Text

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)
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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

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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)

Controlled*

Document Name Document Doc Ref Type**

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. If marked 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)

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

PLEX, RATE Structural Code(s) (See MT Form 3805):

Does the Calculatio EZ YES

[K No `

n:"

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.

Affect piping or supports? (If Yes, Attach MT Form 3544.)

Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation.)

[] YES El YES No No Record Retention: Retain this form with the associated calculation for the life of the plant.

Structural Integrity Associates, 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 Affected Project Manager Preparer(s) &

Revision Pages 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 IN TRO D U CTIO N..................................................................................................

4 2.0 METHODOLOGY..................................................................................................

4 3.0 ASSUMPTIONS / DESIGN INPUTS.....................................................................

9 4.0 CA LCU LA 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 R E FE R E N C E S........................................................................................................................

14 APPENDIX A P-T CURVE INPUT LISTING....................................................................

A-I APPENDIX B BOUNDING BELTL1NE SUPPORTING ANALYSIS......................... B-i File No.: 1000847.303 Revision: 1 Page 2 of 29 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: M NGP, 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........

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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:

K1c = 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:

FKi

-Kit K p-SF (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:

Kit =O0.953 x10-'.CR.t 2.5 (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 ++/--.0.537C i, + 2 0482 t +

.03 C3tj (4) where:

a t

CotClt C2t, C3t

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

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

= thermal stress polynomial coefficients, obtained from a curve-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 + C1

x + C2.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:

File No.: 1000847.303 Page 6 of 29 Revision: 1 F0306-OIRII

Structural Integrity Associates, Inc.2aa 4a'o33p gp lpp

=

[0.706COp +

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

.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 0F, 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 0F.

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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, 156.00F 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 00F 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/cm2. 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 3rd 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 (K1t) 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 Structural Integrity 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 Revision: 1 Page 13 of 29 F0306-O1RII

V Structural Integrity Associates, 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

V Structural Integrity Associates, Inc.

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 A_

psln) 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 Revision: 1 Page 15 of 29 F0306-OIRIl

Structural Integrity Associates, Inc.

Table 3: MNGP Beltline Region, Curve A, for 36 EFPY P-T Curve Temperature 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 61.75 86.10 102.40 114.67 124.52 132.74 139.81 146.00 151.49 156.45 160.96 165.09 168.91 172.47 175.78 178.88 181.82 184.58 187.19 189.69 P-T Curve Pressure 0

50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 File No.: 1000847.303 Revision: 1 Page 16 of 29 F0306-OIRII

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Table 4: MNGP Beltline Region, Curve A, for 40 EFPY P-T Curve Tem perature 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 67.65 92.00 108.30 120.57 130.42 138.64 145.71 151.89 157.39 162.35 166.86 170.99 174.81 178.37 181.68 184.78 187.71 190.48 193.41 196.73 P-T Curve Pressure 0

50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 File No.: 1000847.303 Revision: 1 Page 17 of 29 F0306-01R1

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Table 5: MNGP Beltline Region, Curve A, for 54 EFPY P-T Curve Temperature 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 60.00 82.85 107.19 123.50 135.78 145.62 153.85 160.90 167.09 172.59 177.55 184.05 191.16 197.39 202.93 207.92 212.45 216.61 220.44 224.02 227.33 P-T Curve Pressure 0

50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 File No.: 1000847.303 Revision: 1 Page 18 of 29 F0306-OIRIl

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Table 6: MINGP Bottom Head Region, Curve A, for all EFPY Plant =

MNGP Component =

Bottom Head thickness, t =

Bottom Head Radius, R =

ART =

Kit =

Safety Factor =

Stress Concentration Factor =

Mm =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Bottom Head 5.938 103.1875,

26. 0 0.00 1.50 3.00

2.256 0o.0 758.00 27.4 S0.0 (penetrations portion) inches inches

'F======>

All EFPY (no thermal effects)

(bottom head penetrations)

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

Gauge Fluid Temperature (OF) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 KIc (ksi*inchl1 2) 74.13 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 Kim (ksi*inch 112 )

49.42 49.42 50.53 51.69 52.90 54.15 55.46 56.82 58.23 59.71 61.24 62.84 64.50 66.23 68.03 69.90 71.85 73.88 75.99 78.19 Temperature for P-T Curve (OF) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 Adjusted Pressure for P-T Curve (psig) 0 813 832 851 872 893 915 939 963 988 1,014 1,041 1,069 1,099 1,129 1,161 1,194 1,229 1,265 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 ART=

Vessel Radius, R =

Nozzle comer thickness, t' =

Kit=

Kip-applied =

Crack Depth, a =

Safety Factor =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Reference Pressure =

Unit Pressure =

Flange RTNDT =

Gauge Fluid Temperature

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 AlA JO

-All 0

-V 103 7.732 0.00

ýý69.10 11.933 1.50 0.0 758.00 27.4 0.0 1,000 1,563 10.0 inches inches, approximate (no thermal effects) ksi*inch 1 2 inches

'F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty) psig (pressure at which the FEA stress coefficients are valid) psig (hydrostatic pressure)

'F======>

All EFPY K1.

