ML033230496
| ML033230496 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/14/2003 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033230496 (34) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 NOV 1 2003 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of Tennessee Valley Authority
)
Docket No.50-390 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 -
REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR), REVISION 7 The purpose of this letter is to provide NRC the latest revision of the PTLR in accordance with WBN Technical Specification 5.9.6.c which states that the PTLR shall be provided to NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto.
The enclosed PTLR Revision 7, incorporates the results of the analysis performed on Surveillance Capsule W which was removed during the Unit 1 Cycle 3 Refueling Outage.
The revision also updates the reactor heat up and cooldown curves and the cold overpressure mitigation system (COMS) setpoints for the operating period from seven to sixteen effective full power years.
The revision was incorporated into the plant design basis in October 2003.
If you have any questions about this report, please contact me at (423) 365-1824.
Si y,
P. L. Pace Manager, Site Licensing and Industry Affairs
-$9C,32I -
Enclosure cc:
See page 2 Pnnted on A
Wa
U.S. Nuclear Regulatory Commission Page 2 NOV 1 4 2003 cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 APPENDIX "A" TO RCS SYSTEM DESCRIPTION N3-68-4001 WATTS BAR UNIT 1 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
REVISION 7 Prepared by :
(mQuA~k~L~Wt&
? (ZS (2c23 Checked by:
Approved by :
a
/4z51V 31/2))-2M Unit 1 Watts Bar A-1 Revision 7
DCN D-51236-A TVA Page 16
Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR RCS PRESSURE AND TEMPERATURE LIMITS REPORT FOR WATTS BAR UNIT 1 1.0 RCS Pressure and Temperature Limits Report (PTLR)
This PTLR for Watts Bar Unit 1 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:
RCS Pressure and Temperature (PIT) Limits LCO 3.4.12 Cold Overpressure Mitigation System (COMS) 2.0 RCS Pressure and Temperature Limits The limits for LCO 3.4.3 are presented in the subsection which follows.
These limits have been developed (Ref. 1, 8) using the NRC-approved methodologies specified in Technical Specification 5.9.6.
2.1 RCS 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 100 F per hour.
- b.
A maximum cooldown Rate 100 F per hour.
- c.
A maximum temperature change of 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
2.1.2 The RCS P/T limits for heatup, cooldown, inservice hydrostatic and leak testing, and criticality are specified by Figures 2.1-1 and 2.1-2 (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 2.1-3 for pressure differences (Ref. 2).
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 (O F per hour heatup or cooldown curves) are achieved after maintaining a constant temperature for a duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Ref. 1).
Steady state conditions are maintained if temperature fluctuations remain within 9.20 F (Ref.
1).
3.0 Cold Overpressure Mitigation System (LCO 3.4.12)
Unit 1 Watts Bar A-2 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR 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 NRC-approved methodologies specified in Technical Specification 5.9.6.
3.1 Pressurizer PORV Lift Setting Limits The pressurizer PORV lift setpoints are depicted in Figures 3.1-1 through 3.1-4 and specified by Table 3.1-1 (Ref. 8).
The limits for the COMS setpoints are contained in the 16 EPY curves adjusted per ASME Code Case N-514 for eatup (Figure 3.1-5 and Table 3.1-2) and Cooldown (Figure 3.1-6 and Table 3.1-3) (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 2.1-3 for pressure differences (Ref. 2).
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 -T-68-1B and 1-T-68-43B contain the adjusted curves compensated for pressure differential and instrument inaccuracy which provides the PORV lift limits for the COMS.
4.0 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 4.0-1.
The results of these examinations shall be used to update Figures 2.1-1, 2.1-2, and 3.1-1 through 3.1-4.
The pressure vessel steel surveillance program (Ref. 3) is in compliance with Appendix to 10 CR 50, entitled Reactor Vessel Material Surveillance Program Requirements". The material test requirements and the acceptance standard utilize the reference nil-ductility temperature,
- RTN, which is determined in accordance with ASTM 208.
The empirical relationship between RTNDT and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix G, Protection Against Non-Ductile Failure", to Section III of the ASME Boiler and Pressure Vessel Code.
The surveillance capsule removal schedule meets the requirements of ASTM 185-82. The removal schedule is provided in Table 4.0-1.
5.0 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.
Unit 1 Watts Bar A-3 Revision 7
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RP.ACTOR COOLAN~T SYSTEM N3 4001 Unit PTLR Table 5.2 shows calculations of the surveillance material chemistry factors using surveillance capsule data.
Table 5.3 provides the required Watts Bar Unit. reactor vessel toughness data. The bolt-up temperature is also included in this table.
Table 5.4 provides a summary of the fluence values used in the generation of the heatup and cooldown limit curves.
