ML090640303

Calculation No. 0800297.301, Revision 1 Revised Pressure-Temperature Curves

ML090640303
Person / Time
Site:	Nine Mile Point
Issue date:	01/22/2008
From:	Structural Integrity Associates
To:	Nine Mile Point, Office of Nuclear Reactor Regulation
References
0800297.301, Rev 1
Download: ML090640303 (57)

Text

ATTACHMENT 4 STRUCTURAL INTEGRITY ASSOCIATES, INC.

CALCULATION NO. 0800297.301, REVISION 1 REVISED PRESSURE-TEMPERATURE CURVES Nine Mile Point Nuclear Station, LLC March 3, 2009

Structural Integrity Associates, Inc.

File No.: 0800297.301 CALCULATION PACKAGE Project No.: 0800297 M Q E Non-Q PROJECT NAME:

NMP Materials Update and Revised P-T Curves CONTRACT NO.:

7710734 Revision I CLIENT:

PLANT:

Constellation Energy Nine Mile Point, Unit I CALCULATION TITLE:

Revised Pressure-Temperature Curves Notes:

This calculation supersedes all previous Pressure-Temperature curve calculations for the Nine Mile Point, Unit 1.

Project Manager Approval Signature & Date Preparer(s) &

Checker(s)

Signatures & Date 1 -46, Appendix:

Al - A2, BI -B5, CI -C2 Computer Files Initial Issue T. J. Griesbach 12/23/08 E. J. Houston 12/22/08 S. J. White 12/22/08 V. Marthandam 12/22/08 4

+

I-I 8-47, B2 Incorporate Client Comments T. J. Griesbach 1/26/09 E. J. Houston 1/23/09 S. J. White 1/23/09 V. Marthandam 1/26/09 Page I of 47 F0306-O1RO

Structurai integrity Associates, Inc.

Table of Contents 1.0 IN TR O D U CTIO N..................................................

4 2.0 M E T H O D O L O G Y......................................................................................................................

4 3.0 DESIGN INPUTS / A SSUM PTION S..........................................................................................

8 4.0 C A L C U L A T IO N S......................................................................................................................

10 4.1 Pressure T est (C urve A )................................................................................................

10 4.2 Normal Operation - Core Not Critical (Curve B).........................................................

11 4.3 Normal Operation - Core Critical (Curve C)....................................................................

11 5.0 C O N C L U SIO N S........................................................................................................................

II 6.0 R E F E R E N C E S...........................................................................................................................

13 APPENDIX A: P-T CURVE INPUT LISTING Al APPENDIX B: INCREASED COOL-DOWN RATE P-T CURVE............................................

BI APPENDIX C: ANSYS SUPPORTING FILES.........................................................................

C1 List of Tables Table 1: NMP-I Polynomial Coefficients for Feedwater Nozzle Stress Intensity Distributions............. 15 Table 2: NMP-1 Beltline Region, Curve A, for 28 EFPY.....................................................................

16 Table 3: NMP-1 Beltline Region, Curve A, for 36 EFPY.....................................................................

18 Table 4: NMP-1 Beltline Region, Curve A, for 46 EFPY.....................................................................

20 Table 5: NMP-1 Bottom Head Region, Curve A, for all EFPY.................................

22 Table 6: NMP-1 Upper Vessel Region, Curve A, for all EFPY............................................................

23 Table 7: NMP-1 Beltline Region, Curve B, for 28 EFPY.....................................................................

24 Table 8: NMP-1 Beltline Region, Curve B, for 36 EFPY....................................................................

26 Table 9: NMP-1 Beltline Region, Curve B, for 46 EFPY.....................................................................

28 Table 10: NMP-I Bottom Head Region, Curve B, for all EFPY.........................................................

30 Table 11: NMP-1 Upper Vessel Region, Curve B, for all EFPY.........................................................

31 Table 12: NMP-1 Curve C Values for 28 EFPY..................................................................................

33 Table 13: NMP-1 Curve C Values for 36 EFPY..................................................................................

35 Table 14: NMP-1 Curve C Values for 46 EFPY..................................................................................

37 File No.: 0800297.301 Page 2 of 47 Revision: I F0306-OIRO

V Structural integrity Associates, Inc.

List of Figures Figure 1: NMP-1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 28 EFPY..........................

39 Figure 2: NMP-1 P-T Curve A (Hydrostatic Pressure and Lead Tests) for 36 EFPY.......................... 40 Figure 3: NMP-1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 46 EFPY.......................... 41 Figure 4: NMIP-1 P-T Curve B (Normal Operation - Core Not Critical) for 28 EFPY....................... 42 Figure 5: NMIP-1 P-T Curve B (Normal Operation - Core Not Critical) for 36 EFPY....................... 43 Figure 6: NMP-1 P-T Curve B (Normal Operation - Core Not Critical) for 46 EFPY....................... 44 Figure 7: NMP-1 P-T Curve C (Normal Operation - Core Critical) for 28 EFPY..............................

45 Figure 8: NMLP-1 P-T Curve C (Normal Operation - Core Critical) for 36 EFPY.............................. 46 Figure 9: NMP-I P-T Curve C (Normal Operation - Core Critical) for 46 EFPY..............................

47 File No.: 0800297.301 Revision: I Page 3 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

1.0 INTRODUCTION

This calculation updates the Nine Mile Point, Unit I (NMP-1) pressure-temperature (P-T) curves for the beltline, bottom head, and non-beltline (feedwater nozzle / upper vessel) regions. The P-T curves are created for 28, 36, and 46 effective full power years (EFPY) of operation, and are developed using the methodology of the 2001 Edition, 2003 Addenda of ASME Code,Section XI, Appendix G [1], and I OCFR50 Appendix G [2]. This calculation has been developed in accordance with the methodology of the Boiling Water Reactor Owner's Group (BWROG) Licensing Topical Report, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors" [3].

2.0 METHODOLOGY A full set of P-T curves are computed, including the following plant conditions: Operating Pressure (Leak) Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C). The curves are consolidated into three bounding evaluation regions of the reactor pressure vessel (RPV): (1) the beltline, (2) the bottom head, and (3) the feedwater nozzle / upper vessel.

The primary methodology for calculating P-T curves is described in Reference [3]. Therefore, all methodology in this section is obtained from Reference [3] unless otherwise noted. The P-T curves are calculated by means of an iterative procedure, in which the following steps are completed:

Step 1:

A fluid temperature, T, is assumed. The P-T curves are calculated under the premise of an assumed flaw that has extended 1/4 of the way through the vessel wall. According to Reference [3], the temperature at the assumed flaw tip, T1/4, is conservatively treated as equal to the assumed fluid temperature.

Step 2:

The static fracture toughness factor, K1,, is computed using the following equation:

Klc = 20.734 -e°2(T-ART) + 33.2 (1)

Where:

Ki,

= the lower-bound static fracture toughness factor (ksi'Iin).

T the metal temperature at the tip of the postulated 1/4 through-wall flaw (0F), as described above.

ART

= the Adjusted Reference Temperature (ART) for the limiting material in the RPV region under consideration (°F)

File No.: 0800297.301 Page 4 of 47 Revision: I F0306-OIRO

Structural Integrity Associates, Inc.

Step 3:

The allowable stress intensity factor due to pressure, Kip, is calculated as:

=Ki -

K (2)

SF Where:

Kip

= the allowable stress intensity factor due to membrane (pressure) stress (ksi/in).

Kj,:

= the lower-bound static fracture toughness factor calculated in Equation 1 (ksi*/in).

Kit

= the thermalstress intensity factor (ksi'lin).

SF

= the safety factor, based on the reactor condition.

Note: For hydrostatic and leak test conditions (i.e., P-T Curve A), the SF = 1.5. For normal operation, for both a non-critical and a critical reactor (i.e., P-T Curves B and C), the SF =

2.0. When calculating values for Curve A, the thermal stress intensity factor is neglected (Kit

= 0), since the hydrostatic leak test is performed at or near isothermal conditions (typically, the rate of temperature change is 25°F/hr or less) [3].

For Curve B and Curve C calculations, Kit is computed in different ways based on the evaluation region. For the beltline and bottom head regions, Kit is determined using the following equation based on the ASME Section XI, Nonmandatory Appendix G method:

Kit = 0.953 X 10-3 _ CR-t2.5 (3)

Where:

CR

= the cooldown rate of the vessel (°F/hr).

t

= the RPV wall thickness, unique for each region (in).

For the feedwater nozzle / upper vessel region, Kit is obtained from the stress distribution output of a finite element model (FEM) of the feedwater nozzle, which is the limiting non-beltline component from a stress point-of-view (neglecting the flange, which is separately covered by application of 10 CFR 50 Appendix G limits). A thermal transient finite element analysis (FEA) is performed for the feedwater nozzle, and a polynomial curve-fit is applied to the through-wall stress distribution in the limiting nozzle corner location at each time point of the thermal transient. The subsequent method to evaluate Kit is given as:

Oa+2a 0537C1O

• 4a3 3

=,

+

.537C +-.

0.448C, +

0.393C3(4)

Ir 2

I3T Where:

a

= '/4 through-wall postulated flaw depth, a = '/4 t (in).

t

=thickness of the cross-section through the limiting nozzle inner blend radius corner (in).

C0t,,Ct = thermal stress third order polynomial coefficients, obtained from a C 2t,C 3t curve-fit of the extracted stresses from an FEM transient analysis.

File No.: 0800297.301 Page 5 of 47 Revision: I F0306-O1RO

V Structural Integrity Associates, Inc.

The thermal stress polynomial coefficients are based on the polynomial form of c3-(x) =c + C. (

+aa/

+

+ C3 -

. In this equation, "a" represents the radial distance in inches from the inside surface to any point on the crack front, and "amax" is the maximum crack depth, in inches.

Step 4:

The allowable internal pressure of the RPV is calculated differently for each evaluation region. For the beltline region, the allowable pressure is determined as follows:

p a llow

= - K M, -Ri (5)

Where:

Pallow Kip t

Mm Ri

= the allowable RPV internal pressure (psig).

= the allowable stress intensity factor due to membrane (pressure) stress, as defined in Equation 2 (ksli*n).

= the RPV wall thickness, unique for each region (in).