(ksi*inch 112 )

64.13 64.13 65.39 66.71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 Kip (ksi*inch11Z) 42.75 42.75 43.60 44.47 45.38 46.33 47.32 48.35 49.42 50.53 51.69 52.90 54.15 55.46 56.82 58.23 59.71 61.24 62.84 64.50 66.23 68.03 69.90 71.85 73.88 75.99 78.19 80.47 82.86 85.33 87.91 90.60 93.39 96.30 P-T Curve Temperature

(*F) 60 60 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 102 104 106 108 110 112 114 116 118 120 122 124 P-T Curve 10CFR5O Adjustments (psig) 0 313 313 616 629 643 657 672 688 704 721 738 756 775 795 815 837 859 882 906 931 957 984 1012 1042 1072 1104 1137 1172 1207 1245 1284 1324 1366 File No.: 1000847.303 Revision: 1 Page 20 of 29 F0306-0IRI

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Table 8: MNGP, Beltline Region, Curve B, for 54 EFPY P-T Curve Temperature 60.00 60.00 60.00 60.00 89.07 116.72 134.43 137.89 138.16 147.47 157.81 166.37 174.76 185.75 194.74 202.37 208.98 214.82 220.05 224.78 229.10 233.08 236.77 240.21 243.41 246.43 249.28 251.98 254.53 P-T Curve Pressure 0

50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 File No.: 1000847.303 Revision: 1 Page 21 of 29 F0306-OIRIl

V Structural Integrity Associates, Inc.

Table 9: MNGP, Bottom Head Region, Curve B, for all EFPY Plant =

Component =

Bottom Head thickness, t =

Bottom Head Radius, R =

ART=

Kit =

Safety Factor =

Stress Concentration Factor =

Mm =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Heat Up and Cool Down Rate Gauge Fluid Temperature

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 MNGP Bottom Head 5.938 103.1875 26.0 8.19 2.00 3.00 2.256 OQ.0 758.00 i 27.4 0.0 100 (ksi*inch112) 74.13 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 153.72 158.63 163.75 169.08 KIm (ksi*i nch"z) 32.97 32.97 33.81 34.67 35.58 36.52 37.50 38.52 39.58 40.69 41.84 43.03 44.28 45.58 46.93 48.33 49.79 51.31 52.90 54.55 56.26 58.05 59.91 61.84 63.85 65.95 68.13 70.40 72.76 75.22 77.78 80.45 (penetrations portion) inches inches 0F======>

All EFPY ksi*inch11 2

(bottom head penetrations)

F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full %Aessel at 70'F) psig (instrument uncertainty)

°F/Hr Temperature for P-T Curve

(*F) 60 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 Adjusted Pressure for P-T Curve (psig) 0 533 547 562 578 594 610 628 646 664 684 704 725 747 770 794 819 845 872 900 929 960 991 1,024 1,058 1,094 1,131 1,170 1,210 1,251 1,295 1,340 File No.: 1000847.303 Page 22 of 29 Revision: 1 F0306-01 RI.

V Structural Integrity Associates, Inc.

Table 10: MINGP, Upper Vessel Region, Curve B, for all EFPY Plant =

Component =

ART =

Vessel Radius, R =

Nozzle comer thickness, t =

Kit =

Klp~ppflid=

Crack Depth, a =

Safety Factor =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Reference Pressure =

Unit Pressure =

Flange RTNDT G..

N..P Upper Vessel

-2 40.0 103 7.732 7.06 69.10

,1.933 2.00 0.0.

768.010 27.4 0.0 1,000 1,563 10.0

'F======>

All EFPY inches inches, approximate ksi*inch.

2 ksi-inchl/2 inches

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty) psig (pressure at which the FEA stress coefficrents are valid) psig (hydrostatic pressure)

-F======>

All EFPY Gauge P-T P-T Fluid Curve Curve Temperature K.

Kip Temperature Pressure (IF)

(ksi'inch 112)

(ksi*inch 1 1.)

('F)

(psig) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140,0 142.0 64.13 64.13 65.39 66.71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 83.19 85.23 87.35 89.56 91.86 94.25 96.75 99.34 102.04 104.85 107.77 110.82 113.98 117.28 120.71 124.28 128.00 131.87 135.90 140.09 144.45 148.99 153.72 158.63 163.75 169.08 174.63 180.40 186.40 192.66 28.53 28.53 29.16 29.82 30.51 31.22 31.96 32.73 33.53 34.37 35.24 36.14 37.08 38.06 39.08 40.14 41.25 42.40 43.60 44.84 46.14 47.49 48.89 50.35 51.88 53.46 55.11 56.82 58.61 60.47 62.40 64.42 66.51 68.69 70.96 73.33 75.78 78.34 81.01 83.78 86.67 89.67 92.80 60 60 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 130 132 134 136 138 140 142 0

313 313 404 414 424 435 446 458 470 483 496 509 523 538 554 570 586 603 622 640 660 680 701 723 746 770 795 821 848 876 905 935 967 1000 1034 1069 1106 1145 1185 1227 1270 1315 File No.: 1000847.303 Revision: 1 Page 23 of 29 F0306-OIRIS

V Structural Integrity 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 Temperature 70.00 70.00 70.00 70.00 129.07 156.72 174.43 177.89 206.00 206.00 206.00 206.37 214.76 225.75 234.74 242.37 248.98 254.82 260.05 264.78 269.10 273.08 276.77 280.21 283.41 286.43 289.28 291.98 294.53 P-T Curve Pressure 0

50 100 150 200 250 300 312 313 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 File No.: 1000847.303 Revision: 1 Page 24 of 29 F0306-01RL

w a.

