L-07-130, Submittal of Pressure and Temperature Limits Report, Revision 4

Submittal of Pressure and Temperature Limits Report, Revision 4

ML072670026
Person / Time
Site:	Beaver Valley
Issue date:	09/19/2007
From:	Sena P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-07-130
Download: ML072670026 (14)

Text

FENOC FirstEnergy Nuclear OperatingCompany PeterP. Sena 111 724-682-5234 Site Vice President Fax: 724-643-8069 September 19, 2007 L-07-130 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Unit 1 Pressure and Temperature Limits Report, Revision 4 FirstEnergy Nuclear Operating Company (FENOC) hereby submits revised pages of the Pressure and Temperature Limits Report (PTLR) for Beaver Valley Power Station (BVPS) Unit No. 1 as required by Section 5.6.4 of the BVPS Technical Specifications.

Revision 4 of the BVPS Unit No. 1 PTLR is enclosed.

The revisions to the Unit No. 1 PTLR, effective September 18, 2007, were made to change the applicability of the heatup and cooldown requirement to 30 effective full power years.

No regulatory commitments are contained in this submittal. If there are questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

FENOC Fleet Licensing, at (330) 761-6071.

Sincerely,

ý6ip-P 4E Peter P. Sena III

Enclosure:

Beaver Valley Power Station Unit No. 1, Pressure and Temperature Limits Report, Revision 4 c: Ms. N. S. Morgan, NRR Project Manager Mr. D. L. Werkheiser, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP) Aot/

L-07-130 Enclosure Beaver Valley Power Station Unit No. 1 Pressure and Temperature Limits Report Revision 4

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.1.3 OPPS Enable Temperature (LCO 3.4.12)

Two different temperatures are used to determine the OPPS enable temperature, they are the arming temperature and the calculated enable temperature. The arming temperature (when the OPPS rendered operable) is established per ASME Section Xl, Appendix G. At this temperature, a steam bubble would be present in the pressurizer, thus reducing the potential of a water hammer discharge that could challenge the piping limits. Based on this method, the arming temperature is 3470 F.

The calculated enable temperature is based on either a RCS temperature of less than 200OF or materials concerns (reactor vessel metal temperature less than 0

RTNDT + 50 F), whichever is greater. The calculated enable temperature does not address the piping limit attributed to a water hammer discharge. The calculated enable temperature is 318 0 F.

As the arming temperature is higher and, therefore, more conservative than the calculated enable temperature, the OPPS enable temperature, as shown in Table 5.2-3, is set to equal the arming temperature.

The calculation method governing the heatup and cooldown of the RCS requires the arming of the OPPS at and below the OPPS enable temperature specified in Table 5.2-3, and disarming of the OPPS above this temperature. The OPPS is required to be enabled, i.e., OPERABLE, when any RCS cold leg temperature is less than or equal to this temperature.

From a plant operations viewpoint the terms "armed" and "enabled" are synonymous when it comes to activating the OPPS. As stated in the applicable operating procedure, the OPPS is activated (armed/enabled) manually before entering the applicability of LCO 3.4.12. This is accomplished by placing two keylock switches (one in each train) into their "automatic" position. Once OPPS is activated (armed/enabled) reactor coolant system pressure transmitters will signal a rise in system pressure above the OPPS setpoint. This will initiate an alarm in the control room and open the OPPS PORVs.

5.2.1.4 Reactor Vessel Boltup Temperature (LCO 3.4.3)

The minimum boltup temperature for the Reactor Vessel Flange shall be > 600F.

Boltup is a condition in which the reactor vessel head is installed with tension applied to any stud, and with the RCS vented to atmosphere.

PTLR Revision 4 Beaver Valley Unit 1 5.2 - 3 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.3 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values shown were used as inputs to the P/T limits.

Table 5.2-4, taken from Reference 5, shows the calculation of the surveillance material chemistry factors using surveillance capsule data.

Table 5.2-4a, taken from Reference 2, shows the Calculation of Chemistry Factors based on St. Lucie and Fort Calhoun Surveillance Capsule Data.

Table 5.2-4b, taken from Reference 3, shows the St. Lucie and Fort Calhoun Surveillance Weld Data.

Table 5.2-5, taken from Reference 2, provides the reactor vessel beltline material property table.

Table 5.2-6, taken from Reference 12, provides a summary of the Adjusted Reference Temperature (ARTs) for 30 EFPY.

Table 5.2-7, taken from Reference 12, shows the calculation of ARTs for 30 EFPY.

