ML20135E814
| ML20135E814 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/30/1996 |
| From: | FRAMATOME |
| To: | |
| Shared Package | |
| ML20135E801 | List: |
| References | |
| 77-1258569-01, 77-1258569-1, NUDOCS 9612120076 | |
| Download: ML20135E814 (21) | |
Text
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77-1258569-01 November 1996 i
1 Arkansas Nuclear One - Unit 1 Pressure-Temperature Limits for 32 EFPY
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FTl NON-PROPRIETARY Arkansas Nuclear One - Unit 1 Pressure-Temperature Limits for 32 EFPY B&W Document I.D. 77-1258569-01 November 1996 l
l Prepared for Entergy Operations, Inc.
Prepared by: M%v 11 /1 8 /9 (,
(Te3nical Prepardr)
Reviewed by: '
ee7 ///8!fC (Technical Reviewer)' '
Approved by: [ s/t4 l (Product Manager) l l
Approved by: /
80/ / /[N[
' (Technical Manag'er)
Framatome Technologies, Inc.
Engineering Services Integrated Nuclear Service Business Unit P. O. Box 10935 1 Lynchburg, Virginia 24506-0935
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i RECORD OF REVISION i Pages ,
- Revision Added/
Number Chanced Descriotion r 00 All Original release ;
01 Cover / Updated revision number of document 't Title Page l ii - v Insertion of record of revision page 6 Corrected typographical error on number of figures. l 3
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t CONTENTS i
e Page
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- 1. I N TR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 2. DEVELOPMENT OF PRESSURE-TEMPERATURE LIMITS . . . . . . . . . . . 2
- 3. R E S U LTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
- 4. REFERENCES ........................................... 15 s
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List of Fiaures l
Figure Title Page
- 1. Normal Operation Heatup P/T Limits for 50F/hr at 32 EFPY . . . . . . . . . . . . . 10
- 2. Normal Operation Heatup P/T Limits for 70F/hr at 32 EFPY . . . . . . . . . . . . 11
- 3. Normal Operation Heatup P/T Limits for 90F/hr at 32 EFPY , . . . . . . . . . . . 12
- 4. Normal Operation Cooldown P/T Limits for 32 EFPY .................. 13
- 5. ISLH Heatup and Cooldown for 32 EFPY , . . . . . . . . . . . . . . . . . . . . . . . . . . 14 i
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List of Tables Table Title Page
- 3. Operational Constraints for Plant Heatup .......................... 4
- 4. Operational Constraints for Plant Cooldown . . . . . . . . . . . . . . . . . . . . . . . . 5
- 5. Normal Operation Heatup P/T Limits for 32 EFPY .................... 7
- 6. Normal Operation Cooldown P/T Limits for 32 EFPY .................. 8
- 7. ISLH Heatup and Cooldown P/T Limits for 32 EFPY . . . . . . . . . . . . . . . . . . . 9 i
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! 1. INTRODUCTION This report provides the Arkansas Nuclear One - Unit 1 reactor coolant Technical Specification pressure-temperature operating limits for 32 EFPY, The pressure-temperature limits are generated for normal operation heatup, normal operation cooldown, inservice leak and hydrostatic tests (ISLH), and for reactor core operations. !
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- 2. DEVELOPMENT OF PRESSURE-TEMPERATURE LIMITS The pressure-temperature limits for the reactor coolant pressure boundary (RCPB) of Arkansas Nuclear One, Unit 1 are established in accordance with the requirements of -
10 CFR Part 50, Appendix G'. The methods and criteria employed to establish operating 8
pressure and temperature limits are described in topical report BAW-10046A . The objective of these limits is to prevent nonductile failure during any normal operating l
condition, including anticipated operation occurrences and system hydrostatic tests. The l loading conditions of interest include the following:
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l a. Normal operations, including heatup and cocidown.
- b. Inservice leak and hydrostatic tests.
- c. Reactor core operation. .
The major components of the RCPB have been analyzed in accordance with 10CFR50, Appendix G. The closure head region, the reactor vessel (RV) outlet nozzle and the
! beltline region have been identified as the only regions of the reactor. vessel (and consequently of RCPB) that require the pressure-temperature limits.