= the membrane correction factor for an inside surface axial flaw:

Mm = 1.85 for 4t < 2 Mm = 0.926 4t for 2 <4t < 3.464 Mm = 3.21 for 4t > 3.464

= the inner radius of the RPV (in).

For the bottom head region, the allowable pressure is calculated with the following equation:

SCF. M0, -Ri (6)

Where:

SCF conservative stress concentration factor to account for bottom head penetration discontinuities; SCF = 3.0 per Reference [3].

Pallow, Kip, t, Mm and Ri are defined in the footnotes of Equation 5.

For the feedwater nozzle / upper vessel region, the allowable pressure is determined from a ratio of the allowable and applied stress intensity factors. The applied factor can be determined from an FEM that outputs the stresses due to the internal pressure on the nozzle /

RPV. The methodology for this approach is as follows:

K11 -Prei*

(7)

Where:

Pref

= RPV internal pressure at which the FEA stress coefficients (Equation 8) are valid (psig).

Kip-app

= the applied pressure stress intensity factor (ksi*/in).

Pallow and Kip are defined in the footnotes of Equation 5.

File No.: 0800297.301 Revision: I Page 6 of 47 F0306-01 RO

Structural integrity Associates, Inc.

The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from an FEA, similar to the methodology of Equation 4:

2a a

4a 3 '

K)TaLO=*

.706Cp +/-*

2j3

-aOp 0-.537C 1

2

.448C2p +

.0.393C 3,

(8)

Where:

a

= 1/4 through-wall postulated flaw depth, a = 1/4 t (in).

t

= thickness of the cross-section through the limiting nozzle inner blend radius corner (in).

Cop, Cp = pressure stress polynomial coefficients, obtained from a curve-fit C 2p,C 3 p from the extracted stresses from an FEM unit pressure analysis.

Step 5:

Steps I through 4 are repeated in order to generate a series of P-T points; the fluid temperature is incremented with each repetition. Calculations proceed in this iterative manner until the allowable reactor pressure (Pp-T) exceeds the maximum possible pressure. The maximum pressure limit is set to 1900 psig, since this value bounds the pre-service hydrostatic test pressure of 1,875 psig (see Section 3.0).

Step 6:

The final P-T limits are calculated using the following equations:

TT = T + UT (9)

P-T = Pallo,,w -

P H -UP (10)

Where:

TP-T

= the allowable coolant (metal) temperature (0F).

UT

= the coolant temperature instrument uncertainty ('F).

PP-T

= the allowable reactor pressure (psig).

PH

= the pressure head to account for the water in the RPV (psig).

Can be calculated from the following expression: PH = p Ah.

p

= Water density at ambient temperature (lb/in3).

Ah

= elevation of full height water level in RPV (in.).

Up

= the pressure instrument uncertainty (psig).

Step 7:

The following additional minimum temperature requirements apply to the feedwater nozzle / upper vessel region, according to Table I of IOCFR50, Appendix G [2]:

" If the pressure is greater than 20% of the pre-service hydro-test pressure, the temperature must be greater than the RTNDT of the limiting flange material plus a temperature adjustment. For Curve A calculations, the temperature adjustment is 90'F; for Curve B, the temperature adjustment is 120'F.

• If the pressure is less than or equal to 20% of the pre-service hydro-test pressure, the minimum temperature must be greater than or equal to the RTNDT of the limiting flange material.

File No.: 0800297.301 Page 7 of 47 Revision: 1 F0306-OIRO

V Structural Integrity Associates, Inc.

The P-T Curves for the hydrostatic leak test (Curve A) and normal operation - core not critical (Curve B) can be computed by following Steps I through 7. Values for Curve C, the core-critical operating curve, are generated from the requirements of IOCFR50 Appendix G [2] and the Curve A and Curve B limits. Table I of Reference [2] requires that core critical P-T limits be 40'F above any Curve A or Curve B limits at all pressures. IOCFR50 Appendix G [21 also stipulates that, above the 20% pressure transition point, the Curve C temperatures must be either the reference temperature (RTNDT) of the closure flange region plus 160'F, or the temperature required for the operating pressure (leak) test from Curve A, whichever is greater.

For P-T Curves A and B, the initial fluid temperature assumed in Step 1 is typically taken at the bolt-up temperature of the closure flange. According to Reference [2], the minimum bolt-up temperature is equal to the limiting material RTNDT of the regions affected by bolt-up stresses. Consistent with Reference [3], the minimum bolt-up temperature shall not be lower than 60'F. Thus, the minimum bolt-up temperature shall be 60'F or the material RTNDT, whichever is higher.

For P-T Curve C, when the reactor is critical, the initial fluid temperature is equal to the calculated minimum criticality temperature in this region. Table 1 of Reference [2] indicates that, for a BWR with normal operating water levels, the allowable temperature for initial criticality at the closure flange region is equal to the reference temperature (RTNDT) at the flange region plus 60'F.

3.0 DESIGN INPUTS / ASSUMPTIONS All design inputs and assumptions used to perform the NMP-1 P-T curve calculations are summarized in the input listings in Appendix A.

ART values in the NMP-1 beltline region are obtained from a previous Structural Integrity Associates (SI) calculation [4]. The calculations were performed in accordance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2 (RG1.99) [5]. Based on Table 4 through Table 6 of Reference [4], the limiting beltline material is the P2112 lower shell plate. The limiting plate has ART values of 151.4'F, 159.0°F, and 167.4°F for 28, 36, and 46 EFPY, respectively.

NMP-1 has no large or small diameter nozzles (e.g. instrument nozzles) in the RPV beltline where the fluence exceeds 1.0x10 17 n/cm 2(E>IMeV).

Non-beltline regions are not subjected to significant fluence; therefore, initial reference temperature (RTNDT) values do not change, and are valid substitutions for corresponding ART values for these regions. Limiting RTNDT values for the upper vessel and flange region are taken from Reference [12c]

as 40°F. A complete list of RTNDT values is not available for the bottom head [13]. Of the available data, a value of 40'F is bounding [13]. Since this value is also bounding for the upper vessel and flange region, the limiting bottom head RTNDT is taken as 407F. This is consistent with References [12.d] and

[11, Section 10.3.1.1] which indicate the initial RTNDT for areas of reactor vessel material away from the high flux density region of the core is 40'F.

File No.: 0800297.301 Page 8 of 47 Revision: I F0306-OIRO

V Structural Integrity Associates, Inc.

The inner radius of the RPV, per Reference [6, Table 4-5], is 106.5 inches. The vessel shell thickness is taken as 7.125 inches from the same source. Dimensions for the bottom head radius and thickness are obtained from Reference [10, Appendix A] as 106.719 inches and 8.75 inches, respectively.

The GE design hydro-test is defined as 1,250 psig [14] while the operating pressure test maximum is defined as 1,055 psig [16]. As described by IWB-5220 [15], the system leakage test (Curve A) pressure is taken as the operating pressure. The pre-service system hydrostatic test pressure was taken as 1.5 times the GE design pressure, resulting in a value of 1,875 psig, as confirmed in Reference [12a]. The instrument uncertainties for the Curve A hydrotest are 4°F and 10 psig [17]. For Curves B and C, the instrument uncertainties are 12.2°F and 52.2 psig [17].

The total internal height of the RPV is 766 inches, as shown in Table V-1 of Reference [12b]. The density of the water is assumed to be 62.4 lb/ft3 = 0.0361 lb/in 3. Thus, the static pressure adjustment due to the pressure head of the water in the RPV is conservatively calculated as 766-0.0361 = 27.66 psig for all evaluation regions, which addresses pressure test conditions when the RPV is fully flooded. The maximum cool-down rate of the vessel is 100°F/Hr per Reference [14]. Appendix B presents a bounding curve for a maximum heat-up / cool-down rate of 200°F/Hr.

According to Section 2.8 of Reference [3], the minimum bolt-up temperature for the RPV shall be no lower than 60'F. Since the RTNDT values for all regions highly stressed by bolt preload are all less than 60'F, the initial assumed fluid temperature in the iterative P-T curve calculation process is set equal to 60'F. A temperature increment of 2'F between subsequent iterations is assumed.

The 60'F initial temperature of Reference [3] replaces the previous lower limit of 60'F plus the limiting RTNDT for Curves A and 13, which was applied to the previous NMP-1 P-T curves [7a, 7b]. This additional conservatism was required in pre-1971 ASME Section III Code, but is no longer required in ASME Section XI, Appendix G [1] or IOCFR50, Appendix G [2]. When the Pressure-Temperature Limits Report (PTLR) [3] was developed, SI consciously recognized the additional 60'F margin and chose to exclude it, as it is not technically required.

Post processing was performed for a previously developed finite element analyses to extract the necessary polynomial coefficients describing the hoop stress distribution through the feedwater nozzle's limiting comer location (Equations 4 and 8). The thermal and pressure stresses were extracted using ANSYS [8].

Based upon a previous axisymmetric analysis, the limiting nozzle comer location was chosen based upon the highest total stress intensity due to pressure loading [9]. This path (Nodes 584 to 570) is utilized to extract thermal and pressure hoop stresses from the results databases [9]. For thermal stresses, the feedwater nozzle FEM was run with a thermal shock from 550'F to 100'F applied to the nozzle flow path with 100% flow [9]. This represents the thermal shock during the transient "Increase to Rated Power" [14]. It can be seen from Reference [14] that this is the highest thermal shock for the feedwater nozzle. The thermal stresses are taken as function of time during the transient. Each stress distribution is fit with a third-order polynomial as a function of distance into the nozzle. The thermal stress intensity factor (Equation 4) is calculated for all time steps. The most limiting (highest) value is chosen, corresponding to a time of 5,000 seconds. Since operation is along the saturation curve, the File No.: 0800297.301 Page 9 of 47 Revision: 1 F0306-OIRO

i Structural Integrity Associates, Inc.

thermal stress intensity factor is scaled to reflect the worst-case step change due to available temperature difference. The pressure stresses are taken at steady state. The pressure stress analysis was performed for a 1,000 psig RPV pressure and the results scaled to reflect the operating pressure of 1,055 psig. The supporting *.out files of Reference [9] show that the path selected defines the nozzle comer thickness to be 7.8427 inches. Thus, the postulated flaw location at 1/4t is 1.9607 inches. Appendix C lists the ANSYS files included in the electronic supporting files. Note that only the finite element model developed in Reference [9] is used in this calculation; the Green's Function was not utilized.

