ML12033A181

Calculation CA 11-005, Revised P-T Curves Calculation, Enclosure 8

ML12033A181
Person / Time
Site:	Monticello
Issue date:	02/17/2011
From:	Mcgruder W Xcel Energy
To:	Office of Nuclear Reactor Regulation
References
L-MT-12-002, SIA 1000847.301 CA 11-005, QF-0549(FP-E-CAL-01), Rev. 7
Download: ML12033A181 (66)

Text

ENCLOSURE 8 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE THE TECHNICAL SPECIFICATIONS TO INCLUDE A PRESSURE TEMPERATURE LIMITS REPORT CALCULATION CA 11-005 REVISED P-T CURVES CALCULATION (SIA No. 1000847.303)

(59 pages follow)

Document Information NSPM Calculation (Doc) No: 11-005 Revision: 0

Title:

Revised PT Curves Facility: Z MT E] PI Unit: [1 El2 Safety Class: E SR EI Aug Q EL Non SR Special Codes: El Safeguards El Proprietary Type: Calc Sub-Type:

NOTE: Print and sign name in signature blocks, as required.

Major Revisions E N/A EC Number: 17502 [] Vendor Calc Vendor Name or Code: Structural Integrity Vendor Doc No: 1000847.303 Integrity (SIA)

Description of Revision: New Calculation Issuance The following calculation and attachments have been reviewed and deemed acceptable as a legible QA record Prepared by: (sign) &A Ve*-d* " /(print) SIA Date: 1/11/2011 Reviewed by:(sign) *

• rint) Wynter McGruder Date: 1/24/2011 Type of Review: El 6 esign Verification *Tech Review 0 Suitability Review Method Used (For DV Only :.[l/yiwl Alternate Calc El Test Approved by: (sign),,j_ (print) Steve Kibler Date:!-"/7* /

Minor Revisions El N/A EG No: l Vendor Caic:

Minor Rev. No:

Description of Change:

Pages Affected:

The following calculation and attachments have been reviewed and deemed Ell acceptable as a legible QA record .

Prepared by: (sign) / (print) Date:

Reviewed by: (sign) I(print) Date:

Type of Review: [E Design Verification E] Tech Review [] Suitability Review Method Used (For DV Only): El Review E] Alternate Calc El Test Approved by: (sign) I (print) Date:

Record Retention: Retain this form with the associated calculation for the life of the plant.

This reference table is used for data entry into the PassPort Controlled Documents Module reference tables (C012 Panel). It may NOTE: also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed by using the "TAB" key and filling in the appropriate information in each column.

Reference Documents (PassPort C012 Panel from C020)

Document Name Document Doc Ref Type**

1. Controlled*

Doc?+ Type Number Rev INPUT OUTPUT ASME Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, 2004 Section XI 2004 X Edition 2 US 10 CFR 50 "Domestic Licensing of Production and Utilization Facilities," Appendix G, "Fracture Toughness Requirements," (60 G N/A X FR 65474 Dec. 19, 1995; 73 FR 5723, Jan. 31, 2008) 3 Structural Integrity Associates Report No. SIR-05-044-A, Revision 0, "Pressure-Temperature Limits Report Methodology for Boiling N/A N/A X Water Reactors," April 2007 4 SIA Calculation 1000847.301, "Evaluation of Adjusted Reference x CALC Temperatures and Reference Temperature Shifts, Revision 1" 11- 11-003 0 X 003, Revision 0 5 U.S. NRC, Reg Guide 1.99 Rev. 2, "Radiation Embrittlement of 1.99 2 X Reactor Vessel Materials," May 1988 6 SIA Calculation No. NSP-21Q-303, Revision 1, "Determination of the Initial RTNDT and ART Values for Monticello RPV Materials".

7 X SPEC GE Design Specification No. 22A6996, Revision 0, "Reactor MPS-843 0 X Vessel System Cycling,"

8 x DRAW Chicago Bridge & Iron Drawing No. 1 Revision 8 "General Plan, NX-8290-13 8 x 17'2" L.D x 63'-2" Ins Heads Reactor, " NX-8290-13 9 X SPEC GE Design Specification No. 23A1581, Revision 3, "Reactor MPS-1090 3 X VesseL-Recirculation Inlet Nozzle-Safe End,"

10 GE Hitachi Nuclear Energy Report SASR 88-99, "Implementation of Regulatory Guide 1.99, Revision 2 for the Monticello Nuclear 88-99 1 X Generating Plant," Revision 1, January 1989 x CALC SIA Calculation 1000847.302, "Finite Element Stress Analysis of 11-004 0 X I___ __Monticello RPV Feedwater Nozzle, Revision 0"11-004, Revision 0 1 1 Record Retention: Retain this form with the associated calculation for the life of the plant.

12 SIA Calculation 1000720.301, "Finite Element Stress Analysis of N/A N/A X Monticello RPV Recirculation Inlet Nozzle", Revision 0" 13 ANSYS Mechanical and PrepPost, Release 11.0 (wI Service Pack N/A N/A X 1), ANSYS, Inc. August 2007 14 15 16 17

• Controlled Doc marked with an `X" means the reference can be entered on the C012 panel in black. Unmarked lines will be yellow. Ifmarked with an "X", also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.I Mark with an "X" if the calculation provides inputs and/or outputs or both. If not, leave blank. (Corresponds to PassPort "Ref Type" codes: Inputs I Both=

"ICALC", Outputs = "OCALC", Other I Unknown = blank)

Other PassPort Data Associated System (PassPort Col11, first three columns) OR Equipment References (PassPort C025, all five columns):

Facility Unit System Equipment Type Equipment Number MT 1RPV Superseded Calculations (PassPort C01 9):

Facility Calc Document Number Title NIT 03-101 Determination of Core Critical and Core Non-Critical Pressure Temperature Curves with End of Life RTNDT Shift Description Codes - Optional (PassPort C018):

Record Retention: Retain this form with the associated calculation for the life of the plant.

OF-0549 IFP-E-CAL-01) R v. 7 Paoe 4 of 4 XcelEnergy- Calculation Signature Sheet Code Description (optional) Code Description (optional)

Notes (Nts) - Optional (PassPort X293 from C020):

Topic Notes .. Text El Calc Introduction EI- Copy directly from the calculation Intro Paragraph or [] See write-up below E] (Specify)

Record Retention: Retain this form with the associated calculation for the life of the plant.

Monticello Specific Information 0 YES FI N/A Topic Code(s) (See MT Form 3805): PLEX, RATE E-YES Z N/A Structural Code(s) (See MT Form 3805):

Does the Calculatio n:"

EZ YES [K No ` Require Fire Protection Review? (Using MT Form 3765, "Fire Protection Program Checklist", determine if a Fire Protection Review is required.) If YES, document the engineering review in the EC. If NO, then attach completed MT Form 3765 to the associated EC.

[] YES No Affect piping or supports? (IfYes, Attach MT Form 3544.)

El YES No Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation.)

Record Retention: Retain this form with the associated calculation for the life of the plant.

StructuralIntegrityAssociates, Inc. File No.: 1000847.303 CALCULATION PACKAGE Project No.: 1000847 Quality Program: Z Nuclear E] Commercial PROJECT NAME:

Monticello P-T Curves Revision According to the PTLR Methodology CONTRACT NO.:

1005, Release 18 CLIENT: PLANT:

Xcel Energy, Inc. Monticello Nuclear Generating Plant CALCULATION TITLE:

Revised P-T Curves Calculation Document Revision Affected Pages Project Manager Preparer(s) &

Revision Description Approval Checker(s)

Signature & Date Signatures & Date 0 1 - 24 Initial Issue A-i -A-2 Eric J. Houston Vikram Marthandam B-I -B-li EJH 10/09/10 VM 10/08/10 Steve J. White SJW 10/08/10 1 - 29 Add intermediate P-T A-i - A-4 curve at 36 and 40 B-i - B-21 EFPY for Curve A Eric J. Houston Na EJH 1/11/2011 NC 1/7/2011 Mark J.ae err MJJ 1/7/2011 St J. White SJW 1/7/2011 Page 1 of 29 F0306-OIRI

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Table of Contents 1.0 INTRO D UCTIO N .................................................................................................. 4 2.0 METHODOLOGY .................................................................................................. 4 3.0 ASSUMPTIONS / DESIGN INPUTS ..................................................................... 9 4.0 CALCULA TION S .................................................................................................. 11 4.1 Pressure Test (Curve A) ............................................................................. 11 4.2 Normal Operation - Core Not Critical (Curve B) ...................................... 12 4.3 Normal Operation - Core Critical (Curve C) ....................... 12 5.0 C ON CLU SIO N S ..................................................................................................... 13 RE FEREN CE S ........................................................................................................................ 14 APPENDIX A P-T CURVE INPUT LISTING .................................................................... A-I APPENDIX B BOUNDING BELTL1NE SUPPORTING ANALYSIS ......................... B-i File No.: 1000847.303 Page 2 of 29 Revision: 1 F0306-O1RI:

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List of Tables Table 1: MNGP Polynomial Coefficients for Feedwater Nozzle Stress Intensity D istributions ........................ ..................................................................... 15 Table 2: MNGP Polynomial Coefficients for Recirculation Inlet (N2) Nozzle Stress Intensity D istributions ...................................................................................... 15 Table 3: MNGP Beltline Region, Curve A, for 36 EFPY ................................................. 16 Table 4: MNGP Beltline Region, Curve A, for 40 EFPY ................................................. 17 Table 5: MNGP Beltline Region, Curve A, for 54 EFPY ................................................. 18 Table 6: MNGP Bottom Head Region, Curve A, for all EFPY ......................................... 19 Table 7: MNGP, Upper Vessel Region, Curve A, for all EFPY ...................................... 20 Table 8: MNGP, Beltline Region, Curve B, for 54 EFPY ................................................ 21 Table 9: MNGP, Bottom Head Region, Curve B, for all EFPY ....................................... 22 Table 10: MNGP, Upper Vessel Region, Curve B, for all EFPY ..................................... 23 Table 11: MNGP, Curve C, for 54 EFPY ........................................................................ 24 List of Figures Figure 1. MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 36 EFPY ...... 25 Figure 2: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 40 EFPY ..... 26 Figure 3: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 54 EFPY ..... 27 Figure 4. MNGP P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY .......... 28 Figure 5. MNGP P-T Curve C (Normal Operation - Core Critical) for 54 EFPY ........ 29 File No.: 1000847.303 Page 3 of 29 Revision: 1 F0306-O1RI:

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1.0 INTRODUCTION

This calculation updates the Monticello Nuclear Generating Plant (MNGP) pressure-temperature (P-T) curves for the beltline, bottom head, and feedwater nozzle / upper vessel regions. The P-T curves are developed using the methodology of the 2004 Edition of ASME Code,Section XI, Appendix G [1],

10CFR50 Appendix G [2], and the Boiling Water Reactor Owner's Group (BWROG) Licensing Topical Report on P-T Curves [3]. A full set of P-T curves are developed for all plant conditions at 54 effective full power years (EFPY). In addition, due to operational challenges presented by the leak test results at 54 EFPY, additional Curve A limits are developed at intermediate levels of 36 and 40 EFPY.

2.0 METHODOLOGY A full set of P-T curves are computed, including the following plant conditions: Pressure Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C).

The curves are consolidated into three 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], thus, all equations and values in this section are 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 a 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, may be treated as equal to the assumed fluid temperature.

Step 2: The static fracture toughness factor, KIt, is computed using the following equation:

K 1c = 20.734-e°'°2(T-ART) +33.2 (1) where: KIc = the lower bound static fracture toughness (ksNin).

T = the metal temperature at the tip of the postulated 1/4 through-wall flaw ('F), as described above.

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

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, Step 3: The allowable stress intensity factor due to pressure, Kip, is calculated as:

K p- SF FKi

-Kit (2) where: Kip = the allowable stress intensity factor due to membrane (pressure) stress (ksi*/in).

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

Kit = the thermal stress intensity factor (ksiN/in) from through wall thermal gradients.

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, both non-critical and 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 0F/hr or less).

For Curve B and Curve C calculations, Kit is computed in different ways based on the evaluated region. For the beltline (with the exception of nozzles) and bottom head regions, Kit is determined using the following equation:

25 Kit =O0.953 x10-' .CR .t . (3) where: CR = the cooldown rate of the vessel (°F/hr).

t = the RPV wall thickness, per region (in.).

