LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 11.1-1, Core Activities to 11.1-15

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 11.1-1, Core Activities to 11.1-15

ML17046A493
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: ML17046A493 (17)

Text

TABLE 11.1-1 CORE ACTIVITIES Isotope Core Inventory Isotope Core Inventory cur:i.es/MWt cu:ries/MWt C0-58 2.553E+02 TE-131M 3.707E+03 C0-60 1.953E+02 TE-132 3.690£+04 KR-85 3.056E+02 I-131 2.750E+04 KR-85M 7.222E+03 I-132 3.889E+04 KR-87 1.306E+04 I-133 5.556E+04 KR-88 l.B61E+04 I-134 6.111E+04 RB-86 1.496E+01 I-135 5.278E+04 SR-89 2.844E+04 XE-133 5.556E+04 SR-90 1.535E+03 XE-135 1.389E+04 SR-91 3.656E+04 CS-134 3.425E+03 SR-92 3.805E+04 CS-136 1.042E+03 Y-90 1.647E+03 CS-137 1.915E+03 Y-91 3.465E+04 BA-139 4.976E+04 Y-92 3.819E+04 BA-140 4.924E+04 Y-93 4.320E+04 LA-140 5.032E+04 ZR-95 4.377E+04 LA-141 4.615E+04 ZR-97 4.562E+04 LA-142 4.449E+04 NB-95 4.138E+04 CE-141 4.476E+04 M0-99 4.830E+04 CE-143 4.352E+04 TC-99M 4.169E+04 CE-144 2.697E+04 RU-103 3.598E+04 PR-143 4.273E+04 RU-105 2.340E+04 ND-147 1. 911E+04 RU-106 8.175E+03 NP-239 5.120E+05 RH-105 1.621E+04 PU-238 2.902E+Ol SB-127 2.208E+03 PU-239 6.545E+OO SB-129 7.820E+03 PU-240 8.254E+OO TE-127 2.132E+03 PU-241 1.390E+03 TE-l 27M 2.823E+02 AM-241 9.181E-01 TE-129 7.341E+03 CM-242 3.514E+02 TE-129M 1.935E+03 CM-244 2.056E+01 The LOCA dose analysis (Section 15.4.1) is based on these 60 isotope activities, which are from the RADTRAD default file. A core thermal power of 3632 MWt (=3459 x 1.05) was used. Aerosol inventory is multiplied by 1.10 to make the RADTRAD default file conservative with respect to the SNGS plant-specific ORIGEN inventory file. 1 of 1 SGS-UFSAR Revision 23 October 17, 2007 TABLE 11.1-2 THIS TABLE HAS BEEN DELETED 1 of 1 SGS-UFSAR Revision 16 January 31, 1998 TABLE 11.1-3 THIS TABLE HAS BEEN DELETED 1 of 1 SGS-UFSAR Revision 16 January 31, 1998 TABLE 11.1-4 THIS TABLE HAS BEEN DELETED 1 of 1 SGS-UFSAR Revision 16 January 31, 1998 TABLE 11.1-5 THIS TABLE HAS BEEN DELETED SGS-UFSAR 1 of 1 Revision 16 January 31.1998 TABLE ll.l-6 THIS TABLE HAS BEEN DELETED 1 of 1 SGS-UFSAR Revision 16 January 31, 1998 TABLE 11.1-7 PARAMETERS USED IN THE CALCULATION OF REACTOR COOLANT FISSION PRODUCT ACTIVITIES(1) 1. 2. 3. 4. 5. 6. 7. Core thermal power, max. calculated, MWt Fraction of fuel containing clad defects 3 Reactor coolant liquid volume, ft Reactor coolant average temperature, °F Purification flow rate (normal), gpm Effective cation demineralizer flow, gpm Volume control tank volumes 3 a. Vapor, ft b . . d f 3 . L1.qu1. , t 8. Fission product escape rate coefficients: Noble isotopes, -1 a. gas sec b. I, and Cs isotopes, -1 Br, sec Te isotopes, -1 c. sec d. Mo isotopes, -1 sec and isotopes, -1 e. Sr Ba sec f. La, Pr isotopes, -1 Y, Ce, sec 9. Mixed bed demineralizer decontamination factors: 