WBL-19-026, Revised Pressure and Temperature Limits Report (PTLR)

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Revised Pressure and Temperature Limits Report (PTLR)
ML19094B239
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 04/04/2019
From: Anthony Williams
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
WBL-19-026
Download: ML19094B239 (45)
v • d • e


Text

{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000 Spring City, Tennessee 37381 wBL-19-026 April 4,2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

10 cFR 50 36 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket Nos. 50-390 Watts Bar Nuclear Plant Unit 1 - Revised Pressure and Temperature Limits Report (PTLR) The purpose of this letter is to provide the enclosed copy of the Watts Bar Unit 1 Pressure and Temperature Limits Report (PTLR) Revision 12, in accordance with Technical Specification Section 5.9.6.c. The replacement of the Unit 1 Power Operated Relief Valves (PORVS) and related updates to the Cold Overpressure Mitigation System (COMS) setpoints required the PTLR to be updated. There are no new regulatory commitments in this letter. Should you have questions regarding this submittal, please contact Kim Hulvey, Manager of Watts Bar Site Licensing, at (423) 365-7720. Site Vice President Watts Bar Nuclear Plant Respectfully, thony L. Williams lV

U.S. Nuclear Regulatory Commission wBL-19-026 Page 2 April 4,2019

Enclosure:

Watts Bar Nuclear Plant, Unit 1 Pressure and Temperature Limits Report (PTLR), Revision 12. cc (Enclosure): U. S. Nuclear Regulatory Commission Region ll Marquis One Tower 245 Peachtree CenterAve., NE Suite 1200 Atlanta, Georgia 30303-1 257 NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

ENCLOSURE Watts Bar Nuclear Plant, Unit { Pressure and Temperature Limits Report, Revision 12

System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Document I QA Record Paqe 199 of 260 ,flfflTlfl, Watts Bar Unit 1 - RCS Pressure and Temperature Limits Report (PTLR) - Revision 12 APPENDIX "A' TO RCS SYSTEM DESCRIPTION N3-68-4001 WATTS BAR UNIT 1 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) REVISION 12 Prepared by: W. F. Cetta Checked by C. S. Kerlin Approved by: M. R. Smith

System REACTOR COOLANT SYSTEM ISDD.N3.68.4OO1 Description I Unitl/Unit2 lRev.004f Document I QA Record Paqe 200 of 260 Appendix A (Page 2 ot 421 1.0 RCS PRESSURE AND TEMPERATURE LlMlrS REPORT (PTLR) This PTLR for Watts Bar Unit t has been prepared in accordance with the requirements of Technical Specification 5.9.6. Revisions to the PTLR shall be provided to the NRC after issuance. The Technical Specifications affected by this report are listed below: LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.12 Cold Overpressure Mitigation System (COMS) 2.0 RCS PRESSURE AND TEMPERATURE LITUIITS The limits for LCO 3.4.3 are presented in the subsection which follows. These limits have been developed (Ref. 1) using the NRC-approved methodologies (Ref. a) that are specified in Technical Specification 5.9.6. 2.1 RGS Pressure and Temperature (P/T) Limits (LCO 3.4.3) 2.1.1 The RCS temperature rate-of-change limits are (Ref. 1): A. A maximum heatup Rate 100oF per hour. B. A maximum cooldown Rate 100oF per hour. C. A maximum temperature change of 1OoF in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves. 2,1.2 RCS P/T Limits for Heatup, Cooldown, Inservice Hydrostatic and Leak Testing, and Criticality The RCS P/T limits for heatup, cooldown, inservice hydrostatic and leak testing, and criticality are specified by Figures2.l-1thru 2.1-6 (Ref. 1). NOTE: The heat-up and cool-down curves are based on beltline conditions and do not compensate for pressure differences between the pressure transmitter and reactor midplane/beltline or for instrument inaccuracies. Refer to Table 2.1-5 for pressure differences (Ref. 9). Site Engineering Setpoint and Scaling documents SSD-1-P-68, -63, -64, -66, and -70 provide the adjusted curves for temperature and pressure limits which are compensated for pressure differential and instrument inaccuracy to be used for heatup and cooldown. NOTE: Steady-state conditions (0oF per hour heatup or cooldown curves) are achieved after maintaining a constant temperature for a duration of t hour (Ref. 1). Steady state conditions are maintained if temperature fluctuatlons remain within t 9.2oF (Ref. 1).

System REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 2M of 260 3.0 3.1 4.0 Appendix A (Page 3 ot 421 GOLD OVERPRESSURE MITIGATION SYSTEM (LCO 3.4.121 The lift setpoints for the pressurizer Power Operated Relief Valves (PORVS) are presented in the subsection which follows. These lift setpoints have been developed using the N RC-approved methodolog ies specified in Technical Specification 5. 9.6. Pressurizer PORV Lift Setting Limits The pressurizer PORV lift setpoints in Table 3.1-1 were specified by the Westinghouse Cold Pressure Mitigation Setpoint Analysis (Ref. 9). Per ASME Code N-514, The limits for the COMS setpoints are based on 110Yo of the Steady State 32 EFPY curves (Table 2.1-2) (Ref. 1) which are based on beltline conditions and are not compensated for pressure differences between the pressure transmitter and the reactor midplane/beltline or for instrument inaccuracies. Refer to Table 2.1-5 for pressure differences (Ref. 9). NOTE: These setpoints include allowance for pressure difference between the pressure transmitter and reactor midplane, and also includes 63 psig pressure channel uncertainty. Site Engineering Setpoint and Scaling documents for instrument loop numbers 1-T-68-1B and 1-T-68-438 (Ref. 10, 1 1) contain the adjusted curves compensated for pressure differential and instrument inaccuracy which provides the PORV lift limits for the COMS utilizing the 32 EFPY data. REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM The reactor vessel material irradiation surveillance specimens shall be removed and examined to determine changes in material properties. The removal schedule is provided in Table 4-1. The results of the most recent examination (Ref. 8) was used to update Figures 2.1-1 through 2.1-6 and the corresponding data points in Table 2.1-1 through 2.1-4 as well as the supplemental data tables in Section 5.0. The pressure vessel steel surveillance program (Ref. 3) is in compliance with Appendix H to 10 CFR 50, entitled "Reactor Vessel Material Surveillance Program Requirements". The material test requirements and the acceptance standard utilize the reference nil-ductility temperature, RTxp1, which is determined in accordance with ASTM E23. The empirical relationship between RTNor and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix G, "Fracture Toughness Criteria for Protection Against Failure", to Section Xl of the ASME Boiler and Pressure Vessel Code. The surveillance capsule removal schedule meets the requirements of ASTM E185-82. SUPPLEMENTAL DATA TABLES Table 5-1 contains a comparison of measured surveillance material 30 ft-lb transition temperature shifts and upper shelf energy decreases with Regulatory Guide 1.99, Revision 2, predictions. Table 5-2 shows calculations of the surveillance material chemistry factors using surveillance capsule data. 5.0