Table 5.5 provides a summary of the adjusted reference temperature (ART) values of the Watts Bar Unit 1 reactor vessel beltline materials at the 1/4-T and 3/4-T locations for 16 EPY.
Table 5.6 shows example calculations of the adjusted reference temperature (ART) values at 16 EPY for the limiting Watts Bar Unit 1 reactor vessel material (Intermediate Shell Forging 05).
Table 5.7 provides a summary of the fluence values used in the Pressurized Thermal Shock (PTS) evaluation (Ref. 4).
Table 5.8 provides RT values for Watts Bar Unit 1 for 32 EPY (Ref 4).
Table 5.9 provides RT values for Watts Bar Unit 1 for 48 EPY (Ref 4).
REFERENCES
- 1. Structural Integrity Associates Report, No. SIR-01-140, Revision 1, Heatup and Cooldown Limit Curves for Normal Operation for Watts Bar Unit 1, July 2002.
- 2. Westinghouse Letter to TVA, WAT-D-9448, Revised CONS PORV Setpoints," August 27, 1993.
- 3. WCAP-9298, Revision 1, Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program", April 1993.
- 4. Structural Integrity Associates Report, No. SIR-01-137, Revision 0, RTYs Evaluation for Watts Barn, January 2002.
- 5. WCAP-14040, Revision 1, Methodology Used To Develop Cold Overpressure Mitigating System Setpoints and RCS eatup and Cooldown Limit Curves", December 1994.
- 6. WCAP-15046, Analysis of Capsule U From Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program", June 1998.
- 7. BWXT SERVICES, Inc., "Analysis of Capsule W From The Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Material Surveillance Program", September 2001.
- 8. Structural Integrity Associates Report, No. SIR-01-147, Revision 0, Revised CONS PORV etpointso, January 2002.
Unit 1 Watts Bar A-4 Revision 7
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Title:
[ N3-68-4001 Unit 1 PTLR MATERIAL PROPERTY BASIS LIMITING MATERIAL:
INTERMEDIATE SHELL FORGING 05 INITIAL RT=T 47 F
LIMITING ART AT 16 EFPY: 1/4-T, 191.7 F 3/4-T, 156.7 F 3000 2500 2000 0
P IL Composite 60 and 100 F Curves for Intermedlate Shell Forging 05 I 1 i Zi 1iZ 1
--"LEAK TEST
-0CITICAL (0DEG F/HR)-
CRITICAL(60DEGF/HR) l
-41HEAT UP (1 00 DEG F/HR)
-HEAT UP (60 DEG F/HR)
-SS 0 D EG/H R I
I r
1 I>-~~~~~~0 I
1 500 1000 500 0
0.0 50.0 100.0 150.0 200.0 250.0 Temperature (F) 300.0 350.0 400.0 450.0 Figure 2.1-1 Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup rates of 60 and 100 F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation Errors)
(Plotted Data (Ref. 1) provided on Table 2.1-1 with SS curve from Table 2.1-2)
Unit 1 Watts Bar Ae Revision 7
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REACTOR COOL7=6 SYSTEM l
N3-68-4001 l
Unit PTLR Table 2.1-1 Watts bar Unit Heatup Limits (Data points plotted on Figure 2.1-1)
TEMPERATURE HEATUP HEATUP CRITICALITY CRITICALITY RATE RATE LEAS TEST LIMITS LIMITS (60 F/HR)
(100 F/HR)
LIMITS (60 OF/HR)
(100 F/HR) 60 439.84 399.21 65 439.84 399.21 70 439.84 399.21 75 439.84 399.21 80 439.84 399.21 85 439.84 399.21 90 439.84 399.21 95 439.84 399.21 100 439.84 399.21 905 439.84 399.21 110 439.84 399.21 115 440.08 399.21 120 441.55 399.21 125 443.90 399.21 130 446.98 399.21 135 450.87 399.21 140 455.75 398.97 145 461.23 399.67 150 467.65 400.78 155 474.92 402.94 160 482.62 406.05 165 491.30 409.84 170 501.13 414.52 175 511.70 419.66 180 523.16 425.95 185 535.67 432.79 190 548.99 440.89 195 564.07 449.33 Unit Watts Bar A-6 Revision 7
DCN D.51236-A Page 2-1
