 for the GE14 fuel design remains unchanged at the time of this report (Reference PSEG Transmittal Letter to NRC: LR-N16-0180 from Edward T Casulli, Plant Manager-Hope Creek, to U.S. NRC, "2016 Annual10 CFR 50.46 Report", Dated September 30, 2016). This report is being submitted as a 30 day report as a result of the GNF2 fuel design PCT (1610 °F) increasing more than 50 °F from the GE14 fuel design PCT (1485 °F). No proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 10 CFR 50.46 requirements is provided with this report. All previous 10 CFR 50.46 notifications that are applicable to GNF2 have been analyzed and incorporated in the determination of the GNF2 Licensing Basis PCT. No new notifications of errors or changes have been identified at this time.