-JI LI-C0) 0 w

D 300 280 260 240 220 200 180 160 140 120 100 80 60 40 20 0

I I I I 11111 11 I111111 11I I II I II II I

I

[

l l

[

I OMPLIANCE REQU I RES OPERATION ABOVETHECURVES 00 Belfline Region Bolt-up Temp:

60'F

-Boftom Head

..... UpperVessel 0

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

Figure 1. MINGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 36 EFPY 1300 File No.: 1000847.303 Page 25 of 29 Revision: 1 F0306-OIRII

Lu o

Lu n-Lu I.

w w

n-I-0 Co Lu 300 280 260 240 220 200 180 160 140 120 100 80 60 40 20 0

COMPLIANCE REQU I RES OPERATION ABOVE THE CURVES

.0 0010,1

-YF i ti i -I-r 11 1 f tr r 1 1

_TFF Belfline Region Bolt-up Temp:

60*F Boftom Head UpperVessel 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 PRESSURE LIMIT IN REACTOR VESSEL (psig)

Figure 2: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 40 EFPY 1300 File No.: 1000847.303 Revision: 1 Page 26 of 29 F0306-OIRIl

Ll w

w w

Il I--

w

.-J UJ U) w 0I--

wD.l 300 280 260 240 220 200 180 160 140 120 100 80 60 40 20 0

COMPLIANCE REQUIRES OPERATION ABOVETHE CURVES I LA_

op

-- I I I Lto U

I LL 1 1 1 1 1 1 1 i l l 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1-Beitline Region Bolt-up Temp:li BllnRein--Bto Had-A~~

~ ~

60F-LLIBotto mHead I I I I I-1 1-I-UpperVessel II I~ l~ ll ll!

,R.

0 100 200 300 400 500 600 700 800 900 PRESSURE LIMIT IN REACTOR VESSEL (psig) 1000 1100 1200 1300 Figure 3: MNGP P-T Curve A (Hydrostatic Pressure and Leak Tests) for 54 EFPY File No.: 1000847.303 Revision: 1 Page 27 of 29 F0306-OIRI

300 280' 260 240

. 220 w

,a.

m 200 w

I-

,180 I-w, 160 w

140 w

120 100 w

n, 80 60 2

40 I I I 1 -1 1 1 IT177=

COMPLIANCEREQ UIRESO PERATION ABOVE THE CURV ES I

I I I H I

I I I J-ITIT I ru-j-11 J I

I..

I I.if I i i i i !

I i i i i i i i i I

i I I i i ! i i ! i I

11111 111111111111111 I.1I III!

111111 11111 liii III Ii 11111 I;:

I~lIII 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

I i I ~

i i

i i I

I

7.

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

1.-

Beltline Region

-Bottom Head Bolt-up Temp:'

..,UpperVessel 601tU 07 0° 20 0

0 100

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

.1100 1200 1300 Figure 4. MNGP P-T Curve B (Normal Operation - Core Not Critical) for 54 EFPY File No.: 1000847.303 Revision: 1 Page 28 of 29 F0306-01RL

300 1111 111111111 111171=11 11111 111 111111 1111 111111 11117711IT;M 280 260 240 uJ 220 LU 200 L-180

,-I 160 UJ 140 ILl Lu 120 o

100 C.)

80 UJ 60 D

40 20 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 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 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

!111111111111 HIIIIIIII COMPLIANCE REQUIRES OPERATION ABOVE THE CURVES 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 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 I I..

I ~~

............ i ! i i i I--

i ! i i i I

i I Minimum Criticality Temp:

70*F I IIL El I 0

0 100 200 300 400 500 600 700 800 900 1000 PRESSURE LIMIT IN REACTOR VESSEL TOP HEAD (psig) 1100 1200 1300 Figure 5. MNGP P-T Curve C (Normal Operation - Core Critical) for 54 EFPY File No.: 1000847.303 Revision: 1 Page 29 of 29 F0306-OIRI

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

36 EFPY Input Listing:

I i

P-TC*urve Inputs Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp Reactor Vessel Pressure 0 'F Assumed 0 psig Assumed Geometry Vessel Radius Vessel Shell thickness Bottom Head Thickness Bottom Head Radius Feedwater Nozzle Thickness Recirculation Inlet (N2) Nozzle Thickness ART/RTNDT 36 EFPY Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater) RTNDT Flange Region (Boltup) RTNDT Limiting Recirculation Inlet (N2) Nozzle Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)

Pressure (Curme A)

Lower Penetrations (SCF)

Limiting Recirculation Inlet (N2) Nozzle (SCF) 103 in.

5.63 in.

5.9375 in.

103.1875 in.

7.7317 in.

9.2884 in.

147.4 *F 26 *F 40 'F 10 'F 104.1 'F 2

1.5 3

[7]

[10]

[11]

[12]

[4]

[6]

[4]

[3]

Kit During Pressure Test (near isothermal conditions) 0 ksiqin

[3]

Water Density Pressure Full Water Elevation (pressure head)

Hydrostatic Test Pressure Static Head Pressure Adjustment 62.4 Ib/ft3 1250 psig 758 in 1563 psig 27.4 psig Assumed

[9]

Calculated Calculated

[3]

Assumed Assumed Temperature Rate of Temp Change Bolt Up Temperature Increment 60 *F 2 *F 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 Reactor Vessel Pressure 0 *F Assumed 0 psig Assumed Geometry Vessel Radius Vessel Shell thickness Bottom Head Thickness Bottom Head Radius Feedwater Nozzle Thickness Recirculation Inlet (N2) Nozzle Thickness ARTIRTNDT 40 EFPY Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater) RTNDT Flange Region (Boltup) RTNDT Limiting Recirculation Inlet (N2) Nozzle Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)

Pressure (Curve A)

Lower Penetrations (SCF)

Limiting Recirculation Inlet (N2) Nozzle (SCF) 103 in.