For the feedwater nozzle/upper vessel region and the N2 nozzle, Kit is obtained from the stress distribution output of a finite element model (FEM). A thermal transient finite element analysis (FEA) is performed, and a polynomial curve-fit is applied to the through-wall stress distribution at each time point. The subsequent method to evaluate Kit is:

K 1 ~ViO0C2a a 24a' K~t [ 0. 0 t ++/-- .0.537Ci, + 2 0482t + .03 C3tj (4) where: a = 1/ through-wall postulated flaw depth, a = 1/4 t (in.).

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

CotClt = thermal stress polynomial coefficients, obtained from a curve-C2t, C3t fit of the extracted stresses from an FEM transient analysis.

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The thermal stress polynomial coefficients are based on the assumed polynomial form of Ux = CO + C 1 *x + C 2 .x2 + C3 *x3 . In this equation, "x" represents the radial distance in inches from the inside surface to any point on the crack front.

Step 4: The allowable internal pressure of the RPV is calculated differently for each evaluation region. For the beltline region (with the exception of nozzles), the allowable pressure is determined as follows:

Po - Kpow (5) where: Paiiow = the allowable RPV internal pressure (psig).

Kip = the allowable stress intensity factor due to membrane (pressure) stress, as defined in Equation 2 (ksix/in).

t = the RPV wall thickness, per region (in.).

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

Mm = 1.85 for <t < 2 Mm = 0.926 ýt for 2 <'It < 3.464 Mm = 3.21 for Vt > 3.464 Ri = the inner radius of the RPV, per region (in.).

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

2. Kz .t P -,,,1 (6)

SCF. Mm *Ri 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, and the N2 nozzle, 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:

= KIp"Pref (7)

KIp-app where: Pref = RPV internal pressure at which the FEA stress coefficients (Equation 8) are valid (psi).

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

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

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

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gp = lpp[0.706COp +

2aa -.0.537C*p +--.0.448C2p +

4a'o33p

.O.393C 3p]

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 comer (in.).

Cp,Clp= pressure stress polynomial coefficients, obtained from a curve-fit C2pC3p 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 1,300 psig.

Step 6: The following minimum temperature requirements apply to the feedwater nozzle / upper vessel region, and the N2 nozzle, according to Table 1 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.

Step 7: The final P-T limits are calculated using the following equations:

TrPT =T+UT (9)

TP-T = Pa,,,, - PH - UP (10) where: TP-T = The allowable coolant (metal) temperature (°F).

UT = The coolant temperature instrument uncertainty (TF).

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/in 3).

Ah = Elevation of full height water level in RPV (in.).

Up = The pressure instrument uncertainty (psig).

These additional pressure and temperature limits are not applicable to the IOCFR50 Appendix G [2] limits described in Step 6.

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Nozzles in the beltline introduce stress concentration effects and have the potential to be more limiting than the generic beltline P-T curves. Nozzles or discontinuities outside the beltline are considered to be bounded by the upper vessel / feedwater nozzle or bottom head region P-T curves [3]. Beltline nozzles may be bounded by the upper vessel / feedwater nozzle curve if all of the following are met: the feedwater nozzle experiences more severe thermal transients, the feedwater nozzle RTNDT is greater than or equal to the beltline nozzle ART, and the beltline and feedwater nozzle have similar transition geometry (blend radius).

The P-T Curves for hydrostatic leak test (Curve A) and normal operation - core not critical (Curve B) may be computed by following Steps 1 through 7. Values for Curve C, the core-critical operating curve, are generated from the requirements of 10CFR50 Appendix G [2] and the Curve A and Curve B limits.

Table 1 of Reference [2] requires that core critical P-T limits be 40'F above any Curve A or Curve B limits at all pressures. 10CFR50 Appendix G [2] 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 0 F, or the temperature required for the hydrostatic pressure test, 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 minus coolant temperature instrument uncertainty. 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 I 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 0 F.

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

ART values in the MNGP beltline region are obtained for 36, 40, and 54 EFPY from Reference [4].

Note: the height of the beltline increases in direct proportion with EFPY; this change in the beltline region from initial startup to end of life is referred to as the extended beltline. The calculations were performed in accordance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2 (RG1.99) [5]. Based on Tables 1, 2, and 3 of Reference [4], the limiting beltline material is the Lower/Intermediate shell plate, which has an ART value of 147.4'F for 36 EFPY, 156.0 0 F for 40 EFPY, and 186.6 0F for 54 EFPY.

Non-beltline regions are not subjected to the effects of fluence; therefore, reference temperature (RTNDT) values are valid substitutions for corresponding ART values. RTNDT values for non-beltline regions are obtained from Reference [6].

The inner radius of the RPV at the feedwater (FW) nozzle, per Figure 3 of Reference [7], is 103.0 inches. The vessel shell thickness is taken as 5.63 inches at the FW nozzle from the same source.

Dimensions for the bottom head radius and thickness are obtained from Reference [8], as 103.2 inches and 5.94 inches, respectively.

The GE design hydro-test pressure is defined in Reference [9] as 1,250 psig. Typically, the pre-service system hydrostatic test pressure is taken as 1.25 times the typical GE design pressure, resulting in a value of 1,563 psig. The instrument uncertainty for both temperature and pressure is assumed to be 00 F and 0 psig respectively.

The total height of the RPV is 758 inches, as shown in Reference [8]. The density of the water is assumed to be 64.2 lbm/ft3. Thus, the static pressure adjustment due to the pressure head of the water in the RPV is conservatively calculated as 27.4 psi for all evaluation regions. The maximum cool-down rate of the vessel is 100lF/hr per Reference [10].

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 RTNoT 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 minus coolant temperature uncertainty (0°F in this case). A temperature increment of 2°F between subsequent iterations is assumed.

The 60'F initial temperature does not include the additional 60'F add-on margin for Curves A and B that was previously applied. 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 Licensing Topical Report (LTR) [3] was developed, SI consciously recognized the additional 60'F margin and chose to exclude it, as it is not technically required.

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Vessel nozzles are incorporated into P-T curve calculations using stress distributions from two FEAs

[11, 12] and applying them to geometry specific fracture mechanics models. Both the feedwater (upper vessel region) and N2 (recirculation inlet in the extended beltline region) nozzles require this type of analysis, due to bounding transients they experience and/or limiting ART (RTNDT outside beltline) values.

The feedwater nozzle is the bounding component in the upper vessel because it is a stress concentrator (essentially a hole in a plate) and because it typically experiences more severe thermal transients compared to the rest of the upper vessel region. A one-quarter, 3-dimensional finite element model (FEM) of the feedwater nozzle is created in Reference [ 11] using the ANSYS finite element software

[13]. Both pressure and thermal hoop stress distributions are obtained along a limiting path in the nozzle-to-RPV blend radius. The pressure stress analysis is run for an applied unit pressure of 1,000 psig [11]. Post-processing techniques are used to extract the stresses acting normal to the postulated 1/4t crack (hoop stresses), along the limiting path in Reference [11]. Two thermal transients are also run in Reference [11], and the hoop stresses are extracted along the limiting path at each time step. A 3 rd order polynomial curve fit of the hoop stresses will be performed. The applied stress intensity factor due to pressure will be calculated using Equation 8. The thermal stress intensity factor will be calculated for all time steps using Equation 4, with the bounding, or most limiting value, being applied for all temperatures. The limiting path defines the nozzle corner thickness to be 7.73 inches [11] and the postulated flaw location at 1/4t to be 1.93 inches.

MNGP has one set of nozzles in the RPV beltline where the fluence exceeds 1.0x10 17 n/cm 2 . These nozzles introduce stress concentration effects to the beltline plates and must be specifically analyzed.

The recirculation inlet (N2) nozzles are the only nozzles in the beltline region; there are no instrument nozzles in the extended beltline [4]. The N2 nozzle limiting ART values for 36, 40 and 54 EFPY are 104.1°F, 1 10.0°F, and 125.2°F, respectively, per Reference [4]. Similar to the feedwater nozzle, the thermal and pressure stress distributions for the N2 nozzle are extracted from a FEM in Reference [12]

along a limiting path in the nozzle-to-RPV blend radius. The distributions are fit with a 3 rd order polynomial in Reference [12]. The applied stress intensity factor due to the unit pressure of 1,000 psig will be calculated using Equation 8. The thermal stress intensity factor will be calculated for all time steps using Equation 4, with the bounding value being applied for all temperatures. The limiting path defines the nozzle corner thickness to be 9.29 inches [12] and the postulated flaw location at 1/4t to be 2.32 inches.

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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 1 are applied to Equations 4 and 8. For the feedwater nozzle, the resulting applied pressure stress intensity (Kip-app) and thermal stress intensity (Kit) factors are 69.11 ksi'in and 7.06 ksi*/in, respectively. The resulting applied pressure stress intensity (Kli-app) and thermal stress intensity (Kit) factors are 74.36 ksi'in and 9.45 ksilin for the N2 nozzle (Table 2).

In order to incorporate the limiting recirculation inlet (N2) nozzle curves into the beltline, a composite curve is developed which bounds each of the two curves (Beltline and N2 nozzle). This composite curve is used to describe the pressure and temperature limits for the beltline region. Supporting beltline calculations for pressure test (Curve A) and Normal Operation - Core Not Critical (Curve B) are shown in Appendix B.

The P-T limits for Curve A at 54 EFPY present operability challenges for MNGP, primarily due to the limiting ART value for the beltline region. Reference [4] includes calculations for intermediate ART values at 36 and 40 EFPY. Consequently, P-T limits for Curve A will be developed at 36, 40 and 54 EFPY. The intermediate evaluation will not be performed for Curve B and Curve C, as the 54 EFPY limits for these curves do not present an operational challenge to MNGP.

4.1 Pressure Test (Curve A)

The minimum bolt-up temperature of 60'F minus instrument uncertainty (0°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 KIt, along with a safety factor of 1.5 is used in Equation 2 to calculate the pressure stress intensity factor (Kip). The allowable RPV pressure is calculated for the beltline, bottom head and upper vessel regions using Equations 5, 6, and 7, as appropriate. For the feedwater nozzle / upper vessel region, the additional constraints specified in Step 6 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 is tabulated. Values for the beltline region at 36, 40 and 54 EFPY are provided in Table 3, Table 4 and Table 5, respectively. Data for the bottom head region is listed in Table 6, and data for the feedwater nozzle / upper vessel region is presented in Table 7. The data for each region is graphed, and the resulting P-T curves for 36, 40 and 54 EFPY are provided in Figure 1, Figure 2, and Figure 3, respectively.

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4.2 Normal Operation - Core Not Critical (Curve B)

The minimum bolt-up temperature of 607F minus coolant temperature instrument uncertainty (0°F) is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (Kic) is calculated for all regions using Equation 1. The thermal stress intensity factor (K1 t) is calculated for the beltline plate and bottom head regions using Equation 3, and for the feedwater and N2 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 factor (Kip). The allowable RPV pressure is calculated for the beltline, bottom head, and upper vessel regions using Equations 5, 6, and 7, as appropriate. For the feedwater nozzle / upper vessel region, the additional constraints specified in Step 6 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 is tabulated. Values for the beltline region at 54 EFPY are given in Table 8. Data for the bottom head region is listed in Table 9, data for the feedwater nozzle / upper vessel region is presented in Table 10. The data for each region is graphed, and the resulting P-T curves for 54 EFPY are provided in Figure 4.

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 upper vessel RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: lO0F per Section 3.0) plus 60'F, resulting in a minimum critical temperature of 707F. When the pressure exceeds 20% of the pre-service system hydro-test pressure (20% of 1,563 psig = 312 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 1607F, or the temperature required for the hydrostatic pressure test. The final Curve C values are taken as -the absolute maximum between the three (3) regions of Curve B P-T curves.

Tabulated overall values of Curve C are provided at 54 EFPY in Table 11. The corresponding P-T curve plot is given in Figure 5.

File No.: 1000847.303 Page 12 of 29 Revision: 1 F0306-O1RI

V StructuralIntegrity Associates, Inc.

5.0 CONCLUSION

S P-T curves are developed for MNGP 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 are developed at 54 EFPY, including the following plant conditions: Pressure Test (Curve A), Normal Operation - Core Not Critical (Curve B),

and Normal Operation - Core Critical (Curve C). Calculations are performed for the beltline, bottom head, feedwater nozzle / upper vessel regions and the recirculation inlet (N2) nozzles. In addition, due to operational challenges presented by the leak test results at 54 EFPY, additional Curve A limits are developed at intermediate levels of 36 and 40 EFPY.

Tabulated pressure and temperature values are provided for all regions and EFPY levels in Table 3 through Table 11. The accompanying P-T curve plots are provided in Figure 1 through Figure 5.

File No.: 1000847.303 Page 13 of 29 Revision: 1 F0306-O1RII

V StructuralIntegrityAssociates, Inc.

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, 2004 Edition.