System I REACTOR COOLANT SYSTEM ISDD-Ns-c Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Document I OA Record lPaqe 202o1260 Appendix A (Page 4 ot 42I, 5.0 SUPPLEMENTAL DATA TABLES (continued) o Iable 5-3 provides the required Watts Bar Unit 1 reactor vessel toughness data, along with the unirradiated & best estimate average chemistry, respectively. The bolt-up temperature is also included in this table. o Table 5-4 provides a summary of the fluence values used in the generation of the heatup and cooldown limit curves and in the Pressurized Thermal Shock (PTS) evaluation. o Tables 5-5 and 5-6 provide a summary of the adjusted reference temperature (ART) values of the Watts Bar Unit 1 reactor vessel beltline materials at the 114-T and 314-T locations for 32 and 48 EFPY, respectively. o Tables 5-7 and 5-8 show example calculations of the adjusted reference temperature (ART) values at 32 and 48 EFPY, respectively, for the limiting Watts Bar Unit 1 reactor vessel material (lntermediate Shell Forging 0Q. o Table 5-7 provides a summary of the fluence values used in the Pressurized Thermal Shock (Pf$ evaluation. o Table 5-9 provides RTprs values for Watts Bar Unit 1 for 32 EFPY. o Table 5-10 provides RTprs values for Watts Bar Unit 1 for 48 EFPY.

6.0 REFERENCES

1.

WCAP-16761-NP, Revision 0, "Watts Bar Unit 1 Heatup and Cooldown Curves for Normal Operation," November 2007.

2.

Deleted.

3.

WCAP-9298, Revision 1, "Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program," April 1993.

4.

WCAP-14040, Revision 1, "Methodology Used To Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," December 1994.

5.

Deleted.

6.

B\\ /XT SERVICES, lnc., "Analysis of Capsule W From The Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Material Surveillance Program," September 2001.

7.

Deleted.

8.

WCAP-16760-NP, Revision 0, "Analysis of Capsule Z from the Tennessee Valley Authority, Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2," November 2007.

System Description Document REACTOR COOLANT SYSTEM ISDD.N3.68.4OO1 Unitl/Unit2 QA Record Rev. 0041 Paqe 203 of 260 Appendix A (Page 5 of 421

6.0 REFERENCES

(continued)

9.

LTR-SCS-15-31, Rev 0, "Watts Bar Unit 1 PORV Replacement - Cold Pressure Mitigation System (COMS) Setpoint Analysis", 11412017

10.

NE SSD 1-T68-18, COMS Setpoint and Scaling Document for PORV 1-PCV8-3404 lnstrument Loop Components.

11.

NE SSD 1-T-68-438, COMS Setpoint and Scaling Document for PORV 1-PCV-68-334 lnstrument Loop Components.

12.

Structural lntegrity Associates Report, No. SIR 01 140, Revision 1, "Heatup and Cooldown Limit Curves for Normal Operation for Watts Bar Unit 1", July 2OO2. 13 MRP-326, "Coordinated PWR Reactor Vessel Surveillance Program (CRVSP)' December 2011.

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3-68.4001 Document I OA Record I Paqe 204ot260 Appendix A (Page 6 of 421 7.0 FIGURES AND TABLES M AT H. R IAL.,.P" RP P. F RIJ....FAS.I.S LIMITING MATERIAL: LIMITING ART AT 32 EFPY: INTERMEDIATE SHELL FORGING 05 114-T, 205.7 "F 314-T,171. 15 0F 2500 2250 2000 1754 1 500 1250 1 000 750 500 25A 0 1 00 1 50 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F) Figure 2.1-1: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 60"F/hr) Applicable for 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Plotted Data (Ref. 1) provided on Table 2.1-1) .Aoa o.\\, o L.5{,(, at L. o. Eo {rls IJ C' I tEfJ r..uut.,..1.1L..,...'..

1 I

t 1: i il Criticality Limit based on inseruice hydrostatic test temperature (331 F) for the service period up to 32 EFPY

System REACTOR COOLANT SYSTEM ISDD.N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paoe 205 of 260 7.0 Appendix A (Page 7 ot 421 FIGURES AND TABLES (continued) MATERIAL PROPERTY BASIS LIMITING MATERIAL: LIMITING ART AT 32 EFPY. INTERMEDIATE SHELL FORGING 05 114-T,205.74 "F 314-T, 171.15 0F 2500 2250 2000 1754 1 500 1254 1 000 750 500 250 0 100 150 2A0 250 300 350 400 450 Moderator Temperature (Deg. F) Figure 2.1-2: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100oF/hr) Applicablefor 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Plotted Data (Ref. 1) provided on Table 2.1-1) ,.....-1.... j Aga o. V o l-:'aao Eo. TIo

  • i

-g tI .gG(, li I ...t......... ri I ri i Operlim Version:5.2 Run:28921 Operlim.xls Version: 5.2 Criticality Limit based on inservice hydrostatic test temperature (331 F) for the service period up to 32 EFPY

System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD.N3-68-4001 Document I OA Record I Paqe 206 of260 Appendix A (Page 8 of 421 7.0 FIGURES AND TABLES (continued) Table 2.1-1: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100oF/hr) Applicable for 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/Kp) (Data points plotted on Figures 2.1-1 and 2.1-2) ,:r r'.: -:- _--: i. P,, {psisl f,.i-. illtl't* 60 0 331 0 60 0 331 0 60 465 331 465 60 413 331 413 65 465 331 465 65 413 331 413 70 465 331 466 70 413 331 414 75 465 331 467 75 413 331 414 80 465 331 467 80 413 331 416 85 465 331 470 85 413 331 416 90 465 331 470 90 413 331 418 95 465 331 473 95 413 331 419 100 465 331 474 100 413 331 421 105 465 331 477 105 413 331 422 110 466 331 481 110 413 331 425 115 467 331 481 115 413 331 427 120 470 331 487 120 413 331 429 125 473 331 490 125 413 331 433 130 477 331 492 130 413 331 435 135 481 331 499 135 413 331 440 140 487 331 501 140 414 331 441 145 492 331 506 145 416 331 447

System Description Document REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Unit 1 / Unit2 QA Record Rev. 0041 Paqe 207 of 260 Appendix A (Page 9 of 42) 7.0 FIGURES AND TABLES (continued) Table 2.1-1: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100'F/hr) Applicable for 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Data points plotted on Figures 2.1-1 and 2.1-2) ,.t*'.,I*t l.i'l'."::. -,,'-.,,.i:,,,r.,,.:,..,,;iri ' t,.SSPFlhr Heatup::.,,,,,i 150 499 331 514 150 418 331 449 155 506 331 516 155 421 331 455 160 514 331 523 160 425 331 459 165 523 331 533 165 429 331 463 170 533 331 543 170 435 331 471 175 543 331 554 175 441 331 473 180 554 331 566 180 447 331 483 185 566 331 579 185 455 331 486 190 579 331 593 190 463 331 494 195 593 331 608 195 473 331 502 240 608 331 625 200 483 331 506 205 625 331 642 205 494 331 519 210 642 331 661 210 506 331 520 215 661 331 682 215 519 331 534 220 682 331 704 220 534 331 549 225 704 331 727 225 549 331 566 234 727 331 753 230 566 331 584 235 753 331 780 235 584 331 604 240 780 331 809 244 604 331 625