Table 5.2-8 shows the Reactor Vessel Toughness Data (Unirradiated).

Table 5.2-9, taken from Reference 5, provides RTPTS values for 28 EFPY.

Table 5.2-10, taken from Reference 11, provides RTPTS values for 54 EFPY.

PTLR Revision 4 Beaver Valley Unit 1 5.2 - 5 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.4 References

1. WCAP-14040-NP-A, Revision 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," J. D. Andrachek, et al., January 1996.

2. WCAP-1 5570, Revision 2, "Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," T. J. Laubham, April 2001.

3. WCAP-1 5571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," C. Brown, et. al., November 2000.

4. WCAP-8475, "Duquesne Light Company, Beaver Valley Unit No. 1 Reactor Vessel Radiation Surveillance Program," J. A. Davidson, October 1974.

5. WCAP-1 5569, "Evaluation of Pressurized Thermal Shock for Beaver Valley Unit 1," C. Brown, et al., November 2000.

6. 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements," Federal Register, Volume 60, No. 243, December 19, 1995.

7. 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," May 15, 1991. (PTS Rule)

8. Regulatory Guide 1.99, Rev. 2, "Radiation Embrittlement of Reactor Vessel Materials," U.S. Nuclear Regulatory Commission, May 1988.

9. Deleted

10. FirstEnergy Nuclear Operating Company letter L-01-157, "Supplement to License Amendment Requests Nos. 295 and 167," dated December 21, 2001.

11. WCAP-1 5571, Supplement 1, "Analysis of Capsule Y from FirstEnergy Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," B. N. Burgos, June 2007.

12. WCAP-16799-NP, Revision 1, "Beaver Valley Power Station Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," B. N. Burgos, June 2007.

13. FENOC-07-120, Transmittal of LTOPS Setpoint Analysis Report, July 26, 2007.

14. Westinghouse Calculation CN-SCS-07-27, Rev. 0, LTOPS Setpoint Evaluation for Beaver Valley Unit 1 at 30 EFPY.

PTLR Revision 4 Beaver Valley Unit 1 5.2 - 6 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE LIMITING ART VALUES AT 30 EFPY: 1/4T, 245.7-F 3/4T, 207.6-F 2800 2250 2000 1760 1500 1250 1000 750 600 Criticality Limit based on inservico hydrostatic test temperature (302*F) for the 260 service period up to 30 EFPY 0

0 50 100 150 200 260 300 360 400 460 600 560 INDICATED TEMPERATURE ('F)

Figure 5.2-1 (Page 1 of 1)

Reactor Coolant System Heatup Limitations Applicable for the First 30 EFPY (LCO 3.4.3)

PTLR Revision 4 Beaver Valley Unit I 5.2- 7 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 MATERIAL PROPERTY BASIS LIMITING MATERIAL: LOWER SHELL PLATE LIMITING ART VALUES AT 30 EFPY: 1/4T, 245.7 0 F 3/4T, 207.60 F 26000 2260 2000 1760 1600 1260 1000 760 600

~20OFIHr

• 40*FIHr 60*FIHr 100*FIHr 260 ' Boltup Temperature

/ /I *~~60"F *--

0 0 60 100 ISO 200 250 300 350 400 450 600 650 INDICATED TEMPERATURE (oF)

Figure 5.2-2 (Page 1 of 1)

Reactor Coolant System Cooldown Limitations Applicable for the First 30 EFPY (LCO 3.4.3)

PTLR Revision 4 Beaver Valley Unit 1 5.2- 8 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-1 (Page 1 of 1)

Heatup Curve Data Points for 30 EFPY (LCO 3.4.3) 100°F/hr 100°F/hr 100OFIhr Heatup Heatup Criticality T P T P T P (OF) (psig) (OF) (psig) (OF) (psig) 60 0 245 840 302 0 60 554 250 876 302 981 65 554 255 917 305 1010 70 554 260 961 310 1064 75 554 265 1010 315 1124 80 554 270 1064 320 1189 85 554 275 1124 325 1262 90 554 280 1189 330 1342 95 554 285 1262 335 1431 100 554 290 1342 340 1528 105 554 295 1431 345 1636 110 554 300 1528 350 1754 115 554 305 1636 355 1885 120 554 310 1754 360 2029 125 554 315 1885 365 2151 130 554 320 2029 370 2282 135 554 325 2151 375 2426 140 555 330 2282 376.8 2485 145 557 335 2426 150 560 336.8 2485 155 563 160 567 165 573 170 579 175 585 180 593 185 602 190 613 195 624 200 637 205 651 210 667 215 685 220 705 225 727 230 751 235 778 240 807 284 302 Leak Test Limit Temperature (OF)

