ML15322A092

Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPY

ML15322A092
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Site:	Hatch
Issue date:	09/10/2014
From:	Sommerville D V Structural Integrity Associates
To:	Office of Nuclear Reactor Regulation
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ML15322A088	List: ML15322A089 ML15322A090 ML15322A091 ML15322A092 NL-15-2034, Calculation No. 1001527.303, Revision 0, Feedwater, Water Level Instrument, and Core Dp Nozzle Fracture Mechanics Evaluation for Hatch, Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development NL-15-2034, Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPY NL-15-2034, Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY NL-15-2034, E.I. Hatch, Units 1 and 2 - Enclosure 4, Non-Proprietary Version of the Epri/Bwrvip Information Requested in RAI 1 NL-15-2034, E.I. Hatch, Units 1 and 2 - Response to Request for Additional Information Regarding Application for Amendment to Technical Specifications for Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Repo
References
NL-15-2034 1001527.304, Rev. 2
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S ' Structural Integrity Associates, IncY File No.: 1001527.304 li No.: 1400365CALCULATION PACKAGE Quality Program:

[] Nuclear [] Commercial PROJECT NAME:Plant Hatch Unit 1 &2 P-T Curve Evaluation CONTRACT NO.:P0: SNC19354-0010, Rev. 1 CONTRACT:

19354, Rev. 4CALCULATION TITLE:Hatch Unit 1 P-T Curve Calculation for 38 and 49.3 EFPYDocument Affected Project Manager Preparer(s)

& Checker(s)

Revision Description ApprovalSintrs&De Revision Pages __________

Signature

& DateSintrs&De 0 1 -45 Initial Issue Responsible EngineerA-i -A-3 R. GnagneB-i -B-43 D. V. Sommerville 12/30/2011 12/30/2011 Responsible VerifierG. Licina12/30/2011 D. V. Sommerville 12/30/2011 117 Citations for References Responsible Engineer[1] and [2] have beenupdated to show citation D.V. Sommerville M. Qinfor NRC approved 9/19/2013 9/19/2013 versions.

Citation forReference

[10] has been Responsible verifierupdated to show currentrevision.

Reference

[10] D. V. Sommerville was revised for the same 9/19/2013 reason as identified abovefor References

[1] and[2]. No technical changes are made for thisrevision.

Page 1 of 46F0306-01IRI V' Structural Integrity Associates,/Inc.Y File No.: 1001527.304Project No.: 1001527CALCULATION PACKAGE Quality Program:

[] Nuclear LI] Commercial CALCULATION TITLE:Hatch Unit 1 P-T Curve Calculation for 38 and 49.3 EFPYDocument Affected Project Manager Peae~)&Cekrs Reiin PgsRevision Description Approval Prepaurers)

& C atekrsRevision__Pages

____________

Signature

& DateSintrs&De 2 6, 7, 9, 11 -34, Revised to incorporate Responsible Engineer37 -46 updated fluence data 7 '¢A-I -A-3 to address NRC condition B-1 -B-43 for SIR-05-044-Rev.

1-Aregarding lowest service D. V. Sommerville temperature.

9/10/2014 D. V. Sommerville forC. J. Oberembt9/10/2014 Responsible VerifierD. V. Sommerville 9/10/20 14Page 2 of 46F0306-O1R 1

VStructural Integrity Associates, IncYTable of Contents

1.0 INTRODUCTION

...........................................................................

62.0 METHODOLOGY

..........................................................................

63.0 ASSUMPTIONS...........................................................................

124.0 DESIGN INPUTS.......................14 5.0 CALCULATIONS

.........................

.................................

i.............

155.1 Pressure Test (Curve A)...........................................................

155.2 Normal Operation

-Core Not Critical (Curve B)...............................

165.3 Normal Operation

-Core Critical (Curve C)....................................

1

76.0 CONCLUSION

S............................................................................

1

77.0 REFERENCES

.............

...............................................................

18APPENDIX A : P -T CURVE INPUT LISTING ..............................................

A-iAPPENDIX B : SUPPORTING CALCULATIONS

..........................................

B-iFile No.: 1001527.304 Revision:

2Page 3 of 46F0306-01R1 Structural Integrity Associates, IncYList of TablesTable 1 : Summary of Minimum Temperature Requirements for P-T Limit Curves...................

11Table 2: HNP-1 Beitline Region, Curve A, for 38 EFPY ...............................................

19Table 3: HNP-1 Beitline Region, Curve A, for 49.3 EFPY .............................................

20Table 4: HNP-1 Bottom Head Region, Curve A, for All EFPY ........................................

21Table 5: HNP-1 Non-Beltline Region, Curve A, for All EFPY... .....................................

21Table 6: HNP-1, Beltline Region, Curve B, for 38 EFPY and 100°F/hr Thermal Transient

.........

22Table 7: HNP-1, Beltline Region, Curve B; for 49.3 EFPY and 100°F/hr Thermal Transient

.......23Table 8: HNP-1, Beitline Region, Curve B, for 38 EFPY and 200°F/hr Thermal Transient

.........

24Table 9: HNP-1, Beitline Region, Curve B, for 49.3 EFPY and 200°F/hr Thermal Transient

......25Table 10: HNP-1 Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient...

26Table 11: HNP-1 Bottom Head Region, Curve B for All EFPY and 200°F/hr Thermal Transient...

27Table 12: HNP-1 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient

.. 28Table 13: HNP- 1 Non-Beltline Region, Curve B, for All EFPY and 200°F/hr Thermal Transient

..29Table 14: HiNP-1, Beltline Region, Curve C, for 38 EFPY and 100°F/hr Thermal Transient.........

30Table 15: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 100°F/hr Thermal Transient

.....31Table 16: H-NP-1, Beltline Region, Curve C, for 38 EFPY and 200°F/hr Thermal Transient.......32 Table 17: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 200°F/hr Thermal Transient

.....33Table 18: HNP-1 Bottom Head Region, Curve C for All EFPY and 100°F/hr Thermal Transient...

34Table 19: HNP-1 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient...

35Table 20: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 100°F/hr Thermal Transient

.. 36Table 21: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient

.. 36File No.: 1001527.304 Page 4 of 46Revision:

2F0306-01R1 Structural Integrity Associates, Inc.eList of FiguresFigure 1: INP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPY.......................

37Figure 2: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 49.3 EFPY ...............

.....38Figure 3: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 1000F/hr....39 Figure 4: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 100°F/hr

.. 40Figure 5: TNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 2000F/hr....41 Figure 6: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 2000F/hr .. 42Figure 7: J-NP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 100OF/hr.........

43Figure 8: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and lOO°F/hr......44 Figure 9: HNP-1 P-T Curve C (Normal Operation

-. Core Critical),

38 EFPY and 200°F/hr.........

45Figure 10: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 200°F/hr.....46 File No.: 1001527.304 Revision:

2Page 5 of 46F0306-01R1 VStructural Integrity Associates,

1.0 INTRODUCTION

This calculation develops pressure-temperature (P-T) limit curves for the beltline, bottom head, and non-beitline regions of the Hatch Nuclear Plant, Unit 1 (HNP-1) reactor pressure vessel (RPV). The P-Tcurves are developed for 38 and 49.3 effective full power years (EFPY) of operation, and for 100OF/hrand 200°F/hr thermal transients.

The P-T curves are prepared using the methods documented in theBoiling Water Reactor Owner's Group (BWROG) Licensing Topical Reports (LTRs), "Pressure Temperature Limits Report Methodology for Boiling Water Reactors"

[ 1] and "Linear Elastic FractureMechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles forPressure-Temperature Curve Evaluations"

[2]. These LTRs satisfy the requirements of 1OCFR50Appendix G [3] and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel(B&PV) Code,Section XI, Non-mandatory Appendix G [4].2.0 METHODOLOGY A full set of P-T curves, applicable to the following plant conditions, are prepared:

1. Pressure Test (Curve A),2. Normal Operation

-Core Not Critical (Curve B), and3. Normal Operation

-Core Critical (Curve C).For each plant condition above, separate curves are provided for each of the following three regions ofthe RPV as well as a composite curve for the entire RPV:1. The beltline region,2. The bottom head region,3. The non-beltline region,4. Composite curve (bounding curve for all regions)In some cases, a region may contain more than one component which is considered for development ofthe associated P-T curve. For HINP-1, the curve for each vessel region identified above is composedfrom the bounding P-T limits determined for the following components:

1. Beltline:

a. Beltline shellb. Water level instrument (WLI) nozzle, N162. Non-beltline

a. Feedwater (FW) nozzleb. 10CFR50 Appendix G limits [3]3. Bottom Head:a. Bottom head penetrations (in-core monitor housings, control rod drive housings)

b. Core DP nozzleConsequently, separate curves are prepared for each component considered for each region then abounding curve is drawn from the individual curves.File No.: 1001527.304 Page 6 of 46Revision:

2F0306-01R1 Structural Integrity Associates,

/nc?Complete sets of P-T curves, as identified above, are provided for a 100 °F/hr and 200 °F/hr thermaltransient at 38 and 49.3 EFPY of operation.

The methodology for calculating P-T curves, described below, is taken from Reference

[1] unlessspecified otherwise.

Additional guidance regarding analysis of WLI nozzles is taken from Reference

[2].The P-T curves are calculated by means of an iterative procedure, in which the following steps areperformed:

Step 1: A fluid temperature, T, is assumed.

The P-T curves are calculated considering a postulated flaw with a 6:1 aspect ratio that extends '1/4 of the way through the vessel wall. The temperature at the postulated flaw tip is assumed equal to the coolant temperature.

Step 2: The static fracture toughness, K10, is computed using the following equation:

K1c 33.2 + 20.734 .e°°2(r-AT)

(1)Where: K10 = the lower bound static fracture toughness (ksi'lin).