5.63 in.

5.9375 in.

103.1875 in.

7.7317 in.

9.2884 in.

156 *F 26 *F 40 'F 10 'F 110 'F 2

1.5 3

[7]

[10]

[11]

[12]

[4]

[6]

[4]

[3]

During Pressure Test (near isothermal conditions) 0 ksivin

[3]

Water Density Pressure Full Water Elevation (pressure head)

Hydrostatic Test Pressure Static Head Pressure Adjustment 62.4 lb/ft 3 1250 psig 758 in 1563 psig 27.4 psig Assumed

[9]

Calculated Calculated

[3]

Assumed Assumed Temperature Rate of Temp Change Bolt Up Temperature Increment 60 'F 2 *F Heat Up and Cool Down Rate 100 °F/hour

[11]

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

54 EFPY Input Listing:

>7

~P-T Clurve Inputs Instrument Uncertainty

Reference:

Reactor Vessel Metal Temp Reactor Vessel Pressure 0 'F Assumed 0 psig Assumed Geometry Vessel Radius Vessel Shell thickness Bottom Head Thickness Bottom Head Radius Feedwater Nozzle Thickness Recirculation Inlet (N2) Nozzle Thickness ART/RTNDT 54 EFPY Limiting Beltine Limiting Bottom Head Limiting Upper Vessel (Feedwater) RTNDT Flange Region (Boltup) RTNDT Limiting Recirculation Inlet (N2) Nozzle Safety Factor/Stress Concentration Factor Core Not Critical (Curve B) Core Critical (Curve C)

Pressure (Curve A)

Lower Penetrations (SCF)

Limiting Recirculation Inlet (N2) Nozzle (SCF) 103 in.

5.63 in.

5.9375 in.

103.1875 in.

7.7317 in.

9.2884 in.

186.6 'F 26 'F 40 °F 10 oF 125.2 'F 2

1.5 3

[7]

[10]

[11]

[12]

[4]

[6]

[4]

[3]

During Pressure Test (near isothermal conditions) 0 ksivin

[3]

Water Density Pressure Full Water Elevation (pressure head)

Hydrostatic Test Pressure Static Head Pressure Adjustment 62.4 lb/ft3 1250 psig 758 in 1563 psig 27.4 psig Assumed

[9]

Calculated Calculated

[3]

Assumed Assumed Temperature Rate of Temp Change Bolt Up Temperature Increment 60 'F 2 'F Heat Up and Cool Down Rate 100 °F/hour

[11]

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

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

Table B-i: MNGP, Beltline Region, Curve A, for 36 EFPY Plant =

Component Vessel thickness, t Vessel Radius, R =

ART=

KIT =

Safety Factor Mm Temperature Adjustment Height of Water for a Full Vessel =

Pressure Adjustment Pressure Adjustment MNGP Beltline 5.,630 103 147.4 0.,00 1.50 2.197

-0.0 758.00 27.4 0.0 inches inches

F======>

36 EFPY (no thermal effects)

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70'F) psig (instrument uncertainty)

Gauge Fluid Temperature (7F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 Kic (ksi*inchl1 2) 36.81 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41.23 41.56 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 KIm (ksi*i nch 112) 24.54 24.54 24.64 24.74 24.85 24.96 25.07 25.19 25.32 25.45 25.58 25.72 25.87 26.02 26.18 26.35 26.52 26.70 26.88 27.08 27.28 27.49 27.71 27.94 28.17 28.42 28.68 28.94 29.22 29.51 29.81 30.12 Temperature for P-T Curve (OF) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 Adjusted Pressure for P-T Curve (psig) 0 583 586 588 591 594 596 599 602 606 609 613 616 620 624 628 632 637 641 646 651 657 662 668 673 680 686 693 700 707 714 722 File No.: 1000847.303 Revision: 1 Page B-2 of B-21 F0306-0IRI

Table B-1 Continued: MNGP, Beitline Region, Curve A, for 36 EFPY Gauge Fluid Temperature (OF) 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 K~c (ksi*inch112) 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 50.38 51.08 51.81 52.57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 Kim (ksi*inch112) 30.45 30.79 31.14 31.51 31.89 32.29 32.71 33.14 33.59 34.05 34.54 35.05 35.57 36.12 36.69 37.29 37.91.

38.55 39.22 39.92 40.64 41.40 42.18 43.00 43.85 44.74 45.66 46.62 47.62 48.66 49.75 50.87 52.05 53.27 54.54 Temperature for P-T Curve

(*F) 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 Adjusted Pressure for P-T Curve (psig) 730 739 747 757 766 776 786 797 808 820 832 845 858 871 885 900 916 932 948 966 984 1,003 1,022 1,042 1,064 1,086 1,109 1,133 1,157 1,183 1,210 1,238 1,267 1,298 1,329 File No.: 1000847.303 Revision: 1 Page B-3 of B-21 F0306-01R I

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

Component =

ART =

Vessel Radius, R =

Nozzle comer thickness, t =

Kit =

Kip-applied =

Crack Depth, a =

Safety factor =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Reference Pressure =

Unit Pressure =

MNGP Limiting Recirculation Inlet (N2) 104.10 103;00 9.29 0.00 74.36 2.32 1.50 758.00 27.37 0.00 1,000 1,563 oF======>

36 EFPY inches inches, approximate ksi*inchl1 2

ksi*inch1/

2 inches

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70*F) psig (instrument uncertainty) psig (pressure at which FEA stress coefficients are valid) psig (hydrostatic pressure)