2. U.S. Code of Federal Regulations, Title 10, Energy, 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-05-044-A, 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. 1000847.301, 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. Structural Integrity Associates Calculation No. NSP-21Q-303, Revision 1, "Determination of the Initial RTNDT and ART Values for the Monticello RPV Materials."

7. GE Design Specification No. 22A6996, Revision 0, "Reactor Vessel System Cycling," SI File No. 1000847.201.

8. CB&I Drawing No. 1, Revision 8, "General Plan. 17'2" ID x 63' 2" Ins Heads Nuclear Reactor,"

NX-8290-13, SI File No. NSP-21Q-210.

9. GE Design Specification No. 23A1581, Revision 3, "Reactor Vessel - Recirculation Inlet Safe End," SI File No. 1000720.202.

10. GE Report No. SASR 88-99, Revision 1, "Implementation of Regulatory Guide 1.99, Revision 2 for the Monticello Nuclear Generating Plant," January 1989, SI File No. NSP-21Q-202

11. Structural Integrity Associates Calculation No. 1000847.302, Revision 0, "Finite Element Stress Analysis of Monticello RPV Feedwater Nozzle."

12. Structural Integrity Associates Calculation No. 1000720.301, Revision 0, "Finite Element Stress Analysis of Monticello RPV Recirculation Inlet Nozzle."

13. ANSYS Mechanical and PrepPost, Release 11.0 (w/ Service Pack 1), ANSYS, Inc., August 2007.

File No.: 1000847.303 Page 14 of 29 Revision: 1 F0306-O1RI

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Table 1: MINGP Polynomial Coefficients for Feedwater Nozzle Stress Intensity Distributions Feedwater Nozzle Pressure Stress Coefficients Kip-pp cO cI c2 C3 ________ (psiin) 49728.16 -12761.77 1797.96 -113.63 69,105 Feedwater Nozzle Thermal Stress Coefficients Kit co ~ cl c2 c3 psln)

A_

5737.85 -1934.05 106.77 3.72 7,064 Table 2: MNGP Polynomial Coefficients for Recirculation Inlet (N2) Nozzle Stress Intensity Distributions Recirculation Inlet (N2) Pressure Stress Coefficients .Kip-app co cl c2 0c (.....psjj~ii 49213.40 -10902.90 1312.80 -69.60 74,356 SRecirculatio Inlet (N2) Thermal Stress Coefficients co cl c2**%::: c3 (psiq-3727.90 2331.90 -930.10 67.40 9,454 File No.: 1000847.303 Page 15 of 29 Revision: 1 F0306-OIRIl

StructuralIntegrityAssociates, Inc.

Table 3: MNGP Beltline Region, Curve A, for 36 EFPY P-T Curve P-T Curve Temperature Pressure 60.00 0 60.00 50 60.00 100 60.00 150 60.00 200 60.00 250 60.00 300 60.00 312 60.00 313 61.75 350 86.10 400 102.40 450 114.67 500 124.52 550 132.74 600 139.81 650 146.00 700 151.49 750 156.45 800 160.96 850 165.09 900 168.91 950 172.47 1000 175.78 1050 178.88 1100 181.82 1150 184.58 1200 187.19 1250 189.69 1300 File No.: 1000847.303 Page 16 of 29 Revision: 1 F0306-OIRII

V StructuralIntegrity Associates, Inc.

Table 4: MNGP Beltline Region, Curve A, for 40 EFPY P-T Curve P-T Curve Tem perature Pressure 60.00 0 60.00 50 60.00 100 60.00 150 60.00 200 60.00 250 60.00 300 60.00 312 60.00 313 67.65 350 92.00 400 108.30 450 120.57 500 130.42 550 138.64 600 145.71 650 151.89 700 157.39 750 162.35 800 166.86 850 170.99 900 174.81 950 178.37 1000 181.68 1050 184.78 1100 187.71 1150 190.48 1200 193.41 1250 196.73 1300 File No.: 1000847.303 Page 17 of 29 Revision: 1 F0306-01R1

V StructuralIntegrityAssociates, Inc.

Table 5: MNGP Beltline Region, Curve A, for 54 EFPY P-T Curve P-T Curve Temperature Pressure 60.00 0 60.00 50 60.00 100 60.00 150 60.00 200 60.00 250 60.00 300 60.00 312 60.00 313 82.85 350 107.19 400 123.50 450 135.78 500 145.62 550 153.85 600 160.90 650 167.09 700 172.59 750 177.55 800 184.05 850 191.16 900 197.39 950 202.93 1000 207.92 1050 212.45 1100 216.61 1150 220.44 1200 224.02 1250 227.33 1300 File No.: 1000847.303 Page 18 of 29 Revision: 1 F0306-OIRIl

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Table 6: MINGP Bottom Head Region, Curve A, for all EFPY Plant = MNGP Component = Bottom Head (penetrations portion)

Bottom Head thickness, t = 5.938 inches Bottom Head Radius, R = 103.1875, inches ART = 26. 0 'F ======> All EFPY Kit = 0.00 (no thermal effects)

Safety Factor = 1.50 Stress Concentration Factor = 3.00 (bottom head penetrations)

Mm = *2.256 Temperature Adjustment = 0o.0 °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = S0.0 psig (instrument uncertainty)

Gauge Adjusted Fluid Temperature Pressure for Temperature KIc Kim for P-T Curve P-T Curve (OF) 2 (ksi*inchl1 ) (ksi*inch 112 ) (OF) (psig) 60.0 74.13 49.42 60 0 60.0 74.13 49.42 60 813 62.0 75.80 50.53 62 832 64.0 77.54 51.69 64 851 66.0 79.34 52.90 66 872 68.0 81.23 54.15 68 893 70.0 83.19 55.46 70 915 72.0 85.23 56.82 72 939 74.0 87.35 58.23 74 963 76.0 89.56 59.71 76 988 78.0 91.86 61.24 78 1,014 80.0 94.25 62.84 80 1,041 82.0 96.75 64.50 82 1,069 84.0 99.34 66.23 84 1,099 86.0 102.04 68.03 86 1,129 88.0 104.85 69.90 88 1,161 90.0 107.77 71.85 90 1,194 92.0 110.82 73.88 92 1,229 94.0 113.98 75.99 94 1,265 96.0 117.28 78.19 96 1,302 File No.: 1000847.303 Page 19 of 29 Revision: 1 F0306-OIRII

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Table 7: MNGP, Upper Vessel Region, Curve A, for all EFPY Plant = MNGP Component = Upper Vessel JO - - - -All ART= AlA 0 -V Vessel Radius, R = 103 inches Nozzle comer thickness, t' = 7.732 inches, approximate Kit= 0.00 (no thermal effects) 12 Kip-applied = ýý69.10 ksi*inch Crack Depth, a = 11.933 inches Safety Factor = 1.50 Temperature Adjustment = 0.0 'F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = 0.0 psig (instrument uncertainty)

Reference Pressure = 1,000 psig (pressure at which the FEA stress coefficients are valid)

Unit Pressure = 1,563 psig (hydrostatic pressure)

Flange RTNDT = 10.0 'F ======> All EFPY Gauge P-T P-T Curve Fluid Curve 10CFR5O Temperature K1. Kip Temperature Adjustments

(*F) (ksi*inch )

112 (ksi*inch11Z)

(*F) (psig) 60.0 64.13 42.75 60 0 60.0 64.13 42.75 60 313 62.0 65.39 43.60 100 313 64.0 66.71 44.47 100 616 66.0 68.08 45.38 100 629 68.0 69.50 46.33 100 643 70.0 70.98 47.32 100 657 72.0 72.52 48.35 100 672 74.0 74.13 49.42 100 688 76.0 75.80 50.53 100 704 78.0 77.54 51.69 100 721 80.0 79.34 52.90 100 738 82.0 81.23 54.15 100 756 84.0 83.19 55.46 100 775 86.0 85.23 56.82 100 795 88.0 87.35 58.23 100 815 90.0 89.56 59.71 100 837 92.0 91.86 61.24 100 859 94.0 94.25 62.84 100 882 96.0 96.75 64.50 100 906 98.0 99.34 66.23 100 931 100.0 102.04 68.03 100 957 102.0 104.85 69.90 102 984 104.0 107.77 71.85 104 1012 106.0 110.82 73.88 106 1042 108.0 113.98 75.99 108 1072 110.0 117.28 78.19 110 1104 112.0 120.71 80.47 112 1137 114.0 124.28 82.86 114 1172 116.0 128.00 85.33 116 1207 118.0 131.87 87.91 118 1245 120.0 135.90 90.60 120 1284 122.0 140.09 93.39 122 1324 124.0 144.45 96.30 124 1366 File No.: 1000847.303 Page 20 of 29 Revision: 1 F0306-0IRI

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Table 8: MNGP, Beltline Region, Curve B, for 54 EFPY P-T Curve P-T Curve Temperature Pressure 60.00 0 60.00 50 60.00 100 60.00 150 89.07 200 116.72 250 134.43 300 137.89 312 138.16 313 147.47 350 157.81 400 166.37 450 174.76 500 185.75 550 194.74 600 202.37 650 208.98 700 214.82 750 220.05 800 224.78 850 229.10 900 233.08 950 236.77 1000 240.21 1050 243.41 1100 246.43 1150 249.28 1200 251.98 1250 254.53 1300 File No.: 1000847.303 Page 21 of 29 Revision: 1 F0306-OIRIl

V StructuralIntegrityAssociates, Inc.

Table 9: MNGP, Bottom Head Region, Curve B, for all EFPY Plant = MNGP Component = Bottom Head (penetrations portion)

Bottom Head thickness, t = 5.938 inches Bottom Head Radius, R = 103.1875 inches 0

ART= 26.0 F ======> 2 All EFPY Kit = 8.19 ksi*inch11 Safety Factor = - 2.00 Stress Concentration Factor = 3.00 (bottom head penetrations)

Mm = 2.256 Temperature Adjustment = OQ.0 *F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = i 27.4 psig (hydrostatic pressure head for a full %Aesselat 70'F)

Pressure Adjustment = 0.0 psig (instrument uncertainty)

Heat Up and Cool Down Rate 100 °F/Hr Gauge Adjusted Fluid Temperature Pressure for Temperature KIm for P-T Curve P-T Curve 2

(*F) (ksi*inch11 ) (ksi*i nch"z) (*F) (psig) 60.0 74.13 32.97 60 0 60.0 74.13 32.97 60 533 62.0 75.80 33.81 62 547 64.0 77.54 34.67 64 562 66.0 79.34 35.58 66 578 68.0 81.23 36.52 68 594 70.0 83.19 37.50 70 610 72.0 85.23 38.52 72 628 74.0 87.35 39.58 74 646 76.0 89.56 40.69 76 664 78.0 91.86 41.84 78 684 80.0 94.25 43.03 80 704 82.0 96.75 44.28 82 725 84.0 99.34 45.58 84 747 86.0 102.04 46.93 86 770 88.0 104.85 48.33 88 794 90.0 107.77 49.79 90 819 92.0 110.82 51.31 92 845 94.0 113.98 52.90 94 872 96.0 117.28 54.55 96 900 98.0 120.71 56.26 98 929 100.0 124.28 58.05 100 960 102.0 128.00 59.91 102 991 104.0 131.87 61.84 104 1,024 106.0 135.90 63.85 106 1,058 108.0 140.09 65.95 108 1,094 110.0 144.45 68.13 110 1,131 112.0 148.99 70.40 112 1,170 114.0 153.72 72.76 114 1,210 116.0 158.63 75.22 116 1,251 118.0 163.75 77.78 118 1,295 120.0 169.08 80.45 120 1,340 File No.: 1000847.303 Page 22 of 29 Revision: 1 F0306-01 RI.

V StructuralIntegrity Associates, Inc.

Table 10: MINGP, Upper Vessel Region, Curve B, for all EFPY Plant = N..P G .. .

Component = Upper Vessel ART = -2 40.0 'F ======> All EFPY Vessel Radius, R = 103 inches Nozzle comer thickness, t = 7.732 inches, approximate Kit = 2 7.06 ksi*inch.