! The limit curves for Arkansas Nuclear One, Unit 1 are based on the predicted value of the adjusted reference temperature of the limiting beltline region material at the end of thirty-two EFPY. The adjusted reference temperatures are calculated by adding the l
predicted radiation-induced ARTuor to the initial RTwor plus the margin term. The predicted ARTuor is calculated using the fluence and weld chemistry of the vessel's limiting bettine region material. Table 1 summarizes the predicted reactor vesselinside surface peak fluence value as well as the inside surface fluence value at the limiting weld material. Regulatory Guide 1.99 Revision 28 was used to predict the radiation-induced ARTuoy values as a function of the material's copper and nickel content and neutron fluence. Using the fluence value and chemistry of the limiting weld, the ART i
values of the beltline region at the end of thir(-two full-power year were determined and j l
provided in Table 2. The ART values are given for % t and % t vessel wall locations (t l
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= wall thickness). The assumed RT,of the closure head region and the outlet nozzle steel forgings is 60 F, in accordance with BAW-10046A.
Using the methodology documented in BAW-10046A, pressure-temperature limits for the closure head region, the outlet nozzle and the beltline region were determined for the l
- l l heatup and cooldown rates summarized in Tables 3 and 4 as well as for steady-state i 1 l conditions. Differential pressure corrections were then applied to the unadjusted P/T i limits to account for the pressure differential between the analyzed regions of the reactor j vessel and the system pressure sensor location in the reactor coolant system. The 4
maximum allowable pressure as a function of fluid temperature is obtained through a point-by-point comparison of the three limiting regions, adjusted for sensor location. The I maximum allowable pressure is taken to be the lowest of the calculated allowable pressures (due to the applicable heatup or cooldown rate and steady-state conditions) l for a given time point. The resulting loci of these points determine the bounding P/T l Technical Specification curves. Instrument errors for pressure and temperature were not applied to the Technical Specification limits provided in Figures 1 through 3. I I
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Table 1. Arkansas Nuclear One. Unit 132 EFPY RV. Inside Surface FluenceW Summary of Fluence in the RV Fluence Value, n/cm 2 Peak Surface Fluence 0.871 E19 Fluence at Limiting Location (WF-112) 0.835 E19 l
l Table 2. Arkansas Nuclear One. Unit 132 EFPY RTeor-(1)
I Limiting Location in RV RTuor values at 32 EFPY 1/4t ( F) 3/4t ( F) l i
Weld, WF-112* 212 164 l
- Upper Shell to Lower Shell Circumferential Weld Table 3. Operational Constraints for Plant Heatuo I. Plant Heatup Rates RC Temperature Range Maximum Heatup Rate 60 'F < T s 84 'F s 15 "F in any one hour period T > 84 F < 50 *F/hr,70 F/hr or 90 F/hr ll. RC Pump Constraints during Plant Heatup RC Temperature Range Pump Constraints T < 84 F ,
No RCP running 84 F s T < 225 "F No more than 2 pumps (2/0 pump combination recommended) 225 F s T s 300 F No more than 3 pumps (2/1 pump combination recommended)
T > 300 F None )
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{ l l Table 4. Operational Constraints for Plant Cooldown l
- 1. Plant Cooldown Rates RC Temperature Constraints Maximum Cooldown Rate
- a. T 2: 280 *F 50 *F in any 1/2 hour period l b. For tripping of last two RCP between 200 'F and 255 *F only*
l 150 F s T < 280 'F s 25 F in any 1/2 hour period
- c. T < 150 'F s 25 F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period i
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- Note, tripping of last two RCP below 200 'F and down to 150 F is also permitted, but the cooldown rates in item (b) are modified as follows: ,
i 180 F < T < 280 'F s 25 F in any 1/2 hour period i 150 'F s T s 180 'F 30 'F in 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 1
II. RC Pump Constraints during Plant Cooldown j
RC Temperature Range Pump Constraints !
T > 255 *F None I 150 F s T - s 255 *F No more than 2 pumps (2/0 pump combination recommended with restrictions as noted in item (lb), above). l T < 150 'F No RCP running 1
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- 3. RESULTS The P/T Technical Specification limits for Arkansas Nuclear One, Unit 1 through 32 l EFPY for normal heatup, normal cooldown, inservice leak and hydrotests, and reactor core operation, as required by 10CFR50, Appendix G are provided in Figures 1 through !
- 5. The normal heatup P/T limits are provided for heatup rates of 50 F/hr,70 F/hr and ;
90 F/hr in Figures 1 through 3, respectively. The P/T limits for normal cooldown are l provided in Figure 4. The inservice leak and hydrotest P/T limit is given in Figure 5.