T = the metal temperature at the tip of the postulated 1/4 through-wall flaw (0F).ART = the Adjusted Reference Temperature (ART) for the limitingmaterial in the RPV region under consideration

(°F).Step 3: The allowable stress intensity factor due to pressure, Kip, is calculated as:Kzp -(2)Where: K1ip the allowable stress intensity factor due to membrane(pressure) stress (ksi'Iin).

Ki0 the lower bound static fracture toughness calculated in Eq. (1)(ksi\Iin).

Kit the thermal stress intensity factor (ksi Win) from through wallthermal gradients.

SF =the ASME Code recommended safety factor, based on the reactorcondition.

For hydrostatic and leak test conditions (i.e., P-T CurveA), SF = 1.5. For normal operation, both core non-critical andcore critical (i.e., P-T Curves B and C), 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 rateof temperature change is 25°F/hr or less).File No.: 1001527.304 Page 7 of 46Revision:

2FO306-01R1 VStructural Integrity Associates, IncYFor Curve B and Curve C calculations, K1t is computed in different ways based on theevaluated region. For the beitline, with the exception of nozzles, and bottom head regions, Kitis determined using the following equation:

K1, =O0.953 x10-3**CR. t25 (3)Where: CR = the cooldown rate of the vessel (°F/hr).t= the RPV wall thickness (in).For the FW nozzle, K1t is obtained from the stress distribution output of a plant specific finiteelement analyses (FEA). A polynomial curve-fit is determined for the through-wall stressdistribution at the bounding time point. The linear elastic fracture mechanics (LEFM) solutionfor K1t is:K1 ,no0.06C,0.57 2 c1 0.48 +2 0.33 ~31(4Where: a =/1/4 through-wall postulated flaw depth, a = 1/4 t (in).t = thickness of the cross-section through the nozzle at the limitingpath near the inner blend radius (in).Cot,Clt,

= thermal stress polynomial coefficients, obtained from a curve-Czt,C3t fit of the extracted stresses from a transient FEA.The thermal stress polynomial coefficients are based on the assumed polynomial formofo'(x) =Co +C1.x +C2* x2 + C3*. x3.In this equation, "x" represents the radial distance ininches from the inside surface to any point on the crack face.For the WLI nozzle, the nozzle assembly consists of an insert attached to the RPV with apartial penetration weld. The nozzle material is not ferritic and does not need to be specifically evaluated.

However, the effect of the penetration on the adjacent shell must be considered.

Reference

[2, Equation 8-2] provides the following simplified solution for the thermal stressintensity factor due to a 1 00°F/hr thermal ramp transient:

Ki1-ramp

= 874,

+t.)-]-20.715 (5)Where: Ki-ramp = the K1t (thermal stress intensity factor from through wall thermalgradients) for a WLI nozzle subjected to 1 00°F/hr thermal transient (ksi\/in).

ct = the instrument nozzle material coefficient of thermal expansion atthe highest thermal ramp temperature (in/in/°F).

tv = the vessel thickness (in).tn = the nozzle thickness (in).File No.: 1001527.304 Page 8 of 46Revision:

2F0306-01RI VStructural Integrity Associates, IncYLarger heat-up/cool-down rates are conservatively considered by scaling the stress intensity factor obtained using Eq. (5) by the ratio of the desired heat-up/cool-down rate to 100 °F/hr.Since the P-T curves are applicable to all Level A/B events, the bounding Level A/B events,for each region and component, identified from the vessel and nozzle thermal cycle diagrams[7], are considered when calculating the Kit above.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 asfollows:Pallow -M m .R (6)Where: Pailow = the allowable RPV internal pressure (psig).Kip = the allowable stress intensity factor due to membrane(pressure) stress, as defined in Eq. (2) t = the RPV wall thickness (in).Mm = the membrane correction factor for an inside surface axial flaw:Mm =1.85 for /t< 2Mm = 0.926 "It for 2 <.It < 3.464Mm =3.21 for "It >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.K .tPolw= (7)SCF. Mm

• R,Where: SCF = conservative stress concentration factor to account for bottomhead penetration discontinuities; SCF = 3.0 per Reference

[1].Paiiow, K1p, t, Mm and Ri are defined in Eq. (6).The bottom head region methodology for calculating the allowable pressure shown in Eq. (7)above is applied for the thicker shell portion of the HNP-1 bottom head. It is noted that theCore DP nozzle at HNP-1 penetrates a section of the bottom head in which the shell is 3 3/16"thick. Use of Eq. (7) to treat the effect of the penetration would be excessively conservative.

Preliminary calculations showed that this approach produced a bottom head curve whichbounded the entire vessel. Consequently, the effect of the Core DP nozzle penetration isconsidered in a manner similar to the FW nozzle, as described below.File No.: 1001527.304 Page 9 of 46Revision:

2F0306-01R1 Structural Integrity Associates, Inc.PFor the FW nozzle the allowable pressure is determined from a ratio of the allowable andapplied stress intensity factors.

The applied factor can be determined from a FEA thatdetermines the stresses due to the internal pressure on the nozzle and RPV. The methodology for this approach is as follows:p K1p "refaltlow, -(8)Where: Pref = RPV internal pressure at which the FEA stress coefficients (Eq.(9)) are determined (psi).KIp-app --the applied pressure stress intensity factor Pallow and K1p are defined as in Eq. (6)..The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from a FEA and the LEFMsolution given in Eq. (4):KIp.app=

-p 0.448/-i-12p

+ 0.393(- C~ 9Where: a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in).t = thickness of the cross-section through the limiting nozzle innerblend radius corner (in).C~,l,= pressure stress polynomial coefficients, obtained from a curve-C~,~ fit of the extracted stresses from a FEA.For the WLI nozzle, the nozzle .material is not ferritic and does not need to be specifically evaluated.

However, the effect of the penetration on the adjacent shell must be considered.

The allowable pressure is determined from the ratio of the allowable and applied stressintensity factors given in Equation

8. The applied stress intensity factor, for a 1000 psig loadcase, is calculated generically as follows [2, Equation 8-1]:KI Pressure

=2.9045IR tF.+ +/-t,, 1-4.434 (10)-L. ]"Where: KI-pressure

=generic Kip-app for the WLI nozzle (ksi'lin).

R = RPV nominal inside radius (in).tv and tn are described as in Eq. (5).The allowable pressure for the WLI nozzle is then calculated using Eq. (8), similar to the FWnozzle.File No.: 1001527.304 Page 10 of 46Revision:

2F0306-01IRI Structural Integrity Associates, Inc.*Step 5: Steps 1 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 1,300.psig. This value bounds expected pressures.

Step 6: Table 1 below summarizes the minimum temperature requirements contained in 10OCFR50, Appendix G [3, Table 1], which are applicable to the material highly stressed by the mainclosure flange bolt preload (non-beltline curve). SI also includes additional minimumtemperature requirements for bolt-up as shown in Table 1 below.Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves.Maximum of: ASME Appendix G [4]P<O P RTNDT,max, requirements A

• 60 0F [1],* TSDMP > 20% Ph RTNDT,max

+ 90 0FASEpeniG[4 requirements Maximum of: ASME Appendix G [4]*< %hRTNDT,max, requirements B

• 60 0F [1],* TSDM _______________

P> 20% Ph RTNDT, max + 120 0FASEpeniG[4 requirements Maximum of: ASME Appendix G [4]P<OhRTNDT, max + 60 0F, requirements

+ 40 °F* 60 0F [1],C

• TSDMMaximum of: ASME Appendix G [4]P > 20% Ph

• RTNDT, max + 160 0F, requirements

+ 40 0F* TISHT______________

___wnHere:t~h iS me pre-servlce nyUorotes

pressure, 1~on psigRTNBT,ma, is the maximum RTNoT of the vessel materials highly stressed by the bolt preload.TSDM is the temperature used in the shutdown margin evaluation Tlisfrr is the temperature at which the full in-service hydrotest pressure is allowed per Curve ANote that the minimum bolt-up temperature of 60°F, is used here, consistent with the positiongiven in Reference

[1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-uptemperature requirement; therefore, it is also included in Table 1 above. However, to address theNRC condition regarding lowest service temperature in Reference

[1 ], the minimum temperature is set to 76 0F, which is equal to the RTNDT, max + 60 0F. This value is consistent with theFile No.: 1001527.304 Revision:

2Page 11 of 46F0306-01IR1 V Structural Integrity Associates, Inc.'previous minimum temperature limits developed in [11], and is higher than the minimum bolt-uptemperature specified in [ 12].Step 7: Uncertainty in the RPV pressure and metal temperature measurements is incorporated byadjusting the P-T curve pressure and temperature using the following equations:

TpTr = T +UT (11)PP-r = -PH- UP (12)Where: Tp-T = The allowable coolant (metal) temperature (0F).UT = The coolant temperature instrument uncertainty (0F).PP-j = The allowable reactor pressure (psig).P11 = The pressure head to account for the water in the RPV (psig).Can be calculated from the following expression:

PIH= p"Ah.p = Water density at ambient temperature (lb/in3).Ah = Elevation of full height water level in RPV (in).Up = The pressure instrument uncertainty (psig).Steps 1 through 7, above, are implemented for all components, in all regions, for each heat-up/cool-down rate, and at all EFPY.3.0 " ASSUMPTIONS The 10OCFR5 0 Appendix G [3] and AsME Code [4] requirements and methods are considered to besupported in their respective technical basis documentation; therefore, the assumptions inherent in theASME B&PV Code methods utilized for this evaluation are not specifically identified and justified inthis calculation.

Only those assumptions specific to this calculation are identified and justified here.The following assumptions are used in preparation of the HNP- 1 P-T curves:.1. The bounding ART for the beltline materials is used in the calculation of the WLI nozzle curve.This assumption is conservative since the WLI nozzle is located near the upper limit of thebeltline region and the cumulative fluence at this location is substantially lower than for thebeitline location corresponding to the peak fluence.

