LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.5, Requirements for Further Technical Information

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.5, Requirements for Further Technical Information

ML17046A242
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: ML17046A242 (4)

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• 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION One of the design bases for the Salem Generating Station has been to utilize well-developed and proven design concepts, systems, and equipment, in order to minimize the potential for cost and schedule overruns and to enhance the reliability of operation. As a consequence, there have been few requirements for research and development programs to confirm the adequacy of the design. Those programs identified for Salem have been satisfactorily completed, as described in Section 1.5.1. Other programs were identified as valuable to define margins of conservatism or possible design improvements. Relevant programs in this latter category are described in Section 1.5.2 1.5.1 17 x 17 Fuel Assembly A comprehensive test program for the 17 x 17 assembly has been successfully completed by Westinghouse. Reference 1 contains a summary discussion of the program. The following sections present specific references documenting individual portions of the program. 1.5.1.1 Rod Cluster Control Spider Tests Rod cluster control spider tests have been completed. For a further discussion of these tests, refer to Section 4.2.3.4. 1.5.1.2 Grid Tests Verification tests of the structural adequacy of the grid design have been completed. Refer to Section 4.2.3.4 and Reference 2 for a discussion of these tests. 1.5.1.3 Fuel Assembly Structural Tests Fuel assembly structural tests have been completed. Refer to References 2 and 3 for a discussion of these tests. 1.5-1 SGS-UFSAR Revision 6 February 15, 1987 1.5.1.4 Guide Tube Tests Verification tests of the structural adequacy of the guide tubes have been completed. Refer to References 3 and 4 for a discussion of these tests. 1.5.1.5 Prototxpe Assembly Tests Verification tests of the integrated fuel assembly and rod cluster control performance have been completed. Refer to References 3 and 4 for a discussion of these tests. 1.5.1.6 Departure from Nucleate Boiling Tests The test program for experimentally determining the effect of the fuel assembly geometry on the departure from nucleate boiling (DNB) heat flux has been completed. Refer to Reference 5 for a discussion of these tests. 1.5.1.7 Incore Flow Mixing The experimental test program to determine the effects of the fuel assembly geometry on mixing has been completed. Refer to Reference 6 for a discussion of these tests. 1.5.2 Other Programs 1.5.2.1 Generic Programs of Westinghouse Reference 7 summarizes ongoing safety-related research and development programs that are being carried out for, or by, or in conjunction with the Westinghouse Nuclear Energy System Division and that are applicable to Westinghouse pressurized water reactors. 1.5-2 SGS-UFSAR Revision 6 February 15, 1987 * *

• 1 5.2.2 LOCA Heat Transfer Tests E.xperimental test programs to determine the thermal-hydraulic characteristics of 17 x 17 fuel assemblies and to obtain experirnenta l reflooding transfer data under simulated loss-of-coolant accident (LOCA) conditions have been completed. Refer to Re.fer'ence 8 for a discussion of these test.s. A single rod burst test program to quantify the maximum assembly flow blockage whi,ch is assumed in the LOCA ana yses has been completed. Refer to Reference 9 for a discussion of these tests. The results of these two test programs have been used in the Emergency Core Cooling System analyses in Chapter 15. 1.5.3 References for Section 1.5 1. Eggleston, F. T., 11Safety-Related Research and Development for Westinghouse Pressurized Water Reactors, Program Summaries -Spring 1976,." June 1976. 2. Gesinski, L. and Chiang, D. , "Safety Analysis O*f the 17 x 17 Fuel Assembly for Combined Seismic and Loss-of-Coolant Accident," WCAP-8236 (Proprietary) and WCAP-8288 (Non .. Proprietary), December 1973. 3. DeMario, E. E. , "Hydraulic Flow Test of the 17 x 17 Fuel Assembly, 11 WCAP-8278 (Proprietary) and WCAP-8279 February 1974. 4. Cooper, F. W., Jr., u17 x 17 Component Tests -Phase IB, II, III, D-Loop Drop and Deflection, .. WCAP-8446 (Proprietary) and WCAP-8449 (Non-Proprietary), December 1974p 5. Hill, K. W., et al., t'Effects of 17 x 17 Fuel Assembly Geom.etry on DNB,u WCAP-8296-P-A (Proprietary) and WCAP-8297-A (Non-Proprietary), February 1975 SGS-UFSAR 1.5-3 Revision 6 February 15, 1987

6. Cadek, F. F.; Motley, F. E.; and Dominicis, D.P., "Effect of Axial Spacing on Interchannel Thermal Mixing with the R Mixing Vane Grid," WCAP-7941-P-A (Proprietary) and WCAP-7959-A (Non-Proprietary), January 1975. 7. Eggleston, F. T., "Safety-Related Research and Development for Westinghouse Pressurized Water Reactors, Program Summaries -Winter 1977 -Summer 1978," WCAP-8768, Revision 2, October 1978. 8. "Westinghouse ECCS Evaluation Hodel -October 1975 Version," WCAP-8622 (Proprietary) and WCAP-8623 (Non-Proprietary), November 1975. 9. Kuchirka, P. J., "17 x 17 Design Fuel Rod Behavior During Simulated Loss-of-Coolant Accident Cqnditions," WCAP-8289 (Proprietary) and WCAP-8290 (Non-Proprietary), November 1974. 1.5-4 SGS-UFSAR Revision 6 February 15, 1987 * * *