Gauge Fluid Temperature (OF) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 K.c (ksi*inch112 )

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

Table B-2 Continued: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve A, for 36 EFPY Gauge Fluid Temperature

(*F) 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 K~c (ksi*inchll 2) 57.48 58.47 59.51 60.58 61.70 62.86 64.07 65.33 66.64 68.01 69.43 70.90 72.44 74.04 75.71 77.45 79.25 81.13 83.09 85.12 87.24 89.45 91.74 94.13 96.62 99.21 101.90 104.71 107.62 110.66 113.82 117.11 120.54 124.10 127.81 131.67 135.69 139.87 144.23 148.76 KNP (ksi*inch112) 38.32 38.98 39.67 40.39 41.13 41.91 42.71 43.55 44.43 45.34 46.28 47.27 48.30 49.36 50.47 51.63 52.83 54.09 55.39 56.75 58.16 59.63 61.16 62.76 64.41 66.14 67.93 69.80 71.75 73.77 75.88 78.08 80.36 82.73 85.21 87.78 90.46 93.25 96.15 99.17 Temperature for P-T C urve

(*F) 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 Adjusted Pressure for P-T Curve (psig) 488 497 506 516 526 536 547 558 570 582 595 608 622 636 651 667 683 700 718 736 755 775 795 817 839 862 886 911 938 965 993 1,023 1,053 1,085 1,119 1,153 1,189 1,227 1,266 1,306 File No.: 1000847.303 Revision: I Page B-5 of B-21 F0306-OIRI

Table B-3: MNGP, Beltline Region, Curve A, for 40 EFPY Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ART =

KIT =

Safety Factor =

Mm Temperature Adjustment Height of Water for a Full Vessel Pressure Adjustment =1 Pressure Adjustment Gauge Fluid Temperature

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 MNGP

.Beltline 5.630 103 0.00 1.50<

2.197 0.0 758.00 27.4 0.0 (ksi*inch112) 36.24 36.24 36.36 36.49 36.63 36.77 36.91 37.06 37.22 37.39 37.56 37.73 37.92 38.11 38.31 38.52 38.74 38.96 39.20 39.44 39.70 39.97 40.24 40.53 40.83 41.14 41.46 41.80 42.15 42.52 42.90 43.29 inches inches

°F======>

(no thermal effects)

F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

Kim (ksi*inch 12) 24.16 24.16 24.24 24.33 24.42 24.51 24.61 24.71 24.81 24.92 25.04 25.16 25.28 25.41 25.54 25.68 25.83 25.98 26.13 26.30 26.47 26.64 26.83 27.02 27.22 27.43 27.64 27.87 28.10 28.34 28.60 28.86 40 EFPY Temperature for P-T Curve (OF) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 Adjusted Pressure for P-T Curve (psig) 0 574 576 578 580 582 585 587 590 593 596 598 602 605 608 612 615 619 623 627 631 635 640 645 650 655 660 666 672 678 684 691 File No.: 1000847.303 Revision: 1 Page B-6 of B-21 F0306-O1RI

Table B-3 Continued: MNGP, Beltline Region, Curve A, for 40 EFPY Gauge Fluid Temperature

(*F) 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 Kic (ksi*i nch 112) 43.70 44.13 44.58 45.04 45.53 46.03 46.55 47.10 47.67 48.26 48.87 49.51 50.18 50.87 51.59 52.34 53.12 53.93 54.78 55.66 56.58 57.53 58.52 59.56 60.63 61.75 62.92 64.13 65.39 66.71 68.08 69.50 70.98 72.52 74.13 75.80 77.54 79.34 81.23 Kim (ksi*inchll2 )

29.14 29.42 29.72 30.03 30.35 30.69 31.04 31.40 31.78 32.17 32.58 33.01 33.45 33.91 34.39 34.89 35.41 35.96 36.52 37.11 37.72 38.35 39.02 39.71 40.42 41.17 41.95 42.75 43.60 44.47 45.38 46.33 47.32 48.35 49.42 50.53 51.69 52.90 54.15 Temperature for P-T Curve

(*F) 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 Adjusted Pressure for P-T Curve (psig) 697 705 712 720 728 736 745 754 763 773 783 794 805 816 828 841 854 867 881 896 911 927 943 960 978 997 1,016 1,036 1,057 1,079 1,102 1,125 1,150 1,175 1,202 1,230 1,259 1,289 1,320 File No.: 1000847.303 Revision: 1 Page B-7 of B-21 F0306-OIRI

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

Component =

ART =

Vessel Radius, R =

Nozzle comer thickness, t =

KIt =

Kip-applied =

Crack Depth, a =

Safety factor =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Reference Pressure =

Unit Pressure =

Limiting' Recirculation Inlet (N2) 110.00 103.00 9.29

,74.36 2.32-1.50 0.00 758.00 27.37 0.00, 1,000 1,563

'F======>

40 EFPY inches inches, approximate ksi*inchl1 2

ksi*inch1/

2 inches

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70'F) psig (instrument uncertainty) psig (pressure at which FEA stress coefficients are valid) psig (hydrostatic pressure)

Gauge Fluid Temperature

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 KIc (ksi*inchl1 2) 40.83 40.83 41.14 41.46 41.80 42.15 42.52 42.90 43.29 43.70 44.13 44.58 45.04 45.53 46.03 46.55 47.10 47.67 48.26 48.87 49.51 50.18 50.87 51.59 52.34 53.12 53.93 Kip (ksi*inch112) 27.22 27.22 27.43 27.64 27.87 28.10 28.34 28.60 28.86 29.14 29.42 29.72 30.03 30.35 30.69 31.04 31.40 31.78 32.17 32.58 33.01 33.45 33.91 34.39 34.89 35.41 35.96 Temperature for P-T C urve