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 l
Unit 1 PTLR Table 2.1-1 Watts bar Unit 1 Heatup Limits (Data points plotted on Figure 2.1-1)
TEMPERATURE (IF)
HEATUP HEATUP CRITICALITY CRITICALITY RATE RATE LEAR TEST LIMITS LIMITS (60 F/HR)
(100 MF/R)
LIMITS (60 OF/HR)
(100 F/HR) 200 579.65 459.50 205 596.87 469.97 210 615.60 481.74 215 635.15 494.85 220 656.93 508.79 225 679.70 523.95 230 704.81 540.61 235 731.50 558.85 240 760.51 578.29 245 791.53 599.34 250 824.34 622.09 255 860.28 647.04 260 898.89 673.28 265 940.37 702.05 270 984.93 733.27 275 1032.79 766.47 280 1084.18 802.12 285 1139.36 840.72 290 1198.59 881.97 295 1262.17 927.35 300 1330.39 974.93 304 2000 305 1403.57 1026.14 310 1469.09 1082.37 315 1533.77 1141.03 320 1603.14 1205.73 325 1677.51 1273.73 2485 0 to 1139.36 0 to 840.72 330 1757.23 1346.12 1198.59 881.97 Unit Watts Bar a-7 Revision 7
DCN D-51236-A Page 22 I
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit PTLR Table 2.1-1 Watts bar Unit 1 Heatup Limits (Data points plotted on Figure 2.1-1)
TEMPERATURE (OF)
TEAUP HEATUP CRITICALITY CRITICALITY RATE RATE LEAS TEST LIMITS LIMITS (60 FIHR)
(100 OF/KR)
LIMITS (60 F/HR)
(100 F/HR) 335 1842.64 1425.79 1262.17 927.35 340 1934.10 1511.21 1330.39 974.93 345 2032.01 1602.75 1403.57 1026.14 350 2136.89 1700.67 1469.09 1082.37 355 2248.85 1805.37 1533.77 1141.03 360 2368.47 1917.72 1603.14 1205.73 365 2496.14 2035.38 1677.51 1273.73 370 2632.29 2163.59 1757.23 1346.12 375 2300.46 1842.64 1425.79 380 2446.44 1934.10 1511.21 385 2601.96 2032.01 1602.75 390 2136.89 1700.67 395 2248.85 1805.37 400 2368.47 1917.72 405 2496.14 2035.38 410 2632.29 2163.59 415 2300.46 420 2446.44 425 2601.96 Unit 1 Watts Bar A-8 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR MATERIAL PROPERTY BASIS LIMITING MATERIAL:
INITIAL RT=
INTERMEDIATE SHELL FORGING 05 47 F LIMITING ART AT 16 EPY:
1/4-T, 191.7 F 3/4-T, 156.7 F Composite Cool Down Curves for Intermediate Shell Forging 05 2500 2250 2000 1 750 1 500 0.
0S P
ILso 1250 1 000 750 500 250 0
0.0 50.0 100.0 150.0 200.0 250.0 300.0 350.0 Temperature (F) 400.0 Figure 2.1-2 Watts Bar Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100 0F/hr) Applicable for the First 16 EPY (Without Margins for Instrumentation Errors)
(Plotted Data (Ref. 1) provided on Table 2.1-2)
Unit 1 Watts Bar A-9 Revision 7
DCN D-51236-A Page 2-Ot TVA
Title:
REACTOR COOLANT SYSTEM lN3-68-4001l Unit 1 PTLR Table 2.1-2 Watts Bar Unit 1 Cooldown Limits (Data points plotted on figure 2.1-2)
TEMPERATURE (OF) 100 FIHR 75 F/HR 60 F/HR 40 F/HR 20 F/HR 0
F/HR 60 251.75 307.29 342.16 389.88 437.67 65 254.72 309.64 344.51 392.23 440.02 70 257.87 312.64 347.50 394.76 442.54 490.13 75 261.36 315.51 350.22 397.47 445.25 492.77 80 264.91 318.58 353.14 400.39 448.17 495.72 85 268.82 322.19 356.43 403.53 451.31 498.88 90 273.13 325.72 359.80 406.90 454.68 502.28 95 277.69 329.81 363.43 410.53 458.31 505.94 100 282.84 333.87 367.49 414.43 462.20 509.87 105 288.28 338.68 372.00 418.62 466.40 514.09 110 294.19 343.50 376.66 423.29 470.90 518.64 115 300.59 348.97 381.66 428.13 475.75 523.52 120 307.35 354.96 387.34 433.34 480.96 528.77 125 314.51 361.19 393.10 438.95 486.56 534.42 130 322.56 367.99 399.43 444.97 492.58 540.39 135 331.21 375.71 406.38 451.45 499.05 546.91 140 340.50 383.60 413.96 458.41 506.01 553.93 145 350.79 392.48 422.07 466.36 513.49 561.47 150 361.63 401.92 430.89 