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Document I OA Record I Paoe 208 of260 Appendix A (Page 10 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-1: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 1OOoF/hr) Applicable tor 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Data points plotted on Figures 2.1-1 and 2.1-2) -f=... ['Ftt'",. 245 809 331 841 245 625 331 648 25A 841 331 875 250 648 331 672 255 875 331 912 255 672 331 699 260 912 331 951 260 699 331 727 265 951 331 993 265 727 331 758 270 993 331 1 038 270 758 331 791 275 1 038 331 1087 275 791 331 826 280 1087 331 1 139 280 826 331 864 285 1 139 331 1 195 285 864 331 905 290 1 195 335 1256 290 905 335 949 295 1256 340 1321 295 949 340 996 300 1321 345 1 390 300 996 345 1CI47 305 1 390 350 1465 305 1047 350 1 142 310 1465 355 1540 310 I 102 355 1 160 315 1540 360 1 606 315 1 160 360 1223 320 1 606 365 1677 320 1223 365 1291 325 1677 370 1753 325 1291 370 1363 330 1753 375 1 835 330 1 363 375 1441 335 1 835 380 1922 335 1441 380 1525

System REACTOR COOLANT SYSTEM ISDD-N3-68.4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 209 of 260 Appendix A (Page 11 of 421 7.0 FIGURES AND TABLES (continued) Table 2.1-1: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 't00oF/hr) Applicable for 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Data points plotted on Figures 2.1-1 and 2.1-2) p T rrl 340 1922 385 2017 340 1s25 385 1614 345 2017 390 2118 345 1614 390 17 10 350 2118 39s 2227 350 17 10 395 1814 355 2227 400 2343 355 1814 400 1925 360 2343 405 2469 360 1925 405 2044 365 2469 365 2044 414 2171 370 2171 415 2308 375 2308 420 2455 380 2455 Leak Test Limit Temp. ['F] 310 331 Pressure Ipsig] 2000 2485

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Document I OA Record lPase 21Oot26O 7.0 Appendix A (Page 12 of 421 FIGURES AND TABLES (continued) MA,T,F R I A L _,,p,Rp.p,,H-Rf y,,,-HA S I S LIMITING MATERIAL: LIMITING ART AT 32 EFPY: 2500 2254 2000 I 750 1 500 1250 I 000 750 500 250 0 Figure 2.1-3: INTERMEDIATE SHELL FORGING 05 114-T, 205.74 "F 314-T,171.15 0F a-ro no o.\\, 0, t-s.r}fl! u, o, L G.tt G' t,r!-{-t, r IEo 100 150 2AA 250 300 350 400 450 500 550 Moderator Temperature (Deg. F) Watts Bar Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100"F/hr) Applicable for 32 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/Krn) (Plotted Data (Ref. 1) provided on Table 2.1-2)

System I REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I OA Record lPaqe 211 ot260 Appendix A (Page 13 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-2: 32 EFPY Cooldown Curve Data Points Using 1996 App. G Methodology (w/K6, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-3) 60 0 60 0 60 0 60 0 60 0 60 513 60 465 60 417 60 367 60 264 65 515 65 467 65 419 65 369 65 266 7o 517 70 469 70 421 7A 371 70 268 75 519 75 472 75 423 75 373 75 270 80 522 80 474 80 426 80 376 80 272 85 525 85 477 85 428 85 378 85 275 90 528 90 480 90 431 90 381 90 278 95 531 95 483 95 434 95 385 95 281 100 534 100 486 100 438 100 388 100 285 105 538 105 490 105 442 105 392 105 289 110 542 110 494 110 446 110 396 110 294 115 546 115 499 115 450 115 401 115 299 120 550 120 503 120 455 120 406 120 304 125 555 125 508 125 460 125 411 125 310 130 561 130 514 130 466 130 417 130 316 135 566 135 519 135 472 135 423 135 323 140 572 140 526 140 478 140 430 144 331 145 579 145 533 145 485 145 438 145 339

System Description Document REAGTOR COOLANT SYSTEM ISDD-N3.68.4001 Unitl /Unit2 QA Record Rev. 0041 Paqe 212 of 260 Appendix A (Page 14 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-2: 32 EFPY Cooldown Curve Data Points Using 1996 App. G Methodology (w/K6, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-3) T rrl 150 586 150 540 150 493 150 446 150 349 155 593 155 548 155 501 155 454 155 358 160 602 160 556 160 510 160 464 160 369 165 610 ',l65 565 165 520 165 474 165 381 174 620 170 575 170 530 170 485 170 393 175 630 175 586 175 542 175 497 175 447 180 641 180 597 180 554 180 510 180 422 185 652 185 610 185 567 185 524 185 437 190 665 190 623 190 581 190 539 190 455 195 678 195 637 195 596 195 555 195 473 200 693 2AA 653 200 613 200 573 200 494 205 708 245 669 205 630 205 592 205 516 210 725 210 687 210 649 210 612 210 539 215 743 215 706 215 670 215 634 215 565 224 763 220 727 220 692 224 658 220 592 225 783 225 749 225 716 225 683 225 622 230 806 230 773 230 741 230 711 230 654 235 830 235 799 235 769 235 741 235 689 244 856 240 827 244 799 244 773 240 726 245 884 245 857 245 831 245 807 245 767

System REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 213 of 260 Appendix A (Page 15 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-2: 32 EFPY Cooldown Curve Data Points Using 1996 App. G Methodology (w/Kp, w/Flange Notch & Wo Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-3) lptistr 250 913 250 889 250 865 250 844 250 810 255 946 255 923 255 903 255 884 255 857 260 980 260 960 260 943 260 928 260 908 265 1017 265 1 000 265 986 265 974 265 962 270 1057 270 1043 270 1032 270 1024 270 1021 275 1 100 275 1 090 275 1082 275 1078 275 1078 280 1 147 280 1 139 280 1 136 280 1 136 280 1 136 285 1 196 285 1 193 285 1 193 285 1 193 285 1 193 290 1250 290 1250 290 1250 290 1254 294 1254 295 1307 295 1307 295 1307 295 1347 295 1307 300 1 369 300 1369 300 1369 300 1 369 300 1 369 305 1435 305 1435 305 1435 305 1435 305 1435 310 1 507 310 1507 310 1507 310 1507 310 1507 315 1 583 315 1 583 315 1 583 315 1 583 315 1 583 320 1 666 320 1 666 320 1 666 320 1 666 320 1 666 325 17 55 325 1755 325 1755 325 1755 325 1755 330 1 850 330 1 850 330 1 850 330 1 850 330 1 850 335 1 953 335 1 953 335 1 953 335 1 953 335 1 953 340 2063 340 2063 340 2063 344 2063 340 2063 345 2181 345 2181 345 2181 345 2181 345 2181

System I REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I OA Record I Paqe 214ot260 Appendix A (Page 16 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-2: 32 EFPY Cooldown Curve Data Points Using 1996 App. G Methodology (w/K6, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-3) , l S0oFIhr ,l [.