Klp~ppflid= ksi-inchl/2 69.10 Crack Depth, a = ,1.933 inches Safety Factor = 2.00 Temperature Adjustment = 0.0. °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 768.010 inches Pressure Adjustment = 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = 0.0 psig (instrument uncertainty)

Reference Pressure = 1,000 psig (pressure at which the FEA stress coefficrents are valid)

Unit Pressure = 1,563 psig (hydrostatic pressure)

Flange RTNDT 10.0 -F ======> All EFPY Gauge P-T P-T Fluid Curve Curve Temperature K. Kip Temperature Pressure 112 11 (IF) (ksi'inch ) (ksi*inch .) ('F) (psig) 60.0 64.13 28.53 60 0 60.0 64.13 28.53 60 313 62.0 65.39 29.16 130 313 64.0 66.71 29.82 130 404 66.0 68.08 30.51 130 414 68.0 69.50 31.22 130 424 70.0 70.98 31.96 130 435 72.0 72.52 32.73 130 446 74.0 74.13 33.53 130 458 76.0 75.80 34.37 130 470 78.0 77.54 35.24 130 483 80.0 79.34 36.14 130 496 82.0 81.23 37.08 130 509 84.0 83.19 38.06 130 523 86.0 85.23 39.08 130 538 88.0 87.35 40.14 130 554 90.0 89.56 41.25 130 570 92.0 91.86 42.40 130 586 94.0 94.25 43.60 130 603 96.0 96.75 44.84 130 622 98.0 99.34 46.14 130 640 100.0 102.04 47.49 130 660 102.0 104.85 48.89 130 680 104.0 107.77 50.35 130 701 106.0 110.82 51.88 130 723 108.0 113.98 53.46 130 746 110.0 117.28 55.11 130 770 112.0 120.71 56.82 130 795 114.0 124.28 58.61 130 821 116.0 128.00 60.47 130 848 118.0 131.87 62.40 130 876 120.0 135.90 64.42 130 905 122.0 140.09 66.51 130 935 124.0 144.45 68.69 130 967 126.0 148.99 70.96 130 1000 128.0 153.72 73.33 130 1034 130.0 158.63 75.78 130 1069 132.0 163.75 78.34 132 1106 134.0 169.08 81.01 134 1145 136.0 174.63 83.78 136 1185 138.0 180.40 86.67 138 1227 140,0 186.40 89.67 140 1270 142.0 192.66 92.80 142 1315 File No.: 1000847.303 Page 23 of 29 Revision: 1 F0306-OIRIS

V StructuralIntegrity Associates, Inc.

Table 11: MNGP, Curve C, for 54 EFPY Plant MNGP Curve A Leak Test Temperature = 206.0 oF Curve A Pressure= 1,025.0" -- psig Unit Pressure = 1,563 psig (hydrostatic pressure)

Flange RTNDT 10.0 °F P-T Curve P-T Curve Temperature Pressure 70.00 0 70.00 50 70.00 100 70.00 150 129.07 200 156.72 250 174.43 300 177.89 312 206.00 313 206.00 350 206.00 400 206.37 450 214.76 500 225.75 550 234.74 600 242.37 650 248.98 700 254.82 750 260.05 800 264.78 850 269.10 900 273.08 950 276.77 1000 280.21 1050 283.41 1100 286.43 1150 289.28 1200 291.98 1250 294.53 1300 File No.: 1000847.303 Page 24 of 29 Revision: 1 F0306-01RL

300 I I I I [ I II l l I II

[ l l I111111 11I I II I I 11111 11 280 OMPLIANCE REQU IRES OPERATION ABOVETHECURVES 260 240 220 w 200 a.

-JI 180 LI-160 C0) 140 120 00 0

100 w 80 60 D Belfline Region 40 Bolt-up Temp:

60'F -Boftom Head 20 ..... UpperVessel 0 . . . . . . . . . . . ..... .

0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

Figure 1. MINGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 36 EFPY File No.: 1000847.303 Page 25 of 29 Revision: 1 F0306-OIRII

300 280 COMPLIANCE REQU IRES OPERATION ABOVE THE CURVES 260 oLu 240 Lu n- 220 Lu I. 200 180 160 w

n-140 w

120 .0 I-Co 0010,1 0

Lu100 -YF i ti i -I-r 11

- 1-1-f tr r1 1 80

_TFF 60 Belfline Region 40 Bolt-up Temp:

60*F Boftom Head 20 UpperVessel 0 I t 1. 1

. 1 .1

. 1 .1.1.1 . 1.1.1.!. 1. 1. 1. 1 1 1 1 1 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

Figure 2: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 40 EFPY File No.: 1000847.303 Page 26 of 29 Revision: 1 F0306-OIRIl

300 280 COMPLIANCE REQUIRES OPERATION ABOVETHE CURVES 260 Ll w 240 220 w

200 w

Il I-- 180

.-J w op 160 UJ I LA_

140 -- I I I Lto U ILL U) w 120 0

I--

100 w

D.l 80 60 1i1l 1l 1 1 1 111 1 1 1 1 1 1 1 1 1 1 1 1 1- Beitline Region 40 Bolt-up Temp:li A~~ ~~ 60F-LLIBotto BllnRein--Bto Had-mHead 20 I I I I I-1 1-I- ..... UpperVessel II I~ l~ ll ll! ......... ,R..

0 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

Figure 3: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 54 EFPY File No.: 1000847.303 Page 27 of 29 Revision: 1 F0306-OIRI

300 I I I 1-111IT177=

280' COMPLIANCEREQ UIRESO PERATION ABOVE THE CURV ES I I I I H I

" 260

, 240 -------- I I I J- ITIT

. 220 I ru-j- 11 J w

,a.

m 200 w

I- I .. . . . I... . . I. . . . ... I.if I ... i i i I i ! i i i i i i I i i I Ii i i  ! i i ! i I

,180 I-w, 160 11111 111111111111111 I.1I III! 111111 11111 liii III Ii 11111 I;: I~lIII w 140 . I. I. I. I i i i i i i .W i i i i i i i i i i i i i i i i i i i i i I . . . I . I. ii I ~ i i i i I I w

> 120

.. . 7.  !*...

1...................................

...  ! .. . ...................... 1.- ..

• 100 w

n, 80

- - Beltline Region

60

.- -Bottom Head 2 40 Bolt-up Temp:' . . . .,UpperVessel 0

601tU 7 20 0° .... ... .........

0 0 100 .200 300 400 500 600 700 800 900 1000 .1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL TOP HEAD (psig)

Figure 4. MNGP P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY File No.: 1000847.303 Page 28 of 29 Revision: 1 F0306-01RL

300 1111 111111111 111171=11 11111 111 111111 1111 111111 11117711IT;M 280 260 ....I I I . .I I I I I I . . I i i i i i i i i ii i i I 240 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I uJ

_ 220 i i i i !_ i i i i i i i i i i ! i i i i i i i hw?__ i i  ! i i i i i i i I I I I I I i i i i i i i i + i i i i i ! i i i i i i i I LU 200 L-

,-I 180 !111111111111 HIIIIIIII COMPLIANCE REQUIRES OPERATION ABOVE THE CURVES 1.

UJ 160 1 1 1 1 1 1 1 1 1 1 1 14 1 1 1 1 1 1 1 1 1 1 1 1 1 4 -1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4. 1 1 1 1 1 1 1 1 1 1 1 1 1 1 ILl 140

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I I ..

Lu 120 I ~~ I-- . . . . . . . . . . . . i ! i i i I i ! i i ii I o 100 C.)

<UJ 80 Minimum

• 60 Criticality Temp:

D 40 70*F 20 I IIL El I 0

0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL TOP HEAD (psig)

Figure 5. MNGP P-T Curve C (Normal Operation - Core Critical) for 54 EFPY File No.: 1000847.303 Page 29 of 29 Revision: 1 F0306-OIRI

APPENDIX A P-T CURVE INPUT LISTING File No.: 1000847.303 Page A- I of A-4 Revision: 1 F0306-01 RI

36 EFPY Input Listing:

I i P-TC*urve Inputs Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp 0 'F Assumed Reactor Vessel Pressure 0 psig Assumed Geometry Vessel Radius 103 in. [7]

Vessel Shell thickness 5.63 in. [7]

Bottom Head Thickness 5.9375 in. [10]

Bottom Head Radius 103.1875 in. [10]

Feedwater Nozzle Thickness 7.7317 in. [11]

Recirculation Inlet (N2) Nozzle Thickness 9.2884 in. [12]

ART/RTNDT 36 EFPY Limiting Beltine 147.4 *F [4]

Limiting Bottom Head 26 *F [6]

Limiting Upper Vessel (Feedwater) RTNDT 40 'F [6]

Flange Region (Boltup) RTNDT 10 'F [6]

Limiting Recirculation Inlet (N2) Nozzle 104.1 'F [4]

Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C) 2 [3]

Pressure (Curme A) 1.5 [3]

Lower Penetrations (SCF) 3 [3]

Limiting Recirculation Inlet (N2) Nozzle (SCF)

Kit During Pressure Test (near isothermal conditions) 0 ksiqin [3]

Water 3 Density 62.4 Ib/ft Assumed Pressure 1250 psig [9]

Full Water Elevation (pressure head) 758 in [9]

Hydrostatic Test Pressure 1563 psig Calculated Static Head Pressure Adjustment 27.4 psig Calculated Assumed Temperature Bolt Up Temperature 60 *F [3]

Increment 2 *F Assumed Rate of Temp Change Heat Up and Cool Down Rate 100 °F/hour [11]

File No.: 1000847.303 Page A-2 of A-4 Revision: 1 F0306-OIRI

40 EFPY Input Listing:

P-T Curve Inputs Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp 0 *F Assumed Reactor Vessel Pressure 0 psig Assumed Geometry Vessel Radius 103 in. [7]

Vessel Shell thickness 5.63 in. [7]

Bottom Head Thickness 5.9375 in. [10]

Bottom Head Radius 103.1875 in. [10]

Feedwater Nozzle Thickness 7.7317 in. [11]

Recirculation Inlet (N2) Nozzle Thickness 9.2884 in. [12]

ARTIRTNDT 40 EFPY Limiting Beltine 156 *F [4]

Limiting Bottom Head 26 *F [6]

Limiting Upper Vessel (Feedwater) RTNDT 40 'F [6]

Flange Region (Boltup) RTNDT 10 'F [6]

Limiting Recirculation Inlet (N2) Nozzle 110 'F [4]

Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C) 2 [3]

Pressure (Curve A) 1.5 [3]

Lower Penetrations (SCF) 3 [3]

Limiting Recirculation Inlet (N2) Nozzle (SCF)

During Pressure Test (near isothermal conditions) 0 ksivin [3]

Water 3

Density 62.4 lb/ft Assumed Pressure 1250 psig [9]

Full Water Elevation (pressure head) 758 in [9]

Hydrostatic Test Pressure 1563 psig Calculated Static Head Pressure Adjustment 27.4 psig Calculated Assumed Temperature Bolt Up Temperature 60 'F [3]

Increment 2 *F Assumed Rate of Temp Change Heat Up and Cool Down Rate 100 °F/hour [11]

File No.: 1000847.303 Page A-3 of A-4 Revision: 1 F0306-OIRI

54 EFPY Input Listing:

>7 ~P-T Clurve Inputs .

Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp 0 'F Assumed Reactor Vessel Pressure 0 psig Assumed Geometry Vessel Radius 103 in. [7]

Vessel Shell thickness 5.63 in. [7]

Bottom Head Thickness 5.9375 in. [10]

Bottom Head Radius 103.1875 in. [10]

Feedwater Nozzle Thickness 7.7317 in. [11]

Recirculation Inlet (N2) Nozzle Thickness 9.2884 in. [12]

ART/RTNDT 54 EFPY Limiting Beltine 186.6 'F [4]

Limiting Bottom Head 26 'F [6]

Limiting Upper Vessel (Feedwater) RTNDT 40 °F [6]

Flange Region (Boltup) RTNDT 10 oF [6]

Limiting Recirculation Inlet (N2) Nozzle 125.2 'F [4]

Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C) 2 [3]

Pressure (Curve A) 1.5 [3]

Lower Penetrations (SCF) 3 [3]

Limiting Recirculation Inlet (N2) Nozzle (SCF)

During Pressure Test (near isothermal conditions) 0 ksivin [3]

Water Density 62.4 lb/ft3 Assumed Pressure 1250 psig [9]

Full Water Elevation (pressure head) 758 in [9]

Hydrostatic Test Pressure 1563 psig Calculated Static Head Pressure Adjustment 27.4 psig Calculated Assumed Temperature Bolt Up Temperature 60 'F [3]

Increment 2 'F Assumed Rate of Temp Change Heat Up and Cool Down Rate 100 °F/hour [11]

File No.: 1000847.303 Page A-4 of A-4 Revision: 1 F0306-O1RI

APPENDIX B BOUNDING BELTLINE SUPPORTING ANALYSIS File No.: 1000847.303 Page B-1 of B-21 Revision: 1 F0306-O1RI

Table B-i: MNGP, Beltline Region, Curve A, for 36 EFPY Plant = MNGP Component Beltline Vessel thickness, t 5.,630 inches Vessel Radius, R = 103 inches ART= 147.4 *F ======> 36 EFPY KIT = 0.,00 (no thermal effects)