474.41 521.54 569.58 155 373.38 412.13 440.32 483.22 530.19 578.31 160 386.26 423.46 450.39 492.52 539.48 587.56 165 400.29 435.46 461.63 502.98 549.48 597.63 170 415.07 448.53 473.46 513.89 560.22 608.47 175 431.43 462.41 486.57 526.06 571.78 620.12 180 448.81 478.23 500.85 538.79 584.19 632.50 185 467.89 494.68 516.37 552.76 597.54 645.97 190 488.28 513.21 533.04 567.89 611.89 660.44 195 510.67 532.97 551.40 584.09 627.47 675.98 200 534.52 554.50 571.39 602.07 644.05 692.57 Unit Watts Bar A-10 Revision 7
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REACTOR COOLANT SYSTEM lN3-68-4001 l
Unit 1 PTLR Table 2.1-2 Watts Bar Unit 1 Cooldown Limits (Data points plotted on figure 2.1-2)
TEDPERATURE (IF) 100 F/RR 75 F/HR 60 F/HR 40 F/ER 20 0F/HR 0 F/R 205 560.38 578.03 593.07 621.44 661.88 710.56 210 588.65 603.67 617.01 642.60 681.50 729.70 215 618.95 631.51 642.84 665.97 702.24 750.49 220 651.86 661.80 671.29 691.18 724.84 772.78 225 687.65 695.12 702.76 719.12 749.39 796.64 230 726.27 731.13 736.92 749.75 775.87 822.23 235 768.01 770.72 774.52 783.81 805.33 849.99 240 812.84 813.86 815.67 821.75 837.60 879.55 245 861.52 860.72 861.31 864.02 873.90 911.51 250 912.97 911.88 911.09 911.21 915.45 945.77 255 973.61 965.36 964.42 963.78 982.53 260 1019.03 1019.03 1022.00 265 1064.40 270 1109.98 275 1158.95 280 1211.57 285 1268.05 290 1328.61 295 1393.44 300 1463.21 305 1537.95 310 1618.11 315 1703.92 320 1795.88 325 1894.39 330 1999.72 335 2112.46 340 2232.88 345 2361.41 Unit 1 Watts Bar A-11 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 2.1-3 Pressure Differentials Number of Pumps Delta P (psi) 0 5.2 1
31.0 2
38.0 3
52.0 4
74.0 Table 3.1-1 Watts Bar Unit 1 PORV Setpoints vs Temperature (Data (Ref. 8) plotted on Figures 3.1-1 through 3.1-4)
SETPOINTS (PSIG)
TEMP IRCS PUMP 2 RCS PUMPS 3 RCS PUMPS 4 RCS PUMPS (F)
OPERATING OPERATING OPERATING OPERATING PORV-334 PORV-340A PORV-334 PORV-340A PORV-334 PORV-340A PORV-334 PORV-340A 70 480 453
- 479 452
- 461 434
- 439
- 412
- 100 477 450
- 476 449
- 458*
431
- 436
- 409
- 150 486 458
- 476 448
- 463 436
- 443
- 416
- 200 499 467 499 467 479 447
- 459 427
- 250 549 504 549 509 539 494 514 474 275 581 531 591 541 571 521 556 506 300 575 525 575 525 570 520 560 510 350 745 690 745 690 745 690 745 690 450 2350 2350 2350 2350 2350 2350 2350 2350
- Setpoint violates pump seal limit.
The pump seal adjustment for pressure channel uncertainty.
limit includes a 63 pig Unit 1 Watts Bar A-12 Revision 7
DCN D-51236.A Pao 27 TVA I
Title:
REACTOR COOLANT SYSTEM lN3-68-4001 Unit 1 PTLR 1 OPERATING PUMP ifA L'
70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 290 300 310 320 330 340 350 Temperature (F)
- PORV 334 PORV 340A -Maximum Aowabe Stpoint Figure 3.1-1 PORV Setpoint VS RCS Temperature (Plotted data (Ref. 8) provided on Table 3.1-1)
Unit 1 Watts Bar A-13 Revision 7
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REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR 2 OPERATING PUMPS IL 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 290 300 310 320 330 340 350 Temperatur (fF)
I
- PORV 334
- PORV 340A -Maximum Alowable Setpoint l Figure 3.1-2 PORV Setpoint vs RCS Temperature (Plotted data (Ref. 8) provided on Table 3.1-1)
Unit 1 Watts Bar A-14 Revision 7 COLf
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REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR go e
7c 6C 5!