..- '. :j 1s:Fl.'i IOFI 350 2309 350 2309 350 2309 350 2309 350 2309 355 2446 355 2446 355 2446 355 2446 355 2446

REACTOR COOLANT SYSTEM ISDD-N3.68.4001 System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 215 of 260 7.0 Appendix A (Page 17 of 421 FIGURES AND TABLES (continued) M A T E.R, I A-k,,.P8Ip,.R[;.RI.y,, BA $, I _g LIMITING MATERIAL: LIMITING ART AT 48 EFPY: INTERMEDIATE SHELL FORGING 05 114-T,22A.01 0F 314-T, 185.26 0F 2500 2250 2000 1 750 1 500 1250 1 000 750 500 250 0 1 00 1 50 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F) Figure 2.1-4: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 60'F/hr) Applicable for 48 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/K6) (Plotted Data (Ref. 1) provided on Table 2.1-3) ,boa o,

traa, ok IJ u,a G}

l-o. Eo {., .s5$ I (s (J

System REACTOR COOLANT SYSTEM ISDD-N3-68.4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 216 of 260 7.4 Appendix A (Page 18 of 421 FIGURES AND TABLES (continued) MATERIAL PROPERTY BASIS LIMITING MATERIAL: LIMITING ART AT 48 EFPY: 2500 2250 2000 I 750 1 500 1254 1 000 750 500 250 0 INTERMEDIATE SHELL FORGING 05 114-T, 22A.01 0F 314-T, 185.26 "F ffi I l ,i .i 1....... I ...ri..... .il illlii i ll j.:i

'jl. :..

t. .,::] il l, l'iri l:'i ill ,.lt 'li,.. ,11 i: 1., j' .4.o tfio. V o l-3 Q0o bo, 15o -g3o Til$ t' 100 150 20a 250 300 350 400 Moderator Temperature (Deg. F) Figure 2.1-5: Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100'F/hr) Applicable for 48 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using '1996 App. G Methodology (MK6) (Plotted Data (Ref. 1) provided on Table 2.1-3) Operlim Version:5.2 Run:9162 Operlim.xls Version: 5.2 Unacceptable Operation Criticality Limit based on inservice hydrostatic test temperature (345 F) for the service period up to 48 EFPY Boltup Temperature 60 Deg. F

System Description Document REACTOR COOLANT SYSTEM ISDD.N3.68-4001 Unitl/Unit2 QA Record Rev. 0041 Paqe 217 of 260 Appendix A (Page 19 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-3: 48 EFPY Heatup Curve Data Points Using 1996 App. G Methodology (w/K6, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figures 2.1-4 and 2.1-5) .i:.r p IpsisI 60 0 331 0 60 0 331 0 60 465 331 465 60 413 331 413 65 465 331 465 65 413 331 413 70 465 331 466 7A 413 331 414 75 465 331 467 75 413 331 414 80 465 331 467 80 413 331 416 85 465 331 470 85 413 331 416 90 465 331 470 90 413 331 418 95 465 331 473 95 413 331 419 100 465 331 474 100 413 331 421 105 465 331 477 105 413 331 422 110 466 331 481 110 413 331 425 115 467 331 481 115 413 331 427 120 470 331 487 120 413 331 429 125 473 331 490 125 413 331 433 130 477 331 492 130 413 331 435 135 481 331 499 135 413 331 440 MA 487 331 501 140 414 331 441 145 492 331 506 145 416 331 447

System Description Document REAGTOR COOLANT SYSTEM ISDD-N3-68.4001 Unitl/Unit2 QA Record Rev. 0041 Paqe 218 of 260 Appendix A (Page 20 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-3: 48 EFPY Heatup Curve Data Points Using 1996 App. G Methodology (w/K16, w/Flange Notch & Wo Uncertainties for lnstrumentation Errors) (Data points plotted on Figures 2.1-4 and 2.1-5) -r.:'. t.. "'..:, ',,,,.r1,lr;11;.r'

,,::... j:..-... -

-.....,i.1'.1.,:' -ffiFlhrHeatup 0ritiffilffiil T r,lr','1,[Xp3 irl.ir.lr'ri.: r.rll lti t, i,, i 150 499 331 514 150 418 331 449 155 506 331 516 155 421 331 455 160 514 331 523 160 425 331 459 165 523 331 533 165 429 331 463 170 533 331 543 170 435 331 471 175 543 331 554 175 441 331 473 180 554 331 566 180 447 331 483 185 566 331 579 185 455 331 486 190 579 331 593 190 463 331 494 195 593 331 608 195 473 331 502 200 608 331 625 200 483 331 506 205 625 331 642 205 494 331 519 210 642 331 661 210 506 331 520 215 661 331 682 215 519 331 534 220 682 331 704 220 534 331 549 22s 704 331 727 225 549 331 566 230 727 331 753 230 566 331 584 235 753 331 780 235 584 331 604 240 780 331 809 240 604 331 625

REACTOR COOLANT SYSTEM ISDD-N3-68.4001 System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 Document I OA Record I Paqe 219 of 260 Appendix A (Page 21 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-3: 48 EFPY Heatup Curve Data Points Using 1996 App. G Methodology (w/K;a, wlFlange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figures 2.1-4 and 2.1-5) ,:lrr:i:r

r:i'r.i;i rilii:..r'

,.,r:,t. - "'i:-.-..-1,:', ---..::.ji:'::: Critical Limit .l'i 245 809 331 841 245 625 331 648 250 841 331 875 254 648 331 672 255 875 331 912 255 672 331 699 260 912 331 951 260 699 331 727 265 951 331 993 265 727 331 758 270 993 331 1 038 270 758 331 791 275 1 038 331 1087 275 791 331 826 280 1087 331 1 139 280 826 331 864 285 1 139 331 1 195 285 864 331 905 290 1 195 335 1256 290 905 335 949 295 1256 340 1321 295 949 340 996 300 1321 345 1 390 300 996 345 1047 305 1 390 350 1 465 305 1447 350 1 142 310 1465 355 1540 310 1 102 355 1 160 315 1540 360 1 606 315 1 160 360 1223 320 1 606 365 1677 320 1223 365 1291 325 1677 370 1753 325 1291 370 1 363 330 1753 375 1 835 330 1363 375 1441 335 1 835 380 1922 335 1441 380 1525