Pressure (psig) 2000 2485 PTLR Revision 4 Beaver Valley Unit 1 5.2- 10 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-2 (Page 1 of 2)

Cooldown Curve Data Points for 30 EFPY (LCO 3.4.3)

Steady State 2 0 °F/hr 4 0 °F/hr 6 0 °F/hr 1OO0 Flhr T P T P T P T P T P (OF) (psig) (OF) (psig) (OF) (psig) (OF) (psig) (OF) (psig) 60 0 60 0 60 0 60 0 60 0 60 621 60 606 60 563 60 518 60 425 65 621 65 607 65 563 65 519 65 426 70 621 70 608 70 564 70 519 70 427 75 621 75 609 75 565 75 520 75 428 80 621 80 611 80 567 80 522 80 429 85 621 85 612 85 568 85 523 85 430 90 621 90 614 90 570 90 525 90 432 95 621 95 616 95 571 95 526 95 433 100 621 100 618 100 574 100 528 100 435 105 621 105 620 105 576 105 531 105 438 110 621 110 621 110 578 110 533 110 441 115 621 115 621 115 581 115 536 115 444 120 621 120 621 120 585 120 540 120 448 125 621 125 621 125 588 125 544 125 452 130 621 130 621 130 592 130 548 130 457 135 621 135 621 135 597 135 553 135 462 140 621 140 621 140 602 140 558 140 468 145 621 145 621 145 607 145 564 145 475 150 621 150 621 150 614 150 571 150 483 155 621 155 621 155 621 155 578 155 491 160 621 160 621 160 621 160 586 160 501 165 621 165 621 165 621 165 595 165 512 170 621 170 621 170 621 170 606 170 524 175 621 175 621 175 621 175 617 175 537 180 621 180 621 180 621 180 621 180 552 180 747 180 708 180 669 180 630 185 569 185 758 185 720 185 682 185 644 190 588 190 771 190 733 190 696 190 660 195 608 195 784 195 748 195 713 195 677 200 631 200 800 200 765 200 730 200 697 205 657 205 816 205 783 205 750 205 718 210 685 210 835 210 803 210 772 210 742 215 717 215 856 215 825 215 796 215 768 220 752 220 878 220 850 220 823 220 797 225 791 225 903 225 877 225 853 225 830 230 835 230 931 230 908 230 886 230 866 235 883 235 962 235 941 235 922 235 906 240 936 240 996 240 978 240 962 240 950 245 995 245 1033 245 1019 245 1007 245 999 250 1053 250 1075 250 1064 250 1056 250 1053 255 1111 PTLR Revision 4 Beaver Valley Unit 1 5.2- 11 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-2 (Page 2 of 2)

Cooldown Curve Data Points for 30 EFPY (LCO 3.4.3) I Steady State 2 0 °F/hr 4 0 °Flhr 6 0 °F/hr lOO0 F/hr T P T P T P T P T P (OF) (psig) (OF) (psig) (OF) (psig) (OF) (psig) (OF) (psig) 255 1121 255 1114 255 1111 255 1111 260 1169 260 1171 260 1169 260 1169 260 1169 265 1227 265 1227 265 1227 265 1227 265 1227 270 1289 270 1289 270 1289 270 1289 270 1289 275 1357 275 1357 275 1357 275 1357 275 1357 280 1433 280 1433 280 1433 280 1433 280 1433 285 1516 285 1516 285 1516 285 1516 285 1516 290 1608 290 1608 290 1608 290 1608 290 1608 295 1710 295 1710 295 1710 295 1710 295 1710 300 1823 300 1823 300 1823 300 1823 300 1823 305 1947 305 1947 305 1947 305 1947 305 19,47 310 2085 310 2085 310 2085 310 2085 310 2085 315 2237 315 2237 315 2237 315 2237 315 2237 320 2405 320 2405 320 2405 320 2405 320 2405 322.1 2485 322.1 2485 322.1 2485 322.1 2485 322.1 2485 PTLR Revision 4 Beaver Valley Unit I 5.2 -12 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-3 (Page 1 of 1)

Overpressure Protection System (OPPS) Setpoints (LCO 3.4.12)

FUNCTION SETPOINT OPPS Enable Temperature 347 0 F PORV Setpoint _ 397 si PTLR Revision 4 Beaver Valley Unit 1 5.2- 13 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-6 (Page 1 of 1)

