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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
Security Related Information - Withhold Under 10 CFR 2.390 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)
TS6.15.d NEI 99-04 LR-N18-0123 November 12, 2018 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 23, Hope Creek Technical Specification Bases changes, 2018 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:
- A complete updated copy of the Hope Creek Technical Specification Bases, which includes changes through November 12, 2018, in accordance with the requirements of Hope Creek Generating Station Technical Specification 6.15.d
- 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 AP5 ~
J CD Enclosure 1, CD-1, contains Security Related Information - Withhold Under 10 CFR 2.390. When separated from CD-1, this document is decontrolled.
NOV 12 2018 10 CFR 50.71 (e)
Page 2 10 CFR 54.37(b)
LR-N 18-0123 TS 6.15.d NEI 99-04 Revision No. 23 to the Hope Creek UFSAR is being submitted in its entirety electronically via CD-ROM and contains identified text, table and figure changes required to reflect the plant configuration as of May 11, 2018, 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 but not previously submitted to the Commission is provided in . Hardcopy pages containing the revised material and associated insert/remove instructions will no longer be provided . The previous revision to the Hope Creek UFSAR was issued on May 9, 2017 .
Based on NRG 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 23 of the UFSAR for security-related information (SRI). Consequently, Revision 23 of the UFSAR is being provided in its entirety as two separate versions each on its own CD. One version ,
on CD-1, contains SRI and should be withheld from public disclosure under 10 CFR 2.390. The information that is SRI is designated by the statement "Security-Related Information - Withhold Under 10 CFR 2.390" at the top of the page. The second version, on CD-2, redacts the information that is SRI and designates it as "Security-Related Information - Withheld Under 10 CFR 2.390 ." The version on CD-2 is suitable for public disclosure. contains a complete updated copy of the Hope Creek Technical Specification Bases with changes through November 12, 2018 .
In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRG) commitments and associated NRG 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 2016 and 2017 . The review concluded that there were no changed or closed commitments during that time period .
An evaluation was completed to determine whether any newly-identified Systems, Structures , or Components (SSCs) existed in support of submitting Hope Creek UFSAR Revision 23 . 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 23, accurately reflects information and analy~e~ submitted to the NRC, or prepared purs ant to NRC requirements as described above. There are no regulatory commitments contained in this letter.
NOV 1 2 2018 10 CFR 50.71(e)
Page 3 10 CFR 54.37(b)
LR-N 18-0123 TS 6.15.d NEI 99-04 If you have any questions or require additional information, please do not hesitate to contact Mr. Lee Marabella, at (856) 339-1208.
Sincerely, Paul Duke Manager, Licensing PSEG Nuclear, LLC Attachments:
- 1. Summary Report of UFSAR Changes CD
Enclosures:
- 1. CD-1, Hope Creek UFSAR Rev. 23 (withhold from public disclosure)
- 2. CD-2, Hope Creek UFSAR Rev. 23 (redacted version suitable for public disclosure)
Other
Enclosures:
- 1. Hope Creek Generating Station Technical Specification Bases as of November 12,2018 CC (Cover letter, CD enclosure 1 and 2, and Attachment 1 only)
Administrator - Region I - USNRC Licensing Project Manager - Hope Creek - USNRC USNRC Senior Resident Inspector - Hope Creek Chief, New Jersey Bureau of Nuclear Engineering (Cover letter, Attachment 1 only)
Hope Creek Commitment Coordinator
LR-N 18-0123 Attachment 1 Summary Report of UFSAR Changes
LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 14-016 9.5 9.5-107 UFSAR change reflects the Design Change package 80107326 instituted .
replacement of 20kVA UPS Associated 50 .59 screening is included in the 180484, power supply to the Hope HCN 14-016 package.
Creek Radio System.
HCN 14-018 1.14, 3.9, App 38, 1.14-11, -61, -89, 3.9-52, -76, - UFSAR change reflects Design Change package 80107006 instituted.