System Description Document REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Unit 1 / Untt2 QA Record Rev. 0041 Paqe 220 of 260 Appendix A (Page 22 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.1-3: 48 EFPY Heatup Curve Data Points Using 1996 App. G Methodology (w/K6, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figures 2.1-4 and 2.1-5) i i.. Ji iP., ti ffig]"i=' rEI 340 1922 385 2017 340 1525 385 1614 345 2017 390 2118 345 1614 390 17 1A 350 2118 395 2227 350 17 10 395 1814 355 2227 400 2343 355 1814 400 192s 360 2343 405 2469 360 1925 405 2044 365 2469 365 2044 410 2171 370 2171 415 2308 375 2308 420 2455 380 2455 Leak Test Limit Temp. ["F] 310 331 Pressure [psig] 2000 2485

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I Unitl/Unit2 lRev.0041 REACTOR GOOLANT SYSTEM ISDD-N3-68-4001 Document I OA Record I Paqe 221 ot260 7.0 Appendix A (Page 23 ot 421 FIGURES AND TABLES (continued) M AT E R I A L,,P-RS P E RT-Y.... HASI_$. LIMITING MATERIAL: LIMITING ART AT 48 EFPY: INTERMEDIATE SHELL FORGING 05 114-T, 220.01 0F 314-T, 185.26 "F 2500 2250 2000 I 750 I 500 I 250 { 000 750 500 254 0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F) Figure 2.1-6: Watts Bar Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100'F/hr) Applicable for 48 EFPY (with the "Flange-Notch" & without Margins for lnstrumentation Errors) Using 1996 App. G Methodology (w/Kra) (Plotted Data (Ref. 1) provided on Table 2.1-4) .AlIa o. f.., o LI dt,$ G}ko. ?,s -g =g ts(,

System REACTOR COOLANT SYSTEM ISDD.N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I OA Record I Paqe 222ot260 Appendix A (Page 24 ot 421 7.0 FIGURES AND TABLES (continued) Table 2.14: 48 EFPY Cooldown Curve Data Points Using 1996 App G Methodology (w/K6, w/Flange Notch & Wo Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-O) _l t,i:r,i:' ri.'r i,., 'i:i,':' l '.ltl '),)i,,)t))l .*l. il::llli I ' IJ l,':r..'.: l .: i rr::1.. l-. i-].-.: il l_- .-r x I I I I I I I I I I I I I L I L L I

l l

60 0 60 0 60 0 60 0 60 0 60 513 60 465 60 417 60 367 60 264 65 515 65 467 65 419 65 369 65 266 70 517 70 469 70 421 70 371 70 268 75 519 75 472 75 423 75 373 75 270 80 522 80 474 80 426 80 376 80 272 B5 525 85 477 85 428 85 378 85 275 90 528 90 480 90 431 90 381 90 278 95 531 95 483 95 434 95 385 95 281 100 534 100 486 100 438 100 388 100 285 105 538 105 490 105 442 105 392 105 289 110 542 110 494 110 446 110 396 110 294 115 546 115 499 115 450 115 401 115 299 120 550 120 503 124 455 120 406 120 304 125 555 125 508 125 460 125 411 125 310 130 561 130 514 130 466 130 417 130 316 135 566 135 519 135 472 135 423 135 323 MA 572 140 s26 140 478 140 430 140 331 145 579 145 533 145 485 145 438 145 339

System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD.N3-68-4001 Document I QA Record lPaqe 223ot260 Appendix A (Page 25 ot 421 7.0 FIGURES AND TABLES (continued) Table2.14: 48 EFPY Cooldown Curve Data Points Using 1996 App. G Methodology (w/Kp, w/Flange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-6) , fpeig] :: r:,, r'il.:.:i,ii:i:i i:i:ili: -., ,.: I Sll:ii:iiiiii '.:t fpsigtr 150 586 150 540 150 493 150 446 150 349 155 593 155 548 155 501 155 454 155 358 160 602 160 556 160 510 160 464 160 369 165 610 165 565 165 520 165 474 165 381 170 620 170 575 170 530 174 485 170 393 175 630 175 586 175 542 175 497 175 407 180 641 180 597 180 554 180 510 180 422 185 652 185 610 185 567 185 524 185 437 190 665 190 623 190 581 190 539 190 455 195 678 195 637 195 596 195 555 195 473 200 693 200 653 200 613 200 573 240 494 205 708 2A5 669 205 630 20s 592 205 516 210 725 210 687 210 649 210 612 210 539 215 743 215 706 215 670 215 634 215 565 220 763 220 727 224 692 220 658 220 592 225 783 225 749 225 716 225 683 225 622 230 806 230 773 230 741 230 711 230 654 235 830 235 799 235 769 235 741 235 689 240 856 240 827 240 799 244 773 240 726 245 884 245 857 245 831 245 807 245 767

System REACTOR COOLANT SYSTEM ISDD-N3.68.4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 224 of 260 Appendix A (Page 26 ot 421 7.0 FIGURES AND TABLES (continued) Table2.14: 48 EFPY Cooldown Curve Data Points Using 1996 App G Methodology (w/K6, w/Flange Notch & Mo Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-O) , Hfrl${hr 250 913 250 889 250 865 254 844 250 810 255 946 255 923 255 903 255 884 255 857 260 980 260 960 260 943 260 928 260 908 265 rc17 265 1 000 265 986 265 974 265 962 270 1057 270 1 043 270 1032 270 1024 270 1021 275 1 100 275 1 090 275 1082 275 1078 275 1078 280 1 147 284 1 139 280 1 136 280 1 136 280 1 136 285 1 196 285 1 193 285 1 193 285 1 193 285 1 193 290 1250 290 1250 290 1250 290 1250 294 1250 29s 1307 295 1307 295 1307 295 1347 295 1307 300 1 369 300 1 369 300 1 369 300 1 369 300 1 369 305 1435 305 1435 305 1435 305 1435 305 1435 310 1507 310 1507 310 1507 310 1507 310 1507 315 1 583 315 1 583 315 1 583 315 1 583 315 1 583 320 1 666 320 1 666 320 1 666 320 1 666 320 1 666 325 1755 325 1755 325 1755 325 1755 325 1755 330 1 850 330 1 850 330 1 850 330 1 850 330 1 850 335 1 953 335 1 953 335 1 953 335 1 953 335 1 953 340 2063 340 2063 340 2063 340 2063 340 2063 345 2181 345 2181 345 2181 345 2181 345 2181