10. a. Noble gases and Cs-134, 136, 137, Y-90, 91 and Mo-99 b. All other isotopes Cation bed demineralizer decontamination factor for CS-134, 236, 237, Y-90, 91, and Mo-99 3600 0.01 10,892 (2) 568 77 7.5 200 200 6.5 X 10-8 1.3 X 10-8 1.0 X 10-9 2.0 X 10-9 1.0 X 10-11 1.6 X 10-12 1.0 10.0 10.0 {1) The RCS volume was increased by the introduction of new Unit 2 AREVA NP Model 61/19T steam generators. However, the prior analysis remains conservative, therefore, the prior volumes and activities have not been adjusted. {2) Conservatively bounds 20% tube plugging in Series 51 steam generator and 10% tube plugging in Model-F steam generator. 1 of 2 SGS-UFSAR Revision 24 May 11, 2009 TABLE 11.1-7 (Cont.) 11. Volume control tank noble gas stripping fraction (closed system): Isotope Kr-85 Kr-Ssm Kr-87 Kr-88 Xe-133 xe-133m xe-135 Xe-135m xe-138 (No purge of VCT assumed in the calculation. account only for radioactive decay.) 2 of 2 SGS-UFSAR Stripping Practi.on s.s x 10-s 5.4 X l0-1 8.0 X l0-1 6.5 X 10-1 2.9 X 10-2 6.7 X 10-2 2.9 X 10-1 9.4 X 10-1 9.4 X 10-1 Threfore, stri.pping fractions I Revision 16 January 31, 1998 Br-84 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 Y-92 Zr-95 Nb-95 Mo-99 I-131 I-132 I-133 I-134 I-135 Te-132 Te-134 Cs-134 TABLE 11.1-8 REACTOR COOLANT EQUILIBRIUM FISSION AND CORROSION PRODUCT ACTIVITIES(1) (Based on Parameters Given in Table 11.1-7) Activity gCi/gram 4.7 X 10-2 4.8 2.1 X 10-1 4.3 X 10-3 1.2 X 10-4 6.2 X 10-3 1.3 X 10-3 3.4 X 10-5 -4 5.7 X 10 1.2 X 10-3 6.5 X 10-4 6.5 X 10-4 7.5 X 10-1 2.8 2.8 4.2 5.7 X 10-1 2.3 2.9 X 10-1 3.0 X 10-2 2.3 Isotope Cs-136 Cs-137 Cs-138 Ba-140 La-140 Ce-144 Pr-144 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Mn-54 Mn-56 Co-58 Co-60 Fe-59 Activity gCi/gram 2.9 1.5 9.6 X 10-1 4.2 X 10-3 1.4 X 10-3 3.9 X 10-4 3.9 X 10-4 8.2 1.7 1.0 3.0 260 17.0 8.5 4.9 X 10-1 6.1 X 10-1 4.4 X 10-4 2.0 X 10-2 1.5 X 10-2 1.9 X 10-3 5.2 X 10-4 (1) The RCS volume was increased by the introduction of new Unit 2 AREVA NP Model 61/19T steam generators. However, the prior analysis remains conservative, therefore, the prior volumes and activities have not been adjusted. SGS-UFSAR 1 of 1 Revision 24 May 11, 2009 I TABLE 11.1-9 TRITIUM PRODUCTION IN THE REACTOR COOLANT Released to the Coolant Tritium Source Total Produced Ternary Fissions 10,926 Burnable Poison Rods (Initial Cycle) 973 Soluble Poison Boron (Initial Cycle) 397 (Equilibrium Cycle) 556 Li-7 Reaction 11 Li-6 Reaction 6 Deuterium Reaction 1 Totals Initial Cycle 12,314 Totals Equilibrium Cycle 11,500 (1) Weight of B2o3 = 221 (B10 = 13.58 ) Design Expected Value Value 3240 287 397 556 11 6 1 3942 3814 107 10 397 556 11 6 1 532 685 (2) Initial boron (hot, full power, equilibrium xenon) = 860 ppm (3) Initial boron (hot, full power, equilibrium xenon) = 1200 ppm 1 of 1 SGS-UFSAR Revision 6 February 15, 1987 TABLE 11.1-10 TRITIUM SOURCES FROM THE REACTOR EMPLOYING Ag-In-Cd ABSORBER RODS Basic Assumptions and Plant Parameters: 1. 