5.2, App 9A, 14.2, 111, -112, -120, -121, -123, 38-2 , replacement of 1 of the 14 Target Associated 50.59 screening and Fire 15.1 38-3, 5.2-17, -17a, -17b, -17c, - Rock 2-Stage Main Steam Safety Protection Change Regulatory Review 17d, -18 thru -27, T5.2-1 sh1, Relief Valves (SRVs) with a Target (FPCRR) are included in the HCN 14-018 T5.2-7 sh7a, F5.2-8, F5.2-8A, Rock 3-Stage valve. It also package.
T9A-1 sh29, T9A-8 sh17, 14.2- removes a portion of EPU vibration 217, 15.1-16 monitoring cable and vibration monitoring equipment HCN 15-009 9.5, Appdx 9A 9.5-4, 27, -31, -32, -33, -34, -39, - UFSAR change reflects removal of Design Change package 80112931 instituted.
40, -40a, -40b, -41, -43, -44, -45,
- Foxboro transponder panels and Associated 50.59 screening is included in the 54, -78, -78a, T9.5-19 sh1 & 2, the Pyrotronics System 3 panel and HCN 15-009 package.
9A-38, -59, -60 thru -65, -70, -71, replaces them with Siemens XLS
-75, -76, T9A-1 sh25 thru 36 , fire alarm panels.
T9A-8 sh2 thru 11, sh13 thru 19, sh21 thru 25, T9A-9 sh2 thru 17, sh20 thru 26, T9A-12 sh2 , 4, 8, 9, 10, 11 , 12, 15, 17, 22 - 25, 27, 28, 32 - 35, 39-42 HCN 15-010 Appendix 9A T9A-1 sh43, 48, T9A-50 sh1, UFSAR change reflects addition of Design Change package 80111348 instituted.
T9A-60 sh1, 10, T9A-61 sh1, 3 combustible load to rooms 5403 Associated 50 .59 screening and FPCRR are and 5515 to support replacement of included in the HCN 15-010 package.
PRNM system with GE NUMAC.
LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 16-006 1.2, 1.6, T1 .13 , 1.2-22 , 1.6-2 , -8, T1 .13-1 sh 1, 2, UFSAR change reflects Design Change package 80107709 instituted .
1.14, T3.2 , T3.10, 7 3, 6, 8, 1.14-58, T3 .2-1 sh27, 36, replacement of the Power Range Associated 50.59 screening and FPCRR are TOC , T7.1, F7 .1, T3.10-4 sh2, 7-ii, -viii, T7.1-1 Neutron Monitoring System with a included in the HCN 16-006 package.
7.2, T7.2, 7.6, T7 .6, sh3, T7.1-2 sh2, 4, 6, F7.1 -1, 7.2- Nuclear Measurement Analysis and F7 .6, 7.7, Appendix 7 thru -13 , -20, -29 , -33, -36, -37, Control (NUMAC) based system .
9A, 15.4, Appdx T7 .2-2 sh1 , T7.2-3 sh1 , 7.6-11 150 thru -18b, -43, -44, -4 7 thru -49, T7.6-2 sh1 & 2, T7.6-3 sh1, T7.6-7 sh1, F7 .6-5, 7.7-8, -9, -12, -14, -
57, T9A-1 sh48, T9A-60 sh1 , 10, T9A-61 sh1 , 3, 15.4-5, -20, 15D-5, -8, -10 HCN 16-012 Appendix 9A T9A-1 sh 54, T9A-100 sh1 &2, UFSAR change reflects the addition Design Change package 80107617 instituted.
T9A-101 sh1 , 2 of combustible load for the Associated FPCRR is included in the HCN 16-fiberglass duplex panels being 012 package.
installed in the Hope Creek Service Water building to operate the Service Water Intake Structure (SWIS) .
