View source for ULNRC-05219, Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program

{{Adams
| number = ML053050444
| issue date = 10/21/2005
| title = Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program
| author name = Young K
| author affiliation = AmerenUE, Union Electric Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000483
| license number = 
| contact person = 
| case reference number = ULNRC-05219
| document type = Letter type:ULNRC, Report, Technical
| page count = 28
}}

=Text=
{{#Wiki_filter:Union Electric                                                                   PO Box 620 Callaway Plant                                                                   Fulton, AIO 65251 October 21, 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen:                                             ULNRC-05219 wAmeren                                       DOCKET NUMBER 50483 UE                                      CALLAWAY PLANT UNIT 1 FIGURE 14.9 CALLAWAY PLANT PRESSURE AND TEMPERATURE LIMITS REPORT Attached is the Callaway Plant Pressure and Temperature Limits Report (PTLR), Revision 4. Revision 4 incorporates changes associated with the Replacement Steam Generator Program. This report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.6.c.
If you have any questions concerning this report, please contact us.
Very truly yours, Keith D. Young Manager, Regulatory Affairs DJW/jdg

==Attachment:==
Callaway Pressure and Temperature Limits Report, Revision 4 00l a subsidiary of Ameren Corporation

ULNRC-05219 October 21, 2005 Page 2 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Mr. Ron Reynolds Director Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102

E1 70.0130
* FIGURE 14.9 CALLAWAY PLANT PRESSURE AND TEMPERATURE LIMITS REPORT Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section                                                    Page 1.0      Reactor Coolant System (RCS) PRESSURE AND        1 TEMPERATURE LIMITS REPORT (PTLR) 2.0       Operating Limits                                 1 2.1  RCS Pressure and Temperature Limits         1 2.2 Cold Overpressure Mitigation System          1 3.0       Reactor Vessel Material Surveillance Program     9 4.0       Reactor Vessel Surveillance Data Credibility     9 5.0       Supplemental Data Tables                        16 6.0       References                                      16 Callaway Plant                                 i            Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures Figure                                                                       Page 2.1-1     Callaway Plant Reactor Coolant System Heatup Limitations            3 (Heatup Rates of 60&deg; and 1000F/hhr) Applicable to 20 EFPY (With Margins for Instrumentation Errors) 2.1-2     Callaway Plant Reactor Coolant System Cooldown Limitations          5 (Cooldown Rates of 0, 20, 40, 60 and I 00F/hr) Applicable to 20 EFPY (With Margins for Instrumentation Errors) 2.2-1     Maximum Allowed PORV Setpoint for the Cold Overpressure             7 Mitigation System List of Tables Table                                                                        Page 2.1-1      Callaway Plant Heatup Data at 20 EFPY With Margins for              4 Instrumentation Errors 2.1-2      Callaway Plant Cooldown Data at 20 EFPY With Margins for            6 Instrumentation Errors 2.2-1      Callaway Plant COMS Maximum Allowable PORV Setpoints at 20          8 EFPY Callaway Plant                                  il                             Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT 1.0    Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
This PTLR for Callaway Plant has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.6. The TS addressed in this report are listed below:
LCO 3.4.3       RCS Pressure and Temperature (PIT) Limits LCO 3.4.12      Cold Overpressure Mitigation System (COMS) 2.0    Operating Limits The parameter limits forthe specifications listed in Section 1.0 are presented in the following subsections. The limits were developed in accordance with the NRC-approved methodology specified in Specification 5.6.6 (Ref. 1). NRC approval of this methodologywas received in Amendment No. [134], (Ref. 3).
The methodology listed in WCAP-14040-NP-A, Rovision 2 was used with one exception:
a)     ASME Code Case N-514 was used.
The revised P/T Limit curves account fora requirement of 10 CFR 50, Appendix G, that the temperature of the closure head flange and vessel flange regions must be at least 120 0F higher than the limiting RTNDT for these regions when the pressure exceeds 20% of the preservice hydrostatic test pressure (3107 psig).
2.1     RCS Pressure and Temperature (PIT) Limits (LCO 3.4.3) 2.1.1   The RCS temperature rate-of-change limits are:
: a. A maximum heatup of 10OPF in any 1-hour period.
: b. A maximum coo!down of 100GF in any 1-hour period.
: c. A maximum temperature change of 10F 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.
2.2     Cold Overpressure Mitigation System (COMS) Setpoints (LCO 3.4.12)
The pressurizer power-operated relief valves (PORVs) shall each have lift settings in accordance with Figure 2.2-1. The (COMS) arming temperature is 2750F. These lift setpoints have been developed using the NRC approved methodologies specified in Technical Specification 5.6.6.
Callaway Plant                                     1                                      Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT 2.2     (continued)
The maximum allowed PORV setpoint for COMS is derived by analysis which models the performance of the COMS assuming limiting mass and heat input transients with incorporation of 10% relaxation of the Appendix G limits in accordance with ASME Code Case N-514. Operation with a PORV setpoint less than or equal to the maximum setpointensures that Appendix G criteria will not be violated with consideration for (1) pressure and temperature instrumentation uncertainties; (2)single failure of one PORV; and (3)effects of reactor coolant pump operation.
To ensure mass and heat Input transients more severe than those assumed cannot occur, Technical Specifications place limitations on the number of safety injection pumps and centrifugal charging pumps that are capable of injecting, unisolating accumulators, and starting reactor coolant pumps during the appropriate COMS MODES. These limitations are outlined in TS LCO 3.4.6, LCO 3.4.7, and LCO 3.4.12.
Callaway Plant                                    2                                      Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT AATURIAL PROPERTY BASIS UMTING MATERIAL LOWER SHELL PLATE R2708-3 .
LMTING ART VALUES AT 20 EFPY: 114T, 10A'F 3/4T. 42.2F 2500 482314"53143                      -
t* 2 2 5 0 i iI ! i i                         MITI
            $M 2000 1750.1                           UKACC           PTABLZI 5-8                                    QP11AT ION 1500 VP jPTo                ze          r.I 1250 -                                                                               ACCE IOF   I PTADI AT! ONit   I I up Tot as                  /X1.1 r'sT.    "33 Is CrA 1 000    -
cst~. Ziki is "L3,
                                                                                                                   -. ,    ;y.
R:
           '-4      750 500 I
250 II   ATI      "I I .II I
I1-r Il. T-1LI 1 r~
I LI]
IIr-w I I rrIiI !Ii4t 111ril"I"TIM A I I              3 0 .       -             .  .  .    .
a           50 Ic0 150 200 250 300 350 400 45o soo I n d i c a ILe d Temperature ( D e g . F )
FIGURE 2.1-1       Callaway Unit I Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and 100&deg;F/hr) Applicable for the First 20 EFPY (With Margins for Instrumentation Errors). Includes vessel flange requirements of 170&deg;F and 561 psig per 10CFR 50, Appendix G.
Callaway Plant                                                             3                                               Revision 4