Safety Factor 1.50 Mm 2.197 Temperature Adjustment -0.0 °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment 27.4 psig (hydrostatic pressure head for a full vessel at 70'F)

Pressure Adjustment 0.0 psig (instrument uncertainty)

Gauge Adjusted Fluid Temperature Pressure for Temperature Kic KIm for P-T Curve P-T Curve (7F) (ksi*inchl1 2) (ksi*i nch 11 2) (OF) (psig) 60.0 36.81 24.54 60.0 0 60.0 36.81 24.54 60.0 583 62.0 36.96 24.64 62.0 586 64.0 37.11 24.74 64.0 588 66.0 37.27 24.85 66.0 591 68.0 37.44 24.96 68.0 594 70.0 37.61 25.07 70.0 596 72.0 37.79 25.19 72.0 599 74.0 37.98 25.32 74.0 602 76.0 38.17 25.45 76.0 606 78.0 38.37 25.58 78.0 609 80.0 38.59 25.72 80.0 613 82.0 38.81 25.87 82.0 616 84.0 39.03 26.02 84.0 620 86.0 39.27 26.18 86.0 624 88.0 39.52 26.35 88.0 628 90.0 39.78 26.52 90.0 632 92.0 40.05 26.70 92.0 637 94.0 40.33 26.88 94.0 641 96.0 40.62 27.08 96.0 646 98.0 40.92 27.28 98.0 651 100.0 41.23 27.49 100.0 657 102.0 41.56 27.71 102.0 662 104.0 41.90 27.94 104.0 668 106.0 42.26 28.17 106.0 673 108.0 42.63 28.42 108.0 680 110.0 43.01 28.68 110.0 686 112.0 43.41 28.94 112.0 693 114.0 43.83 29.22 114.0 700 116.0 44.26 29.51 116.0 707 118.0 44.72 29.81 118.0 714 120.0 45.19 30.12 120.0 722 File No.: 1000847.303 Page B-2 of B-21 Revision: 1 F0306-0IRI

Table B-1 Continued: MNGP, Beitline Region, Curve A, for 36 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature K~c Kim for P-T Curve P-T Curve (OF) (ksi*inch112 ) 2 (ksi*inch11 ) (*F) (psig) 122.0 45.68 30.45 122.0 730 124.0 46.18 30.79 124.0 739 126.0 46.71 31.14 126.0 747 128.0 47.27 31.51 128.0 757 130.0 47.84 31.89 130.0 766 132.0 48.44 32.29 132.0 776 134.0 49.06 32.71 134.0 786 136.0 49.71 33.14 136.0 797 138.0 50.38 33.59 138.0 808 140.0 51.08 34.05 140.0 820 142.0 51.81 34.54 142.0 832 144.0 52.57 35.05 144.0 845 146.0 53.36 35.57 146.0 858 148.0 54.18 36.12 148.0 871 150.0 55.04 36.69 150.0 885 152.0 55.93 37.29 152.0 900 154.0 56.86 37.91. 154.0 916 156.0 57.83 38.55 156.0 932 158.0 58.83 39.22 158.0 948 160.0 59.88 39.92 160.0 966 162.0 60.96 40.64 162.0 984 164.0 62.10 41.40 164.0 1,003 166.0 63.28 42.18 166.0 1,022 168.0 64.50 43.00 168.0 1,042 170.0 65.78 43.85 170.0 1,064 172.0 67.11 44.74 172.0 1,086 174.0 68.50 45.66 174.0 1,109 176.0 69.94 46.62 176.0 1,133 178.0 71.44 47.62 178.0 1,157 180.0 73.00 48.66 180.0 1,183 182.0 74.62 49.75 182.0 1,210 184.0 76.31 50.87 184.0 1,238 186.0 78.07 52.05 186.0 1,267 188.0 79.90 53.27 188.0 1,298 190.0 81.81 54.54 190.0 1,329 File No.: 1000847.303 Page B-3 of B-21 Revision: 1 F0306-01R I

Table B-2: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 36 EFPY Plant = MNGP Component = Limiting Recirculation Inlet (N2)

ART = 104.10 oF ======> 36 EFPY 103;00 Vessel Radius, R = inches Nozzle comer thickness, t = 9.29 inches, approximate 2

Kit = ksi*inchl1 0.00 2

Kip-applied = 74.36 ksi*inch1/

Crack Depth, a = 2.32 inches Safety factor = 1.50 Temperature Adjustment = °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.37 psig (hydrostatic pressure head for a full vessel at 70*F)

Pressure Adjustment = 0.00 psig (instrument uncertainty)

Reference Pressure = 1,000 psig (pressure at which FEA stress coefficients are valid)

Unit Pressure = 1,563 psig (hydrostatic pressure)

Gauge Adjusted Fluid Temperature Pressure for Temperature K.c Kt p for P-T C urve P-T Curve (OF) (ksi*inch112 ) (ksi*inch 1 2) (fF) (psig) 60.0 41.78 27.86 60.0 0 60.0 41.78 27.86 60.0 347 62.0 42.13 28.09 62.0 350 64.0 42.50 28.33 64.0 354 66.0 42.88 28.58 66.0 357 68.0 43.27 28.85 68.0 361 70.0 43.68 29.12 70.0 364 72.0 44.11 29.41 72.0 368 74.0 44.56 29.70 74.0 372 76.0 45.02 30.01 76.0 376 78.0 45.50 30.33 78.0 381 80.0 46.00 30.67 80.0 385 82.0 46.53 31.02 82.0 390 84.0 47.07 31.38 84.0 395 86.0 47.64 31.76 86.0 400 88.0 48.23 32.15 88.0 405 90.0 48.84 32.56 90.0 411 92.0 49.48 32.98 92.0 416 94.0 50.14 33.43 94.0 422 96.0 50.83 33.89 96.0 428 98.0 51.55 34.37 98.0 435 100.0 52.30 34.87 100.0 442 102.0 53.08 35.39 102.0 449 104.0 53.89 35.93 104.0 456 106.0 54.74 36.49 106.0 463 108.0 55.62 37.08 108.0 471 110.0 56.53 37.69 110.0 479 File No.: 1000847.303 Page B-4 of B-21 Revision: 1 F0306-OIRI

Table B-2 Continued: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 36 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature K~c KNP for P-T C urve P-T Curve

(*F) (ksi*inchll 2) (ksi*inch112 ) (*F) (psig) 112.0 57.48 38.32 112.0 488 114.0 58.47 38.98 114.0 497 116.0 59.51 39.67 116.0 506 118.0 60.58 40.39 118.0 516 120.0 61.70 41.13 120.0 526 122.0 62.86 41.91 122.0 536 124.0 64.07 42.71 124.0 547 126.0 65.33 43.55 126.0 558 128.0 66.64 44.43 128.0 570 130.0 68.01 45.34 130.0 582 132.0 69.43 46.28 132.0 595 134.0 70.90 47.27 134.0 608 136.0 72.44 48.30 136.0 622 138.0 74.04 49.36 138.0 636 140.0 75.71 50.47 140.0 651 142.0 77.45 51.63 142.0 667 144.0 79.25 52.83 144.0 683 146.0 81.13 54.09 146.0 700 148.0 83.09 55.39 148.0 718 150.0 85.12 56.75 150.0 736 152.0 87.24 58.16 152.0 755 154.0 89.45 59.63 154.0 775 156.0 91.74 61.16 156.0 795 158.0 94.13 62.76 158.0 817 160.0 96.62 64.41 160.0 839 162.0 99.21 66.14 162.0 862 164.0 101.90 67.93 164.0 886 166.0 104.71 69.80 166.0 911 168.0 107.62 71.75 168.0 938 170.0 110.66 73.77 170.0 965 172.0 113.82 75.88 172.0 993 174.0 117.11 78.08 174.0 1,023 176.0 120.54 80.36 176.0 1,053 178.0 124.10 82.73 178.0 1,085 180.0 127.81 85.21 180.0 1,119 182.0 131.67 87.78 182.0 1,153 184.0 135.69 90.46 184.0 1,189 186.0 139.87 93.25 186.0 1,227 188.0 144.23 96.15 188.0 1,266 190.0 148.76 99.17 190.0 1,306 File No.: 1000847.303 Page B-5 of B-21 Revision: I F0306-OIRI

Table B-3: MNGP, Beltline Region, Curve A, for 40 EFPY Plant = MNGP Component = .Beltline Vessel thickness, t = 5.630 inches Vessel Radius, R = 103 inches ART = °F ======> 40 EFPY KIT = 0.00 (no thermal effects)

Safety Factor = 1.50<

Mm 2.197 Temperature Adjustment 0.0 *F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel 758.00 inches Pressure Adjustment =1 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment 0.0 psig (instrument uncertainty)

Gauge Adjusted Fluid Temperature Pressure for Temperature Kim for P-T Curve P-T Curve

(*F) (ksi*inch11 2) (ksi*inch 1 2 ) (OF) (psig) 60.0 36.24 24.16 60.0 0 60.0 36.24 24.16 60.0 574 62.0 36.36 24.24 62.0 576 64.0 36.49 24.33 64.0 578 66.0 36.63 24.42 66.0 580 68.0 36.77 24.51 68.0 582 70.0 36.91 24.61 70.0 585 72.0 37.06 24.71 72.0 587 74.0 37.22 24.81 74.0 590 76.0 37.39 24.92 76.0 593 78.0 37.56 25.04 78.0 596 80.0 37.73 25.16 80.0 598 82.0 37.92 25.28 82.0 602 84.0 38.11 25.41 84.0 605 86.0 38.31 25.54 86.0 608 88.0 38.52 25.68 88.0 612 90.0 38.74 25.83 90.0 615 92.0 38.96 25.98 92.0 619 94.0 39.20 26.13 94.0 623 96.0 39.44 26.30 96.0 627 98.0 39.70 26.47 98.0 631 100.0 39.97 26.64 100.0 635 102.0 40.24 26.83 102.0 640 104.0 40.53 27.02 104.0 645 106.0 40.83 27.22 106.0 650 108.0 41.14 27.43 108.0 655 110.0 41.46 27.64 110.0 660 112.0 41.80 27.87 112.0 666 114.0 42.15 28.10 114.0 672 116.0 42.52 28.34 116.0 678 118.0 42.90 28.60 118.0 684 120.0 43.29 28.86 120.0 691 File No.: 1000847.303 Page B-6 of B-21 Revision: 1 F0306-O1RI

Table B-3 Continued: MNGP, Beltline Region, Curve A, for 40 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature Kic Kim for P-T Curve P-T Curve 2

(*F) (ksi*i nch 112) (ksi*inchll ) (*F) (psig) 122.0 43.70 29.14 122.0 697 124.0 44.13 29.42 124.0 705 126.0 44.58 29.72 126.0 712 128.0 45.04 30.03 128.0 720 130.0 45.53 30.35 130.0 728 132.0 46.03 30.69 132.0 736 134.0 46.55 31.04 134.0 745 136.0 47.10 31.40 136.0 754 138.0 47.67 31.78 138.0 763 140.0 48.26 32.17 140.0 773 142.0 48.87 32.58 142.0 783 144.0 49.51 33.01 144.0 794 146.0 50.18 33.45 146.0 805 148.0 50.87 33.91 148.0 816 150.0 51.59 34.39 150.0 828 152.0 52.34 34.89 152.0 841 154.0 53.12 35.41 154.0 854 156.0 53.93 35.96 156.0 867 158.0 54.78 36.52 158.0 881 160.0 55.66 37.11 160.0 896 162.0 56.58 37.72 162.0 911 164.0 57.53 38.35 164.0 927 166.0 58.52 39.02 166.0 943 168.0 59.56 39.71 168.0 960 170.0 60.63 40.42 170.0 978 172.0 61.75 41.17 172.0 997 174.0 62.92 41.95 174.0 1,016 176.0 64.13 42.75 176.0 1,036 178.0 65.39 43.60 178.0 1,057 180.0 66.71 44.47 180.0 1,079 182.0 68.08 45.38 182.0 1,102 184.0 69.50 46.33 184.0 1,125 186.0 70.98 47.32 186.0 1,150 188.0 72.52 48.35 188.0 1,175 190.0 74.13 49.42 190.0 1,202 192.0 75.80 50.53 192.0 1,230 194.0 77.54 51.69 194.0 1,259 196.0 79.34 52.90 196.0 1,289 198.0 81.23 54.15 198.0 1,320 File No.: 1000847.303 Page B-7 of B-21 Revision: 1 F0306-OIRI

Table B-4: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 40 EFPY Plant =

Limiting' Component =

Recirculation Inlet (N2)

