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Category:Letter
MONTHYEARLR-N25-0003, Emergency Plan EAL Document Revisions Implemented December 18, 20242025-01-13013 January 2025 Emergency Plan EAL Document Revisions Implemented December 18, 2024 LR-N25-0002, Emergency Plan Document Revision Implemented December 18, 20242025-01-13013 January 2025 Emergency Plan Document Revision Implemented December 18, 2024 ML24324A3312024-12-23023 December 2024 Exemption from the Requirements of 10 CFR Part 50, Sections 50.82(a)(8)(1)(A) and 50.75(h)(1)(iv) (EPID L-2024-LLE-0018) (Ltr) ML24351A0952024-12-17017 December 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24317A2472024-12-16016 December 2024 Environmental Assessment and Finding of No Significant Impact Related to Exemption from the Requirements of 10 CFR Part 50 (Letter) ML24346A0912024-12-11011 December 2024 Request for Information for a Post-Approval Site Inspection for License Renewal - Phase 2; Inspection Report 05000354/2025011 LR-N24-0071, Supplement to License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-12-0606 December 2024 Supplement to License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0069, Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests and Experiments2024-12-0202 December 2024 Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests and Experiments ML24295A3742024-10-23023 October 2024 Project Manager Assignment IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-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 IR 05000272/20244032024-09-25025 September 2024 And Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) 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) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24197A0552024-07-15015 July 2024 Requalification Program Inspection ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) 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 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 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement 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 ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 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 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 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 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 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 ML24080A3962024-03-20020 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 05000354/LER-2023-003-01, 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 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) 2025-01-13
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARLR-N23-0027, Updated Final Safety Analysis Report, Rev. 26,2023-04-13013 April 2023 Updated Final Safety Analysis Report, Rev. 26, ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 LR-N22-0086, – Unit 1 and Unit 2, Updated Final Safety Analysis Report, Revision 332022-10-24024 October 2022 – Unit 1 and Unit 2, Updated Final Safety Analysis Report, Revision 33 ML22298A0542022-10-24024 October 2022 – Units 1 and 2, Hope Creek Generating Station, Submittal of Updated Final Safety Analysis Report, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results 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-N21-0046, 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 ML20142A5492020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 6, Engineered Safety Features ML20142A5302020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 1, Introduction & General Description of Plant ML20142A5242020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 3A, Computer Programs Used in Structural Analysis & Design ML20142A5422020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 17, Quality Assurance ML20142A5222020-05-21021 May 2020 Submittal of Updated Final Safety Analysis Report, Revision 24, Summary of Revised Regulatory Commitments and 10 CFR 54.37(b) Review Results ML20142A5312020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 3, Design of Structures, Components, Equipment and Systems LR-N20-0036, 4 to Updated Final Safety Analysis Report, Section 15, Accident Analyses2020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 15, Accident Analyses ML20142A5272020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 13A Through Appendix 13L Intentionally Deleted ML20142A5482020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 3.6, Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping ML20142A5392020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 13, Conduct of Operation ML20142A5252020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Revision 24, Appendix 5A, Compliance with 10CFR50, Appendix G & Appendix H ML20142A5332020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 5, Reactor Coolant System & Connected Systems ML20142A5402020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 14, Initial Test Program ML20142A5432020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 18, Human Factors Engineering ML20142A5352020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 8, Electric Power ML20142A5232020-05-21021 May 2020 Updated Final Safety Analysis Report, Revision 24, Master Table of Contents and List of Current Pages ML20142A5532020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 12, Radiation Protection ML20142A5262020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 6A, Negative Pressure Design Evaluation ML20142A5372020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 10, Steam and Power Conversion System ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications ML20142A5462020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 