                            -!'$,3; ',i                     Figure 14.9         .;
PRESSURE                  AND TEMPERATURE           LIMITS    REPORT TABLE 2.1-1 Callaway Plant Heatup Limits at 20 EFPY With Marains for Instrumentation Errors 60&deg;F/hr          60 &deg;F/hrCrit. Limit                   I100&deg;F1hr         I 00lFhrCriL Limit        Leak Test Limit Temp.         Press. Temp.              Press.      Temp.         Press.      Temp. Press.        Temp.      Press.
('IF)        (psig)      (OF)             (psig)        (OF)         (psig)      (OF)     (Psig)         (OF)  l    psig) 60             0        245                  0          60             0        245         0           225       2000 60            500       245                544          60           494        245        546          245       2485 65            507       245                533          65           494        245        531 70            516       245               527           70           494        245        519                  _
75            524       245                524          75           494         245       509 80            524       245               524           80           494        245       502 85            524       245               527 .         85           494        245       497 90            524       245               533           90           494        245       494 95            524       245                541          95           494        245       494 100            524       245               551           100          494        245       495 105           524        245                563         105           494        245       499                      :
110           524        245                577         110           494        245       504 115            527       245               593           115          494        245        511 120            533       245               611           120          494        245       520 125           541        245               631           125          49.4       245       531 =
130           551        245               653          130           495        245       543 135            561       245               677          135           499        245       557 140           561       245                 703          140          504        245        574 145           561        245               732          145           511    __245         592 -                         X 150            561      245                763          150           520        245       612 155            561      245                796          155           531        245     - 634 160            561       245               832          160           543        245        658 165           561       245                871          165           557        245       685 170           561       245                912           170          561        245       714 170           703       245                957           170          574        245       745 175            732       250               1006          175          592        250       779            .
180           763       255                1058         180           612        255       816 185           796       260                1113         185           634        260       856 190           832       265                1173         190           658        265       899 195           871        270               1238         195           685        270       946 200           912       275                1306        200            714        275       996                   _
205           957       280                1381         205           745        280       1049 210           1006      285                1460         210           779        285       1107 215           1058      290                1544         215           816        290       1169 220           1113      295                1636         220           856        295       1236     _       _    _
225           1173      300                1732         225           899        300       1307 230           1238      305                1837        230            946        305       1384 235           1306      310                1948        235            996        310       1467 240           1381       315               2066         240           1049       315       1555 245           1460      320                2193        245           1107        320       1649 250           1544      325                2328        250           1169        325       1750 255           1636      330               2472         255           1236        330=      1858                          X 260           1732                                      260           1307       335       1973 265           1837                                     265           1384        340      2096 270           1948                          .          270           1467        345      2227 275          2066                     _                275           1555        350      2367 280           2193                              .      280            1649                            .
285          2328                                      285            1750 290          2472                                      290            1858
                                   .                  . 295            1973 1300          2096                             .
         =   _       _ _                  _              305           2227               _       _ l 310           2367 Callaway Plant                                                     4                                            Revision 4