The analyzed transient "Increase to Rated Power" is associated with the startup/shutdown event for the feedwater nozzle [14]. The evaluated shock is from 550'F to 1007F, which represents the design basis definition for this event. Figure 3-3 of Reference [18] shows a plant specific Turbine Roll transient for Unit I to be a shock from 485°F to 161'F. Even considering a potential 357F feedwater temperature, page 4 of Appendix G states that the 1617F temperature would drop to 123°F [18]. Both of these are bounded by the analyzed 5507F to 100°F shock.

4.0 CALCULATIONS The P-T curves in this calculation were developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SI's QA Program.

The polynomial stress coefficients in Table I were applied to Equations 4 and 8. The resulting pressure stress intensity (Kip-applied) and thermal stress intensity (Kt) factors are 86.72 ksi'lin and 45.60 ksi/in, respectively.

4.1 Pressure Test (Curve A)

The minimum bolt-up temperature of 60'F is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K,,) is calculated for all regions using Equation 1. The resulting value of K1t, along with a safety factor of 1.5, is used in Equation 2 to calculate the pressure stress intensity (Kip)- The allowable RPV pressure is calculated for the beltline, bottom head, and upper vessel regions using Equations 5, 6, and 7, respectively. For the feedwater nozzle / upper vessel region, the additional constraints specified in Step 7 of Section 2.0 are applied.

Final P-T limits for temperature and pressure are obtained from Equations 9 and 10, respectively.

The data resulting from each P-T curve calculation was tabulated. Values for the beltline region at 28, 36, and 46 EFPY are given in Table 2, Table 3, and Table 4, respectively. Data for the bottom head region is listed in Table 5, and data for the feedwater nozzle / upper vessel region is presented in Table

6. The data for each region was graphed, and the resulting P-T curves for 28, 36, and 46 EFPY are ided in Figure 1, Figure 2, and Figure 3, respectively.

File No.: 0800297.301 Page 10 of 47 Revision: 1 F0306-OIRO

U Structural Integrity Associates, Inc.

4.2 Normal Operation - Core Not Critical (Curve B)

The minimum bolt-up temperature of 60'F is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (K1t) is calculated for all regions using Equation 1. The thermal stress intensity factor (K,,) is calculated for the beltline and bottom head regions using Equation 3, and for the feedwater nozzle using Equation 4.

The resulting values of Kic and Kit, along with a safety factor of 2.0, are used in Equation 2 to calculate the pressure stress intensity (Kip). The allowable RPV pressure was calculated for the beltline, bottom head, and upper vessel regions using Equations 5, 6, and 7, respectively. For the feedwater nozzle /

upper vessel region, the additional constraints specified in Step 7 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtained from Equations 9 and 10, respectively.

The data resulting from each P-T curve calculation was tabulated. Values for the beltline region at 28, 36, and 46 EFPY are given in Table 7, Table 8, and Table 9, respectively. Data for the bottom head region is listed in Table 10, and data for the feedwater nozzle / upper vessel region is presented in Table

11. The data for each region was graphed, and the resulting P-T curves for 28, 36, and 46 EFPY are provided in Figure 4, Figure 5, and Figure 6, respectively.

4.3 Normal Operation - Core Critical (Curve C)

The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions. The initial evaluation temperature is calculated as the limiting closure flange region RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: 40'F per Section 3.0) plus 60'F, resulting in a minimum critical temperature of 100'F. When the pressure exceeds 20% of the pre-service system hydro-test pressure (20% of 1,875 psig = 375 psig), the P-T limits are specified as 40'F higher than the Curve B values. The minimum temperature above the 20%

pressure transition point is always greater than the reference temperature (RTNDT) of the closure region plus 160'F, or the temperature required for the hydrostatic pressure test. The final Curve C values are taken as the absolute maximum between the three regions of Curve B P-T curves.

Tabulated overall values for Curve C are provided at 28, 36, and 46 EFPY in Table 12, Table 13, and Table 14, respectively. The corresponding P-T curves for 28, 36, and 46 EFPY are provided in Figure 7, Figure 8, and Figure 9, respectively.

5.0 CONCLUSION

S P-T curves were calculated for NMP-1 for 28, 36, and 46 EFPY using the methodology in Section 2.0 and the design inputs and assumptions defined in Section 3.0. A full set of P-T curves were computed, including the following plant conditions: Operating Pressure (Leak) Test (Curve A), Normal Operation -

Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C). Calculations were performed for the beltline, bottom head, and feedwater nozzle / upper vessel regions. Values for the File No.: 0800297.301 Page 11 of 47 Revision: I F0306-OIRD

V Structural Integrity Associates, Inc.

beltline regions were computed at 28, 36, and 46 EFPY. The calculations were performed in accordance with the PTLR methodology approved by the NRC in Reference [3].

Tabulated pressure and temperature values are provided for all regions in Table 2 through Table 14. The accompanying P-T curve plots are provided in Figure 1 through Figure 9.

File No.: 0800297.301 Revision: I Page 12 of 47 F0306-OIRO

Structural Integrity Associates, Inc.

6.0 REFERENCES

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components 2001 Edition including the 2003 Addenda.

2. Part 50 U.S. Code of Federal Regulations, Title 10, EneEgy Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix G, "Fracture Toughness Requirements," (60 FR 65474, Dec. 19, 1995; 73 FR 5723, Jan. 31, 2008).

3. Structural Integrity Associates Report No. SIR-05-044A, Revision 0, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," April 2007, SI File No. GE-10Q-401.

4. Structural Integrity Associates Calculation No. 0800297.300, Revision 1, "Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts."

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

6. MPM Report No. MPM-59838, "Pressure-Temperature Operating Curves for Nine Mile Point Unit 1," May 1998, S1 File No. NMP-05Q-207.

7. Previous Structural Integrity Associates P-T Curve Calculations for NMP-]:

a. NMP-05Q-301, Revision 0, "Benchmark Analysis."

b. NMP-05Q-302, Revision 0, "NMP-1 P-T Curves Generated Using Code Case N-640.".

8. ANSYS/Mechanical Release 6.1 (w/Service Packs 2 and 3), ANSYS, Inc., April 2002.

9. Structural Integrity Associates Calculation No. NMP-09Q-302, Revision 0, "Feedwater Nozzle Green's Functions for Nine Mile Point Unit I."

10. Combustion Engineering, Inc. Report No. CENC-1142, "Analytical Report for Niagara Mohawk Reactor Vessel," SI File No. NMP-09Q-246.

11. GE Specification 21AA 1104, Revision 0, "Reactor Pressure Vessel," SI File No. NMP-09Q-292.

12. Nine Mile Point Unit 1 Updated Final Safety Analysis Report:

a.Section V, "Reactor Coolant System," Revision 16, Table V-i, p. 3 of 3, November 1999, SI File No. NMP-09Q-23 1.

b.Section V, "Reactor Coolant System," Revision 17, Table V-I, p. 1 of 3, October 2001, SI File No. NMP-09Q-23 1.

c.

Section V, "Reactor Coolant System," Revision 16, p. V-12, November 1999, SI File No.

NMP-09Q-23 1.

d.Section I, Revision 17, p. 1-10, October 2001, SI File No. 0800297.215.

13. Westinghouse Report No. DNS-03-001, "Document Transmittal," January 20, 2003, SI File No.

0800297.213.

File No.: 0800297.301 Page 13 of 47 Revision: I F0306-O1RO

6 Structural Integrity Associates, Inc-

14. G.E. Drawing No. 237E434, "Loadings Reactor Vessel," Note: Revision and Sheet Number not legible, SI File No. NMP-09Q-225.

15. ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition w/ Addenda through 2003.

16. Email from G. Inch (NMP) to T. Griesbach (SI), "FW: NMP1 Pressure Test Pressure," October 10, 2008 11:58AM, SI File No. 0800297.214.

17. Niagara Mohawk letter M97-080 to Dr. Michael P. Manahan, Sr., "Re: Instrument Uncertainty for PT Curves," December 18, 1997, SI File No. NMP-05Q-201.

18. MPR Associates Inc. Report No. MPR-1484, Revision 1, "Nine Mile Point Unit I Feedwater Nozzle Fatigue Evaluation," March 1999, SI File No. 0800297.216.

File No.: 0800297.301 Revision: I Page 14 of 47 F0306-O1RO

V Structural Integrity Associates, Inc.

Table 1: NMIP-1 Polynomial Coefficients for Feedwater Nozzle Stress Intensity Distributions File No.: 0800297.301 Revision: I Page 15 of 47 F0306-OIRO

V Structural Integrity Associates, Inc-Table 2: NMP-1 Beltline Region, Curve A, for 28 EFPY Plant NMP I

Component =

i Vessel thickness, t 2

7 S

inches Vessel Radius, R II0,,

inches ART -

1 F.....

2 K, -

(no thermal effects)

Safety Factor =

I1 i

M,,,

27 erature Adjustment I

'°F (instrument unceri ressure Adjustment 2

2 psig (hydrostatic pres ressure Adjustment I

(i psig (instrument unci 8 EFPY Tempi Pr Pr

[ainty) sure head for a full vessel at 70°F) ertainty)

Guage Fluid Temperature (F) 56 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 K36 2ksi-8in) 36.28 36.28 36.40 36.53 36.67 36-81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38-81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41,23 41.56 41,90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 (ksi sin) 24.18 24.18 24.27 24.36 24.45 24.54 24.64 24.74 24.85 24.96 25.07 25.19 25.32 25.45 25.58 25.72 25.87 26.02 26.18 26.35 26.52 26.70 26.88 27.08 27.28 27.49 27.71 27.94 28.17 28.42 28.68 28.94 29.22 29.51 29.81 30.12 30.45 30.79 31.14 31.51 31.89 32.29 32.71 33.14 Guage Pressure (psig) 0 655 657 659 662 664 667 670 673 676 679 682 685 689 692 696 700 704 709 713 718 723 728 733 738 744 750 756 763 769 776 783 791 799 807 815 824 833 843 853 863 874 885 897 Temperature for P-T Curve (F) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 Adjusted Pressure for P-T Curve (psig) 0 617 619 622 624 627 629 632 635 638 641 644 648 651 655 659 663 667 671 675 680 685 690 695 701 706 712 718 725 732 738 746 753 761 769 778 787 796 805 815 826 836 848 859 File No.: 0800297.301 Revision: I Page 16 of 47 F0306-OIRO