Use of a fluence representative of thelocation in the beltline shell corresponding to the WLJ nozzle location would result in an ART,local to the WLI nozzle, which is lower than used in the present evaluation.

Since the fluence atthe WLI nozzle location is not specifically provided in the available fluence analysis

results, thepeak beltline value is used in this calculation.

Conservatism can be removed from the P-Tcurves by considering a WLI nozzle fluence in the ART calculation

[5], which would result in alower ART used in the WLI nozzle beltline curve.2. The full-vessel height is used in the calculation of the static head contributed by the coolant inthe RPV.This assumption is conservative in that the static head at the non-beltline regions is slightly lowerthan that of the bottom head curve; however, the difference in static head is small; therefore, theFile No.: 1001527.304 Page 12 of 46Revision:

2F0306-01RI Structural Integrity Associates, IncYadded complexity in considering different static head values for each region of the vessel is notconsidered beneficial.

3. The FW nozzle is the bounding non-beltline component of the RPV.This assumption is made because:a. The geometric discontinuity caused by the nozzle penetration in the RPV shell causes a stressconcentration which results in larger pressure induced stresses than would be calculated inthe shell regions of the RPV.b. The FW nozzle experiences more severe thermal transients than most of the other nozzlesbecause of the feedwater injection temperature which causes larger thermal stresses than areexperienced in the shell region of the RPV.c. Although some other nozzles can experience thermal transients, which Would cause thermalstresses larger than those calculated for the shell regions of the RPV, and some nozzles arelarger diameter than the FW nozzle, which could result in a slightly larger K1p, the combinedstresses from the applied thermal and pressure loads are considered to bound all other non-beltiline discontinuities.

4. Application of a SCF = 3.0 to the membrane pressure stress in the bottom head bounds the effectof the bottom head penetrations on the stress field in this region of the vessel.Bottom head penetrations will create geometric discontinuities into the bottom head hemisphere resulting in high localized stresses.

This effect must be considered in calculating the stressintensity factor from internal pressure.

Rather than performing a plant specific

analysis, SIapplies a conservative SCF for a circular hole in a flat plate subjected to a uniaxial load to themembrane stress in the shell caused by the internal pressure.

The assumption of SCF -- 3.0 isconservative because:a. It applies a peak SCF to the membrane stress which essentially, intensifies the stress throughthe entire shell thickness and along the entire crack face of the postulated flaw rather thanintensifying the stress local to the penetration and considering the stress attenuation awayfrom the penetration,

b. Review of SCFs for circular holes in plates subjected to an equi-bi-axial stress state as wellas SCFs for arrays of circular holes in shells, shows that the SCF is likely closer to 2-2.5rather than 3.0.Consequently, the method utilized by SI is expedient, as intended, and conservatively bounds theexpected effect of bottom head penetrations because a bounding SCF is used and applied as amembrane stress correction factor.5. ASME XI, Non-mandatory Appendix G, Paragraph G-22 14.3 [4] is used to calculate the thermalstress intensity factor for heat-up / cool-down rates greater than 100 °F/hr.The ASME Code [4] acknowledges that this methodology is conservative when applied to heat-up / cool-down rates greater than 100 0F/hr; therefore, the results obtained using this method forthe 200 0F/hr heat-up / cool-down rate are conservative.

Conservatism can be removed, ifFile No.: 1001527.304 Page 13 of 46Revision:

2F0306-01RI Structural

Integrit, Associates, Inc?necessary, by solving the thermo-elastic problem for the stresses in the vessel shell thencalculating the stress intensity factor using the plant specific stress distribution.

4.0DESIGN INPUTSThe design inputs, also included in Appendix A, used to develop the HNP-1 P-T curves are discussed below:1. Limiting RTNDT and ART [5]:Non-beltline:

Non-beltline:

Bottom Head:Beltline:

• 38 EFPY:49.3 EFPY:2. Shutdown Margin Temperature

[9]:3. RPV Dimensions*.[6]:

Full vessel height:RPV inside radius:RPV shell thickness:

Bottom head inside radius:Bottom head shell thickness:

4. Heat-up / Cool-down Rates [8]:5. Nozzle Stress Intensity Factors [1I0]:FW Nozzle:1 ksi Pressure:

100 °F/hr:200 °F/hr:450°F shock:WLI Nozzle:1 ksi Pressure:

100 °F/hr:200 °F/hr:40 *F (bounding value for non-belItline region, excluding bottom head)16 0F (bounding value for materials highly stressed by bolt preload)10 0F116.3 OF129.0 °F68 0F836.75 inches(Used to calculate maximum water head during pressure test andconservatively applied for normal operation as well)110.375 inches5.375 inches110.5 inches3.188 inches (in region with Core DP penetration) 6.813 inches (in region with CRD9 penetrations) 100 0F/hr200 0F/hr76.6 ksi-in°511.5 ksi-in°523.1 ksi-in°565.3 ksi-in°571.6 ksi-in0517.4 ksi-in0534.8 ksi-in05File No.: 1001527.304 Revision:

2Page 14 of 46F0306-01IRI Structural Integrity Associates, Inc.YCore DP Nozzle:1 ksi Pressure:

32.3 ksi-in°5100 °F/hr: 1.73 ksi-in°5200 °F/hr: 3.46 ksi-in°56. Design Pressure

[7]:, 1250 psig7. Pre-service Hydro-test pressure

[7]: 1563 psig(Taken as 1.25 *Design pressure

= 1563 psig)8. Instrument uncertainties

[8]:Pressure:

0 psigTemperature:

0*F5.0 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 Nuclear QA program.

Four cases areevaluated, corresponding to two EFPY values (38 and 49.3) and two cool-down rates (100 and 200°F/hr). P-T limits are calculated from 0 to 1300 psig. Supporting calculations for all curves areincluded in Appendix B.Because BWR operation is typically along the saturation curve, the limiting K1t for the FW nozzle isscaled to reflect the worst-case step change due to the available temperature difference between thesaturation temperature at a given pressure and the 100 0F feedwater temperature.

It is recognized that atlow temperatures, the available temperature difference is insignificant, which could result in a near zeroKit. Therefore, a minimum K1u is calculated for both the 1000F/hr and 2000F/hr cool-down rates; scalingof the non-beltline

/ feedwater nozzle Kit based on the available temperature difference is not allowedbelow the minimum Kit corresponding to the cool-down rate, being evaluated.

The composite P-T curves are extended below 0 psig to -14.7 psig based on the evaluation documented in Reference

[13], which demonstrates that the P-T curves are applicable to negative gauge pressures.

Since the P-T curve calculation methods used do not specifically apply to negative values of pressure, the tabulated results start at 0 psig. However, the minimum RPV pressure is -14.7 psig.5.1 Pressure Test (Curve A)The minimum bolt-up temperature of 760F minus instrument uncertainty (0°F) is applied to all regionsas the initial temperature in the iterative calculation process.

The static fracture toughness (Kit) iscalculated for all regions using Eq. (1). The resulting value of K1t, along with a safety factor ofl .5 isused in Eq. (2) to calculate the pressure stress intensity factor (K1p). The allowable RPV pressure iscalculated for the beltline, bottom head and Non-Beltline regions 'using Eq. (6, 7, and 8), as appropriate.

For the non-beltline region (feedwater nozzle / upper vessel),

the additional constraints specified in Step6 of Section 2.0 are applied.

Final P-T limits for temperature and pressure are obtained from Eq. (12and 13), respectively.

File No.: 1001527.304 Page 15 of 46Revision:

2F0306-01RI VStructural Integrity Associates, Inc.YSince the thermal stress intensity factor is taken as zero for Curve A, the cool-down rates do not affectthe results for Curve A.Values for the composite beltline region curves for 38 and 49.3 EFPY are listed in Table 2 and Table 3,respectively.

Additionally, more detailed data for the composite beltline are provided in Appendix B.Data for the composite bottom head region curve for all EFPY is listed in Table 4. Data for thecomposite non-beltline (feedwater nozzle / upper vessel) region curve, including the 10OCFR50Appendix G [4] limits, for all EFPY is listed in Table 5. The data for each region is graphed, and theresulting composite Curve A for 38 and 49.3 EFPY are provided in Figure 1 and Figure 2, respectively.

Additional data and curves for each region are included in Appendix B.5.2 Normal Operation

-Core Not Critical (Curve B)The minimum bolt-up temperature of 76°F minus coolant temperature instrument uncertainty (00F) isapplied to all regions as the initial temperature in the iterative calculation process.

The static fracturetoughness (Kic) is calculated for all regions using Eq. (1). The thermal stress intensity factor (K1t) iscalculated for the beltline plate and bottom head regions using Eq. (3), for the FW nozzle using Eq. (4),and for the WLI (N16) nozzle using Eq. (5).The resulting values of Kit and Kit, along with a safety factor of 2.0, are used in Eq. (2) to calculate thepressure stress intensity factor (K1p). The allowable RPV pressure is calculated for the beltline, bottomhead, and non-beltline regions using Eq. (6, 7, and 8), as appropriate.

For the non-beltline (FW nozzle /upper vessel) region, the additional constraints specified in Step 6 of Section 2.0 are applied.

Final P-Tlimits for temperature and pressure are obtained from Eq. (12 and 13), respectively.

The data resulting from each P-T curve calculation is tabulated.

Values for the composite beltlineregion with a 100°F/hr cool-down rate at 38 and 49.3 EFPY are listed in Table 6 and Table 7,respectively.

Values for the composite beltline region with a 200°F/hr cool-down rate at 38 and 49.3EFPY are listed in Table 8 and Table 9, respectively.

Data for the bottom head region with 1 00°F/hrand 200°F/hr cool-down rates are listed in Table 10 and Table 11, respectively.

Data for the FW nozzle/ upper vessel region with 100°F/hr and 200°F/hr cool-down rates are listed in Table 12 and Table 13,respectively.

