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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
Section 17.1 17.2 17.. 3 HCGS-UFSAR SECTION 17 QUALITY ASSURANCE TABLE OF CONTENTS QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION QUALITY ASSURANCE DURING THE OPERATIONS PHASE Quality Assurance of the Independent Spent Fuel Storage Installation 17-i 17.1-1 17.2-1 17.3-.1 Revision 15 October 27, 2006
Table 17.2-1 17.2-2 17.2-3 17.2-4 17.3-1 HCGS-UFSAR Title Deleted Deleted Deleted Deleted Deleted LIST OF TABLES 17-ii Revision 15 October 27, 2006
Figure 17.2-1 Deleted HCGS-UFSAR LIST OF FIGURES 17-iii Revision 15 October 27, 2006
17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION This section is not applicable to the FSAR.
Quality Assurance requirements during design and construction are defined in Section 16 of the HCGS PSAR.
Section 16 of the HCGS PSAR was updated on June 6, 1983, and transmitted to the Office of Inspection and Enforcement, Region I, King of Prussia, Pennsylvania, as required by the amendments to 10CFR50.54 and 10CFR50.55 as published in 48FR, No. 6 on January 10, 1983.
On August 11, 1983.
Pages 16.1-3 and 16.2-9 were replaced to include two minor changes which provided clarification to the PSAR update of June 6, 1983.
These pages have been transmitted to the Office of Inspection and Enforcement, Region I, King of Prussia, Pennsylvania.
On October 30, 1984 a general update to Sections 16.1, 16. 2 and 16.4 were transmitted to the Office of Inspection and Enforcement, Region I, King of Prussia, Pennsylvania as required by 10CFR 50.54.
On November 6, 1985 a general update of Section 16 to reflect Bechtel Corporation organization changes was transmitted to the Office of Inspection and Enforcement, Region I, King of Prussia, Pennsylvania as required by 10CFRSO.SS.
17.1-1 HCGS-UFSAR Revision 0 April 11, 1988
17.2 QUALITY ASSURANCE DORING THE OPERATIONS PHASE The licensee is :responsible :for the operation and maintenance of Salem/Hope Creel Generating Stations.
These activities are presently conducted in accordance with the NRC approved Quality Assurance Topical Report {QATR) which describes the formal and comprehensive control methods established to assure compliance with 10CFR50, Appendix B.
The QATR describes how the Quality Assurance Program is to be functionally implemented with due regard to the safety and health of the public and the personnel on site.
The Salem/Hope Creek Quality Assurance Program as described by the QATR is incorporated herein by reference.
17.2-1 HCGS-UFSAR Revision 15 October 27, 2006
TABLE 17.2-1 This Table Has Been Deleted 1 of 1 HCGS-UFSAR Revision 15 october 27, 2006
TABLE 17.2-2 This Table Has Been Deleted 1 of 1 HCGS-UFSAR Revision 15 October 27, 2006
TABLE 17.2-3 This Table Has Been Deleted 1 of 1 HCGS-UFSAR Revision 15 October 27, 2006
TABLE 17.2-4 This Table Has Been Deleted 1 of 1 HCGS-UFSAR Revision 15 October 27, 2006
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THIS FIGURE HAS BEEN DELETED PSEG NUCLEAR L.L.C.
HOPE CREEK GENERATING STATION NUCLEAR ASSESSMENT HOPE CREEK UFSAR-REV. 15 SHEET -J*ot= 1 FIG.17.2-1
17.3 QUALITY ASSURANCE OF THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION The licensee is responsible for the operation and maintenance of Salem/Hope Creel Generating Stations.
These activities are presently conducted in accordance with the NRC approved Quality Assurance Topical Report (QATR}
which describes the formal and comprehensive control methods established to assure compliance with 1 OCFR5 0, Appendix B. By letter dated may 12, 2 003 1 PSEG Nuclear notified the NRC of it's intent to apply it's previously approved QA Program to the construction and operations of an ISFSI at the Hope Creek and Salem Generating Stations in accordance with 10CFR72.140(d}.
The QATR describes how the Quality Assurance Program as applied to the Independent Spent Fuel Storage Installation is to be functionally implemented. The Salem/Hope Creek Quality Assurance Program as described by the QATR is incorporated herein by reference.
17.3-1 HCGS-UFSAR Revision 15 October 27, 2006
Table 17.3-1 This Table Has Been Deleted 1 of 1 HCGS-UFSAR Revision 15 Octobe~ 27, 2006