Structural Integrity Associates, Inc-Table 2 Continued: NMP-1 Beltline Region, Curve A, for 28 EFPY Adjusted Guage Fluid Temperature Pressure for Temperature K,

Guage for P-T Curve P-T Curve

(°F)

K, (ksi.Vin)

(ksi-.in)

Pressure (psig)

(°F)

(psig) 142 50.38 33.59 909 146 871 144 51.08 34.05 922 148 884 146 51,81 34.54 935 150 897 148 52.57 35.05 949 152 911 150 53.36 35.57 963 154 925 152 54.18 36.12 978 156 940 154 55.04 36.69 993 158 956 1S6 55.93 37.29 1009 160 972 158 56.86 37.91 1026 162 988 160 57.83 38.55 1043 164 1006 162 58.83 39.22 1062 166 1024 164 59.88 39.92 1080 168 1043 166 60.96 40.64 1100 170 1062 168 62.10 41.40 1121 172 1083 170 63.28 42.18 1142 174 1104 172 64.50 43.00 1164 176 1126 174 65.78 43.85 1187 178 1149 176 67.11 44.74 1211 180 1173 178 68.50 45.66 1236 182 1198 180 69.94 46.62 1262 184 1224 182 71.44 47.62 1289 186 1251 184 73.00 48.66 1317 188 1280 186 74.62 49.75 1346 190 1309 188 76.31 50.87 1377 192 1339 190 78.07 52.05 1409 194 1371 192 79.90 53.27 1442 196 1404 194 81.81 54.54 1476 198 1438 196 83.79 55.86 1512 200 1474 198 85.86 57.24 1549 202 1512 200 88.00 58.67 1588 204 1550 202 90.24 60.16 1628 206 1591 204 92.57 61.71 1670 208 1633 206 94.99 63.33 1714 210 1676 208 97.51 65.01 1760 212 1722 210 100.14 66.76 1807 214 1769 212 102.87 68.58 1856 216 1819 214 105.71 70.48 1908 218 1870 216 108.67 72.45 1961 220 1923 File No.: 0800297.301 Page 17 of 47 Revision: I F0306-OIRO

C Structural Integrity Associates, Inc.

Table 3: NWP-1 Beitline Region, Curve A, for 36 EFPY Plant:

I

~MP1 Component Befhl i

Vessel thickness, t =.

inches Vessel Radius, R :

O" inches ART 1Yý5o

°F=====>

36 EFPY K1, 0

n(so thermal effects)

Safety Factor =

i Temperature Adjustment =

0 F (instrument uncertainty)

Pressure Adjustment 7

2 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment =

I(, f, psig (instrument uncertainty)

Adjusted Temperature Pressure for Guage Fluid Temperature (CF) 56 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 K

3ý (ksi-Vin) 35.84 3S.84 35.95 36.06 36.18 36.30 36.43 36.56 36.70 36.84 36.99 37.14 37.30 37.47 37.64 37.83 38.02 38.21 38.42 38.63 38.85 39.08 39.32 39.57 39.83 40.10 40.38 40.68 40.98 41.30 41.63 41.97 42.33 42.70 43.09 43.50 43.92 44.35 44.81 45.28 45.78 46.29 46.82 47.38 Ri.

(ksi-Vin) 23.90 23.90 23.97 24.04 24.12 24.20 24.29 24.37 24.46 24.56 24.66 24.76 24.87 24.98 25.10 25.22 25.34 25.47 25.61 25.75 25.90 26.05 26.21 26.38 26.55 26.73 26.92 27.12 27.32 27.53 27.75 27.98 28.22 28.47 28.73 29.00 29.28 29.57 29.87 30.19 30.52 30.86 31.22 31.59 Guage Pressure (psig) 0 647 649 651 653 655 657 660 662 665 667 670 673 676 679 683 686 690 693 697 701 705 710 714 719 724 729 734 739 745 751 757 764 771 778 785 792 800 809 817 826 835 845 855 for P-T Curve

('F) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 P-T Curve (psig) 0 609 611 613 615 617 620 622 625 627 630 633 635 638 642 645 648 652 656 659 663 668 672 676 681 686 691 696 702 708 714 720 726 733 740 747 7S5 763 771 779 788 798 807 817 File No.: 0800297.301 Revision: I Page 18 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 3 Continued: NMP-1 Beltline Region, Curve A, for 36 EFPY Guage Fluid Temperature

('F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 K,,

(ksi-V-in) 47.96 48.56 4919 49.84 50.52 51.23 51.96 52.73 53.52 54-35 55.22 56.11 57.05 58.02 59.04 60.09 61.19 62.33 63.52 64.76 66.04 67.38 68.78 70.23 71.74 73.32 74.95 76.66 78.43 80.28 82.20 84.20 86.28 88.44 90.70 93.05 95.49 98.03 100.68 103.43 106.30 109.28 Klý (ksi.Vin) 31.97 32.37 32.79 33.23 33.68 34.15 34.64 35.15 35.68 36.24 36.81 37.41 38.03 38.68 39.36 40.06 40.79 41.55 42.35 43.17 44.03 44.92 45.85 46.82 47.83 48.88 49.97 51.10 52.29 53.52 54.80 56.13 57.52 58.96 60.47 62.03 63.66 65.35 67.12 68.95 70.86 72.85 Temperature Guage for P-T Curve Pressure (psig)

('F)

Adjusted Pressure for P-T Curve (psig) 865 876 888 899 912 924 938 951 966 981 996 1013 1029 1047 1065 1084 1104 1125 1146 1168 1192 1216 1241 1267 1295 1323 1352 1383 1415 1449 1483 1519 1557 1596 1637 1679 1723 1769 1817 1866 1918 1972 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 828 839 850 862 874 887 900 914 928 943 959 975 992 1009 1028 2047 1066 1087 1108 1131 1154 1178 1203 1230 1257 1285 1315 1346 1378 1411 1446 1482 1519 1558 1599 1641 1685 1731 1779 1829 1880 1934 File No.: 0800297.301 Revision: I Page 19 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 4: N P-1 Beltline Region, Curve A, for 46 EFPY Plant:-

W11111 i Component

.ý "t

ine Vessel thickness, t 7 121ý inches Vessel Radius, R =

H 1; inches ART 6=74 "F=====>

46 EFPY K :=

(no thermal effects)

Safety Factor =

I Temperature Adjustment I

F (instrument uncertainty)

Pressure Adjustment 27 7 psig (hydrostatic pressure head for a full vessel at 70F)

Pressure Adjustment =

t C.

psig (instrument uncertainty)

Guage Fluid Temperature

(°F)

Kjo 56 S6 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 306 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 (ksi-Vin) 35.43 35.43 35.53 35.62 35.72 35,82 35.93 36.04 36-16 36.28 36.40 36.53 36.67 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 -

41.23 41.56 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 K1.

(ksi.Vin) 23.62 23.62 23.68 23.75 23.81 23.88 23.95 24.03 24.10 24.18 24.27 24.36 24.45 24.54 24.64 24.74 24.85 24.96 25.07 25.19 25.32 25.45 25.58 25.72 25.87 26.02 26.18 26.35 26.52 26.70 26.88 27.08 27.28 27.49 27.71 27.94 28.17 28.42 28.68 28.94 29.22 29.51 29.81 30.12 Guage Pressure (psig) 0 639 641 643 645 646 648 650 652 655 657 659 662 664 667 670 673 676 679 682 685 689 692 696 700 704 709 713 718 723 728 733 738 744 750 756 763 769 776 783 791 799 807 815 Temperature for P-T Curve

(*F) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 Adjusted Pressure for P-T Curve (psig) 0 602 603 605 607 609 611 613 615 617 619 622 624 627 629 632 635 638 641 644 648 651 655 659 663 667 671 675 680 685 690 695 701 706 712 718 725 732 738 746 753 761 769 778 File No.: 0800297.301 Revision: 1 Page 20 of 47 F0306-OI RO

V Structural Integrity Associates, Inc.

Table 4 Continued: NMP-1 Beltline Region, Curve A, for 46 EFPY Guage Fluid Temperature i(F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 Kc (ksi-Vin) 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 50.38 51.08 51.81 52,57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 Km (ksiVin) 30.45 30.79 31.14 31.51 31.89 32.29 32.71 33.14 33.59 34.05 34.54 35.05 35.57 36.12 36.69 37.29 37.91 38.55 39.22 39.92 40.64 41.40 42.18 43.00 43.85 44.74 45.66 46.62 47.62 48.66 49.75 50.87 52.05 53.27 54.54 55.86 57.24 58.67 60.16 61.71 63.33 65.01 66.76 68.58 70.48 72.45 Temperature Guage for P-T Curve Pressure (psig)

('F)

Adjusted Pressure for P-T Curve (psig) 824 833 843 853 863 874 885 897 909 922 935 949 963 978 993 1009 1026 1043 1062 1080 1100 1121 1142 1164 1187 1211 1236 1262 1289 1317 1346 1377 1409 1442 1476 1512 1549 1588 1628 1670 1714 1760 1807 1856 1908 1961 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 787 796 805 815 826 836 848 859 871 884 897 911 925 940 956 972 988 1006 1024 1043 1062 1083 1104 1126 1149 1173 1198 1224 1251 1280 1309 1339 1371 1404 1438 1474 1512 1550 1591 1633 1676 1722 1769 1819 1870 1923 File No.: 0800297.301 Revision: I Page 21 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 5: NMP-1 Bottom Head Region, Curve A, for all EFPY Plant =

Component Bottom Head thickness, t Bottom Head Radius, R ART Kit=

Safety Factor Stress Concetration Factor =

M

=

Temperature Adjustment =

Pressure Adjustment Pressure Adjustment penetrations portion) nches inches

°F====>

All EFPY (no thermal effects)

(bottom head penetrations)

°F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70*F) psig (instrument uncertainty)

Guage Fluid Temperature

('F) 56 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 File No.: 0800297.301 Revision: I K

67 (ksi-Vin) 61.75 61.75 62.92 64-13 65-39 66.71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.3S 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 K1,,,

(ksi.Vin(

41.17 41.17 41.95 42.75 43.60 44.47 45.38 46.33 47.32 48.35 49.42 50,53 51.69 52.90 54.15 55.46 56.82 58.23 59.71 61.24 62.84 64.50 66.23 68.03 69.90 71.85 73.88 75.99 78.19 80.47 82.86 85.33 87.91 90.60 93.39 96.30 99.33 Guage Pressure (psig) 0 822 837 853 870 887 906 925 944 965 986 1008 1031 1056 1081 1107 1134 1162 1191 1222 1254 1287 1322 1357 1395 1434 1474 1516 1560 1606 1653 1703 1754 1808 1864 1922 1982 Temperature for P-T Curve (7F) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 Adjusted Pressure for P-T Curve (psig) 0 784 799 816 832 850 868 887 907 927 948 971 994 1018 1043 1069 1096 1124 1154 1184 1216 1249 1284 1320 1357 1396 1437 1479 1523 1568 1616 1665 1717 1770 1826 1884 1944 Page 22 of 47 F0306-OIRO

Structural Integrity Associates, Inc.