2. 3. 4. Core thermal power Plant load factor Core volume Core volume fractions a. uo2 b. Zr + SS c. H20 5. Initial reactor coolant boron level a. Initial cycle b. Equilibrium cycle 6. Reactor coolant volume 7. Reactor coolant transport times a. In-core b. Out-of-core 8. Reactor coolant peak steady state lithium level (99 pure Li7) 9. Core averaged neutron fluxes: a. E > 6 Mev b. E > 5 Mev c. 3 Mev E 6 Mev d. 1 Mev s E s 5 Mev e. E < 0.625 ev 10. Neutron reaction cross-sections a. s10 (n, 2a) T: cr(1 Mev s E s 5 Mev} spectrum cr(E > 5 Mev) = b. Li7 (n, naV) T: cr(3 Mev s E s 6 Mev) cr(E > 6 Mev) 1 of 2 SGS-UFSAR 3558 MWt 0.8 1153 ft3 0.3052 0.1000 0.5948 840 ppm 1100 ppm 12,560 ft3 0.77 sec 10.87 sec 3.5 +/- 0.15 2 n/cm -sec 2.91 X 1012 7.90 X 1012 2.26 X 1013 5.31 X 1013 2.26 X 1013 31.6mb ppm (spectrum weighted) > 5 rob 39.1 mb (spectrum weighted) 400 rob Revision 24 May 11, 2009 TABLE 11.1-10 (Cont) 11. Fraction of ternary tritium diffusing through zirconium cladding Note: a. Design value b. Expected value 0.30 0.01 Although Unit 1 has Westinghouse Model-F and Unit 2 has AREVA NP Model 61/19T steam generators, the radioactivity values of Unit 1 and Unit 2 are bounded by the values in this Table. The values contained in this Table were based on the original Westinghouse Series 51 steam generators. 2 of 2 SGS-UFSAR Revision 24 May 11, 2009 TABLE 11.1-11 VOLUME CONTROL TANK ACTIVITIES(1) Assumptions are given previously under reactor coolant (Table 11.1-7) Total Activity Isotope (Curies) Kr-83m 1.7 X 101 Kr-85 6.2 X 101 Kr-85m 1.0 X 102 Kr-87 2.7 X 101 Kr-88 1.4 X 102 Xe-131m 1.9 X 102 Xe-133 2.4 X 104 Xe-133m 1.5 X 103 Xe-135 6.6 X 102 Xe-135m 5.0 X 101 Xe-137 2.8 X 10-1 Xe-138 3.4 X 10° (1) The RCS volume was increased by the introduction of new Unit 2 AREVA NP Model 61/19T steam generators. However, the prior analysis remains conservative; therefore, the prior volumes and activities have not been adjusted. 1 of 1 SGS-UFSAR Revision 24 May 11, 2009 Assumptions: SGS-UFSAR TABLE 11.1-12 GAS DECAY TANK ACTIVITY Volume of the tank immaterial to this calculation. Clad Defects in one percent of fuel rods. Operation at 3600 MWt for 497 days. Tank contains entire gaseous activity stripped off from the Reactor Coolant System. 3 Reactor Coolant System Volume is 12,446 ft . Isotope Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 1 of 1 Total Activity Curies 1.5 X 103 1.2 X 102 1.8 X 101 1.5 X 102 2.9 X 102 3.5 X 104 2.2 X 103 8.6 X 102 Revision 23 October 17, 2007 I I TABLE 11.1-13 This Table Has Been deleted 1 of 1 SGS-UFSAR Revision 23 October 17, 2007 TABLE 11.1-14 This Table Has Been Deleted 1 of 1 SGS-UFSAR Revision 23 October 17, 2007 TABLE 11.1-15 This Table Has Been deleted 1 of 1 SGS-UFSAR Revision 23 October 17, 2007