The data for each region is graphed, and the resulting composite Curve B for 38 and 49.3EFPY with a 1O00F/hr cool-down rate are provided in Figure 3 and Figure 4, respectively.

The resulting composite Curve B for 38 and 49.3 EFPY with a 200°F/hr cool-down rate are provided in Figure 5 andFigure 6, respectively.

Additional data and curves for each region are included in Appendix B.File No.: 1001527.304 Page 16 of 46Revision:

2F0306-01R1 Structural.lIntegrity Associates, IncY5.3 Normal Operation

-Core Critical (Curve C)The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, withseveral exceptions.

The initial evaluation temperature is calculated as the limiting non-beltline RTNDTthat is highly stressed by the bolt preload (in this case, that of the closure flange region: 16 0F perSection 3.0) plus 60°F, resulting in a minimum critical temperature of 76 °F. When the pressureexceeds 20% of the system hydrostatic test pressure (20% of 1,563 psig =313 psig), the P-Tlimits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20%of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for thehydrostatic pressure test. The final Curve C values are taken as the absolute maximum between theregions of the beitline, the bottom head, and the non-beitline.

The data resulting from each P-T curve calculation is tabulated.

Values for the composite beltllneregion with a 100°F/hr cool-down rate at 38 and 49.3 EFPY are listed in Table 14 and Table 15,respectively.

Values for the composite beltline region with a 200°F/hr cool-down rate at 38 and 49.3EFPY are listed in Table 16 and Table 17, respectively.

Data for the bottom head region with 100°F/hrand 200°F/hr cool-down rates are listed in Table 18 and Table 19, respectively.

Data for the non-beltline (FW nozzle / upper vessel) region with 100°F/hr and 200°F/hr cool-down rates are listed inTable 20 and Table 21, respectively.

The data for each region is graphed, and the resulting composite Curve C for 38 and 49.3 EFPY with a 100°F/hr cool-down rate are provided in Figure 7 and Figure 8,respectively.

The resulting composite Curve C for 38 and 49.3 EFPY with a 200°F/hr cool-down rateare provided in Figure 9 and Figure 10, respectively.

Additional data and curves for each region areincluded in Appendix B.Note that the Beltline Region curves for the 200 0F/hr thermal transient at 38 and 49.3 EFPY shown inTables 16 and 17 and Figures 9 and 10 exhibit negative pressures at the lower end of the curve. This isnon-realistic and essentially indicates a higher minimum temperature for this region than for the otherregions of the RPV. Since these curves are not intended for normal operation and are intended only todisposition out-of-specification thermal transients these results do not pose any operational difficulties.

6.0 CONCLUSION

S P-T curves are developed for JINP-1 using the methodology, assumptions, and design inputs defined inSections 2.0, 3.0, and 4.0. P-T curves are developed for the beltline, bottom head, and non-beltline

regions, considering a 100 0F/hr and 200 *F/hr thermal transient at 38 and 49.3 EFPY, for the following plant conditions:

Pressure Test (Curve A), Normal Operation

-Core Not Critical (Curve B), and NormalOperation

-Core Critical (Curve C). Tabulated pressure and temperature values are provided for allregions and EFPYs in Tables 2 through 21. The accompanying P-T curve plots are provided in Figures1 through 10.File No.: 1001527.304 Page 17 of 46Revision:

2F0306-0 1RI VStructural Integrity Associates, Inc.Y

7.0 REFERENCES

1. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A, "Pressure-Temperature LimitsReport Methodology for Boiling Water Reactors,"

June 2013, SI File No. GE-10Q-401.

2. Structural Integrity Associates Report No. 0900876.40 1, Revision 0-A, "Linear Elastic FractureMechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzlesfor Pressure-Temperature Curve Evaluations,"

May 2013.3. 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. 2008).4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix G, "Fracture Toughness Criteria for Protection Against Failure,"

2001 Edition including the 2003 Addenda.5. Structural Integrity Associates Calculation No. 1001527.301, Rev 1, "Hatch Unit 1 RPV MaterialSummary and ART Calculation."

6. General Electric Drawing No. E-234-270, Revision 3, "General Arrangement Elevation for: 218"I.D. BWR," SI File No. 100 1527.208.

7. General Electric Drawing No. I135B9990, "Nozzle Thermal Cycles (Feedwater),"

SI File1001527.211.

8. Design Input Requests:

a. DIR, Revision 2, "Revised P-T Curves for Plant Hatch Units 1&2," SI File No.1001527.201.

b. DIR, Revision 0, "Hatch Units 1 and 2 P-T Curve Revisions,"

SI File No. 1400365.200.

9. General Electric Document No. GE-NE-BI1 10069 1-01R1, "Plant Hatch Unit 1 RPV Surveillance Materials Testing and Analysis,"

March 1997, 51 File No. 1001527.202.

10. Structural Integrity Associates Calculation No. 1001527.303, Revision 1, "Feedwater, Water LevelInstrument, and Core DP Nozzle Fracture Mechanics Evaluation for Hatch Unit 1 and Unit 2Pressure-Temperature Limit Curve Development.

11. General Electric Document No. GE-NE-B1 100827-00-01, "Plant Hatch Units 1 & 2 RPV PressureTemperature Limits License Renewal Evaluation,"

March 1999, SI File No. 1400365.202.

12. NRC Docket No. 50-321, "Edwin I. Hatch Nuclear Plant Unit No. 1, Amendment to FacilityOperating License,"

Amendment No. 59, License No. DPR-57, ADAMS Accession No.ML0 12950436, SI File No. 1400365.202.

13. SI Calculation No. 1400365.30 1, Rev. 0, "Hatch RPV Vacuum Assessment."

File No.: 1001527.304 Page 18 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table 2: HNP-I Beltline Region, Curve A, for 38 EFPY°F psi76.0 0.076.0 365.298.8 415.1114.4 465.0126.3 514.9135.9 564.8144.0 614.7150.9 664.6157.0 714.5162.4 764.5167.3 814.4171.8 864.3175.8 914.2179.6 964.1183.1 1014.0186.4 1063.9189.5 1113.8192.4 1163.7195.2 1213.6197.8 1263.5200.2 1313.5202.6 1363.4File No.: 1001527.304 Page 19 of 46Revision:

2F0306-01RI Structural Integrity Associates, IncTable 3:HINP-1 Beltline Region, Curve A, for 49.3 EFPY.A 9. .-76.76.0103.3120.9133.9144.2152.7160.0166.4172.0177.1181.7185.9189.8193.4196.7199.9202.9205.7208.3210.8213.2psi0.0345.8394.5443.2491.9540.6589.3638.0686.6735.3784.0832.7881.4930.1978.81027.41076.11124.81173.51222.21270.91319.6File No.: 1001527.304 Revision:

2Page 20 of 46F0306-01 RI Structural Integrity Associates, lncYTable 4: HNP-1 Bottom Head Region, Curve A, for All EFPYOF psi76.0 0.076.0 1226.178.7 1274.281.2 1322.483.6 1370.5Table 5: HNP-Z Non-Beltline Region, Curve A, for All EFPYP-T Curve P-T CurveTemperature Pressure°F psi76.0 0.076.0 312.6106.0 312.,6106.0 934.2109.5 982.6112.7 1031.0115,7 1079.3118.6 1127.7121,3 1176.1123.9 1224.4126.3 1272.8128.6 1321.2File No.: 1001527.304 Page 21 of 46Revision:

2F0306-01RI

~jStructural Integrity Associates, Inc.YTable 6: HNP-1, Beitline Region, Curve B, for 38 EFPY and 100°F/hr Thermal Transient OF psi76.0 0.076.0 144.9104.2 193.8122.1 242.7135.2 291.6145.6 340.5154.2 389.4161.6 438.3168.0 487.2173.6 536.1178.7 585.0183.4 633.9187.6 682.8191.5 731.7195.1 780.6198.5 829.5201.6 878.4204.6 927.3207.4 976.2210.1 1025.1212.6 1074.0215.0 1122.9217.3 1171.8219.5 1220.7221.6 1269.6223.6 1318.5File No.: 1001527.304 Page 22 of 46Revision:

2F0306-01IRI Structural Integrity Associates, Inc.YTable 7: HNP-I, Beltline Region, Curve B, for 49.3 EFPY and 100°F/hr Thermal Transient

°F psi76.076.0110.3130.4144.7155.9164.9172.6179.3185.2190.4195.2199.5203.5207.2210.7213.9216.9219.8222.5225.1227.5229.8232.0234.2236.20.0130.4179.8229.2278.6328.0377.4426.8476.2525.6575.0624.4673.8723.2772.6822.0871.4920.8970.21019.61069.01118.41167.81217.21266.61316.0File No.: 1001527.304 Revision:

2Page 23 of 46F0306-01 RI Sj1~ tructural Integri~t Associates, IncYeTable 8: HNP-1, Beltline Region, Curve B, for 38 EFPY and 200°F/hr Thermal Transient

°F psi76.076.0104.5122.5135.8146.2154.8162.2168.6174.3179.4184.1188.3192.2195.8199.2202.4205.3208.2210.8213.3215.7218.0220.2222.3224.3226.3228.20.023.372.9122.6172.3222.0271.6321.3371.0420.6470.3520.0569.6619.3669.0718.6768.3818.0867.6917.3967.01016.61066.31116.01165.71215.31265.01314.7File No.: 1001527.304 Revision:

2Page 24 of 46F0306-01 RI Structural Integrity Associates,

/ncYTable 9: HNP-I, Beltline Region, Curve B, for 49.3 EFPY and 200°F/hr Thermal Transient

°F psi76.0 0.076.0 8.8109.9 57.3129.9 105.9144.1 154.5155.2 203.1164.2 251.6171.9 300.2178.6 348.8184.4 397.3189.7 445.9194.4 494.5198.8 543.0202.8 591.6206.5 640.2209.9 688.7213.1 737.3216.1 785.9219.0 834.5221.7 883.0224.3 931.6226.7 980.2229.0 1028.7231.2 1077.3233.4 1125.9235.4 1174.4237.4 1223.0239.2 1271.6241.1 1320.2File No.: 1001527.304 Page 25 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table 10: HNP-I Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient

• a.e*

• U76.76.079.683.086.289.292.094.797.399.7102.0104.2psi0.0813.9863.8913.8963.71013.61063.61113.51163.51213.41263.31313.3File No.: 1001527.304 Revision:

2Page 26 of 46F0306-01 RI

~jjStructuraIiIntegrity Associates, IncYTable 11: HNP-1 Bottom Head Region, Curve B for All EFPY and 2000F/hr Thermal Transient

..- e u°F psi76.076.079.683.086.289.292.094.797.299.6101.9104.1106.2108.30.0715.7765.6815.4865.2915.1964.91014.81064.61114.41164.31214.11264.01313.8File No.: 1001527.304 Revision:

2Page 27 of 46F0306-01I R1 Structural Integrity Associates, IncTable 12:HINP-1 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient OF psi76.0 0.076.0 198.284.6 236.491.8 274.597.9 312.6136.0 312.6136.0 724.2139.0 773.5141.8 822.9144.4 872.2146.8 921.5149.2 970.9151.4 1020.2153.6 1069.6155.6 1118.9157.6 1168.3159.4 1217.6161.2 1266.9163.0 1316.3File No.: 1001527.304 Page 28 of 46Revision:

2F0306-01RI Structural Integrity Associates, lnc~eTable 13: HNP-I Non-Beltline Region, Curve B, for All EFPY and 20O°F/hr Thermal Transient

°F psi76.0 0.076.0 198.284.6 236.491.8 274.597.9 312.6136.0 312.6136.0 724.2139.0 773.5141.8 822.9144.4 872.2146.8 921.5149.2 970.9151.4 1020.2153.6 1069.6155.6 1118.9157.6 1168.3159.4 1217.6161.2 1266.9163.0 1316.3File No.: 1001527.304 Page 29 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.eTable 14: HNP-1, Beitline Region, Curve C, for 38 EFPY and i00°F/hr Thermal Transient 976.76.0125,1149.3165.6177.9187.7195.9203.0209.1214.6219.6224.1228.2232.1235.6238.9242.0245.0247.7250.3252.8255.2257.5259.6261.7263.7psi0.0109.3157.8206.2254.7303.1351.6400.0448.5497.0545.4593.9642.3690.8739.2787.7836.1884.6933.1981.51030.01078.41126.91175.31223.81272.31320.7File No.: 1001527.304 Revision:

2Page 30 of 46F0306-01 RI

$j~tructural Integrity Associates, Inc.*Table 15: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 1000F/hr Thermal Transient OF psi76.076.0133.5159.6176.6189.3199.4207.8215.0221.3226.9231.9236.4240.6244.5248.1251.4254.5257.5260.3262.9265.4267.8270.1272.3274.3276.30.0102.8151.5200.1248.8297.5346.1394.8443.5492.2540.8589.5638.2686.9735.5784.2832.9881.6930.2978.91027.61076.31124.91173.61222.31271.01319.6File No.: 1001527.304 Revision:

2Page 31 of 46F0306-01R1 Structural Integrity Associates, Inc.eTable 16: HNP-1, Beltline Region, Curve C, for 38 EFPY and 200°F/hr Thermal Transient

°F psi76.0 0.076.0 -12.3125.6 36.9149.9 86.1166.3 135.4178.6 184.6188.4 233.8196.6 283.0203.7 332.3209.9 381.5215.4 430.7220.4 480.0224.9 529.2229.0 578.4232.8 627.6236.4 676.9239.7 726.1242.8 775.3245.7 824.6248.5 873.8251.1 923.0253.6 972.3256.0 1021.5258.2 1070.7260.4 1119.9262.5 1169.2264.5 1218.4266.4 1267.6268.2 1316.9NOTE: See the discussion in Section 5.3 regarding the negative pressure in this table.File No.: 1001527.304 Page 32 of 46Revision:

2F0306-01 RI Structural Integrity Associates, IncTable 17: HNP-1, Beitline Region, Curve C, for 49.3 EFPY and 2000F/hr Thermal Transient "F76.076.0134.0160.2177.3190.0200.1208.5215.7222.0227.6232.6237.2241.4245.2248.8252.2255.3258.3261.0263.7266.2268.6270.8273.0275.1277.1279.0280.9psi0.0-18.830.680.0129.4178.9228.3277.7327.2376.6426.0475.5524.9574.3623.8673.2722.6772.1821.5870.9920.4969.81019.21068.71118.11167.51217.01266.41315.8NOTE: See the discussion in Section 5.3 regarding the negative pressure in this table.File No.: 1001527.304 Revision:

2Page 33 of 46F0306-01RI Structural Integrity Associates,

/ncYeTable 18: HNP-1 Bottom Head Region, Curve C for All EFPY and 100°F/hr Thermal Transient 976.076.083.690.195.9101.1105.8110.1114.1117.8121.2124.4127.4130.2132.9135.4137.9140.2142.4144.5psi0.0450.5498.8547.2595.6643.9692.3740.7789.1837.4885.8934.2982.51030.91079.31127.71176.01224.41272.81321.1File No.: 1001527.304 Revision:

2Page 34 of 46F0306-01 R1 Structural Integrity Associates, lnc:Table 19: HNP-I Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient e°F psi76.076.083.690.195.9101.1105.8110.2114.1117.8121.2124.4127.4130.3132.9135.5137.9140.2142.4144.6146.6148.50.0352.3400.7449.2497.6546.0594.4642.9691.3739.7788.1836.6885.0933.4981.91030.31078.71127.11175.61224.01272.41320.9File No.: 1001527.304 Revision:

2Page 35 of 46F0306-01 R1

~Structural Integrity Associates, Inc.*Table 20:tINP-1 Non-Beltline Region, Curve C, for All EFPY and 100°F/hr Thermal Transient

°F psi76.076.098.0112.1122.6130.9137.9217.0217.00.097.6140.6183.6226.6269.6312.6312.61563.0Table 21: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient

• F psi76.076.098.0112.1122.6130.9137.9217.0217.00.097.6140.6183.6226.6269.6312.6312.61563.0File No.: 1001527.304 Revision:

2Page 36 of 46F0306-01R 1

Structural Integrity Associates, Inc.'Curve A -Pressure Test, Composite Curves-Bei .... Bottom Head--- Non-Beltline 13001200110010009008004.E1150300200100I0Minimum Reactor Vessel Metal Temperature

(°F)Figure 1: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPYFile No.: 1001527.304 Revision:

2Page 37 of 46F0306-01R1 Structural Integrity Associates, Curve A -Pressure Test, Composite Curves-Beltline

---

Bottom Head -- -- Non-Beltline

-==,Overall 1300 -____I__I I110'- ____-I I _11o 800... I___ I -_t, I, I!,I'94 0 0 -I- --- ........

-.... ..... .... .. .......-... ..300 -~ -' -i!--!_ _ _ _+/- _ _ _ _200 1.......M inim um............

B olt-Up..

....-

........Teprtre=7 0100, -Minimm RIPrssr i-1. piFieN. 0052.0 Page 3=of 4Revison:F030-OII Structural Integrity Associates, Inc.Curve B -Core Not Critical, Composite Curves-Be...n --Bottom Head -- -Non-Beltline

-=,,Overall

-K....1300120011001000900* 8000.E-I 500El#.400300200100Minimum Reactor Vessel Metal Temperature (0F)Figure 3: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and IOO°F/hrFile No.: 1001527.304 Revision:

2Page 39 of 46F0306-01 RI VStructural Integrity Associates,/lnc.?

Curve B -Core Not Critical, Composite Curves-Beiti.e.---Bottom Head---- Non-Beltline m===Overall 130012001100900800700tE-1 500&- 4003002001000Minimum Reactor Vessel Metal Temperature

('F)Figure 4: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 1O00FfhrFile No.: 1001527.304 Revision:

2Page 40 of 46F0306-01 RI Structural Integrity Associates, lncYCurve B -Core Not Critical, Composite Curves-....n --Bottom Head --1 Non-Beitline

-==Overall 1300120011001000900a.*1ES500&" 40030001!;0 2(X)Minimum Reactor VesselI Metal Temperature

(*F)Figure 5: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 41 of 46F0306-01RI jjStructural Integrity Associates, IncYCurve B -Core Not Critical, Composite Curves-eilie-- -- Bottom Head -- -- Non-Beltline m===Ove rail1300120011001000900800 ....7010 *E-. 500Si3002001000Minimum Reactor Vessel Metal Temperature

(=F)Figure 6: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 42 of 46F0306-01IRI Structural Integrity Associates, IncYCurve C -Core Critical, Composite Curves-....ne --Bottom Head -- -- Non-Beitline

-.mmOverall 1300120011001O00900,6" 6003002001000Minimum Reactor Vessel Metal Temperature

(°F)Figure 7: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 10O°F/hrFigure 7: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 1000F/hrFile No.: 1001527.304 Revision:

2Page 43 of 46F0306-01R1 Structural Integrity Associates, Inc.YCurve C -Core Critical, Composite Curves-Bei....---Bottom Head -- -- Non-Beltline

-Overall13001200110010009000.gi70EA- 4o03002001000Minimum Reactor Vessel Metal Temperature

(@F)Figure 8: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 100°F/hrFile No.: 1001527.304 Revision:

2Page 44 of 46F0306-01RI Structural Integrity Associates, Inc.YCurve C -Core Critical, Composite Curves-....ne -- Bottom Head -- -- Non-Beitline i,,,,,Overall 130012001110010001900OMinimum Bolt-Temperature