System I REAGTOR COOLANT SYSTEM ISDD-N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 225 of 260 Appendix A (Page 27 ot 421 7.A FIGURES AND TABLES (continued) Table2.14: 48 EFPY Cooldown Curve Data Points Using 1996 App G Methodology (w/K6, WFlange Notch & w/o Uncertainties for lnstrumentation Errors) (Data points plotted on Figure 2.1-6) Table 2.1-5 Pressu re Differentia ls Number of Pumps Delta"P (psi) 0 5.2 1 31 0 2 38.0 3 52.0 4 74.0 The COMS analysis considers the following RCP operating restrictions: RCS Temperature < 105 F, maximum of 2 RCPs in operation RCS Temperature > 105 F, maximum of 4 RCPs in operation Figure 3.1-1. DELETED 20"Flhr, 350 2309 350 2309 350 2309 350 2309 350 2309 355 2446 355 2446 355 2446 355 2446 355 2446 Figure 3.1-2'. DELETED

System I REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 226 of 260 7.0 Appendix A (Page 28 ot 421 FIGURES AND TABLES (continued) Watts Table 3.1-1 Bar Unit l Maximum Allowable COMS PORV Setpoints lndicated Cold Leg Temperature oF Maximum Allowable PORV Setpoint (psig) 60 462 105 462 125 481 200 566 225 604 2s0 664 300 688 350 688 Figure 3.1-5: Table 3.1-2: Figure 3.1-6: Table 3.1-3: DELETED DELETED DELETED DELETED

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3.68.4001 Document I OA Record lPase 227 of 260 Appendix A (Page 29 ot 421 7.0 FIGURES AND TABLES (continued) (Notes): (a) Updated from Capsule Z dosimetry analysis. (b) Effective Full Power Years (EFPY) from plant startup. (c) Plant specific evaluation. (d) Capsule V will be removed during the last scheduled outage before estimated capsule exposure to a neutron fluence equal to two times the peak RPV neutron fluence at 60 years of operation (i.e. 54 EFPY). (e) Capsule Y shall remain inserted in the reactor vessel on standby until needed to fulfill future 10 CFR 50, Appendix H or license renewal requirements. Table 4-1 Surveillance Capsule Removal Schedule Capsule Capsule Location Lead Factor(') Withdrawal EFPY(o) Fluence (n/cm2;(a) U 560 5.00 1.20 4.47 x 101t (.) W 124o 5.05 3.88 1.08 x 10'n (c) X 2360 5.03 6.63 1.71 x 101n (.) Z 3040 5.06 9.37 2.40 x 101' (c) V 58.50 4.31 (d) 6.02 x 101e Y 238.5" 4.31 (e) Standby

REACTOR COOLANT SYSTEM ISDD-N3-68-4001 System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I unitl/Unit2 lRev.0041 Document I QA Record Paqe 228 of 260 7.4 Appendix A (Page 30 of 421 FIGURES AND TABLES (continued) TABLE 5-1 Comparison of the Watts Bar Unit 1 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions Material Capsule Fluence(d) (x 101e n/c ffi2, E > 1.0 MeV) 30 ft-lb r Tempera Predicted I 1oP1ta) I 'ransition ture Shift Ir Measured I ("F1tor Upper Shr Decr Predicted I (%!r'-t I

lf Energy ease Ii Measured I

to/i(") lntermediate Shell Forging 05 (Tangential) U 0.447 95.4 98.3 21 19 W 108 125.6 111.4 26 26 X 1.71 141.2 94.7 29 20 Z 244 152.0 144 5 31 23 lntermediate Shell Forging 05 (Axial) U 0 447 954 28.7 21 W 108 125.6 79.0 26 3.2 X 171 141.2 1159 29 Z 2.40 152.0 104.9 31 0 Surveillance Program Weld Metal U 4.447 31.8 0.0(") 16 W 1.08 41 I 305 19 15 X 1.71 47.1 25.8 22 Z 2.40 50.7 13 9 23 Heat Affected Zone Material U 0 447 50.9 11 W 108 488 13 X 1.71 74.5 7.9 Z 2.40 67.7 11

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3.68.4001 Document I QA Record I Paqe 229 of 260 Appendix A (Page 31 ot 421 7.0 FIGURES AND TABLES (continued) TABLE 5-1 Comparison of the Watts Bar Unit 1 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision2, Predictions (Notes): (a) Based on Regulatory Guide '1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material. (b) Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0.2. (c) Values are based on the definition of upper shelf energy given in ASTM E185-82. (d) The fluence values presented here are the "calculated" values. (e) Due to the scatter in the Capsule U Weld Charpy test results, a true Hyperbolic Tangent Curve fit resulted in ATgo values of -6.4"F when compared to unirradiated Charpy test data. A conservative value of OoF was used in RTxpl calculations.

System Description Document REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Unit 1 / Unit2 QA Record Rev. 0041 Paoe 230 of 260 7.0 Appendix A (Page 32 ot 421 FIGURES AND TABLES (continued) TABLE 5-2 Calculation of Chemistry Factors using Watts Bar Unit 1 Surveillance Capsule Data FF? lnter. Shell Forging 05 (Tangential) U 4.447 0.776 98.3 76.28 0.602 W 1.08 1.022 111.4 1 13.80 1.044 X 1.71 1.148 94.7 108.68 1.317 Z 2.40 1 236 144.5 178.60 1.528 lnter. Shell Forging 05 (Axial) U 0.447 0.776 28.7 22.27 0.602 W 1.08 1.022 79.0 80 70 1.444 X 1.71 1.148 1 15.9 133 01 1 317 Z 2.44 1 236 104.9 129.65 1.528 SUM 842.99 8.981 , CFos x f,(FF

  • ARTNm)
  • E(Ff*) = {S4e.9S) + (S,981} = g3.9oF

REACTOR COOLANT SYSTEM ISDD-N3-68-4001 System I REACTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 Document I OA Record I Paqe 231 of 260 7.0 Appendix A (Page 33 of 421 FIGURES AND TABLES (continued) TABLE 5-2 (Cont'd) Calculation of Chemistry Factors using Watts Bar Unit 1 Surveillance Capsule Data Surveillance werd (d'e'f) WB1 -U 0.447 4.776 o.o (o.o(n)) 0.00 0.602 WB1 -W 1.08 1.022 40.26 (30.5) 41.13 1.044 WB1 -X 1.71 1.148 34.06 (25.8) 39.08 1.317 WB1.Z 2.40 1.236 18 3s (13 e) 22.68 1.528 Cat. 1 -Z 0.2993 0 670 o o0) (1.91) 0.00 0.448 Cat. 1 -Y 1.318 1 077 8.52 (17.7e) 9.18 1.160 Cat. 1 -V 2.334 1.229 15.4 (26.5) 18.93 1.510 MG2_V 0.323 0.689 32.s1 (38.51) 22.41 0.475 MG2-X 1.47 1 11 2e.e3 (35.e3) 33.1 3 1.225 MG2-U 2.04 1.19 17.81 (23.81) 21.27 1.426 MG2-W 3.07 1.30 37 76 (43.76) 48.94 1 680 256.75 12.415 cF su*,waa E E(FF *"ARTr,rpr) + !( FF2) * (256.75) + {12.415)

