LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 5.4-1 Through 5.4-10

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 5.4-1 Through 5.4-10

ML17046A393
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: ML17046A393 (10)

Text

TABLE 5. 4-1

• REACTOR VESSEL MATERIAL PROPERTIES 50 Ft-Lb 35 Mil Core Region Plate TNoT Temp RTNoT Shell Plate No. OF OF Inter. Shell 84712-1 0 <60 0 Inter, Shell 84712-2 -20 72 12 Inter. Shell 84712-3 -50 70 10 Lower Shell 84713-1 -10 68 8 Lower Shell 84713-2 -20 68 8 Lower Shell B4713-3 -10 70 10 * (ll USE (Upper Shelf Energy), unirradiated 1 of 1 SGS-UFSAR

• USE(ll Ft-lbs 106 97 107 98 103 121 Revision 19 November 19, 2001 I I

• *

• TABLE 5.4-2 REACTOR VESSEL MATERIAL PROPERTIES CLOSURE HEAD STUDS Heat Mat' l. Bar 0.2 ys UTS(l) No. S:eec. No. No. Ksi Ksi Elon8* 37677 A540, B24 237-1 150.5 165.0 17.0 37677 A540, B24 237 151.0 164.5 17.0 37677 A540, B24 203-1 155.5 165.0 16.0 37677 A540, B24 203 148.0 164.0 15.0 37677 A540, B24 204-1 151.5 166.0 16.5 37677 A540, B24 204 148.5 162.5 16.0 CLOSURE HEAD NUTS AND WASHERS 46251 A540, B23 5 157.5 46251 A540, B23 5-1 149.5 46251 A540, B23 8 152.5 46251 A540, B23 8-1 151.5 46251 A540, B23 11 151.0 46251 A540, B23 11-1 151.0 46251 A540, B23 10 150.5 46251 A540, B23 10-1 148.5 46251 A540, B23 13 153.0 46251 A540, B23 13-1 147.2 46251 A540, B23 17 148.8 46251 A540, B23 17-1 155.5 46251 A540, B23 21 155.5 46251 A540, B23 21-1 150.5 46251 A540, B23 22 150.2 46251 A540, B23 22-1 147.0 UTS (Ultimate Tensile Stress) RA (Reduction Area) 170.0 163.0 164.0 162.2 163.5 164.0 161.0 161.0 164.0 159.0 161.5 167.5 168.0 162.0 162.5 160.0 1 of 1 SGS-UFSAR 16.0 17.0 16.5 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 16.0 16.5 16.5 16.0 17.0 Energy RA(2) At l0°F 57.1 so' 54' 48 57.3 54) 54' 50 57.3 58, 60, 60 56.4 48, 48, 47 57.3 54, so, 56 56.4 54, 54, 55 54.7 42, 46, 46 55.8 50, 54, 53 55.3 so, so, 49 56.9 so, 50, 54 55.8 so, so, 50 56.5 52, 54, 50 56.0 so, so, 53 56.8 50, 55, 48 57.3 54, so, 53 56.5 56, so, 51 56.5 52, so, 55 54.2 51, 51, 50 55.5 48) so, 48 56.2 54) 54, 54 56.0 54, 52, 50 57.3 54, 56, 54 Revision 6 February 15, 1987

• SGS-UFSAR

• TABLE 5.4-3 THIS TABLE INTENTIONALLY DELETED 1 of 1 Revision 19 November 19, 2001 I

• SGS-UFSAR

• TABLE 5.4-4 THIS TABLE INTENTIONALLY DELETED 1 of 1 Revision 19 November 19, 2001

• *

• SGS-UFSAR TABLE 5.4-5 THIS TABLE INTENTIONALLY DELETED 1 of 1 Revision 19 November 19, 2001