HCN 17-004 12.3 12.3-52 UFSAR change reflects the deletion This change was reviewed and approved by of a sentence that references a the Radiation Protection Group who concluded table that was deleted in a previous that the changes met the NEI 98-03 criteria for change notice (HCN 17-003). a non-regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regulatory changes is included in the HCN 17~004 package.
HCN 17-005 8.1 8.1-27 UFSAR change clarifies that Class Design Change package 80120205 instituted.
1E DC power also feeds non-class Associated 50 .59 screening is included in the 1E loads as well as Class 1 E AC HCN 17-005 package.
power.
2
LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 17-006 11 .5 11 .5-20 UFSAR change provides Design Change Package 80111494 instituted.
clarification as to what sources of Associated 50.59 screening is included in the dilution water are available for liquid HCN 17-006 package.
radwaste releases during outages when the cooling tower is OOS and to align with changes being made to the ODCM .
HCN 17-007 5.2 5.2-20 UFSAR change revises Section This change was reviewed and approved by 5.2.2.4.2.1.3.2 to eliminate Plant Engineering who concluded that the unnecessary detail. changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 10CFR50.59 screening was required. The Attachment 5 review form for non-regulatory changes is included in the HCN 17-007 package.
HCN 17-009 1.1, F1.1-1, 1.2, 1.1-1, F1 .1-1, 1.2-33, 4-vi, 4.4-4, - UFSAR changes reflect design Design Change package 80116382 instituted.
4.4, F4.4-1, F4.4- 5, -6, -11, F4.4-1, -1a, 5.4-14, 6.2- changes to support measurement Associated 50.59 screening and FPCRR are 1a, 5.4, 6.2, 7 .5, 5, -13, -16, -18, 7.5-8, 7.6-47, - uncertainty recapture (MUR) uprate. included in the HCN 17-009 package.
7.6, 7.7, 10.1, 10.2, 50, 7.7-24, -25, -30, -49, -51, 14.2, App9A T9A-1 sh16, T9A-6 sh1 , 10.1-3, 10.2-1, 14.2-207 HCN 17-010 9.5 9.5-31, -84 UFSAR changes reflect the This change was reviewed and approved by extension of inspection frequency Programs Engineering . A FPCRR is included for valve position verification of in the HCN 17-010 package.
class 1 and non-class 1 valves.
HCN 17-013 8.3 8.3-62, F8.3-16 UFSARchanges reflect the addition Design Change Package 80120892 instituted.
of new 250 voe HPCI System Associated 50.59 screening is included in the Analysis Calculation . HCN 17-013 package.
3
LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 17-014 12.5 12.5-22 UFSAR change makes a correction This change was reviewed and approved by to page 12.5-22 which was not the Radiation Protection Group who concluded updated during the Rev. 22 update that the changes met the NEI 98-03 criteria for submittal. a non-regulatory:change and therefore no 10CFR50.59 screening was required. The Attachment 5 review form for non-regulatory thanges is inclu~ed in the HCN 17-014 package. i i
I HCN 17-015 4.2, 15.8 4.2-3, 15.8-7 UFSAR change modifies the This change was reviewed and approved by reference to the GNF-2 Compliance Nuclear Fuels who concluded that the changes Report to reflect latest revision vs. met the NEI 98-03 criteria for a non-regulatory specific revision number and date. change and therefore no 10CFR50.59 screening was required. ,The Attachment 5 review form for rion-regulatory changes is included in the HCN 17-015 package.
I I I :
I HCN 17-016 Appendix 9A T9A-1 sh33, 34, 55, T9A-13 sh1, UFSAR change quantifies Design Change package 80120545 instituted.
2, 3 combustible loading changes from Associated FPCRR is included in the HCN 17-the Technical Support Center 016 package. :
expansion effort.
HCN 17-017 5.4, 7.6, 7.7,8.1, 5.4-3, -5, 7.6-58, 7.7-25 thru -33, UFSAR change reflects Design Change package 80115139 instituted.
