ML17046A344

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Section 4.5, Reload Analyses

ML17046A344
Person / Time
Site:	Salem
Issue date:	01/30/2017
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17046A230	List: LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 Through 3.8-56 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 6.3-1A Through 6.3-4 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 9.1-1 Through 9.1-9 LR-N17-0034, Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7 LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.2, Nearby Industrial, Transportation, and Military Facilities LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.6, Figure 3.6-1 Through Figure 3.6-30 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 15.3A, Generic Small Break Analysis LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.6A, Description of Backdraft Damper LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.9A, Bolted Connections for Linear Component Support LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 7A, Program Element Descriptions Resulting from the Implementation of the May 6, 1983 Order LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Figures 15.4-2 to 15.4-111 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Section 15.5, Anticipated Transients Without Scram LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 17, Figures 17.2-1 to 17.2-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.2-1 to 4.2-25 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 to 4.3-35 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4-1 to 4.4-17 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4.1 to 4.4-66d LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.5-1 to 4.5-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Section 4.5, Reload Analyses LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 5.4.1 to 5.4-14 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.2-1 to 4.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.3-1 to 4.3-11 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.4-1 to 4.4-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.5-1 to 4.5-2 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.1-1 to 5.1-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.2-1 to 5.2-24 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.3.1 to 5.3-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Table 5.1-1, System Design and Operating Parameters LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Tables 5.2-1 to 5.2-42 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 14.6-1 Through 14.6-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.1-1 Through 15.1-9 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.2-1 Through 15.2-46 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.3-1 Through 15.3-68 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.7.1 Through 3.7-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.9-1 Through 3.9-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3A-1 Through 3A-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 7.6-1 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 8.2-1 (Intentionally Deleted) and Figure 8.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.2-1 to 10.2-4 Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.3-1A Sheets 1 Through 6 of 6 Intentionally Deleted to 10.3-3, Sheets 1 & 2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.4-1 Sheets 1 & 2 of 2, Intentionally Deleted to 10.4-19 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.2-1A Sheets 1 Through 5 of 5 to 11.2-1B Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.3-1A & B, Sheets 1, 2 & 3 of 3, Intentionally Deleted. Refer to Plant Drawings 205240 & 205340 in Dcrms LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.4-1 to 11.4-9 ... further results
References
LR-N17-0034
Download: ML17046A344 (2)

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• 4.5 RELOAD ANALYSES A Reload Evaluation (RSE)/Safety Assessment (SA) is performed for each cycle using methodology described in Reference 1. Based on this methodology, those events analyzed and reported in the Salem UFSAR, as well as limits given in the Technical Specification or Core Operating Limits Report (COLR) that could potentially be affected by the fuel reload are addressed. These UFSAR analyses and limits contain assumptions which involve parameters whose values are core design dependent. Hence, those parameters sensitive to reload core designs are considered, i.e., core criticality, power distributions, shutdown margin, etc. In addition, changes in fuel assembly design (mechanical, nuclear, and thermal-hydraulic) that could potentially affect the events analyzed are also addressed. The RSE/SA results are used as input into the 10CFR50. 59 process to determine if an Unresolved Safety Question (USQ) exists or a Technical Specification needs to be modified for a reload cycle. As part of the Reload Safety Evaluation process, the values for the parameters defined in the COLR are determined. The COLR contains specific parameter values which were contained in the Technical Specifications: Beginning and End of Cycle Moderator Temperature Moderator Temperature Surveillance Limit, Control Rod Insertion Limits, Axial Flux Difference Range, Heat Flux Hot Channel Factor (FQ{z)), Nuclear Enthalpy Rise Hot Channel Factor (FAH), and Boron Concentration . The Nuclear Design Report (NOR), Curvebook (CB), and Plant Operations Package (POP) are cycle-specific documents which contain the best estimate of the reload's nuclear characteristics. Typical nuclear characteristics consist of boron concentrations, reactivity coefficients, boron and control rod worths. Typical fuel assembly design information consists of assembly enrichments, fuel pellet and rod characteristics, and burnable absorber types. NOR, CB, and POP data is used to support plant operation and to compare measured and predicted plant data. Typical Salem Unit 1 cycle 1 s loading pattern and burnable absorber configuration are given as 4.5-1 and 4.5-2, respectively. Typical Salem Unit 2 cycle 1 s loading pattern and burnable absorber configuration are given as Figures 4.5-3 and 4.5-4, respectively. The cycle specific RSE/SA, COLR, and NDR/CB/POP for Salem Units 1 and 2 can be found in the appropriate site specific document control system . 4.5-1 SGS-UFSAR Revision 23 October 17, 2007 4.5.1 References for Section 4.5 1. Davidson, S. L. 1 (Ed.), et. al. 1 "Westinghouse Reload Safety Evaluation Methodology," WCAP-9273-NP-A, July 1985. 4.5-2 SGS-UFSAR Revision 17 October l61 1998