Figure 14.9.
PRESSURE AND TEMPERATURE LIMITS REPORT        I'  ''
MUATERIAL PROPERTY BASIS TIWNGMATEAL LOWER SHELL PLATE R2708-3 ULMTING ART VALUES AT 20 EFPY:        114T. 100.4-F 3/4T, 842 OF 2500     I   I I
2250       _   __    __  __    __    __
              " '2000 I 750              ______UNACCEPT-ABLE
______OPERATION C,
            =     1500 cn w 1250                                                        IACCEPTA:LEI OPERATI ON 1 000.I a-750-      c C aLI RsT      F C) 500 -
250 0
6          50     1i00     t50 i
200 *250 d
300     350    400 450   s6 Indicated                     T-emp e r a ture           (Deg . F FIGURE 2.1-2       Callaway Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and 100 &deg;F/hr) Applicable for the First 20 EFPY (With Margins for Instrumentation Errors). Includes vessel flangerequirements of 170&deg;F and 561 psig per 10CFR 50, Appendix G Callaway Plant                                                5                                   Revision 4

                                                          - . . -7.
ale,,
                               '                     Figure 14.9          K to PRESSURE AND TEMPERATURE LIMITS REPORT.
TABLE 2.1-2 Callaway Plant Cooldown I-mits at 20 EFPY With Ma gins for Instrumentation Errors 0                         0                                     i          1000Fhr Steady State   l        2O Fhr                    4O    F1hr                 60F/hr Temp.      Press. Temp.       Press.       Temp.          Press.      Temp.      Press.       Temp.        Press.
(OF)      (psig)      (&deg;F)       (psi)            &deg;          F(Psig)      (OF)      (psig)        ('IF)       (psI) 60          0         60           0            60             0          60          0           60           0 60         500        60         468            60            427         60        386           60          302 65        507         65         468            65            427         65        386           65          302 70        516         70         476            70            436         70        396           70          313 75        525         75         486            75            446         75        406           75          325 80        534         80         496            80            457         80        418           80          338 85        544         85         506            85            468         85        430           85          351 90        555         90         518            90            481         90        443           90          366 95        561         95         531            95            494         95        457           95          382 100        561        100         544           100            508        100        472          100          400 105        561        105         559           105            524        105        489          105          419 110        561        110         561           110            540        110        506          110          439 115        561        115         561           115            553         115       526          115          461 120        561        120         561           120            561         120       546          120          485 125        561        125         561           125            561        125        561          125          511 130        561        130         561           130            561        130        561          130          539 135        561        135         561           135            561        135        561          135          561 140        561        140         561           140            561         140       561          140          561 145        561        145         561           145            561        145        561          145          561 150        561        150         561           150            561        150        561          150          561 155        561        155         561           155            561        155        561          155          561 160        561        160         561           160            561        160        561          160          561 165        561        165         561           165            561        165        561          165          561 170        561        170         561           170            561         170       561          170          561 170        899        170         885           170            873        170        864          170          856 175        937        175         925           175            917        175        911          175          910 180        977        180         969           180            963         180       961          180          969 185        1020       185         1015     -185               1014        185        1016 190        1066       190         1065 195        1116    _                        _              _         X X        -          X 200        1170 205        1228 210        1289 215        1355 220        1426 225        1503                                                                                .
230        1584 235        1672                _       _            _
240        1766 245        1866 250        1973 255       2088                           X                                                                 _
260       2211 265       2342                                                                                              .
270       2482                 _           _                                                                        -
Callaway Plant                                             6                                                Revision 4

1    -.
Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT CALLAWAY COMS Maximum Allowable PORV Setpolnts 2500                                                                                    I 4-2000                     .. I. . . . I           I I I I  I I I. I I    . I l/t        .
cn 81500 c
CL 0.
U, 1000     I II I I I&sect; I I I                   I I I I I I I iI I 1 1~.11  1 1 1- 1 1 1 1 0
rL 500 0  I" 0      50        ' 100           150      200       250      300        350      400 RCS Temperature (degree F)
                            -High               PORV Setpoint       --  - - Low PORV Setpoint Figure 2.2-1     Maximum Allowed PORV Setpoint for the Cold Overpressure Mitigation System Callaway Plant                                               7                                              Revision 4

i w * @
Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT TABLE 2.2-1 CALLAWAY PLANT COMS MAXIMUM ALLOWABLE PORV SETPOINTS AT 20 EFPY Maximum Allowable Function Generator Setp nts (Breakpoints)
Breakpoint Number     Temperature -       High Setpoint       Low Setpoint (psig)
RCS (OF)              (psig) 1                   70                  496                  466 2                   80                  496                  466 3                   90                  496                  466 4                  180                  527                  497 5                  230                  558                  512 6                  250                  750                  597 7                  270                  750                  597 8                  280                  750                  597 9                  350                 2335                 2185 Note: Setpoints assume'that all 4 or less RCPs are in operation.
Callaway Plant                               8                                       Revision 4