  • 20.7"F

System REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 232 of 260 Appendix A (Page 34 of 421 7.0 FIGURES AND TABLES (continued) TABLE 5-2 (Cont'd) Calculation of Chemistry Factors using Watts Bar Unit 1 Surveillance Capsule Data (Notes): (a) f = fluence. For Watts Bar Unit '1, see f ab/re 2-2; for Catawba Unit 1, see WCAP-15117, and for McGuire Unit 2, see WCAP-15334. Fluence units are [E+19 n/cm', E > 1.0 MeV]. (b) FF = fluence factor = f0'28 - 0'1"ros D. (c) ARTruor values are the measured 30 ft-lb shift values ['F]. Watts Bar Unit 1 values are taken from WCAP-16760-NP, Catawba Unit '1 values are taken from WCAP-15117, and McGuire Unit 2 values are taken from WCAP-14799. Units are [oF]. The pre-adjusted values are shown in the parentheses; for more details on the adjusted values refer to Notes "d" and "e." (d) The Surveillance Weld ARTxel values have been adjusted for temperature difference from Watts Bar Unit 1 as follows: e Minus 7"F for Catawba Unit 1 (Note: lt is more conservative to adjust for temperature 1st, then apply the ratio.) r Minus 6oF for McGuire Unit 2 (e) The Surveillance Weld ARTxel values have been adjusted for chemistry difference to the best estimate Cu & Ni by a ratio of: o 1.32 for Watts Bar Unit 1 r 0.79 for Catawba Unit 1 e 1.0 for McGuire Unit 2 (0 Surveillance data for Catawba Unit 1 and McGuire Unit 2 come from WCAP-15117 and WCAP-14799. (g) Original value was.4oF, but physically a reduction should not occur, therefore a conservative value of zero will be used for Watts Bar Capsule U weld metal. (h) After the Temperature adjustment and ratio procedure, the value of the shift comes out less than zero, but physically a reduction should not occur, therefore a conservative value of zero will be used.

System I REACTOR COOLANT SYSTEM ISDD-N3-G Description I unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD.N3.68-4001 Document I OA Record I Paqe 233 of 260 Appendix A (Page 35 of 421 7.0 FIGURES AND TABLES (continued) NOTES: (a) Based on measured data. (b) The surveillance weld was made with the same weld wire and flux as the intermediate to lower shell girth weld (weld wire heat # 895075, flux type Grau L.O. # LW320, lot # P46). (c) These values were rounded to two decimal points since the chemistry factor determination uses weight percent chemistry to fwo decimal points. (d) Used in the consideration of flange requirements for heatup/cooldown curves. Per methodology given in WCAP-14M0, the minimum boltup temperature is 60'F. TABLE 5-3 Watts Bar Unit 1 Reactor Vessel Toughness Table (Best Estimate Average, i.e., all data) Material Description Cu 1o1ola) Ni1%1t'r lnitial RTr..ror Closure Head Flange 08 (Heat#910334/710402) 0.13 0.75 -430F Vessel Flange 07 (Heat # 41 1471) _4Op (o) lntermediate Shall Forging 05 (Heat # 527536) 0 16 0.80 47"F Lower Shell Forging 04 (Heat # 528522) 0.08 0.8s 50F tnter. To Lower Shell Girth Weld WO5 (b'c) 0.04 0,73 -430F Watts Bar Unit l surveillance Weld Meta; (b'c) 0.03 0.75 Watts Bar Unit 2 Surveillance Weld Metal (b'c) 0.02 0.69 Catawba Unit l surveillance Weld Metal (b'c) 005 0.73 McGuire Unat2 Surveillance Weld Meta; (b'c) 004 0.74

System REACTOR COOLANT SYSTEM ISDD.N3.68.4OO1 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paqe 234 of 260 Appendix A (Page 36 of 421 7.A FIGURES AND TABLES (continued) NOTES: (a) These values are based on the new evaluation performed from the Capsule Z evaluation (Ref. 8). Units are nlcm2 (E>1.0 MeV). N.9.IH..S;... Notes follow Table 5-6. TABLE 5-4 Watts Bar Unit 1 Reactor Vessel Surface Fluence Values at 32 and 48 EFPY(") Azimuth 0o 15., 300 45" 32.00 48.00 9.49 x 1018 1.45 x 101e 1.41 x 101e 2.15 x 101e 1.42 x 1O1e 2.16 x 101e 1.75 x 101e 2.66 x 101e TABLE 5.5 Summary of ARTs for the Watts Bar Unit 1 Reactor Vessel Beltline Materials at the 1/4-T and 3/4-T Locations for 32 EFPY Component 32 EFPY(,) 1t4-T (.F) 3t4-T ("F) lntermediate Shell Forging 05 (Heat # 527536) 205.74(b) 171. 1 5(b) 176.23 149.82 Lower Shell Forging A4 (Heat # 528522) 90.72 76.38 lntermediate to Lower Shell Girth Weld (Heat # 895075) 66.s3 36.1 5 -1.01 -12.66

System I REACTOR COOLANT SYSTEM ISDD-N3-C Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD.N3.68.4OO1 Document I OA Record I Paqe 235 of 260 Appendix A (Page 37 of 421 7.A FIGURES AND TABLES (continued) NOTES: (a) Fluence used for the PT Limit curves were based on the previous fluence analysis performed from the Capsule Z evaluationt8l (See Table 5-4 above). Units are nlcm2 (E>1.0 MeV). (b) Used to generate the heatup/cooldown curves. TABLE 5-6 Summary of ARTs for the Watts Bar Unit 1 Reactor Vessel Beltline Materials at the 114-T and 314-T Locations for 48 EFPY Component 48 EFPY(,) 114-T ("F) 3t4-T ("F) lntermediate Shell Forging 05 (He at # 527536) 220.010) 195.26$) 187.12 160 60 Lower Shell Forging 04 (Heat # 528522) 96.64 82.23 lntermediate to Lower Shell Girth Weld (Heat # 895075) 74.03 48.55 3.79 -7.91

System REACTOR COOLANT SYSTEM ISDD-N3.68-4001 Description I Unitl/Unit2 lRev.0041 Document I OA Record Paqe 236 of 260 Appendix A (Page 38 of 421 7.A FIGURES AND TABLES (continued) TABLE 5-7 Calculation of Adjusted Reference Temperatures at 32 EFPY for the Limiting Watts Bar Unit 1 Reactor Vessel Material (lntermediate Shell Forging 0Q Parameter Values Operating Time 32 EFPY Material lnter. Shell Forging 05 lnter. Shell Forging 05 Location 1t4-T 3t4-T Chemistry Factor (CF), oP(a) 123 123 Fluence (0, *101e nlcmz (Er1.0MeV;tol 1.05 0.38 Fluence Factor (Fqt'l 1.01 0.73 ARTl.rDr = CF x FF, oF 124.74 90.1 5 lnitial RTppl(l), oF 47 47 Margin (M), oP(d) 34 34 ART=l+(CF.FF)+M,*F lPer Regulatory Guide 1.99, Revision 2l 205.74 17 1.1 5 NOTES: (a) CF is based on the Copper and Nickelfrom Table 5-3. (b) Fluence, f, is based upon frr6 = 1.75 x 101e nlcm2. The Watts Bar Unit 1 reactor vessel wall thickness is 8.465 inches at the beltline region. (c) Ff=floza-ololoso (d) Margin is calculated as M = 2(ai2

  • oo')o u. The standard deviation for the initial RTlro1 m?rgin term, oi, is OoF since the initial RTNor value is a measured value. The standard deviation for the ARTNoT margin term, ol is 17oF for the forging except that oa need not exceed 0.5 times the mean value of ARTxpl.