Table 6: NMP-1 Upper Vessel Region, Curve A, for all EFPY Plant =

J7 Component =.Itfpper esuef ART =

i(

I F===

All EFPY Vessel Radius =

I inches Nozzle corner thickness, t =

inches Nozzle K,,

io thermal effects)

Nozzle K,,

=

ksi-Vin Crack Depth, a =

inches Safety Factor =

Temperature Adjustment =-

1 1, F (instrument uncertainty)

Pressure Adjustment =

psig (hydrostatic pressure head for a full vessel at 70"F)

Pressure Adjustment =

psig (instrument uncertainty)

Reference Pressure =

I "I

-psig (pressure at which FEA stress coefficients are valid) (GREEN]

Unit Pressure =

) I i i.psig (hydrostatic pressure)

Flange RT0 o =

0 f,

F=====

All EFPY P-T Curve Guage Fluid P-T Cuaie IOCFRSO Temperature K.

Guage Temperature Adjustments

(*F)

Ku (ksi-Vin)

(ksi-Vin)

Pressure (psig) 1,F)

(psig) 56 61.75 41.17 0

60 0

56 61.75 41.17 475 60 375 58 62.92 41.95 484 130 375 60 64.13 42.75 493 130 455 62 65.39 43.60 503 130 465 64 66.71 44.47 513 130 475 66 68.08 45.38 523 130 486 68 69.50 46.33 534 130 497 70 70.98 47.32 546 130 50a 72 72.52 48.35 557 130 520 74 74.13 49.42 570 130 532 76 75.80 50.53 583 130 545 78 77.54 51.69 596 130 558 80 79.34 52.90 610 130 572 82 81.23 54.15 624 130 587 84 83.19 55.46 639 130 602 86 85.23 56.82 655 130 618 88 87.35 58.23 671 130 634 90 89.56 59.71 688 130 651 92 91.86 61024 706 130 669 94 94.25 62.84 725 130 687 96 96.75 64,50 744 130 706 98 99.34 66.23 784 130 726 100 102.04 68,03 784 130 747 102 104.85 69.90 806 130 768 104 10777 71,85 828 130 791 106 110.82 73.88 852 130 814 108 113.98 75.99 876 130 839 110 117.28 78.19 902 130 864 112 120-71 80.47 928 130 890 114 124.28 82.86 955 130 918 116 128.00 85.33 984 130 946 118 131.87 87.91 1014 130 976 120 135.90 90.60 1045 130 1007 122 140.09 93.39 1077 130 1039 124 144.45 96.30 1110 130 1073 126 148.99 99.33 1145 130 1108 128 153.72 102.48 1182 132 1144 130 158.63 105.76 1219 134 1182 132 163.75 109.17 1259 136 1221 134 169.08 112.72 1300 138 1262 136 174.63 126.42 1342 140 1305 138 180.40 120.26 1387 142 1349 140 186.40 124.27 1433 144 1395 142 192.66 128.44 1481 146 1443 144 199.16 132.78 1531 148 1493 146 205.94 137.29 1583 150 1545 148 212.99 141.99 1637 152 1600 150 220.32 146.88 1694 154 1656 152 227.96 151.97 1752 156 1715 154 235.91 157.27 1814 158 1776 156 244.18 162.79 1877 160 1839 158 252.79 168.53 1943 162 1906 File No.: 0800297.301 Page 23 of 47 Revision: I F0306-OIRO

V Structural Integrity Associates, Inc.

Table 7: NMP-1 Beltline Region, Curve B, for 28 EFPY Component =-

b' Mi; Vessel thickness, t I

inches Vessel Radius, R =

1065 inches ART-I s

1 "F==z==>

28 EFPY Kt =I i 93.

ksi-Vin Safety Factor =

0 MM 247 Temperature Adjustment ='

°F (instrument uncertainty)

Pressure Adjustment 27 psig (hydrostatic pressure head for a full vessel at 70'F)

Pressure Adjustment =

2Z*

psig (instrument uncertainty)

Heat Up and Cool Down Rate 100 F/Hr Adjusted Guage Fluid Temperature Pressure for Temperature K,.

Guage for P-T Curve P-T Curve (F)

K,,

(ksi.Vin) lksi-An)

Pressure (psig) 11F)

(psie) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 35.82 35.82 35.93 36.04 36.16 36.28 36.40 36.53 36.67 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41.23 41.56 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 11.45 11.45 11.51 11.56 11.62 11.68 11.74 11.81 11.88 11.95 12.02 12.10 12.18 12.26 12.35 12.44 12.53 12.63 12.73 12.84 12.95 13.06 13.18 13.30 13.43 13.57 13.71 13.85 14.00 14.16 14.32 14.50 14.67 14.86 15.05 15.25 15.46 15.68 15.90 16.14 16.38 16.64 16.90 17.18 17.46 17,76 18.07 18.40 310 310 311 313 315 316 318 320 321 323 325 327 330 332 334 337 339 342 345 347 350 353 357 360 364 367 371 375 379 383 388 392 397 402 407 413 418 424 430 437 443 450 457 465 473 481 489 498 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 0

230 232 233 235 236 238 240 242 244 246 248 250 2S2 254 257 259 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 364 370 378 385 393 401 409 418 File No.: 0800297.301 Revision: I Page 24 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 7 Continued: NMP-1 Beltline Region, Curve B, for 28 EFPY Guage Fluid Temperature

('F)

Adjusted Temperature Pressure for Kjý Guage for P-T Curve P-T Curve K,,

(ksi-Vin)

(ksi.Vin)

Pressure (psig)

('F)

(psig) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 50.38 51,08 51,81 52,57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 111.75 114.96 118.30 121.77 125.38 129.14 133.06 137.14 141.38 145.79 150.39 155.17 160.15 18.73 19.08 19.45 19.83 20.22 20.64 21.06 21.51 21.97 22.46 22.96 23.48 24.03 24.59 25.18 25.80 26.43 27.10 27.79 28.51 29.26 30.04 30.85 31.70 32.58 33.49 34.45 35.44 36.47 37.55 38.66 39.83 41.04 42.30 43.61 44.98 46.40 47.88 49.42 51.02 52.69 54.43 56.23 58.12 60.07 62.11 64.23 66.44 68.74 71.13 73.62 507 517 526 537 547 559 570 582 595 608 621 636 650 666 682 698 715 733 752 772 792 813 835 858 882 907 932 959 987 1016 1046 1078 1111 1145 1180 1217 1256 1296 1338 1381 1426 1473 1522 1573 1626 1681 1739 1798 1860 1925 1993 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 427 437 447 457 468 479 490 502 515 528 542 556 570 586 602 618 636 654 672 692 712 733 755 778 802 827 852 879 907 936 967 998 1031 1065 1101 1138 1176 1216 1258 1301 1346 1393 1442 1493 1546 1601 1659 1718 1781 1845 1913 File No.: 0800297.301 Revision: I Page 25 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 8: N P-1 Beltline Region, Curve B, for 36 EFPY Plant Component Vessel thickness, t:

Vessel Radius, R ART Kl, Safety Factor Mv Temperature Adjustment Pressure Adjustment Pressure Adjustment Heat Up and Cool Down Rate full vessel at 70*F)

Guage Fluid Temperature

('F)

Adjusted Temperature Pressure for Ku, Guage for P-T Curve P-T Curve K,

(ksi.Vin)

(ksi-Vin)

Pressure !psig)

(*F)

(psigj 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 35.45 35.45 35.54 35.64 35.74 35.84 35.95 36.06 36.18 36.30 36.43 36.56 36.70 36.84 36.99 37.14 37.30 37.47 37.64 37.83 38.02 38.21 38.42 38.63 38.85 39.08 39.32 39.S7 39.83 40.10 40.38 40.68 40.98 41.30 41.63 41.97 42.33 42.70 43.09 43.50 43.92 44.35 44.81 45.28 45.78 46.29 46.82 47.38 11.27 11.27 11.31 11.36 11.41 11.46 11.52 11.57 11.63 11.69 11.76 11.82 11.89 11.96 12.04 12.11 12.19 12.28 12.37 12.46 12.55 12.65 12.75 12.86 12.97 13.08 13.20 13.33 13.46 13.59 13.73 13.88 14.03 14.19 14.36 14.53 14.71 14.90 15.09 15.29 15.50 15.72 15.95 16.18 16.43 16.69 16.95 17.23 305 305 306 308 309 310 312 313 315 317 318 320 322 324 326 328 330 332 335 337 340 342 345 348 351 354 357 361 364 368 372 376 380 384 389 393 398 403 408 414 420 425 432 438 445 452 459 466 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 10 152 0

22S 226 228 229 230 232 233 235 237 238 240 242 244 246 248 250 252 255 257 260 263 265 268 271 274 278 281 284 288 292 296 300 304 309 313 318 323 329 334 340 346 352 358 365 372 379 387 File No.: 0800297.301 Revision: 1 Page 26 of 47 F0306-OIRO

C Structural integrity Associates, Inc.

Table 8 Continued: NMP-1 Beltline Region, Curve B, for 36 EFPY Guage Fluid Temperature

("F)

Adjusted Temperature Pressure for K,.