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 Adjusted Pressure for P-T Curve (psig) 0 339 341 344 347 351 354 357 361 364 368 372 376 381 385 390 395 400 405 411 417 422 429 435 442 449 456 File No.: 1000847.303 Revision: 1 Page B-8 of B-21 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 =

Vessel thickness, t =

Vessel Radius, R =

ART =

KIT =

Safety Factor =

Mm =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Gauge Fluid Temperature

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 Beli ne 5.630 103 S186.5 0.00 1.50, 2.197 0.0 758.00 27.4 0.0 KIC (ksi*inchl12 )

34.85 34.85 34.92 34.99 35.06 35.13 35.21 35.30 35.38 35.47 35.56 35.66 35.76 35.86 35.97 36.09 36.20 36.33 36.45 36.59 36.72 36.87 37.02 37.17 37.34 37.50 37.68 37.86 38.05 38.25 38.46 38.67 38.90 39.13 39.37 39.62 39.88 0F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

Kim (ksi*inch112) 23.23 23.23 23.28 23.32 23.37 23.42 23.48 23.53 23.59 23.65 23.71 23.77 23.84 23.91 23.98 24.06 24.14 24.22 24.30 24.39 24.48 24.58 24.68 24.78 24.89 25.00 25.12 25.24 25.37 25.50 25.64 25.78 25.93 26.09 26.25 26.41 26.59 inches inches F.....

=>

654 EFPY (no thermal effects)

Temperature for P-T Curve

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 Adjusted Pressure for P-T Curve (psig) 0 551 552 553 554 555 557 558 559 561 562 564 566 567 569 571 573 575 577 579 582 584 587 589 592 595 598 601 604 607 610 614 618 622 626 630 634 File No.: 1000847.303 Revision: 1 Page B-10 of B-21 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 =

Component =

ART =

Vessel Radius, R =

Nozzle comer thickness, t =

Kit =

Kip-applied =

Crack Depth, a =

Safety factor =

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Reference Pressure =

Unit Pressure MNGP Limiting Recirculation Inlet (N 125.20

, 103.00 929

,,r;!*0.00 174.36 2.32 1.50 0.00 758.00 27.37 0.00 1,000 1,L~~563 2) 0F======>

54 EFPY inches inches, approximate ksi*inchl1 2

ksi*inch1/

2 inches

°F (applied after bolt-up, instrument uncertainty) inches psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

.psig (pressure at which FEA stress coefficients are valid) psig (hydrostatic pressure)

Gauge Fluid Temperature (OF) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 K'c (ksi*inch 112) 38.83 38.83 39.06 39.30 39.55 39.80 40.07 40.35 40.65 40.95 41.27 41.60 41.94 42.30 42.67 43.05 43.46 43.87 44.31 44.76 45.23 45.73 46.24 46.77 47.32 47.90 48.50 49.12 49.77 50.45 51.15 51.89 (ksi*inchl1 2) 25.89 25.89 26.04 26.20 26.36 26.54 26.72 26.90 27.10 27.30 27.51 27.73 27.96 28.20 28.44 28.70 28.97 29.25 29.54 29.84 30.16 30.48 30.82 31.18 31.55 31.93 32.33 32.75 33.18 33.63 34.10 34.59 Temperature for P-T C urve

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 Adjusted Pressure for P-T Curve (psig) 0 321 323 325 327 330 332 334 337 340 343 346 349 352 355 359 362 366 370 374 378 383 387 392 397 402 407 413 419 425 431 438 File No.: 1000847.303 Revision: 1 Page B-12 of B-21 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 =

Component =

Vessel thickness, t =

Vessel Radius, R =

ART =

Kit =

Safety Factor =

Mm=

Temperature Adjustment Height of Water for a Full Vessel =

Pressure Adjustment =

Heat Up and Cool Down Rate =

Gauge Fluid Temperature

(°F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 MNGP Beltline 5.630 inches 103 inches 186.6

'F

======>

64 EFPY 7.17 ksi*inchl/

2 2.00 2.197 0.0

°F (applied after bolt-up, instrument uncertainty) 758.00 inches 27.4 psig (hydrostatic pressure head for a full vessel at 70°F) 0.0 psig (instrument uncertainty) 100

'°F/Hr KiC (ksi*inchl1 2) 34.85 34.85 34.92 34.99 35.06 35.13 35.21 35.30 35.38 35.47 35.56 35.66 35.76 35.86 35.97 36.09 36.20 36.33 36.45 36.59 36.72 36.87 37.02 37.17 37.34 37.50 37.68 37.86 38.05 38.25 38.46 38.67 38.90 39.13 39.37 39.62 39.88 40.16 40.44 40.74 41.04 41.36 KIm (ksi*inch1/2) 13.84 13.84 13.87 13.91 13.95 13.98 14.02 14.06 14.11 14.15 14.20 14.25 14.30 14.35 14.40 14.46 14.52 14.58 14.64 14.71 14.78 14.85 14.93 15.00 15.08 15.17 15.26 15.35 15.44 15.54 15.65 15.75 15.86 15.98 16.10 16.23 16.36 16.49 16.64 16.78 16.94 17.10 Temperature for P-T Curve