ART = 110.00 'F ======> 40 EFPY Vessel Radius, R = 103.00 inches Nozzle comer thickness, t = 9.29 inches, approximate 2

KIt = ksi*inchl1 2

Kip-applied = ,74.36 ksi*inch1/

Crack Depth, a = 2.32- inches Safety factor = 1.50 Temperature Adjustment = 0.00 °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.37 psig (hydrostatic pressure head for a full vessel at 70'F)

Pressure Adjustment = 0.00, psig (instrument uncertainty)

Reference Pressure = 1,000 psig (pressure at which FEA stress coefficients are valid)

Unit Pressure = 1,563 psig (hydrostatic pressure)

Gauge Adjusted Fluid Temperature Pressure for Temperature KIc Kip for P-T C urve P-T Curve

(*F) (ksi*inchl1 2) 2 (ksi*inch11 ) (*F) (psig) 60.0 40.83 27.22 60.0 0 60.0 40.83 27.22 60.0 339 62.0 41.14 27.43 62.0 341 64.0 41.46 27.64 64.0 344 66.0 41.80 27.87 66.0 347 68.0 42.15 28.10 68.0 351 70.0 42.52 28.34 70.0 354 72.0 42.90 28.60 72.0 357 74.0 43.29 28.86 74.0 361 76.0 43.70 29.14 76.0 364 78.0 44.13 29.42 78.0 368 80.0 44.58 29.72 80.0 372 82.0 45.04 30.03 82.0 376 84.0 45.53 30.35 84.0 381 86.0 46.03 30.69 86.0 385 88.0 46.55 31.04 88.0 390 90.0 47.10 31.40 90.0 395 92.0 47.67 31.78 92.0 400 94.0 48.26 32.17 94.0 405 96.0 48.87 32.58 96.0 411 98.0 49.51 33.01 98.0 417 100.0 50.18 33.45 100.0 422 102.0 50.87 33.91 102.0 429 104.0 51.59 34.39 104.0 435 106.0 52.34 34.89 106.0 442 108.0 53.12 35.41 108.0 449 110.0 53.93 35.96 110.0 456 File No.: 1000847.303 Page B-8 of B-21 Revision: 1 F0306-OIRI

Table B-4 Continued: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 40 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature KKC IP for P-T C urve P-T Curve

(*F) (ksi*inch1/2 ) (ksi*inchl12) (*F) (psig) 112.0 54.78 36.52 112.0 464 114.0 55.66 37.11 114.0 472 116.0 56.58 37.72 116.0 480 118.0 57.53 38.35 118.0 488 120.0 58.52 39.02 120.0 497 122.0 59.56 39.71 122.0 507 124.0 60.63 40.42 124.0 516 126.0 61.75 41.17' 126.0 526 128.0 62.92 41.95 128.0 537 130.0 64.13 42.75 130.0 548 132.0 65.39 43.60 132.0 559 134.0 66.71 44.47 134.0 571 136.0 68.08 45.38 136.0 583 138.0 69.50 46.33 138.0 596 140.0 70.98 47.32 140.0 609 142.0 72.52 48.35 142.0 623 144.0 74.13 49.42 144.0 637 146.0 75.80 50.53 146.0 652 148.0 77.54 51.69 148.0 668 150.0 79.34 52.90 150.0 684 152.0 81.23 54.15 152.0 701 154.0 83.19 55.46 154.0 718 156.0 85.23 56.82 156.0 737 158.0 87.35 58.23 158.0 756 160.0 89.56 59.71 160.0 .776 162.0 91.86 61.24 162.0 796 164.0 94.25 62.84 164.0 818 166.0 96.75 64.50 166.0 840 168.0 99.34 66.23 168.0 863 170.0 102.04 68.03 170.0 887 172.0 104.85 69.90 172.0 913 174.0 107.77 71.85 174.0 939 176.0 110.82 73.88 176.0 966 178.0 113.98 75.99 178.0 995 180.0 117.28 78.19 180.0 1,024 182.0 120.71 80.47 182.0 1,055 184.0 124.28 82.86 184.0 1,087 186.0 128.00 85.33 186.0 1,120 188.0 131.87 87.91 188.0 1,155 190.0 135.90 90.60 190.0 1,191 192.0 140.09 93.39 192.0 1,229 194.0 144.45 96.30 194.0 1,268 196.0 148.99 99.33 196.0 1,308 File No.: 1000847.303 Page B-9 of B-21 Revision: 1 F0306-OIRI

Table B-5: MNGP, Beltline Region, Curve A, for 54 EFPY Plant =

Component = Beli ne Vessel thickness, t = 5.630 inches Vessel Radius, R = 103 inches ART =

S186.5 F ..... => 654 EFPY KIT = 0.00 (no thermal effects)

Safety Factor = 1.50, Mm = 2.197 0

Temperature Adjustment = 0.0 F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = 0.0 psig (instrument uncertainty)

Gauge Adjusted Fluid Temperature Pressure for Temperature KIC Kim for P-T Curve P-T Curve

(*F) (ksi*inchl12 ) (ksi*inch112) (*F) (psig) 60.0 34.85 23.23 60.0 0 60.0 34.85 23.23 60.0 551 62.0 34.92 23.28 62.0 552 64.0 34.99 23.32 64.0 553 66.0 35.06 23.37 66.0 554 68.0 35.13 23.42 68.0 555 70.0 35.21 23.48 70.0 557 72.0 35.30 23.53 72.0 558 74.0 35.38 23.59 74.0 559 76.0 35.47 23.65 76.0 561 78.0 35.56 23.71 78.0 562 80.0 35.66 23.77 80.0 564 82.0 35.76 23.84 82.0 566 84.0 35.86 23.91 84.0 567 86.0 35.97 23.98 86.0 569 88.0 36.09 24.06 88.0 571 90.0 36.20 24.14 90.0 573 92.0 36.33 24.22 92.0 575 94.0 36.45 24.30 94.0 577 96.0 36.59 24.39 96.0 579 98.0 36.72 24.48 98.0 582 100.0 36.87 24.58 100.0 584 102.0 37.02 24.68 102.0 587 104.0 37.17 24.78 104.0 589 106.0 37.34 24.89 106.0 592 108.0 37.50 25.00 108.0 595 110.0 37.68 25.12 110.0 598 112.0 37.86 25.24 112.0 601 114.0 38.05 25.37 114.0 604 116.0 38.25 25.50 116.0 607 118.0 38.46 25.64 118.0 610 120.0 38.67 25.78 120.0 614 122.0 38.90 25.93 122.0 618 124.0 39.13 26.09 124.0 622 126.0 39.37 26.25 126.0 626 128.0 39.62 26.41 128.0 630 130.0 39.88 26.59 130.0 634 File No.: 1000847.303 Page B- 10 of B-21 Revision: 1 F0306-OIRI

Table B-5 Continued: MNGP, Beltline Region, Curve A, for 54 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature KM. Km for P-T Curve P-T Curve

(*F) (ksi*inchl/ 2 ) (ksi*inch 112 ) (*F) (psig) 132.0 40.16 26.77 132.0 639 134.0 40.44 26.96 134.0 643 136.0 40.74 27.16 136.0 648 138.0 41.04 27.36 138.0 653 140.0 41.36 27.58 140.0 659 142.0 41.70 27.80 142.0 664 144.0 42.04 28.03 144.0 670 146.0 42.41 28.27 146.0 676 148.0 42.78 28.52 148.0 682 150.0 43.17 28.78 150.0 689 152.0 43.58 29.05 152.0 695 154.0 44.00 29.33 154.0 702 156.0 44.44 29.63 156.0 710 158.0 44.90 29.93 158.0 717 160.0 45.38 30.25 160.0 725 162.0 45.88 30.58 162.0 733 164.0 46.39 30.93 164.0 742 166.0 46.93 31.29 166.0 751 168.0 47.49 31.66 168.0 760 170.0 48.08 32.05 170.0 770 172.0 48.68 32.46 172.0 780 174.0 49.32 32.88 174.0 791 176.0 49.97 33.32 176.0 801 178.0 50.66 33.77 178.0 813 180.0 51.37 34.25 180.0 825 182.0 52.11 34.74 182.0 837 184.0 52.88 35.26 184.0 850 186.0 53.69 35.79 186.0 863 188.0 54.52 36.35 188.0 877 190.0 55.39 36.93 190.0 891 192.0 56.30 37.53 192.0 906 194.0 57.24 38.16 194.0 922 196.0 58.22 38.81 196.0 938 198.0 59.24 39.50 198.0 955 200.0 60.31 40.20 200.0 973 202.0 61.41 40.94 202.0 991 204.0 62.56 41.71 204.0 1,010 206.0 63.76 42.51 206.0 1,030 208.0 65.01 43.34 208.0 1,051 210.0 66.31 44.21 210.0 1,072 212.0 67.66 45.11 212.0 1,095 214.0 69.07 46.04 214.0 1,118 216.0 70.53 47.02 216.0 1,142 218.0 72.05 48.04 218.0 1,168 220.0 73.64 49.09 220.0 1,194 222.0 75.29 50.19 222.0 1,221 224.0 77.01 51.34 224.0 1,250 226.0 78.79 52.53 226.0 1,279 228.0 80.65 53.77 228.0 1,310 File No.: 1000847.303 Page B-I I of B-21 Revision: 1 F0306-O1RI

Table B-6: MNGP, Recirculation Inlet (N2) Nozzle Beitline Region, Curve A, for 54 EFPY Plant = MNGP Component = Limiting Recirculation Inlet (N2) 125.20 0 ART = F ======> 54 EFPY Vessel Radius, R = , 103.00 inches Nozzle comer thickness, t = 929 inches, approximate 2

Kit =

,,r;!*0.00 ksi*inchl1 2

Kip-applied = 174.36 ksi*inch1/

Crack Depth, a = 2.32 inches Safety factor = 1.50 Temperature Adjustment = 0.00 °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.37 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = 0.00 psig (instrument uncertainty)

Reference Pressure = 1,000 .psig (pressure at which FEA stress coefficients are valid)

Unit Pressure 1,L~~563 psig (hydrostatic pressure)

Gauge Adjusted Fluid Temperature Pressure for Temperature K'c for P-T C urve P-T Curve (OF) (ksi*inch 112) (ksi*inchl1 2

) (*F) (psig) 60.0 38.83 25.89 60.0 0 60.0 38.83 25.89 60.0 321 62.0 39.06 26.04 62.0 323 64.0 39.30 26.20 64.0 325 66.0 39.55 26.36 66.0 327 68.0 39.80 26.54 68.0 330 70.0 40.07 26.72 70.0 332 72.0 40.35 26.90 72.0 334 74.0 40.65 27.10 74.0 337 76.0 40.95 27.30 76.0 340 78.0 41.27 27.51 78.0 343 80.0 41.60 27.73 80.0 346 82.0 41.94 27.96 82.0 349 84.0 42.30 28.20 84.0 352 86.0 42.67 28.44 86.0 355 88.0 43.05 28.70 88.0 359 90.0 43.46 28.97 90.0 362 92.0 43.87 29.25 92.0 366 94.0 44.31 29.54 94.0 370 96.0 44.76 29.84 96.0 374 98.0 45.23 30.16 98.0 378 100.0 45.73 30.48 100.0 383 102.0 46.24 30.82 102.0 387 104.0 46.77 31.18 104.0 392 106.0 47.32 31.55 106.0 397 108.0 47.90 31.93 108.0 402 110.0 48.50 32.33 110.0 407 112.0 49.12 32.75 112.0 413 114.0 49.77 33.18 114.0 419 116.0 50.45 33.63 116.0 425 118.0 51.15 34.10 118.0 431 120.0 51.89 34.59 120.0 438 File No.: 1000847.303 Page B-12 of B-21 Revision: 1 F0306-O1RI