• *

• TABLE 5.4-6 NUCLEAR CONSTANTS FOR NEUTRON FLUX MONITORS CONTAINED IN THE SALEM UNIT 1 SURVEILLANCE CAPSULES Monitor Material Reaction of Interest Copper cu63 (n,a) eo60 Iron Fe 54 (n,p) Mn54 Nickel Ni58 (n,p) co 58 Uranium-23a(a) u238 (n,f) c8137 Neptunium-237(a) Np237 (n,f) c8137 Cobalt-aluminum(a) eo 59 (n,"Y) co60 to halt-aluminum co 59 ( n, ")') co60 a. Denotes that monitor is cadmium-shielded SGS-UFSAR 1 of 1 Target Weight Fraction 0.6917 0.0585 0.6777 1. 0 1.0 0.0015 0.0015 Fission Product Yield Half-life (%) 5.27 years 314 days 71.4 days 30.2 years 6.3 30.2 years 6.5 5.27 years 5.27 years Revision 7 July 22, 1987

• *

• TA8LE5.4-7 FAST FLUENCE (>IMeV) FOR SALEM 1 REACTOR VESSEL BEL1LINE MATERIALS' Fluence at clad-bare metal interface (nlcm2) Intermediate Shell 1.64 X 1019 82402-1 Intermediate Shell 1.64 X 1019 82402-2 Intermediate Shell 1.64 X 1019 B2402-3 Lower Shell B2403-l 1.64 X 1019 Lower Shell B2403*2 1.64 X 1019 Lower Shell B2403-3 1.64 X 1019 Intermediate to Lower Shell Circumferential 1.64 X 1019 Weld Seam 9-042 Intermediate Shell Longitudinal Weld 1.18 X 1019 Seams 2-042 A&B Intermediate Shell Longitudinal Weld 6.85 X 1018 Seam2-042C Lower Shell Longitudinal Weld 1.08 X 101!> Seams 3-042 A&B Lower Shell Longitudinal Weld 1.64 X 1019 Seam 3-042 C "' Fluence calculated for EOL (32EFPY) 1 of 1 SGS-UFSAR Fluence at V..T (nlcm2) 9.77 X 1018 9.77 X 1018 9.77 X 1018 9.77 X 1018 9.77 X 1018 9.?7 X 1018 9.77 X 101& 7.03 X 1018 4.08 x 1018 6.44 X 1018 9.77 X 1018 Fluence at %T (nlcm2) 3.47x 1018 3.47 X 1018 3.47 X 1018 3.47 X 1018 3.47 X 1011 3.47 X 1018 3.47x 1013 2.50 X 1018 1.45 X 1018 2.29 X 1018 3.47 X 1018 Revision 19 November 19, 2001

• *

• TABLE 5.4-8 FAST FLUENCE (>!MeV) FOR SALEM 2 REACTOR VESSEL BELTLINE MA TERIALS* Fluence at clad-bare metal interface (nlcm2) Intennediate Shell 1.77 X 1019 B4712-l Intennediate Shell 1.77 X 1019 B4712-2 Intennediate Shell 1.77 X 1019 B4712-3 Lower Shell B4713-1 1.77 X 1019 Lower Shell B4713-2 1.77 X 1019 Lower Shell B4713-3 1.77 X 1019 Intennediate to Lower Shell Circumferential 1.77 X 1019 Weld Seam 9-442 Intermediate Shell Longitudinal Weld 6.94 X 1018 Seam 2-442 A Intermediate Shell Longitudinal Weld 1.20 X 1019 Seams 2-442 B&C Lower Shell Longitudinal Weld 1.20 X 1019 Seams 3-442 A&C Lower Shell Longitudinal Weld 6.94 X 1018 Seam 3-442 B

• Fluence calculated for EOL (32EFPY) 1 of 1 SGS-UFSAR Fluence at (nlcm1) 1.06 X 1019 1.06x 1019 1.06x 1019 1.06x 1019 1.06 X 1019 1.06 X 1019 1.06x 1019 4.14x 1018 7.15 X 1018 7.]5 X 1018 4.14 X 1018 Fluence at 34T (nlcm,) 3.17 X 1018 3.77 X 1018 3.77 X 1018 3.77 X 1018 3.77 X 1018 3.77 X lOIS 3.77 X 1018 1.47 X 1018 2.54 X 1018 -2.54 X 1018 1.47 X 1018 Revision 19 November 19, 2001

• *

• SGS-OFSAR TABLE 5.4-9 THIS TABLE INTENTIONALLY DELETED 1 of 1 Revision 19 November 19, 2001 I

• SGS-UFSAR

• TABLE 5.4-10 THIS TABLE INTENTIONALLY DELETED 1 of 1 Revision 19 November 19, 2001 I