Guage for P-T Curve P-T Curve Kt.

ksi-Vin) fksi-Vin)

Pressure (psiw) fly)

[psiR) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 47,96 48.56 49.19 49.84 50.52 51.23 51.96 52.73 53.52 54.35 55.22 56.11 57.05 58.02 59.04 60.09 61.19 62.33 63.52 64.76 66.04 67.38 68.78 70.23 71.74 73.32 74.95 76.66 78.43 80.28 82.20 84.20 86.28 88.44 90.70 93.05 95.49 98.03 100.68 103.43 106.30 109.28 112.38 115.62 118.98 122.48 126.12 129.92 133.86 137.97 142.25 146.70 151.33 156.15 161.17 17.52 17.82 18.14 18.46 18.80 19.16 19.52 19.91 20.30 20.72 21.15 21.60 22.07 22.55 23.06 23.59 24.14 24.71 25.30 25.92 26.57 27.24 27.93 28.66 29.41 30.20 31.02 31.87 32.76 33.68 34.64 35.64 36.68 37.77 38.89 40.07 41.29 42.56 43.88 45.26 46.69 48.18 49.74 51.35 53.03 54.78 56.60 58.50 60.47 62.53 64.67 66.89 69.21 71.62 74.13 474 482 491 500 509 518 528 539 550 561 572 585 597 610 624 638 653 669 685 702 719 737 756 776 796 817 840 863 887 912 938 965 993 1022 1053 1084 1118 1152 1188 1225 1264 1304 1346 1390 1435 1483 1532 1583 1637 1692 1750 1811 1873 1938 2006 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 394 403 411 420 429 439 449 459 470 481 493 505 517 531 544 559 573 589 605 622 639 657 676 696 716 738 760 783 807 832 858 885 913 942 973 1005 1038 1072 1108 1145 1184 1224 1266 1310 1356 1403 1452 1504 1557 1613 1670 1731 1793 1859 1926 File No.: 0800297.301 Revision: I Page 27 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

Table 9: NMP-1 Beltline Region, Curve B, for 46 EFPY Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ART =

K,=

Safety Factor Mm =

Temperature Adjustment =

Pressure Adjustment =

Pressure Adjustment:

Heat Up and Cool Down Rate =

nches nches F=====>

46 EFPY ksi-Vin F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70"F) psig (instrument uncertainty)

F/Hr Guage Fluid Temperature

('F)

Adjusted Temperature Pressure for K.m Guage for P-T Curve P-T Curve K.,

(ksi-Vin)

(ksi-Vin)

Pressure (psig)

(F)

(psig) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 35.10 35.10 35.18 35.26 35.35 35.43 35.53 35.62 35.72 35.82 35.93 36.04 36.16 36.28 36.40 36.53 36.67 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41.23 41.S6 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 11.09 11.09 11.13 11.17 11.22 11.26 11.31 11.35 11.40 11.45 11.51 11.56 11.62 11.68 11.74 11.81 11.88 11.95 12.02 12.10 12.18 12.26 12.35 12.44 12.53 12.63 12.73 12.84 12.95 13.06 13.18 13.30 13.43 13.57 13.71 13.85 14.00 14.16 14.32 14.50 14.67 14.86 15.05 15.25 15.46 15.68 15.90 16.14 300 300 301 302 304 305 306 307 309 310 311 313 315 316 318 320 321 323 325 327 330 332 334 337 339 342 345 347 35O 353 357 360 364 367 371 375 379 383 388 392 397 402 407 413 418 424 430 437 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 0

220 221 223 224 225 226 227 229 230 232 233 235 236 238 240 242 244 246 248 250 252 254 257 259 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 File No.: 0800297.301 Revision: I Page 28 of 47 F0306-OIRO

Structural Integrity Associates, Inc.

Table 9 Continued: NMP-1 Beltline Region, Curve B, for 46 EFPY Adjusted Guage Fluid Temperature Pressure for Temperature K,,

Guage for P-T Curve P-T Curve 1[F) _

K,f (ksi.Vin) fksi.Vin)

Pressure (psig)

('F) fpsig) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 50.38 51.08 51.81 52.57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 111.75 114.96 128.30 121.77 125.33 129.14 133.06 137.14 141.38 145.79 150.39 155.17 160.15 16.38 16.64 16.90 17.18 17.46 17.76 18.07 18.40 18.73 19.08 19.45 19.83 20.22 20.64 21.06 21.51 21.97 22.46 22.96 23.48 24.03 24.59 25.18 25.80 26.43 27.10 27.79 28.51 29.26 30.04 30.85 31.70 32.58 33.49 34.45 35.44 36.47 37.55 38.66 39.83 41.04 42.30 43.61 44.98 46.40 47.88 49.42 51.02 52.69 54.43 56.23 58.12 60.07 62.11 64.23 66.44 68.74 71.13 73.62 443 450 457 465 473 481 489 498 507 517 526 537 547 559 570 582 595 608 621 636 65O 666 682 698 715 733 752 772 792 813 835 858 882 907 932 959 987 1016 1046 1078 1111 1145 1180 1217 1256 1296 1338 1381 1426 1473 1522 1573 1626 1681 1739 1798 1860 1925 1993 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 264 256 268 270 364 370 378 385 393 401 409 418 427 437 447 457 468 479 490 502 515 528 542 556 570 586 602 618 636 654 672 692 712 733 755 778 802 827 852 879 907 936 967 998 1031 1065 1101 1138 1176 1216 1258 1301 1346 1393 1442 1493 1546 1601 1659 1718 1781 1845 1913 File No.: 0800297.301 Revision: 1 Page 29 of 47 F0306-OIRO

E Structural integrity Associates, Inc.

Table 10: NM1P-1 Bottom Head Region, Curve B, for all EFPY Plant-t4P.<

Component =

t, (penetrations portion)

Bottom Head thickness, t =

8 inches Bottom Head Radius, R t

inches ART 400 F===U- >

All EFPY K. =

I S

• ~ ks/-'n Safety Factor =

m Stress Concetration Factor =

(bottom head penetrations)

Temperature Adjustment -

• F (instrument uncertainty)

Pressure Adjustment- =

i" psig (hydrostatic pressure head for a full vessel at 70"F)

P res.ure Adjustment -

5 psig (instrumnent uncertainty)

Heat Up and Cool Down Rate =p 1

'F/Hr Adjusted Guage Fluid Temperature Pressure for Temperature K,

Guage for P-T Curve P-T Curve

(*Fl K-(ksi.Vin)

Iksi.Vin)

Pressure fosie)

['F)

()sie) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 88 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 57.53 57.53 58.52 59,56 60,63 6175 6292 64.13 65.39 66,71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 153.72 158.63 163.75 169.08 174.63 180.40 186.40 192.66 199.16 205.94 212.99 220.32 17.97 17.97 18.47 18.99 19.53 20.09 20.67 21.27 21.91 22.56 23.25 23.96 24.70 25.47 26.27 27.11 27.98 28.88 29.82 30.80 31.82 32.88 33.99 35.14 36.34 37.58 38.88 40.23 41.63 43.09 44.62 46.20 47.85 49.56 51.35 53.21 55.14 S7.16 59.25 61.43 63.70 66.07 68.S3 71.08 73.75 76.S2 79.41 82.41 85.54 88.79 92.18 95.70 99.37 0

60 359 60 369 62 379 64 390 66 401 68 412 70 425 72 437 74 450 76 464 78 478 80 493 82 S08 84 524 86 541 88 558 90 576 92 595 94 615 96 635 98 656 100 678 102 701 104 725 106 750 108 776 110 803 112 831 114 860 116 890 118 922 120 955 122 989 124 1025 126 1062 128 1100 130 1141 132 1182 134 1226 136 1271 138 1318 140 1367 142 1419 144 1472 146 1527 148 1185 ISO 1645 152 1707 154 1772 156 1839 158 1910 160 1983 162 0

279 289 299 310 321 333 345 357 370 384 398 413 428 444 461 478 496 515 535

$55 576 598 621 645 670 696 723 751 780 810 842 875 909 945 982 1021 1061 1103 1146 1191 1239 1288 1339 1392 1447 1505 1565 1627 1692 1760 1830 1903 File No.: 0800297.301 Revision: 1 Page 30 of 47 F0306-O1RO

V Structural Integrity Associates, Inc.

Table 11: NMP-1 Upper Vessel Region, Curve B, for all EFPY Plant=

N41t Component -

'Up 'pe'Ves e[

ART 40 F...

All EFPY Vessel Radius =

It L) nches Nozzle corner thickness, t 3

riches Nozzle K, 4560 ksi-Vin Nozzle Klpp

.d

<62 si Vie Crack Depth, a I861

-inches Safety Factor =

>>2.{P Temperature Adjustment 1,.

'F (instrument uncertainty)

Pressure Adjustment = i 7-7

)psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment =

5

) psig (instrument uncertainty)

Reference Pressure 1

'1' 000-psig (pressure at which FEA stress coefficients are valid) [GREEN Unit Pressure =

1 I psig (hydrostatic pressure)

Flange RT,0T =

I

>I0' T=

=

All EFPY Guage Fluid Temperature (F)

P-T Curve P-T Curve IOCFR5O K,

Guage Temperature Adjustments K,,

lksi-Vin)

(ksi-Vin)

Pressure (psig)

(F)

(psin) 48 48 so 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 57.53 57.53 58.52 59.56 60.63 61.75 62.92 64.13 65.39 66.71 68.08 69.50 70.98 72.52 74-13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 153.72 158.63 16.74 16.74 17.10 17.48 17.88 18.29 18.73 19.19 19.66 20.17 20.69 21.24 21.82 22.43 23.06 23.73 24.42 25.15 25.91 26.71 27.55 28.43 29.34 30.30 31.31 32.36 33.46 34.61 35.81 37.07 38.38 39.83 41.48 43.20 44.98 46.84 48.78 50.79 52.89 55.07 57.34 59.70 62.16 0

193 197 202 206 211 216 221 227 233 239 245 252 259 266 274 282 290 299 308 318 328 338 349 361 373 386 399 413 427 443 459 478 498 519 540 562 586 610 635 661 688 717 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 130 130 130 130 130 130 132 134 136 138 140 142 0

113 117 122 126 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 259 270 281 293 306 319 333 348 363 375 375 375 375 375 375 375 375 375 375 375 375 File No.: 0800297.301 Revision: I Page 31 of 47 F0306-O1RO

VStructural Integrity Associates, Inc.