Figure 14.9     :: t PRESSURE AND TEMPERATURE LIMITS REPORT 3.0     Reactor Vessel Material Surveillance Program The reactor vessel material surveillance program is in compliance with Appendix H to 10 CFR 50, entitled "ReactorVessel Material Surveillance Program Requirements' and Section 5.3 of the Callaway Final Safety Analysis Report. The surveillance capsule withdrawal schedule is presented in FSAR Table 5.3-10. The surveillance capsule reports are as follows:
: 1.       WCAP-1 1374, Revision 1, June 1987, "Analysis of Capsule U from the Union Electric Company Callaway Unit 1 ReactorVessel Radiation Surveillance Program.*
: 2.       WCAP-12946, June 1991, 'Analysis of Capsule Y from the Union Electric Company Callaway Unit 1 Reactor Vessel Radiation Surveillance Program."
: 3.       WCAP-14895, July 1997, "Analysis of Capsule V from the Union Electric Company Callaway Unit 1 Reactor Vessel Radiation Surveillance Program."
: 4.       WCAP-1 5400, June 2000, "Analysis of Capsule X from the AmerenUE Callaway Unit I Reactor Vessel Radiation Surveillance Program."
4.0     Reactor Vessel Surveillance Data Credibility Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used forlight-water-cooled reactorvessels. Position C.2 of RegulatoryGuide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.
To date four surveillance capsules have been removed and analyzed from the Callaway Plant reactor vessel. To use these surveillance data sets, they must be shown to be credible. Inaccordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.
The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Callaway Plant reactorvessel surveillance data and determine ifthe Callaway Plant surveillance data is credible.
Criterion 1:      Materials in the capsules should be those judged most likelyto be controlling with regard to radiation embrittlement.
The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements," as follows:
               "the reactorvessel (shell material including welds, heataffectedzones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage.'
Callaway Plant                                     9                                       Revision 4

Figure 14.9      r PRESSURE AND TEMPERATURE LIMITS REPORT The Callaway Plant reactor vessel consists of the followirg beltline region materials:
          -     Intermediate shell plate R2707-1,
          -    Intermediate shell plate R2707-2,
          -    Intermediate shell plate R2707-3,
          -    Lower shell plate R2708-1,
          -    Lower shell plate R2708-2,
          -    Lower shell plate R2708-3, and
          -    Intermediate shell longitudinal weld seams, lower shell longitudinal weld seams, and a intermediate to lower shell circumferential weld seam All vessel beltline weld seams were fabricated with weld wire heat number G0077. The intermediate to lower shell circumferential weld seam 101-171 was fabricated with Flux Type 124 Lot Number 1061.
The intermediate and lower shell longitudinal weld seams were fabricated with Flux Type 0091 Lot Number 0842.
The Callaway Plant surveillance program utilizes longitudinal and transverse test specimens from lower shell plate R2708-1. The surveillance weld metal was fabricated with weld wire heat number 90077, Flux Type 124 Lot Number 1061.
At the time when the surveillance program was selected it was believed that copper and phosphorus werethe elements mostimportanttoembrittlementofreactorvessel steels. Since all plate materials had approximately the same content of copper and phosphorus, lower shell plate R2708-1 was chosen forthe surveillance program since it had the highest initial RTNDT and the lowest initial upper shelf energy of the plate material. In addition, the current pressurized thermal shock (PTS) evaluation shows that if surveillance data is not used, lower shell plate R2708-1 is the plate that is predicted to have the highest embdttlement rate.
Per Regulatory Guide 1.99, Revision 2, "weight-percent coppert and "weight-percent nickel* are the best-estimate values for the material, which will normally be the mean cf the measured values for a plate or forging or for weld samples made with the weld wire heat number that matches the critical vessel weld. Since the surveillance weld metal was made with the same weld wire heat as all of the vessel beltline weld seams, it is representative of the limiting beltline weld metal.
Based on the above discussion, the Callaway Plant surveillance materials are those judged most likely to be controlled with regard to radiation embrittlement and the Callaway Plant surveillance program meets this criteria.
-Criterion  2:     Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are Callaway Plant                                     10                                      Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT presented in WCAP-15400, June 2000, Analysis of Capsule X from the AmerenUE Callaway Unit I Reactor Vessel Radiation Surveillance Program.
Based on engineering judgement, the scatter inthe data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the uppershelf energy of the Callaway Plant surveillance materials unambiguously. Hence, the Callaway Plant surveillance program meets this criterion.
Criterion 3:      When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 280F for welds and 170F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82.
The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of theA RTNDT values about this line is less than 28&deg;F for welds and less than 1 F for the plate.
Following is the calculation of the best-fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2.
Callaway Plant                                       11                                       Revision 4