9.2, 9.4, Appendix F?.7-6, 8.1-18, -23, T9.2-4 sh1, replacement of Recirc Pump MG Associated 50.5~ screening and evaluation are 9A, 15.3, 15.4, 15.9 1a, 1b, 2c, 9.4-69, -74, T9A-1 Sets with Variable Frequency Drive included in the HCN 17-017 package.
sh?, 8, 16, 38, T9A-6 sh 1, T9A- Units.
31 sh1, 15.3-6 thru -9, 15.4-7, -9,
-10, -11, 15.9-48, F15.9-18 4
LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 18-001 12.3 12.3-52 UFSAR change reflects clarification This change was reviewed and approved by of air sampling requirements for Radiation Protection who concluded that the continuous air monitors changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regulatory changes is included in the HCN 18-001 package.
HCN 18-004 4 toe, 4,3, 5 toe, 4-ii, -v, 4.3-2, -3, -4, T4.3-1 sh1, UFSAR changes reflect the removal License Amendment 209 implemented .
5.3, Appendix 5A 5-xii, 5.3-6, -8, -11, -11a, -11b, - of old Pressure - Temperature (P-T) Associated 50.59 applicability and NRC Safety 17, -18, -34, F5.3-1A, -1B, -1C, Curves to correspond with TS Evaluation is included in the HCN 18-004 5A-9 Amendment 209. package.
HCN 18-006 Appendix 9A T9A-1 sh16, T9A-6 sh1 UFSAR change reflects This change was reviewed and approved by incorporation of the dress-out area Programs Engineering . A FPCRR is included into the Fire Hazards Analysis to in the HCN 18-006 package.
eliminate the need for transient combustible permits.
HCN 18-007 6.3, Appendix 150 T6.3-7 sh1 , 2, 3, 150-i, 150-1, - UFSAR change reflects Fuel Change Package 80119250 instituted .
2, -4, -6, -7 , -9 , T150-1 sh1, -2, incorporation of cycle specific Associated 50.59 screening is included in the T150-2 sh1, T150-3 sh1, T150- reload analysis results for Cycle 22 . HCN 18-007 package .
8 sh1, T150-9 sh1 , F150-1, -2, -
3 HCN 18-009 13 toe, 13.1 13-i, 13-1 thru 13-12, F13.1-2, -3, UFSAR change reflects Engineering This change was reviewed and approved by
-4 and Training organizational Human Resources and Licensing . A 10 CFR changes. 50.54( q) evaluation is included in the HCN 18-009 package.
HCN 18-010 Appendix 9A T9A-1 sh41, T9A-25 sh 1 & 6 UFSAR change incorporates This change was reviewed and approved by additional fire loading in room 5315. Programs Engineering . A FPCRR is included in the HCN 18-010 package.
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LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN# SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 18-011 Appendix 9A T9A-1 sh16, T9A-6 sh1 UFSAR change incorporates new This change was reviewed and approved by plastic material added under DCP Programs Engineering . A FPCRR is included 80048294 into Room 3449 and Fire in the HCN 18-011 package.
Area AB3.
HCN 18-017 Appendix 9A 9A-55 UFSAR change corrects an This change was reviewed and approved by inconsistency discovered during Programs Engineering who concluded that the response to NRC triennial fire changes met the NEI 98-03 criteria fo r a non-inspection . regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regu latory changes is included in the HCN 18-017 package.
HCN 18-018 9.5 9.5-159 UFSAR change removes the words, This change was reviewed and approved by "in accordance with Station Plant Engineering which concluded that the Administrative Procedures", from changes met the NEI 98-03 criteria for a non-Diesel Generator 55 gal lube oil regulatory change and therefore no drum storage requirement 10CFR50.59 screening was required . The statement to eliminate excessive Attachment 5 review form for non-regulatory detail. changes is .included in the HCN 18-018 package.
6