Table 11 Continued: NMP-1 Upper Vessel Region, Curve B, for all EFPY P-T Curve Guage Fluid P-T Curve 10CFR50 Temperature K1, Guage Temperature Adjustments

(°F)

K1, (ksi.Vin)

(ksi-Vin)

Pressure (psig)

(°F)

(psig) 132 163.75 64.72 746 144 375 134 169-08 67.38 777 146 375 136 174.63 70.15 809 148 375 138 180.40 73.04 542 150 375 140 186.40 76.04 877 152 375 142 192.66 79.17 913 154 375 144 199.16 82.42 950 156 375 146 205.94 85.81 989 158 375 148 212.99 89.34 1030 160 375 148 212.99 84.61 976 160 896 150 220.32 88.02 1015 162 935 152 227.96 91.58 1056 164 976 154 235.91 95.29 1099 166 1019 156 244.18 99.17 1143 168 1064 158 252.79 103.21 1190 170 1110 160 261.75 107.42 1239 172 1159 162 271.08 111.81 1289 174 1209 164 280.79 116.40 1342 176 1262 166 290.89 121.17 1397 178 1317 168 301.41 126.16 1455 180 1375 170 312.36 131.35 1515 182 1435 172 323.75 136.77 1577 184 1497 174 335.61 142.41 1642 186 1562 176 347.95 148.30 1710 188 1630 178 360.79 154.43 1781 190 1701 180 374.16 160.82 1854 192 1775 182 388.08 167.49 1931 194 1851 184 402.56 174.43 2011 196 1932 File No.: 0800297.301 Page 32 of 47 Revision: I F0306-O1RO

C Structural Integrity Associates, Inc.

Table 12: NMP-1 Curve C Values for 28 EFPY Plant =

Curve A Leak Test Temperature Curve A Leak Test Pressure Unit Pressure Flange RTNDT pressure)

Adjusted P-T Curve Temperature

(°F) 100 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 Adjusted P-T Curve Pressure (psig) 0 113 119 122 126 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 259 270 281 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 364 370 375 375 375 375 375 File No.: 0800297.301 Revision: I Page 33 of 47 F0306-O1 RO

Structural Integrity Associates, Inc.

Table 12 Continued: NMW-1 Curve C Values for 28 EFPY Adjusted P-T CurveAdjusted P-T CurveCurve Temperature Pressure (psig)

(rF) 192 375 194 375 196 375 198 375 200 375 200 457 202 468 204 479 206 490 208 502 210 515 212 528 214 542 216 556 218 570 220 586 222 602 224 618 226 636 228 654 230 672 232 692 234 712 236 733 238 755 240 778 242 802 244 827 246 852 248 879 250 907 252 936 254 967 256 998 258 1031 260 1065 262 1101 264 1138 266 1176 268 1216 270 1258 272 1301 274 1346 276 1393 278 1442 280 1493 282 1546 284 1601 286 1659 288 1718 290 1781 292 1845 294 1913 File No.: 0800297.301 Page 34 of 47 Revision: I F0306-OIRO

V Structural Integrity Associates, Inc.

Table 13: NVP-1 Curve C Values for 36 EFPY Plant =

Curve A Leak Test Temperature =

PF Curve A Leak Test Pressure 1

psig Unit Pressure =*

>87 psig (hydrostatic pressure)

Flange RToT F

O'!

F Adjusted P-T Curve Temperature (7) 100 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 Adjusted P-T Curve Pressure (psig) 0 113 119 122 126 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 259 268 271 274 278 281 284 288 292 296 300 304 309 313 318 323 329 334 340 346 352 358 365 372 375 File No.: 0800297.301 Revision-I Page 35 of 47 F0306-01 RD

IUStructural Integrity Associates, Inc-Table 13 Continued: NMP-1 Curve C Values for 36 EFPY Adjusted P-T Curve Temperature

('F) 192 194 196 198 200 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 264 266 268 270 272 274 276 278 280 282 284 286 288 290 292 294 296 298 300 302 Adjusted P-T Curve Pressure (psig) 375 375 375 375 375 420 429 439 449 459 470 481 493 505 517 531 544 559 573 589 605 622 639 657 676 696 716 738 760 783 807 832 858 885 913 942 973 1005 1038 1072 1108 1145 1184 1224 1266 1310 1356 1403 1452 1504 1557 1613 1670 1731 1793 1859 1926 File No.: 0800297.301 Revision: I Pag~e 36 of 47 F0306-OIRO

V Structural Integrity Associates, Inc-Table 14: NMP-1 Curve C Values for 46 EFPY Plant =

Curve A Leak Test Temperature =

Curve A Leak Test Pressure Unit Pressure =

Flange RTNST

=

Adjusted P-T Curve Temperature

(")

100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200

'Fpsig

-psig (hydrostatic pressure)

Adjusted P-T Curve Pressure (psig) 0 113 119 122 126 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 254 257 259 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 364 370 375 375 File No.: 0800297.301 Revision: I Page 37 of 47 F0306-01R0

V Structural Integrity Associates, Inc.

Table 14 Continued: NMP-1 Curve C Values for 46 EFPY Adjusted P-T Curve Temperature

('F) 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 264 266 268 270 272 274 276 278 280 282 284 286 288 290 292 294 296 298 300 302 304 306 308 310 Adjusted P-T Curve Pressure (psig) 385 393 401 409 418 427 437 447 457 468 479 490 502 515 528 542 556 570 586 602 618 636 654 672 692 712 733 755 778 802 827 852 879 907 936 967 998 1031 1065 1101 1138 1176 1216 1258 1301 1346 1393 1442 1493 1546 1601 1659 1718 1781 1845 1913 File No.: 0800297.301 Revision: I Page 38 of 47 F0306-O1RO

Structural Integrity Associates, Inc.

NMP-1 Pressure Test (Curve A), 28 EFPY 1.900 1,800 1,700 1.600 1.500

.- 1.400 Lj 1.300 0m 1.200 a

Ix 1.1000 got 1,00 D

1.000 z

I-900 700 600 500 400 300 200 100 0

I Bolt-up Temp:

60-F Beltiine Regton

-- - Bottom Head Upper Vessel H

0 20 40 60 80 100 120 140 160 180 200 2.20 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)

Figure 1: NMP-1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 28 EFPY File No.: 0800297.301 Revision: I Page 39 of 47 F0306-0IRO

V Structural Integrity Associates, Inc.

NMP-1 Pressure Test (Curve A), 36 EFPY 1t900 1.800 1,700 1.400 1.500

.2 1.400 1.0 U) 1.2000-8-

1.100 Dm

'ix 6

1.000 z

5 900 4 800 3 700 600 500 400 300 200 100 0

I I I

f Bolt-up Temp:

60:F Beltlin e Region

-- - Bottom Head

............. Upper Vessel

-n

-n B w I

-n

-n 0

20 40 50 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE ("F)

Figure 2: NMP-1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 36 EFPY Page 40 of 47 File No.: 0800297.301 Revision: 1 Page 40 of 47 F0306-OIRO

V Structural Integrity Associates, Inc-NMP-1 Pressure Test (Curve A), 46 EFPY 1,900 1t800 1.700 1.600 1,500

._* 1.400 ILI 1.300 1.200 o

1-1.100 U

1.000 z

900

• u 800 u) m 700 0,.

600 500 400 300 200 100 0

II I

I:I i

i

+

+-i Bolt-up Temp:

60F BelfJin e Region

- Bottom Head

.. -......... Upper Vessel liii. II V

__j LfzLLIA I. I LI L 4.

4. 4.

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE {F)

Figure 3: NMP-1 P-T Curve A (Hydrostatic Pressure and Leak Tests) for 46 EFPY File No.: 0800297.301 Revision: I Page 41 of 47 F0306-O1RO

3' Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Not Critical (Curve B), 28 EFPY 1.900 1.800 1,700-1,600-1,500

.- ' 1.400

• j I 1,300 Ln uji> 12o00

.,.-I?0 p 1.000 -

g W-1100-D 900 800 302 700 Ioo al-600 500 400 300 200 100-0-

I i I

I I

Bolt-up Tem p:

60'F

____ Beeldin e Region

-- - Bottom Head

........ Upper Vessel 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Figure 4: NMP-1 P-T Curve B (Normal Operation - Core Not Critical) for 28 EFPY File No.: 0800297.301 Revision: I Page 42 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Not Critical (Curve B), 36 EFPY 1,900 1.800 1.700 1.600 1.500

• -ý1,400

" 1,300 l 1.200 1-1.100 4

ILU te 1.000 900 m

800 0

700 ILl GL.

600 500 400 300 If If f

Bolt-up Ternp:

60'F eeltin e Region Bottom Head

........... Upper Vessel j

200 100 I

I 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 5: NMP-1 P-T Curve B (Normal Operation - Core Not Critical) for 36 EFPY File No.: 0800297.301 Revision: I Page 43 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Not Critical (Curve B), 46 EFPY 1.900 1,800 1.700 1.600 1.500

,_' 1.400

1. aoo

,,-)

" 1.200 Ix 0)- 1.100 U

ui

" 1.00 I-go 9.00 S800 U) 0 700 Iii 600 500

-400 300 200 100 0

I Bolt-up Temp:

60WF i-i i i A i

i i

i i

.~

t i

Beltdine Region

- Bottom Head

............. Upper Vessel I-

-AIL 0 20 40 60 80 100 120 140 160 180 200 220 240 260 Z80 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 6: NMP-1 P-T Curve B (Normal Operation - Core Not Critical) for 46 EFPY File No.: 0800297.301 Revision: I Page 44 of 47 F0306-01RD

V Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Critical (Curve C), 28 EFPY 1.900 1.800 1.600 1,500 21 1L 1 11U

.-B 1.40D w 1.300:

0 S1,00 goo uI 1.200 f:3 0I-1.1002 C) 14 w SO

• , 1,000-900 W

800-LU 70O 600 J

500 400 300 200 100 I~u~

i Minimium

-4 Criticality:

1 00: F i

i 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 7: NVIP-1 P-T Curve C (Normal Operation - Core Critical) for 28 EFPY File No.: 0800297.301 Revision: I Page 45 of 47 F0306-O1RO

C Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Critical (Curve C), 36 EFPY 1.900 1.800 1.700 1.600 1.500

.- 1.400 EI1.3,00

> 1.200 0:

" 1.100 LU U'

600 2

1.00 10-v-1.00

=: 1.000 a-4 00 1 00 I

1..,..