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 132.0 134.0 136.0 138.0 140.0 Adjusted Pressure for P-T Curve (psig) 0 317 318 319 320 321 321 323 324 325 326 327 328 330 331 332 334 335 337 339 340 342 344 346 348 350 352 354 357 359 362 365 367 370 373 376 380 383 387 390 394 398 File No.: 1000847.303 Revision: 1 Page B-14 of B-21 F0306-O0RI

Table B-7: Continued: MNGP, Beltline Region, Curve B, for 54 EFPY Gauge Fluid Temperature

(*F) 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 214.0 216.0 218.0 220.0 222.0 224.0 226.0 228.0 230.0 232.0 234.0 236.0 238.0 240.0 242.0 244.0 246.0 248.0 250.0 252.0 254.0 256.0 Kic (ksi*inch 1 2) 41.70 42.04 42.41 42.78 43.17 43.58 44.00 44.44 44.90 45.38 45.88 46.39 46.93 47.49 48.08 48.68 49.32 49.97 50.66 51.37 52.11 52.88 53.69 54.52 55.39 56.30 57.24 58.22 59.24 60.31 61.41 62.56 63.76 65.01 66.31 67.66 69.07 70.53 72.05 73.64 75.29 77.01 78.79 80.65 82.59 84.61 86.70 88.89 91.16 93.53 95.99 98.55 101.22 103.99 106.88 109.89 113.02 116.28 K.m (ksi*inch 1 2) 17.27 17.44 17.62 17.81 18.00 18.21 18.42 18.64 18.87 19.11 19.35 19.61 19.88 20.16 20.45 20.76 21.07 21.40 21.75 22.10 22.47 22.86 23.26 23.68 24.11 24.57 25.04 25.53 26.04 26.57 27.12 27.70 28.30 28.92 29.57 30.25 30.95 31.68 32.44 33.24 34.06 34.92 35.81 36.74 37.71 38.72 39.77 40.86 42.00 43.18 44.41 45.69 47.03 48.41 49.86 51.36 52.93 54.56 Temperature for P-T Curve

(*F) 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 164.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 214.0 216.0 218.0 220.0 222.0 224.0 226.0 228.0 230.0 232.0 234.0 236.0 238.0 240.0 242.0 244.0 246.0 248.0 250.0 252.0 254.0 256.0 Adjusted Pressure for P-T Curve (psig) 402 406 411 416 420 426 431 436 442 448 454 461 467 474 481 489 497 505 514 522 532 541 551 562 572 584 595 608 620 634 647 662 677 692 708 725 743 761 780 799 820 641 864 887 911 936 962 989 1,017 1,047 1,077 1,109 1,142 1,177 1,213 1,250 1,289 1,330 File No.: 1000847.303 Revision: 1 Page 13-15 of B-21 F0306-OIRI

Table B-8: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve B, for 54 EFPY Plant =

Component =

ART =

Vessel Radius, R =

Nozzle corner thickness, t =

Kit Kip.applied Crack Depth, a =

Safety factor Temperature Adjustment Height of Water for a Full Vessel =

Pressure Adjustment -

Pressure Adjustment Reference Pressure =

Unit Pressure Gauge Fluid Temperature

('F) 60.0 60.0 62.0 64.0 66.0 68,0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102.0 104.0 106.0 108.0 110.0 112.0, 114.0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 MNGP Limiting Recirculation Inlet (N2) Nozzle 125.20

'F=====>

54 EFPY 1t03.00" inches 9.29 inches, approximate 9.45 ksi*inch"' 2 74.36 ksi*inchl1 2

2.32 inches 2.00 0.00

F (applied after bolt-up, instrument uncertainty) 758.00 rinches y 27.37 L psig (hydrostatic pressure head for a full \\essel at 70*F) 0.00.

psig (instrument uncertainty) 1,000 psig (pressure at which FEA stress coefficients are valid) 1,563 psig (hydrostatic pressure)

Kic (ksi*inch112) 38.83 38.83 39.06 39.30 39.55 39,80 40.07 40.35 40.65 40.95 41.27 41.60 41.94 42.30 42.67 43.05 43.46 43.87 44.31 44.76 45.23 45.73 46.24 46.77 47.32 47.90 48.50 49.12 49.77 50.45 51.15 51.89 52.65 53.44 54.27 55.13 56.02 (ksi*inch 1 2) 14.69 14.69 14.80 14.92 15.05 15.18 15.31 15.45 15.60 15.75 15.91 16.07 16.24 16.42 16.61 16.80 17.00 17.21 17.43 17.65 17.89 18.14 18.39 18.66 18.93 19.22 19.52 19.83 20.16 20.50 20.85 21.22 21.60 21.99 22.41 22.84 23.28 Temperature for P-T Curve

(*F) 60.0 60.0 62.0 64.0 66.0 68.0 70.0 72.0 74.0 76.0 78.0 80.0 82.0 84.0 86.0 88.0 90.0 92.0 94.0 96.0 98.0 100.0 102,0 104.0 106.0 108.0 110.0 112,0 114,0 116.0 118.0 120.0 122.0 124.0 126.0 128.0 130.0 Adjusted Pressure for P-T Curve (psig) 0 170 172 173 175 177 179 180 182 184 187 189 191 193 196 199 201 204 207 210 213 217 220 224 227 231 235 239 244 248 253 258 263 268 274 280 286 n

1~

rn ni rage u-ID ci fl-LI File No.: 1000847.303 Revision: 1 Page B-I6 OI B-2l F0306-ORI