=7Minimum BeltliTemperature

= 5Minimum RP\Pressure

= -14.7a.SE-,Sg800700op l ! anI!940FI __ aI aVe Ipsig jiaaaIIaIaIIIIIIII I* i /I A, Iiii,iiii'i, .../600400-.. ......300200100 ,0520025030o+/-_Minimum Reactor Vessel Metal Temperature (0F)Figure 9: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 45 of 46F0306-01RI Structural Integrity Associates, IncYeCurve C -Core Critical, Composite Curves-Bei..ne---Bottom Head -- -- Non-Beitline

-Overall1300120011001000900J 6004..E"1 500&" 4003002001000Minimum Reactor Vessel Metal Temperature

('F)Figure I0: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 20O°F/hrFigure 10: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 2000F/hrFile No.: 1001527.304 Revision:

2Page 46 of 46F0306-01I RI Structural Integrity Associates, Inc5APPENDIX A:P -T CURVE INPUT LISTINGFile No.: 1001527.304 Revision:

2Page A-i1 of A-3F0306-01 RI jjStructural Integrity Associates, Inc~eTable A-i: HINP-I Stress Intensity Factors for Feedwater and WLI Nozzles 1131Feedwater 76.6 65.3 11.5 23.1WLI 71.6 N/A 17.4 34.8Core DP 32.3 N/A 1.7 3.5Notes:1. K1 in units of ksi-in0s2. 200 "F/hr results are scaled from 100 "F/hr assuming response is linearTable A-2: HNP-I P-T Curve Input ListingGeneral Parameters English Unit System for Tables and Plots0 Temperature Instrument Uncertainty Adjustment

(°F)0 Pressure Instrument Uncertainty Adjustment (psig)62.4 Water Density (lbm/ft3)836.75 Full-Vessel Water Height (in)1.5 Safety Factor for Curve A2 Safety Factor for Curves B and C76 Bolt-up Temperature

(°F)16 ART of Closure Flange Region (°F)10 Default Temperature Increment for Tables (0F)50 Default Pressure Increment for Composite Tables (psig)Beltline Parameters 116.3 Adjusted Reference Temperature, 38 EFPY (°F)129.0 Adjusted Reference Temperature, 49.3 EFPY (0F)110.375 Vessel Radius (in)5.375 Vessel Thickness (in)100 Heat-up / Cool-down Rate (°F/hr)200 Heat-up / Cool-down Rate (°F/hr)Generic Type of Static Pressure Head AdditionN/A Specific Water Height for Static Pressure Head Addition (in)Generic Type of Temperature Increment for Tables5 Specific Temperature Increment for Tables (°F)File No.: 100 1527.304 Page A-2 of A-3Revision:

2F0306-01RI Structural Integrity Associates,

/nc*P- uv nputsInstrument Nozzle Parameters 116.3 Adjusted Reference Temperature, 38 EFPY (OF)129.0 Adjusted Reference Temperature, 49.3 EFPY ('F)110.375 Vessel Radius (in)5.375 Vessel Thickness (in)See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)

A-i Applied Thermal Stress Intensity Factor (ksi*in^0.5) 7.70E-06 Coefficient of Thermal Expansion (in!/in/'F) 1000 Reference Pressure (psig)Generic Type of Static Pressure Head AdditionN/A Specific Water Height for Static Pressure Head Addition (in)Generic Type of Temperature Increment for Tables5 Specific Temperature Increment for Tables (*F)Bottom Heai10110.56.81251002003GenericN/AGeneric5Non-Beltline 40See TableA-iYes1005501000GenericN/AGeneric5d Parameters Adjusted Reference Temperature

(°F)Vessel Radius (in)Vessel Thickness (in)Heat-up / Cool-down Rate (°F/hr)Heat-up / Cool-down Rate (°F/hr)Stress Concentration FactorType of Static Pressure Head AdditionSpecific Water Height for Static Pressure Head Addition (in)Type of Temperature Increment for TablesSpecific Temperature Increment for Tables (°F)(Feedwater Nozzle) Parameters Adjusted Reference Temperature

(°F)Applied Pressure Stress Intensity Factor (ksi* in^0.5)Applied Thermal Stress Intensity Factor (ksi*in^0.5)

Minimum Thermal Stress Intensity Factor (ksi*in^0.5)

Scale KIT based on Saturation Temperature?

Minimum Transient Temperature

(°F)Maximum Transient Temperature

(*F)Reference Pressure for Thermal Transient (psig)Type of Static Pressure Head AdditionSpecific Water Height for Static Pressure Head Addition (in)Type of Temperature Increment for TablesSpecific Temperature Increment for Tables (°F)File No.: 1001527.304 Revision:

2Page A-3 of A-3F0306-01RI jjStructural Integrity Associates, Inc.*APPENDIX B:SUPPORTING CALCULATIONS File No.: 1001527.304 Revision:

2Page B-I of B-43F0306-01RI

~jStructoral Integrity Associates, Inc.*Table B-I: HNP-1, Beltline Region, Curve A Calculations, for 38 EFPY-A

• I°ksi*in^0.5

°ksi*inAO.5

-IFps'76.076.086.096.0106.0116.0126.0136.0146.0156.0166.042.542,544.547.050.153.858.463.970.879.189.228.328.329.731.333.435.938.942.647.252.759.576.076.086.096.0106.0116.0126.0136.0146.0156.0166.00.0611.9642.9680.8727.0783.5852.5936.81039.71165.51319.0File No.: 1001527.304 Revision:

2Page B-2 of B-43F0306-01R I

Structural Integrity Associates, Inc.tTable B-2: HNP-1, WLI (N16) Nozzle Beltline Region, Curve A Calculations, for 38 EFPY-A U -- -ksiifl^O.5

-IFpsi76.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.042.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.928.328.329.731.333.435.938.942.647.252.759.567.877.990.2105.376.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.00.0365.2384.3407.6436.1470.9513.4565.3628.7706.1800.6916.21057.21229.51440.0File No.: 1001527.304 Revision:

2Page B-3 of B-43F0306-0tRI Structural Integrity Associates, Inc.YTable B-3: HNP-1, Beitline Region, Curve A Calculations, for 49.3 EFPY-A U -Gageiiiii Fl idiiiTemprtr°ksi*inAO.5

°ksi*inAO.5 P- Crvpsi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.926.926.927.428.028.629.330.030.931.832.833.935.236.538.039.741.643.645.948.351.154.257.561.276.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.00.0580.5591.9604.5618.5633.9650.9669.8690.6713.6739.0767.1798.2832.5870.4912.4958.71009.91066.51129.01198.11274.51358.9File No.: 1001527.304 Page B-4 of B-43Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table B-4: HNP-I, WLI (N16) Nozzle Beitline Region, Curve A Calculations, for 49.3 EFPY-A F --°F psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.326.926.927.428.028.629.330.030.931.832.833.935.236.538.039.741.643.645.948.351.154.2,57.561.265.469.974.980.586.693.4100.976.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.00.0345.8352.9360.7369.2378.7389.2400.8413.7427.8443.5460.8479.9501.0524.4550.2578.7610.3645.1683.6726.2773.2825.2882.7946.21016.31093.91179.61274.31379.0File No.: 1001527.304 Revision:

2Page B-5 of B-43F0306-01 RI Structural Integrity Associates, Inc.*Table B-5: HNP-1, Bottom Head Region, Curve A Calculations, All EFPYA .-°ksi *inA0.5 °ksi*inA0.5 psi76.0 110.8 73.9 76.0 0.076.0 110.8 73.9 76.0 1226.181.0 119.0 79.3 81.0 1318.686.0 128.0 85.3 86.0 1420.9File No.: 1001527.304 Revision:

2Page B-6 of B-43F0306-01RI j§StructuraI Integrity Associates, Inc.eTable B-6: HNP-I, FW Nozzle / Non-Beitline, Curve A Calculations, All EFPY76.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0°ksi*inA0.5 75.875.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7°ksi*inA0.5 50.550.552.955.558.261.264.568.071.876.080.585.390.696.3102.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0psi0.0629.5660.3693.8730.0769.3811.8857.9907.8961.81020.41083.81152.51227.01307.6File No.: 1001527.304 Page B-7 of B-43Revision:

2F0306-01RI Structural Integrity Associates, Inc.?Table B-7: HNP-1, Beitline Region, Curve B Calculations, for 38 EFPY and 100°F/hr ThermalTransient

..* a a76.76.076.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0°ksi*inA0.5 42.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3°ksi*inAO.5 18.018.019.120.321.823.726.028.832.236.341.447.655.264.476.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0psi0.0379.0402.2430.6465.3507.7559.4622.6699.9794.2909.31050.01221.81431.7File No.: 1001527.304 Revision:

2Page B-8 of B-43F0306-01IRI Structural Integrity Associates,

/nc.YTable B-8: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 38 EFPY and100°F/hr Thermal Transient

• SS *- 9 D°F ksi*inA0.5

°ksi*inAO.5 psi76.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.042.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.9185.5219.212.512.513.614.816.318.220.523.326.730.835.942.149.758.970.284.1100.976.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.00.0144.9159.2176.7198.1224.2256.0295.0342.5400.6471.5558.1663.9793.2951.01143.81379.3File No.: 1001527.304 Revision:

2Page B-9 of B-43F0306-01RI Structural Integrity Associates, IncYtTable B-9: HNP-I, Beltline Region, Curve B Calculations, for 49.3 EFPY and 100°F/hr ThermalTransient

..* .UGage fluid P-T Curve P-T CurveTemperature K1Temperature Pressure°F °ksi*in^0.5

°ksi*in^0.5 76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.917.017.017.417.818.318.819.320.020.621.422.223.224.225.326.628.029.531.233.135.137.439.942.745.849.253.057.261.876.76.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0psi0.0355.4364.0373.4383.9395.5408.3422.4438.0455.3474.3495.4518.7544.4572.9604.3639.1677.5719.9766.8818.6875.9939.21009.21086.51172.01266.51370.8File No.: 1001527.304 Revision:

