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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: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 2, Updated Final Safety Analysis Report, Revision 332022-10-24024 October 2022 Unit 2, Updated Final Safety Analysis Report, Revision 33 ML22298A0542022-10-24024 October 2022 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 ML20142A5392020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 13, Conduct of Operation ML20142A5382020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management ML20142A5262020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 6A, Negative Pressure Design Evaluation ML20142A5322020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 4, Reactor ML20142A5372020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 10, Steam and Power Conversion System ML20142A5272020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 13A Through Appendix 13L Intentionally Deleted ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications 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 ML20142A5312020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 3, Design of Structures, Components, Equipment and Systems ML20142A5242020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 3A, Computer Programs Used in Structural Analysis & Design ML20142A5352020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 8, Electric Power ML20142A5402020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 14, Initial Test Program ML20142A5332020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 5, Reactor Coolant System & Connected Systems ML20142A5492020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 6, Engineered Safety Features 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 ML20142A5302020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 1, Introduction & General Description of Plant ML20142A5522020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 2, Site Characteristics ML20142A5462020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 9A, Appendix R Comparison ML20142A5532020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 12, Radiation Protection 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 ML20142A5342020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls ML20142A5282020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix 15A, Purpose ML20142A5252020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Revision 24, Appendix 5A, Compliance with 10CFR50, Appendix G & Appendix H ML20142A5422020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 17, Quality Assurance ML20142A5232020-05-21021 May 2020 Updated Final Safety Analysis Report, Revision 24, Master Table of Contents and List of Current Pages ML20142A5432020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 18, Human Factors Engineering ML20142A5292020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Appendix a, Supplement ML18334A1432018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 13, Conduct of Operation ML18334A1442018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 14, Initial Test Program ML18334A1482018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 17, Quality Assurance ML18334A1492018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 18, Human Factors Engineering ML18334A1502018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Appendix a, License Renewal Final Safety Analysis Report Supplement ML18334A1412018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management ML18334A1402018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 10, Steam and Power Conversion System ML18334A1452018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 15, Accident Analyses ML18334A1462018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 16, Technical Specifications ML18334A1302018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 5, Reactor Coolant System and Connected Systems ML18334A1272018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 3, Design of Structures, Components, Equipment and Systems, Part 2 of 2 ML18334A1282018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 4, Reactor 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 ML18334A1362018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls ML18334A1422018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 12, Radiation Protection ML18334A1242018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Section 1, Introduction and General Description of Plant ML18044A0022017-05-19019 May 2017 Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 12, Radiation Protection 2023-04-13
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC 10 CFR 50.71(e) 10 CFR 54.37(b)
NEI 99-04 LR-N21-0081 November 15, 2021 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 25, 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. 25 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 2020 and 2021 to date in accordance with Nuclear Energy Institute (NEI) 99-04.
Revision No. 25 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 May 15, 2021, 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 10 CFR 50.59
10 CFR 50.71(e)
Page 2 10 CFR 54.37(b)
LR-N21-0081 NEI 99-04 November 15, 2021 but not previously submitted to the Commission is provided in Attachment 1. The previous revision to the Hope Creek UFSAR was issued on May 21, 2020.
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 25 of the UFSAR for security-related information (SRI). Consequently, Revision 25 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 NEI process for managing NRC commitments and associated NRC notifications, PSEG performed a review of regulatory commitments to determine if there were any changed/closed Hope Creek commitments that were not reported by other means during 2020 and 2021 to date. The review concluded that there was one changed commitment 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 SSCs existed in support of submitting Hope Creek UFSAR Revision 25. 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 files attached to this submittal and Attachments to this letter, which pertains to the Hope Creek UFSAR Revision 25, 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, Montgomery Digitally signed by Montgomery, Richard
, Richard Date: 2021.11.15 12:11:38
-05'00' Richard Montgomery Manager, Licensing PSEG Nuclear, LLC
10 CFR 50.71(e)
Page 3 10 CFR 54.37(b)
LR-N21-0081 NEI 99-04 November 15, 2021
Attachment:
- 1. Summary Report of UFSAR Changes
- 2. Summary Report of Hope Creek Changed/Closed Regulatory Commitments
Enclosures:
- 1. Hope Creek UFSAR Rev. 25 (redacted version suitable for public disclosure)
- 2 files submitted electronically CC (Cover letter, Attachments 1 and 2, Enclosure 1)
Administrator - Region I - USNRC USNRC Project Manager USNRC Senior Resident Inspector - Hope Creek Manager, New Jersey Bureau of Nuclear Engineering (without Enclosure 1)
Site Compliance Commitment Coordinator (without Enclosure 1)
Corporate Commitment Coordinator (without Enclosure 1)
LR-N21-0081 Attachment 1 Summary Report of UFSAR Changes
LR-N21-0081 Summary Report of UFSAR Changes CN # SECTION DESCRIPTION BASIS HCN T3.4-4, Site Sewage Treatment plant being 10 CFR 50.59 11-002 9TOC, 9.2, replaced. screening performed F9.2-12 for DCP 80101825.
HCN 8.3 Enhance 500 kV and 13kV electrical 10 CFR 50.59 18-003 systems with new protective relay screening performed scheme to protect against open phase for DCP 80119206.
condition HCN 9TOC, Adds new Table 9A-103 to fire hazards Fire Protection 18-005 T9.5-19, analysis to support addition of a new air Change Regulatory T9A-103 compressor to SWIS Room 202 Review (FPCRR) performed for EC 80120609. 10 CFR 50.59 screening performed for HCN 18-005.