Table B-8 Cont: MNGP, Recirculation Inlet (N2) Nozzle Beltline Region, Curve B, for 54 EFPY Gauge Fluid Temperature (oF) 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 214.0 216.0 218.0 220.0 222.0 224.0 226.0 228.0 230.0 232.0 K.c (ksi*inch112 )

56.95 57.92 58.93 59.98 61.08 62.21 63.40 64.63 65.91 67.25 68.64 70.08 71.59 73.16 74.79 76.48 78.25 80.09 82.00 83.99 86.07 88.22 90.47 92.81 95.24 97.77 100.41 103.15 106.00 108.98 112.07 115.29 118.64 122.12 125.75 129.53 133.46 137.55 141.81 146.24 150.86 155.66 160.66 165.86 171.27 176.91 182.77 188.88 195.23 201.84 208.72 Kip (ksi*inchlI2 )

23.75 24.23 24.74 25.26 25.81 26.38 26.97 27.59 28.23 28.90 29.59 30.31 31.07 31.85 32.67 33.51 34.40 35.32 36.27 37.27 38.31 39.38 40.51 41.68 42.89 44.16 45.48 46.85 48.27 49.76 51.31 52.92 54.59 56.33 58.15 60.04 62.00 64.05 66.18 68.39 70.70 73.10 75.60 78.20 80.91 83.73 86.66 89.71 92.89 96.19 99.63 Temperature for P-T Curve (CF) 132.0 134.0 136.0 138.0 140.0 142.0 144.0 146.0 148.0 150.0 152.0 154.0 156.0 158.0 160.0 162.0 164.0 166.0 168.0 170.0 172.0 174.0 176.0 178.0 180.0 182.0 184.0 186.0 188.0 190.0 192.0 194.0 196.0 198.0 200.0 202.0 204.0 206.0 208.0 210.0 212.0 214.0 216.0 218.0 220.0 222.0 224.0 226.0 228.0 230.0 232.0 Adjusted Pressure for P-T Curve (psig) 292 299 305 312 320 327 335 344 352 361 371 380 390 401 412 423 435 448 460 474 488 502 517 533 549 567 584 603 622 642 663 684 707 730 755 780 806 834 863 892 923 956 989 1,024 1,061 1,099 1,138 1,179 1,222 1,266 1,313 File No.: 1000847.303 Revision: 1 Page B-17 of B-21 F0306-O1Rl

V Structural Integrity Associates, Inc.

MNGP Pressure Test (Curve A), 36 EFPY 300 280 260 U-LU 240 220

a.

200 LU I-180

-J 160 uJ 140 cr)

(/)

120 o

100 Lu 80 60 40 20 0

I I I I I I I I I I I I I I II F F I I I IIit 1 1i COMPLIANCE REO.U IRES OPERATION ABOVE THE CU RVES I

J io i i 0 i I00

'000,

.10 0

ti 60

.F --- tm~a J J~ l Upper Vessel

.EE H

..1

,1.

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 Structural Integrity Associates, 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

10 I

0 LU 80 60 Beltline Reg ion

=* 40 Bt-pTm:===Beltline N2 Nozzle j

40 Bolt-up Temp.

Z 60'F Bottom Head I0 IIIIII Upper Vessel I I I I I I In l ll l I

=

. I ---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

Structural Integrity Associates, Inc.

MNGP Pressure Test (Curve A), 54 EFPY 300 I

I I I

1 II I

II liii 1111 111111 II 1111111111111 liii IIIIIIIIIII IIIIIIIIIII 111111111 II I III II W

U-w w

a-wI-

-1 I-w

--Jw CO) 0l)w 0I-wU 280 260 240 220 200 180 160 140 120 100 80 g

I l

I II COMPLIANCE REQUIRES OPERATION ABOVETHE CURVES I i i 1 i 1 i i i I I I I 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1...... 1 1 11 1 1 I IIIB I

~

I l1 1 1 1 11 1 1 11 1111111111 1IIý r m I I iI II L... t I7 11111111111

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

I 11 11 11 1 111111 II1ý?J i

I.1 IIIIl 1 1 1 1 1111111111 III1I1iM 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 60 40 20 0

-Belt]in e Region Bolt-up Temp:

p:

Beltline N2 Nozzle 60'F Bottom Head Upper Vessel 0

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

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

V Structural Integrity Associates, Inc.

MNGP Normal Operation - Core Not Critical (Curve B), 54 EFPY 300 280 260 uJ 240 220 wa. 200 w

180 m 160 140 Cn C,,

Lu 120 0

100 w

80 60 I

40 20 0

il--

-B toIa

-pp er-esse i.000001 II

/

I...

i i g

.. ""1" Bol-u Tem r

-I omH a 6 0 'F U p p e r V e s s e l 0

100 200 300 400 500 600 700 800 900 1000 1100 1200 PRESSURE LIMIT IN REACTOR VESSEL TOP HEAD (psig) 1300 File No.: 1000847.303 Revision: 1 Page B-21 of B-21 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, i.

iwnriting; 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 a lsubstantial 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.

!Stru cturai 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 0n1 this 19Lh day of August, 2011.

Mar/os Legsie ra P'.

gaspi I-lerrera, PRE.

Vice President Nuclear Plant Services State of California Coun-Ity of, ksCA?

ýa-Subscribed'aild sworn. to (o-affirmed) before me, 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 Strutura in teg'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 [ý have 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, in writing, 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

- a-L) ;.

T,.

mr 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__'

ML12033A181

Text

Title:

1.0 INTRODUCTION

5.0 CONCLUSION

Reference:

Reference:

Reference:

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