9A, Appendix R Comparison ML20142A5322020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 4, Reactor ML20142A5282020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 15A, Purpose ML20142A5342020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls ML20142A5522020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 2, Site Characteristics ML20142A5382020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management ML20142A5292020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix a, Supplement ML19360A0872019-12-0505 December 2019 Submittal of Revision 31 to Updated Final Safety Analysis Report and Technical Specification Bases Changes & Quality Assurance Topical Report, NO-AA-10, Rev. 88 LR-N18-0123, Submittal of Hope Creek Generating Station, Revision 23 to Updated Final Safety Analysis Report2018-11-12012 November 2018 Submittal of Hope Creek Generating Station, Revision 23 to Updated Final Safety Analysis Report ML18334A1502018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Appendix a, License Renewal Final Safety Analysis Report Supplement ML18334A1492018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 18, Human Factors Engineering ML18334A1452018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 15, Accident Analyses ML18334A1362018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls ML18334A1412018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management ML18334A1462018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 16, Technical Specifications ML18334A1482018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 17, Quality Assurance ML18334A1382018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 8, Electric Power ML18334A1422018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 12, Radiation Protection ML18334A1252018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 2, Site Characteristics ML18334A1282018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 4, Reactor ML18334A1442018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 14, Initial Test Program ML18334A1402018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 10, Steam and Power Conversion System ML18334A1432018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 13, Conduct of Operation ML18334A1302018-11-12012 November 2018 3 to Updated Final Safety Analysis Report, Section 5, Reactor Coolant System and Connected Systems 2023-04-13
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 10 CFR 50.71(e) 10 CFR 54.37(b)
NEI 99-04 LR-N20-0036 May 21, 2020 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 24, Summary of Revised Regulatory Commitments for Hope Creek, and 10 CFR 54.37(b) review results for Hope Creek PSEG Nuclear LLC (PSEG) hereby submits:
Revision No. 24 to the Hope Creek Generating Station Updated Final Safety Analysis Report (UFSAR) in accordance with the requirements of 10 CFR 50.71(e)(4) and 10 CFR 50.4(b)(6)
The results of a review performed as required by 10 CFR 54.37(b) to identify any newly-identified Structure, System or Component (SSC) that would be subjected to an aging management review or evaluation of time-limited aging analyses (TLAAs) in accordance with 10 CFR 54.21 A summary of changed/closed regulatory commitments that were not reported by other means during 2019 and 2020 to date in accordance with NEI 99-04.
Revision No. 24 to the Hope Creek UFSAR is being submitted in its entirety electronically and contains identified text, table and figure changes required to reflect the plant configuration as of November 23, 2019, six months prior to this submittal.
In addition, there are general editorial changes. In accordance with 10 CFR 50.71(e)(2)(ii), a summary of changes made under the provisions of
Page 2 LR-N20-0036 10 CFR 54.37(b)
NEI 99-04 10 CFR 50.59 but not previously submitted to the Commission is provided in. The previous revision to the Hope Creek UFSAR was issued on November 12, 2018.
Based on NRC Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents," PSEG has reviewed Revision 24 of the UFSAR for security-related information (SRI). Consequently, Revision 24 of the UFSAR is being provided in its entirety as two separate submittals. This submittal redacts the information that is SRI and designates it as "Security-Related Information - Withheld Under 10 CFR 2.390." This version is suitable for public disclosure. A separate submittal contains the SRI.
In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG performed a review of regulatory commitments to determine if there were any Hope Creek changed/closed commitments that were not reported by other means during 2019 and 2020 to date. The review concluded that there were 2 changed or closed commitments during that time period and a summary of that review is provided in Attachment 2.
An evaluation was completed to determine whether any newly-identified Systems, Structures, or Components (SSCs) existed in support of submitting Hope Creek UFSAR Revision 24. This evaluation involved reviewing pertinent documentation for the period subsequent to the last Hope Creek UFSAR revision. The evaluation concluded that there were no newly-identified SSCs and no changes to the Hope Creek current licensing basis that would have caused any newly-identified SSCs for which aging management reviews or time-limited aging analyses would apply.
As required by 10 CFR 50.71(e)(2)(i), I certify that to the best of my knowledge, the information contained in the CD Enclosures and Attachments to this letter, which pertains to the Hope Creek UFSAR Revision 24, accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. 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. Lee Marabella, at (856) 339-1208.