(,Sl:             Figure 14.9          - r-PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.0-1 CallawavPiantSurveillance Capsule Data Material          Capsule Capsule Fia)         FF&deg;b         ARTNT(c)      FF X ARTNDT        FF2 Lower Shell             U           0.331       0.696            0.0(e)          0.0          0.48 R2708-1               Y            1.27        1.07           25.15           26.91         1.14 (Longitudinal)            V            2.52        1.25           16.45           20.56         1.56 X            3.33        1.32           25.71           33.94         1.74 Lower Shell Plate           U           0.331       0.696           25.86           18.00         0.48 R2708-1               Y            1.27        1.07           46.39           49.64         1.14 (Transverse)             V            2.52        1.25           44.82           56.03         1.56 X             3.33        1.32           30.77           40.62         1.74 Sum:            8.6411          215.15           245.7         9.84 Surveillance Weld                 C 05 =7(FF* R DT)+(F        2 ) = (245.70) - (9.84) =25.0 0 F _
Materiald         _U               0.331       0.696          68.53d'          47.70         0.48 Y             1.27        1.07          36.92(d)         39.50         1.14 V             2.52        1.25          48.21 (d)        60.26         1.56 X             3.33        1.32          51.81(d)         68.39         1.74 Sum:              4.32          205.47          215.85         4.92 CF Surv.YUI = I(FF
* RTNDT) d  -(FF 2) (215.850F)    + (4.92) =43.90 F Notes:
(a) f = calculated fluence from capsule X dosimetry analysis results, (x 19 n/cm 2 , E>1.0 MeV).
These values were re-evaluated as part of capsule X analysis. (See Section 6 of WCAP-15400).
(b) FF = fluence factor = fO.28s0.1-ito.
(c) ARTNDT values are the measured 30 ftlb shift.
(c) These measured ARTNDT values do not include the adjustment ratio procedure of Reg. Guide 1.99 Revision 2, Position 2.1, since this calculatbn is based on the actual surveillance weld metal measured shift values and based on the copper and nickel content the ratio would be 1.
In addition, the only surveillance data available is from the Callaway Unit I reactor vessel, therefore, no temperature adjustment is required.
(e) The actual value is -7.33, but for conservatism a value of zero is considered.
The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table 4.0-2.
Per the 27t Edition of the CRC Standard Mathematical Tables (page 497), for a straight line fit by the method of least squares, the valuesb. and b1 are obtained by solving the normal equations nbo +          blXx1 =       Eyi       and boY:x1  +      bDi 2 =       FAyi Callaway Plant                                      12                                       Revision 4

I.              Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT These equations can be re-written as follows (b,= a and b,= b):
n                      n xyi    =      an + bcx,      and i=1                    i=1 n             n              n 7xiYi =                +    bxi2 1=1          1=1              i=1 Lower shell plate R2708-1:
Based on the data provided in Table 4.0-1 these equations become:
215.15 = 3a            +     8.6411b                 and 245.70 = 8.6411        +    9.84b Thus, b = 24.8405 and a = 0.1669, and the equation of the straight line which provides the bestfit in the sense of least squares is:
Yr = 24.8405 (X) + 0.1669 The scatter in predicting a value Y corresponding to a given X value is:
e=Y-Y' Table 4.0-2 Callaway Plant Lower Shell Plate R2708-1 Base Material           FF       Measured         Best Fit(a)     Scatter of    <17*F (Base ARTNDT       ARTNDT (0F)      ARTNDT (OF)       Metals)
(30 ft-lb)(OF)
Lower Shell        0.696           0.00            17.4           -17.4            NO Plate R2708-1         1.07          25.15           26.75            -1.6            Yes (Longitudinal)        1.25          16.45           31.25           -14.8            Yes 1.32          25.71            33.0           -7.29            Yes Lower Shell        0.696          25.86            17.4            8.46            Yes Plate R2708-1         1.07          46.39           26.75           19.64            NO (Transverse)         1.25          44.82           31.25           13.57            Yes
__             1.32          30.77            33.0           -2.23            Yes NOTES:
(a) Best Fit Line Per Equation 2 of Reg. Guide 1.99 Rev. 2 Position 1.1.
Callaway Plant                                    13                                     Revision 4

                                                ..    -.  - -1 Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.0-2 indicates that one measured plate ARTNDT value is below the lower bound I a of 17O1F by less than 1OF. Meaning the best fit line is slightly over predicting this measured ARTNDTvalue. Table 4.0-2 also indicates that one measured plate ARTNDTvalue is above the upper bound 1a of 170 F by less than 30F. From a statistical point of view + 1a (170F) would be expected to encompass 68% of the data. Therefore, it is still statisticallyacceptable to have two of the plate data points fall outside the + 1a bounds. The fact that two of the measured plate ARTNDTvalues are outside of 1a bound of 170F can be attributed to several factors, such as 1)the inherent uncertainty in Charpy test data, 2) the use of a symmetric hyperbolic tangent Charpy curve fitting program versus an asymmetric tangent Charpy curve fitting program or hand drawn curves using engineering judgment, and/or 3) rounding errors.
In summary, all measured plate is within acceptable range. Therefore, the plate data meets this criteria.
Weld Metal:
Based on the data provided in Table 4.0-1 the equations become:
205.47 = 3a               +       4.321b         and 215.13 = 4.321a           +       4.897b Thus, b = 60.9 and a = -19.3, and the equation of the straight line which provides the best fit in the sense of the least squares is:
Y = 60.9 (X) - 19.3 The scatter in predicting a value of Y corresponding to a given X value is:
e=Y-Y' Table 4.0-3 Callaway Plant Surveillance Weld Metal FF               Measured            Best Fitf)     Scatter of     <28&deg;F (Weld ARTNDT                     0 ARTNDT ( F) ARTNDT (OF)           Metal)
(30 ft-lb) (OF) 0.696                 68.53              30.55          37.98             NO 1.07                36.92               46.97         -10.05            Yes 1.25                48.21               54.88          -6.67            Yes 1.32                51.81               57.95          -6.14            Yes NOTES:
(a) Best Fit Line Per Equation 2 of Reg. Guide 1.99 Rev. 2 Pcsition 1.1.
One measured weld ARTNDT Is below the lower I a at 280F. The fact that one of the measured weld ARTNDT is out of la bound of 280 F can be attributed to several factors, such as 1) the inherent uncertainty in Charpy test data, 2) the use of a symmetric hyperbolic tangent Charpy curve fitting program versus an asymmetric tangent Charpy curve fitting program or hand drawn curves using engineering judgement, and/or 3) rounding errors.
Callaway Plant                                         14                                     Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT Criterion 4:      The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/ 250F.
The capsule specimens are located in the reactor between the neutron pads and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pads. The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25 0F. Hence this criterion is met.
Criterion 5:        The surveillance data for the correlation monitormaterial in the capsule should fall within the scatter band of the data base for that material.
The Callaway Plant surveillance program does not contain correlation monitor material. Therefore, this criterion is not applicable to the Callaway Plant surveillance program.
Based on the preceding positive responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B, the Callaway Plant surveillance data is credible.
Callaway Plant                                     15                                      Revision 4