5c 4C 31 21 3 OPERATING PUMPS 70 8090 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 29 300 310 320 33 340 30 Tenmrture (F)
- PORV& 33 P0RV 340A -Maimmlowale Setpontj 102 Figure 3.1-3 PORV Setpoint vs RCS Tenperature (Plotted data (Ref. 8) provided on Table 3.1-1)
Unit 1 Watts Bar A-15 Revision 7
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REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR 4 OPERATING PUMPS 70 -
9 -
1 1
1 1
1 1
1 1
1 2
2 2
2 2
2 2
2 2
2 3
3 3
3 3
3 150 -
250 70 80 go 100110lo120 130 140 150 160 170 10190 20D0210 220 230 240 250 260 270 28D290 30310 320 330340 350 Temperature (F)
- PORV 334
- PORV 340A -Madmum Aowable Stpoint Figure 3.1-4 PORV Setpoint vs RCS Temperature (Plotted data (Ref. 8) provided on Table 3.1-1)
GQ Unit 1 Watts Bar A-16 Revision 7
1 DCN D-51236-A TVA Page 31
Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR MATERIAL PROPERTY BASIS LIMITING MATERIAL:
INITIAL RTT LIMITING ART AT 16 INTERMEDIATE SHELL FORGING 05 47 F
FFPY: 1/4-T, 3/4-T, 191.7 F 156.6 F Composite 60 and 100 F 10% Relaxation Curves for Intermediate Shell Forging 05 3000 _
2500 2000 a
a 0
00 tL_
a 1000 500 _
0-0.0 50.0 100.0 150.0 200.0 250.0 300.0 350.0 400.0 450.0 Temperature (F)
Figure 3.1-5 Watts Bar Unit 1 Reactor Coolant System Heatup Limitations (Heatup rates of 60 and 100 0F/hr) Applicable for the First 16 FPY (Without Margins for Instrumentation Errors) Including 10% Relaxation in Pressure for Temperature < 241.70F per ASME Code Case N-514 (Plotted Data (Ref. 1) provided on Table 3.1-2)
A-17 Unit 1 Watts Ba3 Revision 7 CQfl
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Title:
REACTOR COOLANT SYSTEM N3-68-4001
]
Unit 1 PTLR Table 3.1-2 Watts Bar Unit 1 Heatup Limits (Data (Ref. 1) plotted on Figure 3.1-5)
TEMPERATURE HEATUP HEATUP LEAK TEST CRITICALITY CRITICALITY RATE RATE LIMITS LIMITS LIMITS (60 0F/HR)
(100 F/HR)
(60 F/HR)
(100 F/RR) 85 483.83 439.13 90 483.83 439.13 95 483.83 439.13 100 483.83 439.13 105 483.83 439.13 110 483.83 439.13 115 484.09 439.13 120 485.71 439.13 125 488.29 439.13 130 491.68 439.13 135 495.96 439.13 140 501.33 438.87 145 507.35 439.64 150 514.42 440.85 155 522.42 443.23 160 530.88 446.65 165 540.43 450.83 170 551.24 455.98 175 562.87 461.63 180 575.48 468.55 185 589.24 476.07 190 603.89 484.98 195 620.48 494.27 200 637.62 505.45 205 656.56 516.97 210 677.16 529.91 215 698.67 544.33 220 722.62 559.67 Unit 1 Watts Bar A-18 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 3.1-2 Watts Bar Unit 1 Heatup Limits (Data (Ref. 1) plotted on Figure 3.1-5)
TEMPERATURE (OF)
HEATUP HEATUP LEAK TEST CRITICALITY CRITICALITY RATE RATE LIMITS LIMITS LIMITS (60 F/HR)
(100 F/HR)
(60 F/HR)
(100 F/HR) 225 747.67 576.34 230 775.30 594.67 235 804.65 614.74 240 836.56 636.12 241.7 847.78 642.71 241.7 770.71 584.28 245 791.53 599.34 250 824.34 622.09 255 860.28 647.04 260 898.89 673.28 265 940.37 702.05 270 984.93 733.27 275 1032.79 766.47 280 1084.18 802.12 285 1139.36 840.72 290 1198.59 881.97 295 1262.17 927.35 300 1330.39 974.93 304 2000 305 1403.57 1026.14 310 1469.09 1082.37 315 1533.77 1141.03 320 1603.14 1205.73 325 1677.51 1273.73 2485 0 to 1139.36 0 to 840.72 330 1757.23 1346.12 1198.59 881.97 335 1842.64 1425.79 1262.17 927.35 340 1934.10 1511.21 1330.39 974.93 345 2032.01 1602.75 1403.57 1026.14 Unit Watts Bar A-19 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 3.1-2 Watts Bar Unit 1 Heatup Limits (Data (Ref.
- 1) plotted on Figure 3.1-5)
TEMPERATURE (OF)
HEATUP HEATUP LEAK TEST CRITICALITY CRITICALITY RATE RATE LIMITS LIMITS LIMITS (60 F/HR)
(100 F/HR)
(60 F/HR)
(100 F/HR) 350 2136.89 1700.67 1469.09 1082.37 355 2248.85 1805.37 1533.77 1141.03 360 2368.47 1917.72 1603.14 1205.73 365 2496.14 2035.38 1677.51 1273.73 370 2632.29 2163.59 1757.23 1346.12 375 2300.46 1842.64 1425.79 380 2446.44 1934.10 1511.21 385 2601.96 2032.01 1602.75 390 2136.89 1700.67 395 2248.85 1805.37 400 2368.47 1917.72 405 2496.14 2035.38 410 2632.29 2163.59 415 2300.46 420 2446.44 425 2601.96 Unit 1 Watts Bar a-20 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR MATERIAL PROPERTY BASIS LIMITING MATERIAL:
INITIAL RT=T LIMITING ART AT 16 INTERMEDIATE SHELL FORGING 05 47 OF FPY: 1/4-T, 3/4-T, 191.7 F
156.7 F
Compos ite 10% Relaxation Cool Down Curves for IntermedIat Shell Forg Ing 05 2500 2000 1 500 a
0.