I Minimun Criticality:

100F Eý I II 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 2SO 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATUR E (fF)

Figure 8: NMP-1 P-T Curve C (Normal Operation - Core Critical) for 36 EFPY File No.: 0800297.301 Page 46 of 47 Revision: I F0306-O0RO

V Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Critical (Curve C), 46 EFPY 1.900 1,800 1,700-1.600-1.500

.2 1.400 (0

1,300 1,0 0

m 1.200 go 700 1.00 3:1000 200 1 00 EU 800 0

700 6O0 500 400 300 200 100 I

I I I

-4 Minimum A

ii Criticality:

I O0F'F I

F--

I I

I I II

-- 1 -1 1 1 f

g l

[

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE ("FJ Figure 9: NMP-1 P-T Curve C (Normal Operation - Core Critical) for 46 EFPY.

File No.: 0800297.301 Revision: 1 Page 47 of 47 F0306-OIRO

V Structural Integrity Associates, Inc.

APPENDIX A:

P-T CURVE INPUT LISTING File No.: 0800297.301 Revision: I Page A1 of A2 F0306-OIRO

V Structural Integrity Associates, Inc.

List of Design Inputs and Source References for NMP-1 P-T Curves at 28, 36, and 46 EFPY Instrument Uncertainty Reactor Vessel Metal Temperature (Hydrotest)

Reactor Vessel Pressure (Hydrotest)

Reactor Vessel Metal Temperature Reactor Vessel Pressure 4 'F 10 psig 12.2 'F 52.2 psig Reference

[171 (171

[17]

[17]

1171 Geometry ART/RTNOT Vessel Radius Vessel Shell Thickness Bottom Head Thickness Bottom Head Radius Feedwater Nozzle Blend Radius Thickness Water Elevation - Full Height (pressure head)

Limiting Bottom Head RTNDT

• Limiting Upper Vessel (Feedwater) RTNDT Flange Region (Boltup) RTNDT Limiting Beltline ART (28 EFPY)

Limiting Beltline ART (36 EFPY)

Limiting Beltline ART (46 EFPY) 106.5 in 7.125 in 8.75 in 106.719 in 7.8427 in 766 in 40 °F 40 'F 40 'F 151.4 'F 159.0 'F 167.4 'F

[6, Table 4-5]

[6, Table 4-5]

[10, p. A-3]

[10, p. A-6]

[9, Supporting Files]

[12b]

[13]

[12c, p. V-12]

[12c, p. V-12]

[4, Table 4]

[4, Table 5]

[4, Table 6]

Safety Factors/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)

Pressure (Curve A)

Lower Penetrations (SCF)

Water Density Operating Pressure Pre-Service Hydrostatic Test Pressure Static Pressure Head Adjustment Temperatures Heat Up and Cool Down Rate Bolt Up Temperature Bottom head RTNDT value bounded by that of the upper vessel/flange 2

1.5 3

PTLR [31 PTLR [3]

PTLR [3]

62.4 lb/ft3 1055 psig 1875 psig 27.66 psig 100 'F/hr 60 'F Assumed

[16]

[12a]

Calculated

[11]

PTLR [31 File No.: 0800297.301 Revision: 1 Page A2 of A2 F0306-O1RO

V Structural Integrity Associates, Inc.

APPENDIX B:

INCREASED COOL-DOWN RATE P-T CURVE File No.: 0800297.301 Revision: 1 Page BI of B5 F0306-OIRO

V Structural Integrity Associates, Inc.

BLO INTRODUCTION This appendix modifies the Nine Mile Point, Unit 1 P-T curves for a heat-up/cool-down rate of up to 200°F/Hr. A single curve is presented that bounds the beltline, bottom head, and non-beltline (feedwater nozzle / upper vessel) regions and is valid for up to 46 EFPY. The curve bounds the following plant conditions: Operating Pressure (Leak) Test (Curve A), Normal Operation - Core Not Critical (Curve B),

and Normal Operation - Core Critical (Curve C). The curve is developed using the methodology of the 2001 Edition, 2003 Addenda of the ASME Code,Section XI, Appendix G [1], and IOCFR50 Appendix G [2]. This appendix has been developed in accordance with the methodology of the BWROG Licensing Topical Report, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors" [3]. This appendix is provided for engineering purposes only and is not intended to be included in the PTLR.

B2.0 MIETHODOLOGY The methodology for calculating the P-T curve described in Section 2.0 remains unchanged. Only the calculation of the thermal stress intensity factor, Kit, is affected by the increased heat-up / cool-down rate. Kit is computed in different ways based on the evaluation region. As described in Section 2.0, the feedwater nozzle / upper vessel region Kit is obtained from the stress distribution output of a finite element model. The transient "Turbine Roll and Increase to Rated Power" consists of a 450'F step change [14], which bounds the increased heat-up / cool-down rate. Thus, the Kit calculation for the feedwater nozzle / upper vessel region is unaffected. For the beltline and bottom head regions, Kit is determined based on the ASME Section XI, Nonmandatory Appendix G method, using the following equation from Section 2.0:

Ki, = 0.953 x 1063 -CR. t2 5 (3)

Where:

CR

= the cooldown rate of the vessel (°F/hr).

t

= the RPV wall thickness, unique for each region (in).

B3.0 CALCULATIONS The P-T curve is developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SI's QA Program.

Figure BI presets the bounding curve for a 200°F/Hr heat-up / cool-down rate. This information is also presented in tabular form in Table B1. The P-T curve bounds the beltline, bottom head, and non-beltline (feedwater nozzle / upper vessel) regions and is valid for up to 46 EFPY. The curve bounds the following plant conditions: Operating Pressure (Leak) Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C).

File No.: 0800297.301 Page B2 of B5 Revision: 1 F0306-OIRO

V Structural Integrity Associates, Inc.

Table BI: NXP-1 Bounding P-T Curve for 2000F/Hr Heat-up / Cool-Down P lant:~tPMr Curve A Leak Test Temperature *

• riS12'2 "F

Curve A Leak Test Pressure: =P5 Unit Pressure psig (hydrostatic pressure)

Flange PRTr s

o Adjusted P-T Adjusted P-T CCurve Temperature C'

e F)

Pressure (psig) 100 0

100 46 102 47 104 48 106 49 108 s0 110 51 112 53 114 54 116 55 118 57 120 56 122 60 124 62 126 63 128 65 130 67 132 69 134 71 136 73 138 75 140 77 142 80 144 82 146 85 148 87 150 90 112 93 154 96 156 99 158 102 160 105 162 109 164 113 166 116 168 120 170 124 172 129 174 133 176 138 178 143 180 148 182 153 184 158 186 164 188 170 190 176 192 182 194 189 196 196 198 203 200 210 200 210 202 218 204 226 206 235 208 243 210 252 212 262 214 272 216 282 218 293 220 304 File No.: 0800297.301 Page B3 of B5 Revision: 1 F0306-O]RO

Structural Integrity Associates, Inc.

Table Bi Cont.: NMIP-1 Bounding P-T Curve for 200°F/Hr Heat-up / Cool-Down Adjusted P-T urve Adjusted P-T Curve Temperature IepeatrePressure (psig) 222 315 224 328 226 340 228 353 230 367 232 383 234 396 236 411 238 427 240 444 242 461 244 479 246 498 248 517 250 537 252 558 254 580 256 603 258 627 260 652 262 678 264 705 266 733 268 7Q2 270 793 272 823 274 856 276 890 278 926 280 963 Z82 1001 284 1041 286 1083 288 1126 290 1172 292 1219 294 1267 296 1318 298 1371 300 2427 302 1484 304 1544 306 1606 308 1671 310 1738 312 1808 314 1881 316 1957 File No.: 0800297.301 Page B4 of B5 Revision: I F0306-OIRO

V Structural Integrity Associates, Inc.

NMP-1 Normal Operation - Core Critical (Curve C), 46 EFPY 200"F/hr Heatup/Cooldown 1,900 1.800 1,700 1.600 1.500 S1.400 d 1.300 1,200 I-1,100

= 1.000 z

l 900 7s00 Goo a.

"800 I

I S00 400 300 200 100 0

Minimum Criticality:

1 00T' r

0 20 40 60 80 100 120 140 160180 200 220 240260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE fF)

Figure Bi: NMi-1 Bounding P-T Curve for 200'F/Hr Heat-up / Cool-Down File No.: 0800297.301 Revision: I Page B5 of B5 F0306-O1RO

6ý Structural Integrity Associates, Inc.

APPENDIX C:

ANSYS SUPPORTING FILES File No.: 0800297.301 Revision: I Page CI of C2 F0306-O1RO

C Structural Integrity Associates, Inc.

The following list of electronic files is included in the project files:

FILE NAME DESCRIPTION NMPFWNGEOM.inp ANSYS input file for creation of nozzle geometry NMPFWN PRES.inp ANSYS input file for application of pressure loads NMPFWNTHSTR.inp ANSYS input file for application of thermal shock Blend Radius Stress Intensity output file from extraction of Thermal Load Application BRFLW.OUT (Used only to determine nozzle corner thickness)

Blend Radius Stress Intensity output file from extraction of Pressure Load Application BRPRESFLW.OUT (Used only to determine nozzle corner thickness) map stress_press.POS Hoop stress extraction file for Blend Radius location from Pressure Load application mapstress therm.POS Hoop stress extraction file for Blend Radius location from Thermal Shock application MAPPRESSHOOP_1.TXT Output file containing hoop stresses for Blend Radius location from Pressure Load MAP TH HOOP_1.TXT Output file containing hoop stresses for Blend Radius location from Thermal Shock MAP PRESS HOOP l(Scaled).TXT Output file containing scaled hoop stresses for Blend Radius location from Pressure M

S H

P -Load Excel file containing Blend Radius polynomial coefficients and Kit (scaled hoop MAPPRESSHOOP 1(Scaled).xls stresses) from Pressure Load MAPTH HOOP_I.xis Excel file containing Blend Radius polynomial coefficients and Kit from Thermal Shock File No.: 0800297.301 Page C2 of C2 Revision: I F0306-OIRO