                                 ,            Figure 14.9    ,   zi
                                                                 .1 PRESSURE AND TEMPERATURE LIMITS REPORT 5.0    Supplemental Data Tables Table 5.0-1    Comparison of Callaway Plant Surveillance Material 30ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions.
Table 5.0-2    Calculation of Chemistry Factors Using Surveillance Capsule Data.
Table 5.0-3    Provides the unirradiated reactor vessel toughness data. The boltup temperature is also included in this Table.
Table 5.0-4    Provides a summary of the pressure vessel neutron fluence values at 20 EFPY used for the calculation of ART values.
Table 5.0-5    Provides a summary of the adjusted reference temperature (ARTs) for reactor vessel beltline materials at the Ye-T and 3/-T locations for 20 EFPY.
Table 5.0-6    Shows the calculation of the ART at 20 EFPY for the limiting reactor vessel material (lower shell plate R-2708-3).
Table 5.0-7    Provides RTpTs values for 35 EFPY.
6.0    References
: 1. Technical Specification 5.6.6, *Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)."
: 2. NRC letter dated [March 24, 2000], [CALLAWAY PLANT, UNIT I - ISSUANCE OF AMENDMENT RE: PRESSURE TEMPERATURE LIMITS REPORT]
: 3. License Amendment No. [134], dated [March24,2000], from [Jack Donohew, Senior Project Manager, Section 2] to [Garry L. Randolph, Vice President and Chief Nuclear Officer].
: 4. WCAP-14040-NP-A, Revision 2, "Methodology Usedto Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," January, 1996.
: 5. WCAP-16140, July 2004, 'Callaway Replacement Steam Generator Program NSSS I             Engineering Report' Callaway Plant                                  16                                       Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT
                         ,    -..                                 Z i' V, Table 5.0-1 Comparison of Callaway Unit I Surveillance Material 30 ftlb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99,Revision 2,
                                            - Predictions 30 ft-lb Transition       Upper Shelf Energy Temperature Shift -             Decrease Materials       Capsule        Fluence         Predicted Measured Predicte Measured (X 1 0 19n/cm2 )     (OF) (a)          (,F) (b) d (%) (a)     (%) (c)
Lower Shell          U            0.331           30.62              o.o0)     14.5           0 Plate R2708-1          Y             1.27.          47.08             25.15       20            6 V            1.252            55.0             16.45      23.5           0 (Longitudinal)         X             3.33           58.08             25.71       25            5 Lower Shell          U            0.331           30.62             25.86      14.5          11 Plate R2708-1          Y             1.27          -47.08             46.39       20           13 V           -1.252            55.0             44.82      23.5          3 (Transverse)          X             3.33           58.08             30.77       25           5 Weld Metal           U            0.331           22.13             68.53      14.5          11 Y             1.27           34.02             36.92       20           14 V            1.252           39.75             48.21      23.5          8 X            3.33            41.98             51.81       25           8 HAZ Metal            U            0.331              _              65.93       -            0 Y             1.27                             56.38        _           14 v            1.252       :                      56.1        _           0 X            3.33               -              42.11                    0 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 4.1 .
(c)    Values are based on the definition of upper shelf energy given in ASTM E18582.
(d)    Actual measured value forARTNDT is -7.33. This physically should not occur, therefore for conservatism a value of zero will be used.
Callaway Plant                                    17                                         Revision 4
* t,    h   VS Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.0-2 Calculation of Chemistry Factors Using Surveillance Capsule Data Material       Capsule Capsule )                FFWbl ARTNDT(C)         FF x ARTNDT         FF Lower Shell          U           0.331           0.696      0.0(e)              0.0          0.48 PlateR2708-1           Y            1.27            1.07     25.15              26.91          1.14 V            2.52            1.25      16.45             20.56          1.56 (Longitudinal)         X            3.33            1.32     25.71              33.94          1.74 Lower Shell          U           0.331           0.696     25.86              18.00          0.48 Plate             Y            1.27            1.07     46.39              49.64          1.14 R2708-1             V           2.52             1.25     44.82              56.03          1.56 X            3.33            1.32     30.77              40.62          1.74 (Transverse)                                                        SUM       245.70          9.84 C 0f 5 = X(FF
* RTNDT) + XiFF2) = (245.70) (9.84) =25.00 F Surveillance          UL          0.331           0.696    68.53(')           47.70          0.48 Weld Material(d)        Y            1.27            1.07    36.921('             39.5          1.14 V           2.52             1.25    48.21'g'            60.26          1.56 X           3.33             1.32    51.81()             68.39          1.74 SUM       215.85         4.92 CF surv wee = E(FF
* RTNDT) + X(FF 2 ) = (215.85"F) + (4.92) =43.90F NOTES:
(a) f = calculated fluence from capsule X dosimetry analysis results, (Id9 n/cm2, E > 1.0 MeV).
All updated fluence values from the Capsule X analysis (Table 01 of WCAP 15400).
(b) FF = fluence factor =
(c) ARTNDTvalues are the measured 30 flb shift.
(d) These measured ARTNDT values do not include the adjustment ratio procedure of Reg.
Guide 1.99 Revision 2, Position 2.1, since this calculation is based on the actual surveillance weld metal measured shift values and based on the copper and nickel content the ratio would be 1. In addition, the only surveillance data available is from the Callaway Unit 1 reactor vessel, therefore, no temperature adjustment is required.
(e) The actual value is -7.33, but for conservatism a value of zero is considered.
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                                        -1      !
Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT eats * '~SA                            o TABLE 5.0-3 Reactor Vessel Beltline Material Unirradiated Toughness Properties Material Description            l   Cu             Ni(%)         Initial RTNDT Closure Head Flange R2704-1           l            l                        300F(c)
Vessel Flange R2701-1             l            l       -       l        400F(c)
Intermediate Shell Plate R2707-1             0.05           0.58               400 F Intermediate Shell Plate R2707-2             0.06           0.61               10'F Intermediate Shell Plate R2707-3             0.06           0.62              -10F Lower Shell Plate R2708-1               0.07           0.58               500F Lower Shell Plate R2708-2                0.06           0.57               10F Lower Shell Plate R27083                 0.08           0.62               200F Intermediate and Lower Shell                        . 0.06              -600 F Longitudinal Weld Seams___
Intermediate to Lower Shell              0.04          0.06                60&deg;F Circumferential Weld Seam046 The Initial RTNDT values for the plates and welds are based on measured data (WCAFL 12948).
All vessel beltline weld seams were fabricated with weld wire heat number 90077. The intermediate to lower shell circumferential weld seam 101-171 was fabricated with Flux Type 124 Lot Number 1061. The intermediate and lower shell longitudinal weld seams were fabricated with Flux Type 0091 Lot 0842. The surveillance weld metal was fabricated with weld wire heat number 90077, Flux Type 124 Lot number 1061. Per Regulatory Guide 1.99, Revision 2, 'weight-percent copper *and "weight-percent nickel, are the best-estimate values for the material, which will normally be the mean of the measured values for a plate or forging or for weld samples made with the weldwire heat number that matches the critical vessel weld. The surveillance weld metal was made with the same weld wire heat as all of the vessel beltline weld seams and is therefore representative of all of the beltline weld seams.
l')  These values are used for considering flange requirements for the heatup/cooldown curves. Per the methodology given in WCAP-1404O-NP-A (Ref. 4), the minimum boltup temperature is 60"F.
Callaway Plant                                    19                                      Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT TABLE 6.0-4 Fluence (109 nlcm2 , E > 1.0 MeV) on the Pressure Vessel CladlBase Metal Interface for Callaway Plant EFPY          00             150    l    300        450 12.40        0.445          0.649        0.756      0.768 16          0.565          0.822        0.956      0.964 24          0.832           1.21         1.40       1.40 32           1.10           1.59         1.85       1.83 54           1.83           2.64         3.07       3.02 Callaway Plant                             20                            Revision 4