i0 DE F/HR
-20 DEG F/HR
-4!!P-40DEG F/HR
-"100 DEG F/HR L t-DEG 1 8F/HR i :t711 1 000 500 o 4D l
l I
4 r
l I
l E
I I
1 l
j I
l
,,~
I 50.0 1 00.0 150.0 200.0 Temperature (F) 250.0 300.0 350.0 400.0 Figure 3.1-6 Watts Bar Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100°F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation Errors)
Including 10% Relaxation in Pressure for Temperatures < 241.7 0 F per ASME Code Case N-514 (Plotted Data (Ref. 1) provided on Table 3.1-3)
Unit 1 Watts Bar A-21 Revision 7
DCN D-51236-A lPage 36l TVA
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REACTOR COOLANT SYSTEM N3-68-4001 Unit PTLR Table 3.1-3 Watts Bar Unit Cooldown Limits (Data (Ref. 1) plotted on Fig 3.1-6)
TEMPERATURE (OF) 100 F/R 75 F/HR 60 F/HR 40 F/HR 20 F/SRf 0 OFER 60 276.92 338.02 376.37 428.87 481.43 65 280.19 340.61 378.96 431.45 484.02 70 283.66 343.90 382.25 434.23 486.79 539.14 75 287.50 347.06 385.24 437.22 489.78 542.05 80 291.40 350.44 388.45 440.43 492.99 545.29 85 295.71 354.41 392.07 443.88 496.44 548.77 90 300.44 358.29 395.78 447.59 500.15 552.51 95 305.46 362.79 399.78 451.58 504.14 556.53 100 311.12 367.26 404.24 455.87 508.43 560.86 105 317.11 372.55 409.20 460.49 513.04 565.50 110 323.61 377.85 414.33 465.61 517.99 570.50 115 330.65 383.87 419.83 470.95 523.32 575.87 120 338.09 390.46 426.07 476.68 529.05 581.65 125 345.96 397.30 432.41 482.84 535.21 587.86 130 354.81 404.79 439.37 489.47 541.84 594.43 135 364.33 413.28 447.01 496.59 548.96 601.60 140 374.55 421.96 455.36 504.25 556.61 609.32 145 385.86 431.73 464.27 513.00 564.84 617.62 150 397.79 442.12 473.98 521.85 573.69 626.54 155 410.72 453.34 484.35 531.54 583.20 636.14 160 424.88 465.62 495.43 541.77 593.43 646.32 165 440.32 479.00 507.80 553.28 604.43 657.39 170 456.58 493.38 520.81 565.28 616.25 669.32 175 474.57 508.65 535.22 578.67 628.95 682.13 180 493.69 526.06 550.93 592.67 642.61 695.75 185 514.68 544.15 568.00 608.04 657.30 710.57 190 537.11 564.53 586.34 624.68 673.08 726.48 195 561.74 586.26 606.54 642.50 690.22 743.58 Unit 1 Watts Bar A-22 Revision 7
DCN D-51236-A Page 37 I
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Title:
N3-68-4001 Unit 1 PTLR Table 3.1-3 Watts Bar Unit 1 Cooldown Limits (Data (Ref. 1) plotted on Fig 3.1-6)
TEMPERATURE
(°F) 100 F/HR 75 F/HR 60 F/HR 40 F/HR 20 F/HR l 0 F/HR 200 587.98 609.95 628.52 662.28 708.46 761.83 205 616.42 635.84 652.38 683.58 728.07 781.62 210 647.51 664.04 678.71 706.86 749.65 802.67 215 680.85 694.66 707.12 732.57 772.47 825.54 220 717.05 727.98 738.41 760.30 797.32 850.06 225 756.41 764.64 773.04 791.03 824.33 876.30 230 798.90 804.24 810.62 824.72 853.46 904.45 235 844.81 847.79 851.97 862.19 885.86 934.99 240 894.12 895.25 897.24 903.92 921.36 967.51 241.7 924.36 931.07 929.70 927.11 937.98 968.61 241.7 840.32 846.43 845.18 842.82 860.19 886.34 245 861.52 860.72 861.31 864.02 873.90 911.51 250 912.97 911.88 911.09 911.21 915.45 945.77 255 973.61 965.36 964.42 963.78 982.53 260 1019.03 1019.03 1022.00 265 1064.40 270 1109.98 275 1158.95 280 1211.57 285 1268.05 290 1328.61 295 1393.44 300 1463.21 305 1537.95 310 1618.11 315 1703.92 320 1795.88 325 1894.39 Unit 1 Watts Bar A-23 Revision 7
DCN D-51236-A Page 3?