Table B-6 Continued: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 54 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature KI KP for P-T C urve P-T Curve (OF) (ksi*inch112) (ksi*inchl1 2) ('F) (psig) 122.0 52.65 35.10 122.0 445 124.0 53.44 35.63 124.0 452 126.0 54.27 36.18 126.0 459 128.0 55.13 36.75 128.0 467 130.0 56.02 37.35 130.0 475 132.0 56.95 37.97 132.0 483 134.0 57.92 38.62 134.0 492 136.0 58.93 39.29 136.0 501 138.0 59.98 39.99 138.0 510 140.0 61.08 40.72 140.0 520 142.0 62.21 41.48 142,0 530 144.0 63.40 42.27 144.0 541 146.0 64.63 43.09 146.0 552 148.0 65.91 43.94 148.0 564 150.0 67.25 44.83 150,0 576 152.0 68.64 45.76 152.0 588 154.0 70.08 46.72 154.0 601 156.0 71.59 47.73 156,0 614 158.0 73.16 48.77 158.0 629 160.0 74.79 49.86 160.0 643 162.0 76.48 50.99 162.0 658 164.0 78.25 52.17 164.0 674 166.0 80.09 53.39 166.0 691 168.0 82.00 54.67 168.0 708 170.0 83.99 56.00 170.0 726 172.0 86.07 57.38 172.0 744 174.0 88.22 58.82 174.0 764 176.0 90.47 60.31 176.0 784 178.0 92.81 61.87 178.0 805 180.0 95.24 63.49 180.0 827 182.0 97.77 65.18 182.0 849 184.0 100.41 66.94 184.0 873 186.0 103.15 68.77 186.0 897 188.0 106.00 70.67 188.0 923 190.0 108,98 72.65 190.0 950 192.0 112.07 74.71 192.0 977 194.0 115.29 76.86 194.0 1,006 196.0 118.64 79.09 196.0 1,036 198.0 122.12 81.42 198.0 1,068 200.0 125.75 83.83 200.0 1,100 202.0 129.53 86.35 202.0 1,134 204.0 133.46 88.97 204.0 1,169 206.0 137.55 91.70 206.0 1,206 208.0 141.81 94.54 208.0 1,244 210.0 146.24 97.50 210.0 1,284 212.0 150.86 100.57 212.0 1,325 File No.: 1000847.303 Page B-13 of B-21 Revision: 1 F0306-OIRI

Table B-7: MNGP, Beltline Region, Curve B, for 54 EFPY Plant = MNGP Component = Beltline Vessel thickness, t = 5.630 inches Vessel Radius, R = 103 inches ART = 186.6 , 'F ======> 2 64 EFPY Kit = 7.17 ksi*inchl/

Safety Factor = 2.00 Mm= 2.197 Temperature Adjustment 0.0 °F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 inches Pressure Adjustment = 27.4 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment = 0.0 psig (instrument uncertainty)

Heat Up and Cool Down Rate = 100 '°F/Hr Gauge Adjusted Fluid Temperature Pressure for Temperature KiC KIm for P-T Curve P-T Curve 2

(°F) (ksi*inchl1 ) (ksi*inch1/2) (*F) (psig) 60.0 34.85 13.84 60.0 0 60.0 34.85 13.84 60.0 317 62.0 34.92 13.87 62.0 318 64.0 34.99 13.91 64.0 319 66.0 35.06 13.95 66.0 320 68.0 35.13 13.98 68.0 321 70.0 35.21 14.02 70.0 321 72.0 35.30 14.06 72.0 323 74.0 35.38 14.11 74.0 324 76.0 35.47 14.15 76.0 325 78.0 35.56 14.20 78.0 326 80.0 35.66 14.25 80.0 327 82.0 35.76 14.30 82.0 328 84.0 35.86 14.35 84.0 330 86.0 35.97 14.40 86.0 331 88.0 36.09 14.46 88.0 332 90.0 36.20 14.52 90.0 334 92.0 36.33 14.58 92.0 335 94.0 36.45 14.64 94.0 337 96.0 36.59 14.71 96.0 339 98.0 36.72 14.78 98.0 340 100.0 36.87 14.85 100.0 342 102.0 37.02 14.93 102.0 344 104.0 37.17 15.00 104.0 346 106.0 37.34 15.08 106.0 348 108.0 37.50 15.17 108.0 350 110.0 37.68 15.26 110.0 352 112.0 37.86 15.35 112.0 354 114.0 38.05 15.44 114.0 357 116.0 38.25 15.54 116.0 359 118.0 38.46 15.65 118.0 362 120.0 38.67 15.75 120.0 365 122.0 38.90 15.86 122.0 367 124.0 39.13 15.98 124.0 370 126.0 39.37 16.10 126.0 373 128.0 39.62 16.23 128.0 376 130.0 39.88 16.36 130.0 380 132.0 40.16 16.49 132.0 383 134.0 40.44 16.64 134.0 387 136.0 40.74 16.78 136.0 390 138.0 41.04 16.94 138.0 394 140.0 41.36 17.10 140.0 398 File No.: 1000847.303 Page B-14 of B-21 Revision: 1 F0306-O0RI

Table B-7: Continued: MNGP, Beltline Region, Curve B, for 54 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature Kic K.m for P-T Curve P-T Curve 2 12

(*F) (ksi*inch 1 ) (ksi*inch ) (*F) (psig) 142.0 41.70 17.27 142.0 402 144.0 42.04 17.44 144.0 406 146.0 42.41 17.62 146.0 411 148.0 42.78 17.81 148.0 416 150.0 43.17 18.00 150.0 420 152.0 43.58 18.21 152.0 426 154.0 44.00 18.42 154.0 431 156.0 44.44 18.64 156.0 436 158.0 44.90 18.87 158.0 442 160.0 45.38 19.11 160.0 448 162.0 45.88 19.35 162.0 454 164.0 46.39 19.61 164.0 461 166.0 46.93 19.88 166.0 467 168.0 47.49 20.16 168.0 474 170.0 48.08 20.45 170.0 481 172.0 48.68 20.76 172.0 489 174.0 49.32 21.07 174.0 497 176.0 49.97 21.40 176.0 505 178.0 50.66 21.75 178.0 514 180.0 51.37 22.10 180.0 522 182.0 52.11 22.47 182.0 532 184.0 52.88 22.86 164.0 541 186.0 53.69 23.26 186.0 551 188.0 54.52 23.68 188.0 562 190.0 55.39 24.11 190.0 572 192.0 56.30 24.57 192.0 584 194.0 57.24 25.04 194.0 595 196.0 58.22 25.53 196.0 608 198.0 59.24 26.04 198.0 620 200.0 60.31 26.57 200.0 634 202.0 61.41 27.12 202.0 647 204.0 62.56 27.70 204.0 662 206.0 63.76 28.30 206.0 677 208.0 65.01 28.92 208.0 692 210.0 66.31 29.57 210.0 708 212.0 67.66 30.25 212.0 725 214.0 69.07 30.95 214.0 743 216.0 70.53 31.68 216.0 761 218.0 72.05 32.44 218.0 780 220.0 73.64 33.24 220.0 799 222.0 75.29 34.06 222.0 820 224.0 77.01 34.92 224.0 641 226.0 78.79 35.81 226.0 864 228.0 80.65 36.74 228.0 887 230.0 82.59 37.71 230.0 911 232.0 84.61 38.72 232.0 936 234.0 86.70 39.77 234.0 962 236.0 88.89 40.86 236.0 989 238.0 91.16 42.00 238.0 1,017 240.0 93.53 43.18 240.0 1,047 242.0 95.99 44.41 242.0 1,077 244.0 98.55 45.69 244.0 1,109 246.0 101.22 47.03 246.0 1,142 248.0 103.99 48.41 248.0 1,177 250.0 106.88 49.86 250.0 1,213 252.0 109.89 51.36 252.0 1,250 254.0 113.02 52.93 254.0 1,289 256.0 116.28 54.56 256.0 1,330 File No.: 1000847.303 Page 13-15 of B-21 Revision: 1 F0306-OIRI

Table B-8: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve B, for 54 EFPY Plant = MNGP Component = Limiting Recirculation Inlet (N2) Nozzle ART = 125.20 'F =====> 54 EFPY Vessel Radius, R = 1t03.00" inches Nozzle corner thickness, t = 9.29 inches, approximate Kit 9.45 ksi*inch"' 2 2

Kip.applied 74.36 ksi*inchl1 Crack Depth, a = 2.32 inches Safety factor 2.00 Temperature Adjustment 0.00 *F (applied after bolt-up, instrument uncertainty)

Height of Water for a Full Vessel = 758.00 rinches Pressure Adjustment - y 27.37 L psig (hydrostatic pressure head for a full \essel at 70*F)

Pressure Adjustment 0.00. psig (instrument uncertainty)

Reference Pressure = 1,000 psig (pressure at which FEA stress coefficients are valid)

Unit Pressure 1,563 psig (hydrostatic pressure)

Gauge Adjusted Fluid Temperature Pressure for Temperature for P-T Curve P-T Curve Kic 2 1 2

('F) (ksi*inch11 ) (ksi*inch ) (*F) (psig) 60.0 38.83 14.69 60.0 0 60.0 38.83 14.69 60.0 170 62.0 39.06 14.80 62.0 172 64.0 39.30 14.92 64.0 173 66.0 39.55 15.05 66.0 175 68,0 39,80 15.18 68.0 177 70.0 40.07 15.31 70.0 179 72.0 40.35 15.45 72.0 180 74.0 40.65 15.60 74.0 182 76.0 40.95 15.75 76.0 184 78.0 41.27 15.91 78.0 187 80.0 41.60 16.07 80.0 189 82.0 41.94 16.24 82.0 191 84.0 42.30 16.42 84.0 193 86.0 42.67 16.61 86.0 196 88.0 43.05 16.80 88.0 199 90.0 43.46 17.00 90.0 201 92.0 43.87 17.21 92.0 204 94.0 44.31 17.43 94.0 207 96.0 44.76 17.65 96.0 210 98.0 45.23 17.89 98.0 213 100.0 45.73 18.14 100.0 217 102.0 46.24 18.39 102,0 220 104.0 46.77 18.66 104.0 224 106.0 47.32 18.93 106.0 227 108.0 47.90 19.22 108.0 231 110.0 48.50 19.52 110.0 235 112.0, 49.12 19.83 112,0 239 114.0 49.77 20.16 114,0 244 116.0 50.45 20.50 116.0 248 118.0 51.15 20.85 118.0 253 120.0 51.89 21.22 120.0 258 122.0 52.65 21.60 122.0 263 124.0 53.44 21.99 124.0 268 126.0 54.27 22.41 126.0 274 128.0 55.13 22.84 128.0 280 130.0 56.02 23.28 130.0 286 File No.: 1000847.303 rage nu-ID cirnfl-LI 1~ ni Page B-I6 OI B-2l Revision: 1 F0306-ORI

Table B-8 Cont: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve B, for 54 EFPY Gauge Adjusted Fluid Temperature Pressure for Temperature K.c Kip for P-T Curve P-T Curve 112 2 (oF) (ksi*inch ) (ksi*inchlI ) (CF) (psig) 132.0 56.95 23.75 132.0 292 134.0 57.92 24.23 134.0 299 136.0 58.93 24.74 136.0 305 138.0 59.98 25.26 138.0 312 140.0 61.08 25.81 140.0 320 142.0 62.21 26.38 142.0 327 144.0 63.40 26.97 144.0 335 146.0 64.63 27.59 146.0 344 148.0 65.91 28.23 148.0 352 150.0 67.25 28.90 150.0 361 152.0 68.64 29.59 152.0 371 154.0 70.08 30.31 154.0 380 156.0 71.59 31.07 156.0 390 158.0 73.16 31.85 158.0 401 160.0 74.79 32.67 160.0 412 162.0 76.48 33.51 162.0 423 164.0 78.25 34.40 164.0 435 166.0 80.09 35.32 166.0 448 168.0 82.00 36.27 168.0 460 170.0 83.99 37.27 170.0 474 172.0 86.07 38.31 172.0 488 174.0 88.22 39.38 174.0 502 176.0 90.47 40.51 176.0 517 178.0 92.81 41.68 178.0 533 180.0 95.24 42.89 180.0 549 182.0 97.77 44.16 182.0 567 184.0 100.41 45.48 184.0 584 186.0 103.15 46.85 186.0 603 188.0 106.00 48.27 188.0 622 190.0 108.98 49.76 190.0 642 192.0 112.07 51.31 192.0 663 194.0 115.29 52.92 194.0 684 196.0 118.64 54.59 196.0 707 198.0 122.12 56.33 198.0 730 200.0 125.75 58.15 200.0 755 202.0 129.53 60.04 202.0 780 204.0 133.46 62.00 204.0 806 206.0 137.55 64.05 206.0 834 208.0 141.81 66.18 208.0 863 210.0 146.24 68.39 210.0 892 212.0 150.86 70.70 212.0 923 214.0 155.66 73.10 214.0 956 216.0 160.66 75.60 216.0 989 218.0 165.86 78.20 218.0 1,024 220.0 171.27 80.91 220.0 1,061 222.0 176.91 83.73 222.0 1,099 224.0 182.77 86.66 224.0 1,138 226.0 188.88 89.71 226.0 1,179 228.0 195.23 92.89 228.0 1,222 230.0 201.84 96.19 230.0 1,266 232.0 208.72 99.63 232.0 1,313 File No.: 1000847.303 Page B-17 of B-21 Revision: 1 F0306-O1Rl

V StructuralIntegrityAssociates, Inc.