Sincerely,
- 1::;}-4 Manager, Licensing PSEG Nuclear, LLC
10 CFR 50.71(e)
Page 3 10 CFR 54.37(b)
LR-N20-0036 NEI 99-04
Attachment:
- 1. Summary Report of UFSAR Changes
- 2. Summary Report of Hope Creek Changed/Closed Regulatory Commitments
Enclosures:
- 1. Hope Creek UFSAR Rev. 24 (redacted version suitable for public disclosure) 27 files submitted electronically in 3 parts due to EIE submittal size restrictions CC (Cover letter, Attachments 1 and 2, Enclosure 1)
Administrator - Region I - USNRC USNRC Project Manager USNRC Senior Resident Inspector - Hope Creek Chief, New Jersey Bureau of Nuclear Engineering
10 CFR 50.71(e)
Page 4 10 CFR 54.37(b)
LR-N20-0036 NEI 99-04 bcc:
(Cover letter, Attachments 1 and 2 only)
Plant Manager - Hope Creek Sr. Director, Regulatory Operations and Nuclear Oversight Director, Site Regulatory Compliance Manager, Licensing Site Compliance Commitment Coordinator Records Management
LR-N20-0036 Summary Report of UFSAR Changes
LR-N20-0036 Summary Report Of UFSAR Changes 1
CN #
SECTION DESCRIPTION BASIS HCN 13-003 9.2, T9.2-7 & 8 Reflect removal of the chemical addition tanks in Auxiliary Building Control Area Chilled Water System (CWS) and replacement with a side stream demineralizer.
10 CFR 50.59 screening performed for DCP 80108102.
HCN 18-002 T3.6-13 Reflect revised High Pressure Coolant Injection (HPCI) system stress levels.
10 CFR 50.59 screening performed for DCP 80120777.
HCN 18-008 Appendix 9A Reflect revised analysis of reactor overfill events caused by HPCI malfunction due to postulated Appendix R fire events.
Fire Protection Change Regulatory Review (FPCRR) performed for DCP 80118326.
HCN 18-015 6.2 Include individual MSIV leakage testing.
10 CFR 50.59 screening performed for HCN 18-015.
HCN 18-016 T9A-1, T9A-6 Update combustible fire loading in Room 3553 and Fire Area AB3.
FPCRR performed for HCN 18-016.
HCN 18-020 8.2 Reflect change to carrier line protection circuitry for the Hope Creek 5023 line.
10 CFR 50.59 screening performed for HCN 18-020.
HCN 18-021 Appendix 9A Correct room numbers and their respective fire areas.
The change meets the NEI 98-03 criteria for a non-regulatory change.
HCN 18-024 Appendix 9A Clarify single spurious operation licensing basis; provide the technical basis for acceptance of unrated fire barriers between Fire Area RB5 and fire areas RB1 and RB2; revise the list of high-low pressure interface valves; identify the document containing surveillance requirements and limiting conditions for operation for alternate shutdown; and clarify cable locations.
FPCRR performed for HCN 18-024.
HCN 18-025 6 TOC, T6.3 Incorporate an additional change/error reported in the 2018 Annual 10 CFR 50.46 report, correct a typographical error, and add clarifying information.
The changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN 18-026 2.4 Correct reference to Reg. Guide 1.59.
The change meets the NEI 98-03 criteria for a non-regulatory change.
HCN 18-027 9.5 Reflect installation of a main power transformer fire protection online initiation interlock.
10 CFR 50.59 screening and FPCRR performed for DCP 80122468.
HCN 18-029 F7.1-1, 7.2, 7.6 Incorporate corrections associated with the Power Range Neutron Monitoring system.
10 CFR 50.59 screening performed for DCP 80107709.
LR-N20-0036 Summary Report Of UFSAR Changes 2
CN #
SECTION DESCRIPTION BASIS HCN 19-001 Appendix 9A, T9A-2, T9A-3, T9A-8, T9A-9 Add information to ensure consistency in description of repair actions and add components missing from the Safe Shutdown Equipment List.
The changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN 19-002 4.6, 10.4 Delete control rod drive system surveillance frequencies and add reference to the Surveillance Frequency Control Program.
The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)
HCN 19-003 1.8, T1.8-1 Adopt Revision 4 of Regulatory Guide 1.31, Control of Ferrite Content in Stainless Steel Weld Metal.
10 CFR 50.59 screening performed for HCN 19-003.
HCN 19-004 Appendix 9A, T9A-4, T9A-6 Include basis for acceptance of unrated floor between fire areas and correctly identify rooms containing safe shutdown cables.
FPCRR performed for HCN 19-004.
HCN 19-005 6.3 Correct the calculated HPCI pump available net positive suction head.
The change meets the NEI 98-03 criteria for a non-regulatory change.