These P/T limits have invoked additional operational constraints, identified in Tables 3 and 4, that must be maintained for future operation.
Protection against nonductile failure is ensured by maintaining the reactor coolant system ;
pressure below the upper limits of the pressure-temperature limit curves. The l acceptable pressure and temperature combinations for reactor vessel operation are j l
below and to the right of the limit curve. The reactor is not permitted to be critical until i the pressure-temperature combinations are to the right of the criticality limit curve. l i
- The numerical values for the Technical Specification P/T curves provided in Figures 1 !
through 5 are given in Tables 5 through 7. i i
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Table 5. Normal Operation Heatup P/T Limits for 32 EFPY, ANO-1 Unit 1 l l
t I l (a) Normal Operation Heatup P/T Limits 50 F/hr Heatup Limit 70 F/hr Heatup Limit 90 F/hr Heatup Limit l Indicated Indicated Indicated Indicated Indicated Indicated l RCS Inlet Pressure, RCS Inlet Pressure, RCS Inlet Pressure, Temp., F Temp., F psig Temp., F psig psig 63 343 63 309 63 276 130 343 130 309 130 276 145 352 145 309 145 276 I 160 369 160 315 160 276 175 394 175 330 175 281 190 426 190 352 190 294 ,
220 512 220 413 220 333 250 638 250 523 250 417 I 290 857 290 794 290 635 330 1227 330 1141 330 1015 360 1694 360 1564 360 1449 385 2250 385 2074 385 1914 393 2250 395 2140 l
399.5 2250 (b) Criticality Limit Curve For 50 F/hr Heatup Rate For 70 F/hr Heatup Rate For 90 F/hr Heatup Rate Indicated Indicated Indicated Indicated Indicated Indicated RCS Inlet Pressure, RCS Inlet Pressure, RCS Inlet Pressure, Temp., F psig Temp., F psig Temp., F psig 365 0 372 0 379 0 365 1166 372 1164 379 1140 375 1292 390 1403 400 1449 385 1437 400 1564 415 1708 j 400 1694 425 2074 435 2140 l
425 2250 433 2250 439.5 2250 1 1
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- Table 6. Normal Operatior, Cooldown P/T Limits for 32 EFPY, ANO-1 Unit 1 l~
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Indicated RCS Inlet Indicated RCS Pressure (at )
Temperature, F RCS "A" Hot Leg Tap),- l psig l
377 2250
! 330 1494 ;
i 300 1090 280 895 270 794 l 250 626 l 225 527 200 436 l 180 383 l
60 348 ,
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Table 7. ISLH Heatup and Cooldown P/T Limits for 32 EFPY, ANO-1 Unit 1 .
Indicated RCS Inlet Indicated RCS Pressure (at Temperature, F RCS "A" Hot Leg Tap), 1 psig
- i 60 395 ,
t 160 395 j 205 442 225 479 250 588 748 275 1 300 964 [
325 1299 t l 350 1753 ;
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s Figure 5. ISLH Heatup and Cooldown for 32 EFPY - Arkansas Nuclear One Unit 1 Tech. Spec. ISLH Heatup and Cooldown Limitation for 32 EFPY ,
2600 2400 ,
g 2200 a
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a f1800 e s
E 1600 /
1 P 1400 /
2 1200
- 2 1000 /
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200 0
0 50 100 150 200 250 300 350 400 ladicated Reactor Coolant inlet Temperature, F
__ .-. . . - . -. - . . . = - - - - - . - - . _. - -.
l e o*s l l 4. REFERENCES 1
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- 1. Code of Federal Regulation, Title 10, Part 50, Appendix G, " Fracture Toughness ,
, l l Requirements, " Federal Register, Vol,48, No.194, May 17,1983.
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H.W. Behnke, et al, " Methods of Compliance with Fracture Toughness and 2.
Operational Requirements of 10CFR50, Appendix G," BAW-10046A, Rev. 2, B&W, Lynchburg, Virginia, June 1986.
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- 3. U.S. Nuclear Regulatory Commission, " Radiation Damage to Reactor Vessel !
1 Material," Regulatory Guide 1.99, Revision 2, May 1988. ;
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- 5. FTl Document 32-1257716-00, " Alt. Calc for 32-1245917-00," July 1996.
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