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 3.1-3 Watts Bar Unit 1 Cooldown Limits (Data (Ref. 1) plotted on Fig 3.1-6)
TEMPERATURE (OF) 100 F/HR 75 F/HR 60 F/HR 40 F/R 20 F/HR 0 F/HR 330 1999.72 335 2112.46 340 2232.88 345 2361.41 Unit Watts Bar A-24 Revsion 7
DCN D-51236-A Page 3
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 4.0-1 Surveillance Capsule Removal Schedule Capsule Vessel Capsule Removal Time Capsule Location Lead (a)(b)
Fluence (deg.)
Factor (n/cm2,E>l.0 a
Me
(
U 56.0 5.39 1.20 5.05 x 1015 (
W 124.0 5.21 3.80 1.23 x 1019"(0 X
236.0 5.37 5.98 1.84 x 1019 C)
Z 304.0 5.21 9.25 2.76 x 101 ()
V h 58.5 4.64 Stand-By Y W 238.5 4.64 Stand-By (a) Effective Full Power Years (EFPY) from plant startup.
(b) Removal times are based on nearest vessel refueling date of ASTM E185-82, Section 7.6.3.4.
Capsules should be removed during the nearest refueling outage to the indicated time.
(c) Updated from Capsule W dosimetry analysis from BWXT Services, Inc.
Report, Section 7 Ref.7).
(d) The fluence is from plant specific evaluation.
(e) The fluence is from plant specific evaluation, and approximates the fluence at Y4 T at end-of-life (32 EFPY).
(f)
This fluence is equal to the calculated peak reactor vessel surface fluence at EOL (32 EFPY).
(g) This fluence is not less than once or greater than twice the peak EOL fluence, and is approximately equal to the peak vessel fluence at 48 EFPY.
(h) These capsules will reach a fluence of 2.8 x 1019 (48 EFPY Peak Fluence) at approximately 10.7 EFPY.
Unit 1 Watts Bar A-25 Revision 7
DCN D-51236-A Paee 4o I
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR TABLE 5.1 Comparison of the Watts Bar Unit 1 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decrease with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Capsule Temperature Shift (ART=m)
Decrease Material Capsule Fluence (x 1019 n/cm2,
E > 1.0 MeV)
Predicted"'
Measured Predicted"")
Measured (OF)
(07)
(b)
()}
Intermediate Shell Forging 05 U
5.05 x 1018 100 98 22 19 (tangential)
Intermediate Shell Forging 05 U
5.05 x 1018 100 29 22 0
(axial)
Weld Metal U
5.05 x o1 33 0
16 0
HAZ Metal U
5.05 x l8--
51 11 Intermediate Shell Forging 05 W
1.23 x 1019 91.3 111 28 26 (tangential)
Intermediate Shell Forging 05 W
1.23 x 1019 91.3 81 28 3
(axial)
Weld Metal W
1.23 x 1019 19.6 31 20 14 HAZ Metal W
1.23 x 1019 50 8
(a)
(b)
(c)
Based on Regulatory Guide 1.99, Revision 2, methodology using mean weight percent values o cu and Ni of the surveillance material.
Calculated using measured Charpy data plotted using CVGRAPH, Version 4.1 (Ref. 6) for Capsule U.
Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0 (Ref. 7) for Capsule W.
Values are based on the definition of upper shelf energy given in ASTM E185-82.
Unit 1 Watts Bar A-26 Revision 7
DCN D.51236-A Page 41 I
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR TABLE 5.2 Watts Bar Unit 1 Calculation of Chemistry Factors Using Surveillance Capsule Data (32 EFPY)
Material Capsule Fluence FF Measured FF*,RT FF2 (n/cmO, ARTwT (OF)
E > 1.0 lIF)
Intermediate Shell Forging 05 U
5.05 x1018 0.81 98.0 79.4 0.66 (Tangential)
W 1.23 x10"9 1.06 111.0 117.7 1.12 Intermediate Shell Forging 05 U
5.05 x101' 0.81 29.0 23.5 0.66 (Axial)
W 1.23 101' 1.06 81.0 85.9 1.12 Sum:
306.5 3.56 Chemistry Factor 86.1 Weld Metal U
5.05 x10 1 0.81 0.0 0.0 0.66 W
1.23 x101 '
1.06 31.0 32.9 1.12 Sum:
32.9 1.78 Chemistry Factor = 18.5 Unit 1 Watts Bar A-27 Revision 7
DCN D-51236-A TVA Page +2.
Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR TABLE 5.3 Watts Bar Unit 1 Reactor Vessel Toughness Table (Unirradiated)
Material Description Cu ()(a)
Ni (%)'))
Initial RTT(
) (
b )
Closure Read Flange 0.13 0.75
-42 Vessel Flange 0.92
-40 {e)
Intermediate Shell Forging 05 0.17 0.80 47 Lower Shell Forging 04 0.08 0.83 5
Circumferential Weld 0.05 0.70
-43 NOTES:
a)
Average values of copper and nickel weight percent.
b)
Initial RT=,
values are measured values.
c)
Used in the consideration of flange requirements for heatup/cooldown curves. Per methodology given in WCAP-14040, the minimum boltup temperature is 60 0F.
TABLE 5.4 Watts Bar Unit 1 Reactor Vessel Surface Fluence Values at 16 EFPY (n/cm?, E > 1.0 MeV)
Unit 1 Watts Bar A-28 Revision 7
DCN D-51236-A Page 43 I
Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR 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 16 EFPY Component 1
16 EFPY a) 1/4-T (F) 3/4-T (F)
Intermediate Shell Forging 05 191.7 156.7 Lower Shell Forging 04 81.8 68.2 Circumferential Weld 70.0 52.0 NOTES:
(a) Calculated using the peak vessel fluence of 9.34 x 10 1/cm2 (E >
1.0 eV).
(b) Used to generate the heatup/cooldown curves.
Unit 1 Watts Bar A-29 Revision 7
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Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR TABLE 5.6 Calculation of Adjusted Reference Temperatures at 16 EFPY for the Limiting Watts Bar Unit 1 Reactor Vessel Material (Intermediate Shell Forging 05)
Parameter Values Operating Time 16 EFPY Material Inter.
Inter.
Shell Shell Forging 05 Forging 05 Location 1/4-T 3/4-T Chemistry Factor (CF),
F 132 132 Fluence f), *101" n/cmr (E > 1.0 MeV) 0.561 0.2033 (a)
Fluence Factor (FF) ()
0.839 0.573 ARE CF x FF, OF 110.7 75.7 Initial RTr (I),
F 47 47 Margin M),
F (c) 34 34 ART - I + (CFxFF) + M, F
191.7 156.7 per Regulatory Guide 1.99, Revision 2 NOTES:
(a) Fluence, f, is based upon frfs 9.34 x 10 Icm2.
The Watts Bar Unit 1 reactor vessel wall thickness is 8.465 inches at the beltline region.
(b) FF f.
2
- O.lOlog fa (c) Margin is calculated as M 2(0+/-2 +
42)05.
The standard deviation for the initial RT= margin term, i, is 0 F since the initial RTMT value is a measured value.
The standard deviation for the ART margin term, om, is 17 F for the forging, except that a need not exceed 0.5 times the mean value of ART=T.
Unit 1 Watts Bar A-30 Revision 7
DCN D-51236-A TVA l Page 45
Title:
REACTOR COOLANT SYSTEM N3-68-4001 Unit 1 PTLR Table 5.7 Watts Bar Unit 1 Reactor Vessel Surface Fluence Values at 32 and 48 EFPY (n/ce2, E > 1.0 MeV)
EFPY 0O 150 30° 450 32 9.83 x 1015 1.44 x 10"s 1.55 x 10l 1.84 x 109 48 1.47 x 1019 2.16 x 10" 2.32 x 1019 2.76 x 109 TABLE 5.8 RTTs Values for Watts Bar Unit 1 for 32 EPY Surface RTmn Material CF Fluence (CF x FF)
I M
RTpN
(°F)
(n/cm2, FF
(°F)
("F)
(OF)
(°F)
E > 1.0 MeV)
Inter. Shell Forging 05 132 1.84 x 10l" 1.17 154.1 47 34 235 Lower Shell Forging 04 51 1.84 x 10l9 1.17 59.5 5
34 99 Circ. Weld 68 1.84 x 10"9 1.17 79.4
-43 56 92 TABLE 5.9 RTp"z Values for Watts Bar Unit 1 for 48 EFPY Surface RTM CF Fluence (CF x I
M RTpT8 Material
(°F)
(n/cm2, FF FF)
(OF)
(OF)
(°F)
E > 1.0 MeV)
(OF)
Inter. Shell Forging 05 132 2.76 x 1019 1.27 167.7 47 34 249 Lower Shell Forging 04 51 2.76 x 109" 1.27 64.8 5
34 104 Circ. Weld 68 2.76 x 10" 1.27 86.4
-43 56 99 Unit 1 Watts Bar A-31 Revision 7
Unit 1 PTLR SOURCE NOTES
- 1.
NCO820285003
- 2.
NCO820285004 Unit 1 Watts Bar A-32 Revision 7