HCN T9A-1, Revise combustible loading in room 3219 FPCRR and 10 CFR 18-022 T9A-6 50.59 screening performed for HCN 18-022.
HCN 3.9, 5.2, Replacement of the 13 remaining Target 10 CFR 50.59 18-028 T5.2-1, Rock 2-stage Main Steam Safety Relief screening performed T5.2-7, Valves (SRVs) with 3-stage valves. for DCP 80122932.
F5.2-8 HCN 2.2, T2.2-5, Installs the Purate (chlorine dioxide) 10 CFR 50.59 19-012 T2.2-6, biocide water treatment system design to screening performed T9.5-3, treat the Circulating Water (CW) System. for DCP 80124128.
10.4.5.2, T10.4-6 HCN 9.5 Modify Diesel and electric motor driven FPCRR performed for 19-015 fire pumps circuitry by lifting leads from DCP 80125227.
the remote control panel 10C682 in the control room and local panels 00C530 and 00C531 to eliminate the remote start option.
HCN T9A-1, The proposed change creates a fire FPCRR performed for 20-001 T9A-75 hazard analysis for Rooms 5702 and HCN 20-001.
5706 in Fire Area CD60. In addition, Table 9A-1 will be revised to include Rooms 5702 and 5706, and Table 9A-75 page 1 is revised to reflect the full floor area and average fire loading for Fire Area CD60.
1
LR-N21-0081 Summary Report of UFSAR Changes CN # SECTION DESCRIPTION BASIS HCN T9A-1, Incorporates transient storage for the FPCRR performed for 20-004 T9A-25 Operations Department in the caged HCN 20-004.
area of Rooms 5315/5308.
HCN 9.1 Revise UFSAR Sections 9.1.1.3.1 & 10 CFR 50.59 20-010 9.1.2.3.1, "Criticality Control", to screening performed document compliance with 10 CFR 50.68 for HCN 20-010.
and 10 CFR 70.24, Criticality Accident Requirements.
HCN 1.8 Updates the Revision to which PSEG 10 CFR 50.59 21-002 Nuclear conforms in Section 1.8 for NRC screening performed Regulatory Guides 1.21 from Revision 1 for HCN 21-002.
to Revision 2, and RG 1.23 from Revision 0 to Revision 1.
HCN 1.8 Add an exception to the regulatory guide 10 CFR 50.59 21-004 1.140 section of the UFSAR. The leak screening performed testing frequency of the activated carbon for HCN 21-004.
absorber section will be conducted in accordance with the Preventative Maintenance (PM) program.
HCN T7.7-4 Change Seismic Monitoring 10 CFR 50.59 21-006 Instrumentation channel calibration screening performed frequency to be controlled under the for HCN 21-006.
Preventative Maintenance Program.
HCN T3.6-10, Mark table data as historical information The changes meet the 21-007 T3.6-11 and refer to applicable stress NEI 98-03 criteria for a calculations for current data. non-regulatory change.
HCN 15.1, Incorporates cycle specific reload 10 CFR 50.59 21-008 Appendix analysis results for Cycle 24 and non- screening performed 15D, F15D, regulatory changes. for FCP 80126636.
T15D The additional changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN Appendix A Revise the BWRVIP-48-A to The change meets the 21-009 "BWRVIP-48-A or later revision". NEI 98-03 criteria for a non-regulatory change.
2
LR-N21-0081 Summary Report of UFSAR Changes CN # SECTION DESCRIPTION BASIS HCN 8.2 Revise description of Red Lion line 10 CFR 50.59 21-013 primary and backup protection schemes. screening performed Delete carrier equipment failure from the for DCP 80127900.
system monitoring and annunciation section. Revise switchyard fault recorder parameter status inputs for the Red Lion (61X) line.
HCN 9.5, Remove and delete redundant and The change meets the 21-016 Appendix 9A duplicate information associated with NEI 98-03 criteria for a equivalent fire severity for the Main non-regulatory Control Room and peripheral rooms. change.
HCN 9.2 Corrects an error in incorporating The change meets the 21-017 previously evaluated change to NEI 98-03 criteria for a description of equipment cooled by non-regulatory Turbine Auxiliaries Cooling System. change.
3
LR-N21-0081 Attachment 2 Summary Report of Hope Creek Changed/Closed Regulatory Commitments
LR-N21-0081 Summary Report of Hope Creek Changed/Closed Regulatory Commitments Original Commitment Revised Commitment Justification for Change Description Original Commitment: Component testing or Hope Creek Regulatory Any component testing or maintenance of safety Commitment CM.HC.2011-816 was maintenance that increases the systems and important revised to align with NRC likelihood of a plant transient shall non safety equipment in expectations listed in NUREG-0800, be avoided during the extended 14 the offsite power systems Branch Technical Position 8-8, day AOT. This encompasses work that can increase the Onsite (Emergency Diesel activities categorized as Production likelihood of a plant Generators) and Offsite Power Risk. transient (unit trip) or Sources Allowed Outage Time LOOP will be avoided. In Extensions.
Source Document: addition, no discretionary Amendment No. 188 to Facility switchyard maintenance The existing commitment was Operating License No. NPF-57 for will be performed. broader than necessary when NRC the Hope Creek Generating Station. recently approved license amendment 216 (April 2019).
Issuance of Amendment re:
Emergency Diesel Generators A and B Allowed Outage Time Extension (TAC No. ME3597).
References:
CM-HC-2011-816 70215722 / 0010 80128524 / 0060 Date of Change:
05/29/2021 1
Enclosure 1 to LR-N21-0081 Hope Creek UFSAR Rev. 25 (redacted version suitable for public disclosure) 2 files submitted electronically 1