System I REAGTOR COOLANT SYSTEM ISDD-N3-6 Description I Unitl/Unit2 lRev.0041 REACTOR COOLANT SYSTEM ISDD-N3-68.4001 Document I OA Record I Paqe 237 ot260 Appendix A (Page 39 of 421 7.0 FIGURES AND TABLES (continued) TABLE 5-8 Calculation of Adjusted Reference Temperatures at 48 EFPY for the Limiting Watts Bar Unit 1 Reactor Vessel Material (lntermediate Shell Forging 0Q Parameter Values Operating Time 48 EFPY Material Inter. Shell Forging 05 Inter. Shell Forging 05 Location 114-T 3t4-T Chemistry Factor (CF), oP(a) 123 123 Fluence (0, *101e n/cm2 (E>1.0MeV;tol 1.60 058 Fluence Factor (FFltcl 1.13 0.85 ARTr,rDr = CF x FF, oF 139.01 104.26 lnitial RTruor(l), 0F 47 47 Margin (M), o5(d) 34 34 ART=l+(CF"FF)+M,oF lPer Regulatory Guide 1.99, Revision 2l 224.01 185.26 NOTES: (a) CF is based on the Copper and Nickelfrom Table 5-3. (b) Fluence, f, is based upon frr6 = 2.66 x 101e nlcm2. The Watts Bar Unit 1 reactor vessel wall thickness is 8.465 inches at the beltline region. (c) Ff=floza-ololoso (d) Margin is calculated as M = 2(ai2

  • oo')o u. The standard deviation for the initial RT'rol margin term, o;, is OoF since the initial RTrvor value is a measured value. The standard deviation for the ARTNoT margin term, o6 is 17oF for the forging except that oa need not exceed 0.5 times the mean value of ARTruor.

System REACTOR COOLANT SYSTEM ISDD.N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paoe 238 of 260 Appendix A (Page 40 of 421 7.0 FIGURES AND TABLES (continued) Notes: (a) The fluence, f, was taken from the peak azimuthal location (See Table 544);.101e n/cm2, E>1.0 MeV. (b) FF - t'28{'11os0; where f is the clad/base metal interface fluence. (c) The Position 1 (non-surveillance data) Chemistry Factor is obtain from the best estimate Cu & Ni in Table 5-3. The Position 2 (Surveillance Data) Chemistry Factor is obtained from Table 5-2. Units are oF. (d) ARTprs = CF"FF; oF (e) Margin = 2*(6t2 + 6^?)1t2i oF (0 lnitial RTror values are measured values (See Table 5-3); 'F (g) RTprs = RTuor(u) + ARTprs + Margin (Ihis value was rounded per ASTM E29, using the "Rounding Method'); 'F (h) o6 exceeded 1/2ARTNor; thus, the calculated value of 1/2ARTrvor was used. Surveillance data is "credible". See WCAP-16760 (Ref.8). (i) Surveillance Data deemed "not-credible," thus the fullo6 must be applied. See WCAP-16760 (Ref. 8). TABLE 5-9 RTprs Calculations for Watts Bar Beltline Region Materials at 32 EFPY Material Fluence, fltl FF(b) cF(') ARTprs(d) MargiP(e) RTr.ror(u)(o RTrrs(s) Intermediate Shell Forging 05 (Heat # 527536) 1.75 1.1s 123 141.88 34 47 222.88 Using Surv. Cap. Data -+ 1.75 1.15 939 108.32 340) 47 189.32 Lower Shell Forging 04 (Heat # 528522) 1.75 1.15 51 58.83 34 5 97.83 lnter. To Lower Shell Gifrh Weld (Heat # 89507q 1.75 1.15 54 62.29 56 -43 75.29 Using Surv. Cap. Data -+ 1.75 1.15 20.7 23.88 24(n) -43 4.76

System REACTOR COOLANT SYSTEM ISDD.N3.68-4001 Description I Unitl/Unit2 lRev.0041 Document I QA Record Paoe 239 of 260 Appendix A (Page 41 ot 421 7.A FIGURES AND TABLES (continued) Notes: (a) The fluence, f, was taken from the peak azimuthal location (See Table 544); *101s nlcm2, E>1.0 MeV. (b) FF = f(28-01.roe0; where f is the clad/base metal interface fluence. (c) The Position 1 (non-surveillance data) Chemistry Factor is obtain from the best estimate Cu & Ni in Table 5-3. The Position 2 (Surveillance Data) Chemistry Factor is obtained frornTable 5-2. Units are oF. (d) aRTprs = CF*FF; oF (e) Margin =2*@rl + 6^2)1t2;"F (f) lnitial RTxel values are measured values (See Table 5-3); 'F (g) RTprs = RTr,rorrul + ARTprs + Margin (This value was rounded per ASTM E29, using the "Rounding Method"); 'F (h) o6 exceeded 1/2ARTNor, thus, the calculated value of 1/2ARTr.ror was used. Surveillance data is "credible". See WCAP-16760 (Ref. 8). (i) Surveillance Data deemed "not-credible," thus the full <16 mUSt be applied. See WCAP-16760 (Ref. 8). TABLE 5,10 RTprs Calculations for Watts Bar Beltline Region Materials at 48 EFPY Material Fluence, f(t) pp(o) 6p(c) ARTprs(d) Margin(") RTruor(u)(o RTrrr(s) Intermediate Shell Forging 05 (Heat # 527536) 2.66 1,26 123 155.21 34 47 236.21 Using Surv. Cap. Data -> 2.66 1.26 93.9 1 1B.49 34(i) 47 199.49 Lower Shell Forging 04 (Heat # 528522) 2.66 1.26 51 64.35 34 5 103.35 Inter. To Lower Shell Girth Weld (Heat # 895075) 2.66 1.26 54 68.14 56 -43 81.14 Using Surv. Cap. Data -+ 2.66 1.26 24.7 26.12 26(n) -43 9.24

System I REACTOR COOLANT SYSTEM ISDD-N3-68-4001 Description I Unitl/Unit2 lRev.0041 Document I OA Record I Paqe 240 of 260 Appendix A (Page 42 ot 421 8.0 SOURCE NOTES NCO82A285003 NCO820285004 1. 2.}}

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