HCN 19-006 1.8, 8.3 Add reference to the Surveillance Frequency Control Program as an exception to conformance with Regulatory Guide 1.129, Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants.
The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)
HCN 19-007 13 TOC, 13.1, T13.1-1, F13.1-1, -2, -3,
-4 Remove organizational information that is duplicated in the Quality Assurance Topical Report or that contains excessive detail not important to providing an understanding of the plant's design and operation.
The changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN 19-008 1.8 Add exception to conformance with Regulatory Guide 1.108, Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants.
The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)
HCN 19-011 10.2 Replace turbine valve testing frequencies with a reference to the Preventative Maintenance Program.
The change meets the NEI 98-03 criteria for a non-regulatory change.
LR-N20-0036 Summary Report Of UFSAR Changes 3
CN #
SECTION DESCRIPTION BASIS HCN 19-013 F6.2-47 sh. 1 and 2 Correct error introduced in HCN 15-026 on subject figures.
The change meets the NEI 98-03 criteria for a non-regulatory change.
HCN 19-014 Appendix 15D TOC, 15D, T15D-1, -2, -3,
-4, -5, -8, -9, F15D-1, -2, -3,
-4 Incorporates cycle specific reload analysis results for Cycle 23 and non-regulatory changes.
10 CFR 50.59 screening performed for FCP 80122683.
The additional changes meet the NEI 98-03 criteria for a non-regulatory change.
LR-N20-0036 Summary Report of Hope Creek Changed/Closed Regulatory Commitments
LR-N20-0036 Summary Report Of Hope Creek Changed/Closed Regulatory Commitments 1
Original Commitment Revised Commitment Description Justification for Change Original Commitment:
Hope Creek Generating Station will Include the SFP external makeup strategy and SFP external spray strategy as described In the general description in Attachment 1 In plant procedures (Tables A.2 A.2-6).
Source Document:
Hope Creek Generating Station Renewed Facility Operating License NPF-57 / 2.C(16)(b)7, Spent fuel pool mitigation measures Hope Creek Safety Evaluation for Order EA-02-026 dated August 9, 2007
References:
CM-HC-2007-41 80124591 / 0080 Date of Change:
12/04/2019 Hope Creek Generating Station Implements a two-path mitigation strategy for Spent Fuel Pool (SFP) mitigation measures, The preferred method credits Time Critical Actions for SFP external makeup and SFP external spray implementation within 120 minutes. The alternate method disperses discharged fuel assemblies In an approved pattern until they have been subcritical for more than 295 days.
The current SFP mitigation measures consist of a single-path strategy of dispersing discharged fuel assemblies in an approved pattern until they have been subcritical for more than 295 days.
This strategy results in a significant number of irradiated fuel assembly movements in the SFP every cycle to allow for discharged fuel assemblies to be placed in an approved pattern. Each movement of an irradiated fuel assembly represents risk.
The new SFP mitigation measures designate this path as the alternate path and establish the preferred path as one that credits the Time Critical Actions for SFP external makeup and external spray implementation. This two-path strategy results in an improvement in nuclear safety by significantly reducing the number of irradiated fuel assembly movements in the SFP Original Commitment:
Hope Creek Generating Station will fully implement the BWR mitigation strategies as described in the general description in Attachment 1 in plant procedures (Tables A.5-1 --
A.5-10).
Source Document:
Hope Creek Generating Station Renewed Facility Operating License NPF-57 / 2.C(16)(b)7, Spent fuel pool mitigation measures Hope Creek Safety Evaluation for Order EA-02-026 dated August 9, 2007
References:
CM-HC-2007-43 80124591 / 0210 Date of Change:
03/12/2020 Hope Creek Generating Station will fully implement the BWR mitigation strategies as described in the general description in Attachment 1 in plant procedures (Tables A.5-1 -- A.5-10).
Commitments related to SFP Mitigation Measure are described in CM-HC-2007-41, SFP Mitigation Measures.
CM-HC-2007-41 addresses Spent Fuel Pool Mitigation Measures. It is unnecessary to duplicate them in CM-HC-2007-43. CM-HC-2007-43 is being revised to reference CM-HC-2007-41 for Spent Fuel Pool Mitigation Measures. HC.RE-FR.ZZ-0001 is being removed as an Implementing Document from CM-HC-2007-43 since it was associated with Spent Fuel Pool Mitigation Measures.
1