MNGP Pressure Test (Curve A), 36 EFPY 300 I II II I I I I I I I I I II F F I I1I IIit 1i COMPLIANCE REO.U IRES OPERATION ABOVE THE CU RVES I 280 260 U-LU 240 J io 220

,' ii 0i

a. 200 I00

'000, LU I-

-J 180 .10 0

,, 160 uJ 140 cr)

(/)

> 120 o 100 Lu 80 60 ti 60 .F--- tm~a 40 20 J J~ l ..... Upper Vessel

. .. ..1 ,1. ..- . .

0 .. ... EE

. H 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

File No.: 1000847.303 Page B-18 ofB-21 Revision: 1 F0306-OIRI

V StructuralIntegrityAssociates, Inc.

MNGP Pressure Test (Curve A), 40 EFPY 300 280 COMLIANCEREQUIRESOPERATIONABOVETHE CURVES 260 uJ 240 S 220 LU

a. 200 - - -

Lii 18 I-Lu 160

-J I*.*

wu 140 LU

> 120 o 0 10 I LU 80 60 *; - Beltline Reg ion

=* 40 -- Bt-pTm:===Beltline - N2 Nozzle j 40 Bolt-up Temp.

60'F Z - Bottom Head I0IIIIII .... Upper Vessel I I I I I IIn I = _ . I ---L l ll l 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

File No.: 1000847.303 Page B-19 ofB-21 Revision: 1 F0306-OIRI

StructuralIntegrityAssociates, Inc.

MNGP Pressure Test (Curve A), 54 EFPY 300 I I I I I I I 1 II I II liii 1111 111111 II 1111111111111 liii IIIIIIIIIII IIIIIIIIIII 111111111 II I III II 280 COMPLIANCE REQUIRES OPERATION ABOVETHE CURVES g I l I II IIIB 260 IIiIi1111 i111i1i1i1II1 1 11 11111111 1 11 111.. ... . 1111 1 1 I U-W 240 I ~ ~ ~ ~ ~ ~ . . . . .

220 w

a- 200 wI-w

-1 I-180 I l1 1 1 1 11 1 1I I11 iI1111111111 II L ...1IIý t I7r m 11111111111 w 160

. . . . . . . . . .~~~I .. . . . . . . . I . . . . . . . . . I .

--J w 140 CO) 0l) w 120 11 11 11 1 111111 II1ý?J *i I.1 IIIIl 1 1 1 1 1111111111 III1I1iM 0 100 I I I I I I I I I I I I I I~1.W' 4I~I~I *1 I~ ~ I t 1#1 I I ~ 4 IlIt~I I I I I I I I I I I I I I I I I-wU 80 60 -- . .. . . . . . . . . . . . . .. .....,

-Belt]in e Region 40 Bolt-up Temp: p: *Beltline N2 Nozzle 60'F , Bottom Head 20 Upper Vessel 0

0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL (psig)

File No.: 1000847.303 Page B-20 of B-21 Revision: 1 F0306-OIRI

V StructuralIntegrity Associates, Inc.

MNGP Normal Operation - Core Not Critical (Curve B), 54 EFPY 300 280 260 uJ 240 220

,, .... - - er-esse -pp w

a. 200 w i.000001

'- 180 II *" / I...

m 160 ii il--

• g -B toIa .. ""1"

• 140 Cn C,,

Lu 120 0 100 w 80 60 Bol-u Tem  : -I r

-- ' omH a I 40 6 0 'F - - - - - U p p e r Ve s s e l 20 0

0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 PRESSURE LIMIT IN REACTOR VESSEL TOP HEAD (psig)

File No.: 1000847.303 Page B-21 of B-21 Revision: 1 F0306-O1RI

ENCLOSURE 9 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE THE TECHNICAL SPECIFICATIONS TO INCLUDE A PRESSURE TEMPERATURE LIMITS REPORT CALCULATION CA 11-003 AFFADAVITS FROM STRUCTURAL INTEGRITY ASSOCIATES, INC AND EPRI FOR THE PROPIETARY CALCULATION EVALUATION OF ADJUSTED REFERENCE TEMPERATURES AND REFERENCE TEMPERATURE SHIFTS (SIA No. 1000847.301)

PROPRIETARY VERSION (5 pages follow)

...... ur. .r.. Associates, In

,5215 Hellyer AMe.

Suie 210 SanJose, CA 95138-1025, Phone: 408-978-8200 Fax: 408-97808964 NINAI.stiublint.com August 19, 2011 AFFIDAVIT I, Mardos Legaspi Herrera, state as follows:

(1) 1 am aVice President of Structural Integrity Ass.ociates; Inc. (SI) and have been delegated the function of reviewing the informalion described.in paragraph (2) which is sotight to be Withleld, and have been authorized to apply for fits withholding.

(2) The information sought to.be withheld is cbntaiied iin SIKCdiulation 10.00847.301, Rev.'2, "Evaluation of Adjusted Reference Temperatures ftnd Reference Temperature Shifts." This calculation is to be treated as SI proprietary informatioti, because itcontains signi fic6,iht informati6io thatis deemed proprietary and confidential to Electric Power Research histitute, Inc. (EPRI). EPRI design input information was providedcto SI in strictest confidence so that we.could generate the afoi-eienfioned-calculation. on behalf of Si's client, XcelEnergy, Inc..

Paragraph 3 of this Affidavit provides the basis for the proprietary determinati on.

(3) ST is: making this application for withholding of prprietary information on the basis.that such, information was provided to SI under the protection of a Proprietary/Confidentiality and Nondisclosure Agreement between SI ald EPRI. In a separate Affidavit requesti fg withholding ofssuch proprietary informnation prepared by EPRI, EPRI relies upon 'th!e exemption of disclosure set forth in NRC Regulation 10. CFR 2.390(a)(4),pertaining to

"'withlholding based upon privileged and confidential trade secrets or commhercial or financial information" (Exkepptibn 4).- As delineated in EPR1's Affidavit, the material for Whichl exemiption frfni disclosure is herein sought is coqsideed:.prprietary for the followiJng ieasons ý(takeft'directly froni lteis a, b, d, and e of EPRI'sAffidavit):

a) The Proprietary Information is. owned 'byEPRI -aid has been field in ýonfid&Vdce bY' EPRI. All entities acceptinggcopies, of ýtle Pro prietaryIn formation do so subject t6 writteh ag!,eeiients imposingan, obligationlupon. the recipienptto maintain:the confideintiality of the Popriet-'iUYTiihforniation. ThePiroprietary Infoi-inatiori:is,-disclosed: only to parties Who agree, iwnriting;

i. to'pieser9e the confidentiali-(y ithereof.

SI Aff!davitfbr.Calculation 1000847 30L, .Revý. ,2 . August 19, 204 1:

Rige 2 of 3 b) EPRI considers the Proprietary _hformation conta.ined tferein to constitute trade secrets of EPR[. As such, EPRI holds the Information in confidencemand disclosure thereof is.strictly limited to individuals and entities who have agreed, in writing, -to maintain the.confidentiality of the Information. EPRi.made a substantial economic investment to develop the Proprietary InfQrmation and, by proh ibitilig public disclosure, EPRI derives an econom.ic'benefit in the form of licensing royalties andother additiondtil fees from the confidential nature of tile Proprietary Info.rmation. If the Proprietary Informatidn were publicly available to consultants and/or other businesses providing.services-in the electric and/or nuclear power industry, fhey would be able to use the Proprietary hiforination for their own comrnercial benefit and profit and without, expending the substantial econom ic resources req Oi redI of EPR[ to develop the.Proprietary Information.

c) The Proprietary Information contained therejn are not generally known,or available to.the public. EPRI developed the Information only after making a determination that the Proprietary fnfornation was not available from public, sources. EPRIJ miade alsubstantial inivestment of both hioney and employee hours in the development of tIe Proprietary information. EPRI was required to devote these:resources and effort toderive the Proprietary'Information. As a-result of such effort and-cost,.both in terms.of dollars spent and dedicatedemployee time, the Proprietary Information is highly valuable to EPRI.

d) A public disclosure of theProprietary Information would be highly likely toqcause substantialt harm to EPRI's .coinpetitive position and the ability ofEPRI to license-the Proprietary Information both domestically and-intemnationally. The Proprietary information Can only be aclquired and/or duplicated by others-using an equivalent investment of. time and effort' Publio disclosure of the inforniation s'oughtgto be withhe ,ld is likely to cause Substantial harm to EPRI with which SIhas established a Proprietary/Confidentiality andNondisclosure Agreement.

cturai!Stru 1aegrity..Associates, Inc.6

Si .Affidavii for Calculation 1 000847.301, ýRev. 2 Aulgus-( 1i9,.20.11

'Page,3 of 3 ideclai-e nder penalty of perjury tha t ihe above information and request are trie, correct, and complete wo~the best of 'ny knowledge, in formation, an-ld'belief.

Executed at San Jose, Ca i.forn]'a 0n1this 1 9Lh day of August, 2011.

Mar/os Legsie ra P'.

gaspi I-lerrera, PRE.

Vice President Nuclear Plant Services State of California Subscribed'aild sworn. to (o- affirmed) before me, Coun-Ity of, ksCA? ýa- oil this I~day'of-'4L,20 ,

.Dai* u Molfý Year by

• :.* .Nan-OW Signx~r.*

proved to me oni Ole: basis of satisfa'ctory evidence tO .be the person whlo appeared before, me-(.)

(akd:

(2)

Namhe of Signer

,proved to me on the basis. of:satisfactoryevidence to. be the person Mho appeared befbre me;)

• Signature (Nt-i/yPb 1lnce. N.otary. Seal' andor StampAbove Struturainteg'tyi. Associates,, Inc!

I ELECTRIC POWER RESEARCH INSTITUTE AFFIDAVIT RE: Request for Withholding of the Following Proprietary Information Included In::

"Monticello P-T Curves Revision According to the PTLR Methodology" Structural Integrity Associates Report No: 1000847.301 Revision 2, Project No: 1100730, August 2011 I, David J. Modeen, being duly sworn, depose and state as follows:

I am the Director, External Affairs, Nuclear Sector at Electric Power Research Institute, Inc. whose principal office is located at 1300 W WT Harris Blvd, Charlotte North Carolina ("EPRI) and [ýhave been specifically delegated responsibility for the above-listed report that contains EPRI Proprietary Information that is sought under this Affidavit to be withheld "Proprietary Information". I am authorized to apply to the U.S. Nuclear Regulatory Commission ("NRC") for the withholding of the Proprietary Information on behalf of EPRI.

EPRI requests that the Proprietary Information be withheld from the public on the following bases:

Withholding Based Upon Privileged And Confidential Trade Secrets Or Commercial Or Financial Information:

a. The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information is disclosed only to parties who agree, inwriting, to preserve the confidentiality thereof.

b. EPRI considers the Proprietary Information contained therein to constitute trade secrets of EPRI. As such, EPRI holds the Information in confidence and disclosure thereof is strictly limited to individuals and entities who have agreed, in writing, to maintain the confidentiality of the Information. EPRI made a substantial economic investment to develop the Proprietary Information and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. If the Proprietary Information were publicly available to consultants and/or other businesses providing services in the electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit and profit and without expending the substantial economic resources required of EPRI to develop the Proprietary Information.

c. EPRI's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act which California adopted in 1984 and a version of which has been adopted by over forty states. The California Uniform Trade Secrets Act, California Civil Code §§3426 - 3426.11, defines a "trade secret' as follows:

"'Trade secret' means information, including a formula, pattern, compilation,.

program device, method, technique, or process, that:

(1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and

(2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."

d. The Proprietary Information contained therein are not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Proprietary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information. As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietary Information is highly valuable to EPRI.

e. A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRI's competitive position and the ability of EPRI to license the Proprietary Information both domestically and internationally. The Proprietary Information can only be acquired and/or duplicated by others using an equivalent investment of time and effort.

, have read the foregoing and the matters stated herein are true and correct to the best of my knowledge, information and belief. I make this affidavit under penalty of perjury under the laws of the United States of America and under the laws of the State of California.

Executed at 1300 W WT Harris Blvd being the premises and place of business of Electric Power Research Institute, Inc.

Date: cZL -/ -o//

David J. Modeen (State of North Carolina)

(County of Mecklenburg)

Subscribed and sworn to (or affirmed) before me on this day of Aug +/-..., 201/, by mr

- a- L); . T,. A ee-,j , proved to me on the basis of safsfactory evidence to be the person(s) who appeared before me.

Signature (Seal)

My Commission Expires, ay of ,,i_,A*L. 20__'