t         J 1I                    I
                                    ,., I.  :I  ' -. W I   ;   -
Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT TABLE 5.0-5 Summary of Adjusted Reference Temperature (ART) Mlues at the 4/-T and
                                 %-T Locations for 20 EFPY 20 EFPY ART(a)
Material                         1
                                                     %-T ART                    %-T ART
                        ._,                               (OF)                      ('F)
Intermediate Shell Plate R2707-1                  96.4                      79.0 Intermediate Shell Plate R2707-2                  77.4                      56.6 Intermediate Shell Plate R2707-3                  57.4                      36.6 Lower Shell Plate R2708-1                   124.0                      105.4 Using Surveillance Capsule Data                   90.9                      83.2 Lower Shell Plate R2708-2                     77.4                      56.6 Lower Shell Plate R2708-3                  100.4A'                     84.2(t)
Intermediate & Lower Shell Longitudinal Weld Seams 101-                   -15.4                      -30.8 124A & 101-142A (900 Azimuth)
Using Surveillance Capsule Data                    0.8                     -17.2 Intermediate & Lower Shell Longitudinal weld Seams 101-124B&C and 101-142B&C (2100 &                      -6.6                     -23.2 3300 Azimuth)
Using Surveillance Capsule Data                    7.3                      -5.8 Intermediate to Lower Shell Circumferential Weld Seam 101-                    -6.0                     -22.6 171                                                 .
Using Surveillance Capsule Data                    7.8                      -5.0 ART = Initial RTNDT + ARTNDT + Margin (OF)
(b) These ART values are used to generate the heatup and cooldown curves.
Note:When two or more credible surveillance data sets become available, the data sets may be used to determine ART values as described in Regulatory Guide 1.99, Revision 2, Position 2.1. If the ART values based on surveillance capsule data are larger than those calculated per Regulatory Guide 1.99, Revision 2. Position 1.1, the surveillance data mist be used. If the surveillance capsule data gives lower values, either may be used.
Callaway Plant                                     21                                     Revision 4