Summary of Adjusted Reference Temperature (ARTs) for 30 EFPY 30 EFPY MATERIAL DESCRIPTION 1/4T ART(°F)(a) 3/4T ART(oF)(a)

Intermediate Shell Plate B6607-1 201.4 175.8 Intermediate Shell Plate B6607-2 231.4 205.8 Lower Shell Plate B7203-2 176.2 151 Lower Shell Plate B6903-1 243.2 205.7

- Using S/C Data(b) 245.7 207.6 Intermediate Shell Longitudinal Weld 19-714A/B 161.9 115.4

- Using S/C Data(b) 159.6 113.8 Intermediate to Lower Shell Circ. Weld 11-714 163.4 131.7

- Using SIC Data (c) 93.0 71.4 Lower Shell Longitudinal Weld 20-714A/B 176.8 125.8

- Using S/C Data(d) 187.5 133.2 Notes:

(a) ART = I +ARTNDT + M.

(b) Based on Beaver Valley Unit 1 surveillance data. (Data not credible. ART calculated with a full oh.)

(c) Based on credible St. Lucie Unit 1 surveillance data.

(d) Based on Fort Calhoun Unit 1 surveillance data. (Data not credible. ART calculated with a full OA.)

PTLR Revision 4 Beaver Valley Unit 1 5.2- 18 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-7 (Page 1 of 1)

Calculation of Adjusted Reference Temperatures (ARTs) for 30 EFPY Parameter VALUES Operating Time 30 EFPY Material Plate B6903-1 Plate B6903-1 Location Lower Shell Lower Shell Plate Plate 1/4T ART(°F) 3/4T ART(°F)

Chemistry Factor, CF (OF) 149.2 149.2 Fluence (f), n/cm2 (E>1.0 Mev)(a) 2.4194 x 10'9 9.404 x 1015 Fluence Factor, FF 1.238 .9828 ARTNDT = CF x FF(OF)(c) 184.7(c) 146.6 Initial RTNDT, I(OF)(a) 27 27 Margin, M(°F) 34(c) 34 ART = I+(CF*FF)+M, OF(b) per RG 1.99, Revision 2 245.7 207.6 Notes:

(a) Initial RTNDT values are measured values for plate material.

(b) This value was rounded per ASTM E29, using the "Rounding Method."

(c) Based on Beaver Valley Unit 1 surveillance data. (Data not credible.

ART calculated with a full GA.)

PTLR Revision 4 Beaver Valley Unit 1 5.2- 19 LRM Revision 58

Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-10 (Page 1 of 1)

RTpTs Calculation for Beltline Region Materials at Life Extension (54 EFPY)

Fluence N (a) (b)

Material (1019 n/cm 2, FF CF A RTpTS Margin RTNDT(U) RTPTS (OF) (OF) (OF) (OF) (OF)

E>1.0 MeV)

Intermediate Shell Plate B6607-1 6.06 1.44 100.5 144.6 34 43 221.6 Intermediate Shell Plate B6607-2 6.06 1.44 100.5 144.6 34 73 251.6 Lower Shell Plate B7203-2 6.09 1.44 98.7 142.1 34 20 196.1 Lower Shell Plate B6903-1 6.09 1.44 147.2 211.9 34 27 272.9

-- Using S/C Data(e) 6.09 1.44 149.2 214.7 34 27 275.7 Inter. Shell Long. Weld 19-714A/B 1.17 1.04 191.7 200.1 65.5 -56 209.6

-> Using S/C Data(e) 1.17 1.04 188.8 197.1 65.5 -56 206.6 Lower Shell Long. Weld 20-714A/B 1.17 1.04 210.5 219.7 65.5 -56 229.2

-- Using S/C Data(f) 1.17 1.04 223.9 233.7 65.5 -56 243.2 Circumferential Weld 11-714 6.07 1.44 124.3 178.8 65.5 -56 188.3

-> Using S/C Data(d) 6.07 1.44 84.8 122.0 44 -56 110.0 Notes:

(a) Initial RTNDT values of the plate material are measured values while the weld material values are generic.

(b) RTPTS = RTNDT(U) + ARTPTS + Margin (°F).

(c) ARTPTs= CF

• FF.

(d) Based on credible St. Lucie Unit 1 surveillance data.

(e) Based on non-credible Beaver Valley Unit 1 surveillance data with a full Ca.

(f) Based on non-credible Fort Calhoun Unit 1 surveillance data with a full oFA.

PTLR Revision 4 Beaver Valley Unit 1 5.2 -22 LRM Revision 58