                                           .  .l    I  '1,l 4.
I      ,
i        I Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT
                                         ;l      .~
TABLE 5.0-6 Calculation of Adjusted Reference Temperature Values at 20 EFPY for the Limiting Callaway Plant Reactor Vessel Material (Lower Shell Plate R270&3)
Parameter                          [                ART Value Location                                     1/4-T     l   _       _     _-T Chemistry Factor, CF CF)                               51.0               51.0 Fluence, f (10'9 n/cm2 )(a)                         0.7174              0.2547 Fluence Factor, FFH)                               0.91                0.63 ARTNDT =     CF x FF, eF)                           46.4                32.1 Initial RTNDT, I (CF)                               20                 20 Margin, M f)c)                                     34                32.1 ART = I + (CF x FF) + M eF)                             100.4               84.2 per Regulatory Guide 1.99, Rev. 2 (a
Fluence, f, is based upon fe (10o' rnicm', E > 1.0 MeV) = 1.204 at 20 EFPY. The Callaway Plant reactor vessel wall thickness is 8.63 inches at the beltline region.
(b)
Fluence Factor (FF) per Regulatory Guide 1.99, Revision 2, is defined as FF = f0.28-0.1019ogo (C)      Margin is calculated as M = 2,2+ a02)0 5. The standard deviation for the initial RTNDT margin term a,, is 0F since the initial RTNDT is a measured value. The standard deviation for ARTNDT term A, is 17 0F for the plate, except that a, need not exceed 0.5 times the mean value of ARTNDT.
Callaway Plant                                        22                                 Revision 4

Figure 14.9 PRESSURE AND TEMPERATURE LIMITS REPORT TABLE 5.0-7 RTpTS Calculations for Callaway Plant Beitline Region Materials at 35 EFPPd Material              l          Fluence (1019                        FF n/cm2 , E >1.0 MeV)I 1CF    (OF)
ARTpTs(
(O 1         ). Margin F)
RTNOT(U)(a)
(OF)
RTpTs b
('F)
Intermediate Shell                                   2.074                    1.20               31.0                    37.2              34.0                 40                111 Plate R2707-1 Intermediate Shell                                   2.074                    1.20               37.0                   44.4               34.0                  10                88 Plate R2707-2 Intermediate Shell                                    2.074                    1.20               37.0                   44.4               34.0                -10                 68 Plate R2707-3 Lower Shell Plate                                   2.074                     1.20              44.0                    52.8               34.0                 50                137 R2708-1 Using S/C Data                                    2.074                     1.20              26.3                    31.6               17.0                 50                 99 Lower Shell Plate                                   2.074                    1.20               37.0                    44.4               34.0                 10                 88 R2708-2 Lower Shell Plate                                   2.074                    1.20               51.0                    61.2               34.0                 20               115 R2708-3 Inter. and Lower Shell                                    1.167                   1.04               29.7                    30.9               30.9                -60                  2 Long. Weld Seams101-124A &
101-142A (90&deg; Azimuth)
Using S/C Data                                     1.167                    1.04               43.7                    45.4              28.0                 -60                13 Inter. and Lower Shell                                   2.042                    1.19               29.7                    35.3              35.3              .-60                  11 Long. Weld Seams101-124B&C &
101-142B&C (210&deg; &
3300 Azimuth)
Using SIC Data                                     2.042                    1.19              43.7                     52.0              28.0                -60                 20 Intermediate to Lower                                    2.074                    1.20              29.7                     35.6              35.6                -60                 11 Shell Circumferential Weld Seam                 101 -171
.................... i          ....              .................... ..........     ..............             ............                              ..............       ......
Using SIC Data                                    2.074                     1.20              43.7                     52.4              28.0                -60                20 (a)                Initial RTNDT values are measured values (b)                RTpTs = RTNDT(u) + Margin + ARTmrn (c)                ARTps= CF
* FF (d)                 Projected no. of EPFY at the EOL.
Callaway Plant                                                                                 23                                                                       Revision 4}}