2Page B-1l0 of B-43F0306-01RI Structural Integrity Associates, Inc.~Table B-I0: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 49.3 EFPY and100°F/hr Thermal Transient

-Sp **

• e-ksi~in^O.5 "ksi~inAO.5 psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.3163.8177.5192.7209.411.511.511.912.312.813.313.814.515.115.916.717.718.719.821.122.524.025.727.629.631.934.437.240.343.747.551.756.361.467.073.280.087.696.076.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.00.0130.4135.7141.5148.0155.1163.0171.6181.3191.9203.6216.6231.0246.8264.3283.7305.1328.7354.9383.7415.7450.9489.9533.0580.6633.3691.4755.7826.7905.3992.01087.91193.91311.0File No.: 1001527.304 Revision:

2Page B- 11 of B-43F0306-01RI Structural Integrity Associates, Inc.YTable B-Il: HNP-I, Bottom Head Region, Curve B Calculations, for All EFPY and 100°F/hrThermal Transient

• e. e U-/-°ksi*inAO.5

°ksi*in^0.5 "1-psi76.076.081.086.091.096.0101.0106.0110.8110.8119.0128.0138.0149.0161.2174.649.649.653.758.263.268.774.881.576.076.081.086.091.096.0101.0106.00.0813.9883.3960.01044.81138.41242.01356.4File No.: 1001527.304 Revision:

2Page B-12 of B-43F0306-01RI Structural Integrity Associates, lnc.*Table B-12: HNP-I, FW Nozzle / Non-Beitline, Curve B Calculations, for All EFPY and 100°F/hrThermal Transient

... 9 F°ksi*inAO.5

°ksi*inAO.5

°F psi76.076,080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.075.875.879.383.287.491.996.7102.0107.8114.0120,7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.832.117.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.00.0198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-13 of B-43F0306-01RI Structural Integrity Associates,

/InCYTable B-13: HNP-I, Beltline Region, Curve B Calculations, for 38 EFPY and 200°Ffhr ThermalTransient

• SS *~ 9Gage Fluid P-T curve P-T CurveTemperature Temperature Pressure°F ksi*inAO.5 76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.042.542.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3°ksi*inA0.5 14.814.815.315.916.517.117.918.719.520.521.622.824.125.627.229.031.033.235.638.241.244.448.052.056.461.3"F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0psi0.0306.6317.6329.8343.3358.2374.7392.9413.0435.3459.9487.0517.1550.3586.9627.5672.3721.8776.5836.9903.8977.61059.21149.41249.11359.3File No.: 100 1527.304Revision:

2Page B-14 of B-43F0306-01 RI1 Structural Integrity Associates, IncYTable B-14: HNP-I, WLI (N16) Nozzle Beitline Region, Curve B Calculations, for 38 EFPY and2000F/hr Thermal Transient

.e* e F°F ksi*in^0.5

°ksi*inA0.5 0Fpsi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.042.542.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3146.0157.9171.0185.5201.5219.2238.83.83.84.34.95.56.16.87.68.59.510.611.813.114.616.218.020.022.124.527.230.233.437.041.045.450.255.661.568.175.383.492.2102.076.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.00.023.330.137.645.955.165.276.488.8102.5117.7134.4152.9173.3195.9220.9248.4278.9312.6349.8391.0436.5486.7542.3603.6671.5746.4829.3920.91022.11133.91257.51394.1File No.: 100 1527.304Revision:

2Page B-15 of B-43F0306-01R1 Structural Integrity Associates, Inc,Table B-15: HNP-I, Beltline Region, Curve B Calculations, for 49.3 EFPY and 2000F/hr ThermalTransient

• a9 e*

• FGage Fluid P-T Curve P-T CurveTemperature K11Temperature Pressure°F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0°ksi*inA0.5 40.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1°ksi*in^0.5 13.813.814.214.615.115.616.116.817.418.219.120.021.022.123.424.826.328.029.931.934.236.839.542.646.049.854.058.663.776.76.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0psi0.0283.0291.6301.0311.5323.1335.9350.0365.6382.9401.9423.0446.3472.0500.5531.9566.7605.1647.5694.4746.2803.5866.8936.81014.21099.61194.11298.51413.8File No.: 1001527.304 Revision:

2Page B-16 of B-43F0306-01RI Structural Integrity Associates, IncYeTable B-16: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 49.3 EFPY and200°F/hr Thermal Transient

..- 9 93=°ksi*inA0.5 "ksi*inAO.5 psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.3163.8177.5192.7209.4228.02.82.83.23.64.04.65.15.76.47.28.09.010.011.112.413.815.317.018.920.923.225.728.531.635.038.843.047.652.658.364.571.378.987.396.676.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.00.08.814.119.926.333.441.350.059.670.382.095.0109.3125.2142.7162.0183.4207.1233.2262.1294.0329.3368.3411.3459.0511.6569.7634.0705.0783.5870.3966.21072.11189.21318.7File No.: 1001527.304 Revision:

2Page B- 17 of B-43F0306-01 R1 Structural Integrity Associates, Inc.Table B-17: HNP-1, Bottom Head Region, Curve B Calculations, for All EFPY and 200°F/hrThermal Transient a **

• UGage FluId P-T Curve P-T CurveTemperature Temperature Pressure76.76.081.086.091.096.0101.0106.0111.0°ksi*inAO.5 110.8110.8119.0128.0138.0149.0161.2174.6189.5°ksi*inAO.5 43.943.947.952.557.463.069.075.883.276.76.081.086.091.096.0101.0106.0111.0psi0.0715.7785.1861.8946.61040.31143.81258.31384.7File No.: 1001527.304 Revision:

2Page B-I18 of B-43F0306-01RI j7Structural Integrity Associates,

/nc,5Table B-18: HNP-I, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 200°F/hrThermal Transient

.e* 9 U°F ksi*in^0.5

°ksi*inA0.5 psi76.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.075.875.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.826.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.00.0198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B- 19 of B-43F0306-01Rt Structural Integrity Associates, IncTable B-19: HNP-I, Beltline Region, Curve C Calculations, for 38 EFPY and 100°F/hr ThermalTransient O°ksi*inA0.5

°ksi*inAO.5

°Fpsi36.0 37.4 15.5 76.0 0.036.0 37.4 15.5 76.0 321.146.0 38.3 15.9 86.0 331.656.0 39.4 16.5 96.0 344.366.0 40.8 17.2 106.0 359.976.0 42.5 18.0 116.0 379.086.0 44.5 19.1 126.0 402.296.0 47.0 20.3 136.0 430.6106.0 50.1 21.8 146.0 465.3116.0 53.8 23.7 156.0 507.7126.0 58.4 26.0 166.0 559.4136.0 63.9 28.8 176.0 622.6146.0 70.8 32.2 186.0 699.9156.0 79.1 36.3 196.0 794.2166.0 89.2 41.4 206.0 909.3176.0 101.6 47.6 216.0 1050.0186.0 116.8 55.2 226.0 1221.8196.0 135.3 64.4 236.0 1431.7File No.: 1001527.304 Page B-20 of B-43Revision:

2F0306-01 RI Structural Integrity Associates, Inc.YTable B-20: HNP-I, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 38 EFPY and100°F/hr Thermal Transient Gage Fluid P-T Curve P-T CurveTemperature Temperature Pressure36.36.046.056.066.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.0°ksi*inAO.5 37.437.438.339.440.842.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.9185.5219.2°ksi*inA0.5 10.010.010.411.011.712.513.614.816.318.220.523.326.730.835.942.149.758.970.284.1100.976.76.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.0236.0246.0256.0266.0psi0.0109.3115.7123.6133.2144.9159.2176.7198.1224.2256.0295.0342.5400.6471.5558.1663.9793.2951.01143.81379.3File No.: 1001527.304 Revision:

2Page B-21 of B-43F0306-01RI S~tructural Integrity Associates, IncYeTable B-21:. HNP-I, Beltline Region, Curve C Calculations, for 49.3 EFPY and 100°F/hr ThermalTransient 36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0°ksi*inA0.5 36.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9°ksi*inAO.5 15.015.015.215.415.615.816.116.316.717.017.417.818.318.819.320.020.621.422.223.224.225.326.628.029.531.233.135.137.439.942.745.849.253.057.261.8°F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0psi0.0310.5314.4318.6323.3328.5334.3340.6347.7355.4364.0373.4383.9395.5408.3422.4438.0455.3474.3495.4518.7544.4572.9604.3639.1677.5719.9766.8818.6875.9939.21009.21086.51172.01266.51370.8File No.: 1001527.304 Revision:

2Page B-22 of B-43F0306-01R 1

Structural Integrity Associates, Inc:Table B-22: HNP-I, WLI (NI6) Nozzle Beitline Region, Curve C Calculations, for 49.3 EFPY and1O00F/hr Thermal Transient "F"ksi'inA0.5 "ksi'inA0.5 "Fpsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.19.59.59.79.910.110.310.610.811.211.511.912.312.813.313.814.515.115.916.717.718.719.821.122.524.025.727.629.631.934.437.240.343.747.551.756.361.476.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0102.8105.1107.8110.7113.9117.4121.3125.6130.4135.7141.5148.0155.1163.0171.6181.3191.9203.6216.6231.0246.8264.3283.7305.1328.7354.9383.7415.7450.9489.9533.0580.6633.3691.4755.7826.7File No.: 1001527.304 Revision:

2Page B-23 of B-43F0306-01 RI j§Structural Integrity Associates, Inc:~216.0221.0226.0231.0236.0151.3163.8177.5192.7209.467.073.280.087.696.0256.0261.0266.0271.0276.0905.3992.01087.91193.91311.0Table B-23:HNP-I, Bottom Head Region, Curve C Calculations, for All EFPY and 100°F/hrThermal Transient Temperature II*F °ksi*inA0.5 36.0 68.136.0 68.141.0 71.746.0 75.851.0 80.356.0 85.261.0 90.766.0 96.771.0 103.476.0 110.881.0 119.086.0 128.091.0 138.096.0 149.0101.0 161.2106.0 174.6::Temperature Pesr°ksi*inAO.5 OF psi28.3 76.0 0.028.3 76.0 450.530.1 81.0 481.632.1 86.0 516.134.4 91.0 554.236.8 96.0 596.339.6 101.0 642.842.6 106.0 694.245.9 111.0 751.149.6 116.0 813.953.7 121.0 883.358.2 126.0 960.063.2 131.0 1044.868.7 136.0 1138.474.8 141.0 1242.081.5 146.0 1356.4File No.: 1001527.304 Revision:

2Page B-24 of B-43F0306-01R 1

Structural Integrity Associates,/Inc.:

Table B-24: HNP-1, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 100°F/hrThermal Transient e36.36.040.044.048.052.056.060.064.068.072.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0°ksi*inAO.5 52.352.353.955.757.559.661.864.166.769.572.575.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.8°ksi*inA0.5 psi20.49.810.310.811.412.012.713.514.315.316.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0168.0172.0176.0180.0184.0188.0192.0196.0200.0204.00.097.6103.8110.6118.1126.5135.7145.8157.1169.5183.1198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-25 of B-43F0306-01RI Structural

Integrit, Associates, Inc."Table B-25: HNP-I, Beitline Region, Curve C Calculations, for 38 EFPY and 200°F/hr ThermalTransient

-9. D°ksi*inA0.5

°ksi*inAO.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.037.437.437.838.338.839.440.140.841.642.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.312.312.312.512.813.013.313.614.014.414.815.315.916.517.117.918.719.520.521.622.824.125.627.229.031.033.235.638.241.244.448.052.056.461.376.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.00.0248.7253.7259.2265.2271.9279.3287.5296.6306.6317.6329.8343.3358.2374.7392.9413.0435.3459.9487.0517.1550.3586.9627.5672.3721.8776.5836.9903.8977.61059.21149.41249.11359.3File No.: 1001527.304 Revision:

2Page B-26 of B-43F0306-01IRI Structural Integrity Associates, Inc.:Table B-26: HNP-1, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 38 EFPY and2000F/hr Thermal Transient GaeFli°ksi*inAO.5 "ksi*in^0.5 P-T CurveTemperature "FP-T CurvePressurepsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.037.437.437.838.338.839.440.140.841.642.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3146.0157.9171.01.31.31.51.72.02.32.63.03.43.84.34.95.56.16.87.68.59.510.611.813.114.616.218.020.022.124.527.230.233.437.041.045.450.255.661.568.176.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0-12.3-9.3-5.9-2.22.06.511.617.123.330.137.645.955.165.276.488.8102.5117.7134.4152.9173.3195.9220.9248.4278.9312.6349.8391.0436.5486.7542.3603.6671.5746.4829.3920.9File No.: 1001527.304 Revision:

2Page B-27 of B-43F0306-01 RI Structural Integrity Associates, Inc.e216.0221.0226.0231.0185.5201.5219.2238.875.383.492.2102.0256.0261.0266.0271.01022.11133.91257.51394.1File No.: 1001527.304 Revision:

2Page B-28 of B-43F0306-01R1 Structural Integrity Associates, InC*:Table B-27: HNP-I, Beltline Region, Curve C Calculations, for 49.3 EFPY and 200°F/hr ThermalTransient

e. 9°F oksi*inAO.5

°ksi*inA0.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140,111.811.812.012.212.412.612.913.213.513.814.214.615.115.616.116.817.418.219.120.021.022.123.424.826.328.029.931.934.236.839.542.646.049.854.058.663.776.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0238.1242.0246.2251.0256.1261.9268.2275.3283.0291.6301.0311.5323.1335.9350.0365.6382.9401.9423.0446.3472.0500.5531.9566.7605.1647.5694.4746.2803.5866.8936.81014.21099.61194.11298.51413.8File No.: 100 1527.304Revision:

2Page B-29 of B-43F030-01R 1

Structural Integrity Associates, IncYTable B-28: HNP-1, WLI (N16) Nozzle Beitline Region, Curve C Calculations, for 49.3 EFPY and200°F/hr Thermal Transient Temprtr°ksi*inA0.5

°ksi~inA0.5 P °FCrvP-T CurvePressurepsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.10.80.81.01.21.41.61.92.12.42.83.23.64.04.65.15.76.47.28.09.010.012.413.815.317.018.920.923.225.728.531.635.038.843.047.652.676.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0-18.8-16.5-13.9-11.0-7.8-4.2-0.34.08.814.119.926.333.441.350.059.670.382.095.0109.3125.2142.7162.0183.4207.1233.2262.1294.0329.3368.3411.3459.0511.6569.7634.0705.0File No.: 100 1527.304Revision:

2Page B-30 of B-43F0306-01RI Structural Integrity Associates, IncYe216.0221.0226.0231.0236.0241.0151.3163.8177.5192.7209.4228.058.364.571.378.987.396.6256.0261.0266.0271.0276.0281.0783.5870.3966.21072.11189.21318.7File No.: 1001527.304 Revision:

2Page B-31I of B-43F0306-01 R1 S~tructural Integrity Associates, Inc.tTable B-29: HNP-1, Bottom Head Region, Curve C Calculations, for All EFPY and 200°F/hrThermal Transient 9OF ksi*in^0.5

°ksi*in^0.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.068.168.171.775.880.385.290.796.7103.4110.8119.0128.0138.0149.0161.2174.6189.522.522.524.326.428.631.133.836.840.243.947.952.557.463.069.075.883.276.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.00.0352.3383.5418.0456.0498.1544.7596.1652.9715.7785.1861.8946.61040.31143.81258.31384.7File No.: 1001527.304 Revision:

2Page B-32 of B-43F0306-01RI Structural Integrity Associates, lnc.YTable B-30: HNP-1, FW Nozzle / Non-Beitline, Curve C Calculations, for All EFPY and 2000F/hrThermal Transient

-.- 9°F ksi*inAO.5

°ksi*inA0.5 psi36.036.040.044.048.052.056.060.064.068.072.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.052.352.353.955.757.559.661.864.166.769.572.575.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.814.69.810.310.811.412.012.713.514.315.316.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0168.0172.0176.0180.0184.0188.0192.0196.0200.0204.00.097.6103.8110.6118.1126.5135.7145.8157.1169.5183.1198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-33 of B-43F0306-01RI jjStructural Integrity Associates, Inc.Curve A -Pressure Test, All Components

-BL ....-N16 -- -- BH -.-FWN -* OCFR50 ....CDPN1300120011001000900hiu 0*140030020010000-I ____ ________

________

_______100 150 200 250Minimum Reactor Vessel Metal Temperature

(*F)50300Figure B-I: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPYNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-34 of B-43F0306-01R I

Structural Integrity Associates, Inc.YCurve A -Pressure Test, All Components

-BL .... N16 --BH -- --FWN 10CFR50 ....CDPN1300120011001000900.~800p70'UlUIE 0iU-4003002001000050 100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-2: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 49.3 EFPYNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-35 of B-43F0306-01RI Structural Integrity Associates, lncYCurve B -Core Not Critical, All Components

-BL .... N16 --- BH --.-FWN -. 1OCFR50O....CDPN 1300120011001000{906Il6006Il500SI4003002001000 50}100 150Minimum Reactor Vessel Metal Temperature

(°F)200250Figure B-3: HNP-I P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 100OF/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-36 of B-43F0306-01R1 Structural Integrity Associates, Inc.YCurve B -Core Not Critical, All Components

-BL ....-N16 --- BH -- -FWN -- 10CFRSO0....CDPN 1300- __1200 ~--11001000 ...900I=ED300 +200- _-1000o0 50100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-4:HINP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and100°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-37 of B-43F0306-01R 1

~jjStructural Integrity Associates, Inc.eCurve B -Core Not Critical, All Components

-BL .... N16 --BH -- --FWN -* OCFRSO ....CDPN1300O-12001100 -,...1000900 -.:800S700j ÷600 ---U400 ...300: I I" I: l i* I___ I I *-ii;, 4/:17II!/IIIIIIIFii tI i÷__IIIII__~1~IIIIII'I/2001! ItI/ ltll1004 4 ~-~----------~-

,o i2500 4---50300100 150 200Minimum Reactor Vessel Metal Temperature

(*F)Figure B-5: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 200°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-38 of B-43F0306-01RI Structural Integrity Associates, lnc.eCurve B -Core Not Critical, All Components

-BL ....-N16 --BH --.--FWN -, 1OCFR50 ....CDPN1300120011001O00900Ip76Ie,0@16oE400~300200 I1000o40100 150 200Minimum Reactor Vessel Metal Temperature (0F)*25050300Figure B-6: HNP-I P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and200°F/hrNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-39 of B-43F0306-01RI Sj~tructural Integrity Associates, Curve C -Core Critical, All Components

-BL .... N16 --- BH --.-FWN -. 10CFR50 ....CDPN1300120011001000900S800b700S600~5004-4003002001000050100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-7: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 100°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-40 of B-43F0306-01RI V$tructural Integrity Associates, InceCurve C -Core Critical, All Components

-BL .... N16 -- -- BH -.-FWN IOCFRSO ....CDPN1300120011001000900.~800p700Els00U-4003002001000 4-0100 150 200Minimum Reactor Vessel Metal Temperature

(*F)50250300Figure B-8: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 1000F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-41 of B-43F0306-01RI Structural Integrity Associates, IncYtCurve C -Core Critical, All Components

-BL ....-N16 --BH -.-FWN -. 1OCFR50 ... CDPN1300120011001000900.~800p 700:; 6006Ew504OO3002001000i °- I100 150 200Minimum Reacto Vessel Metal Temperature I*F)300Figure B-9: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 200°F/hrNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-42 of B-43F0306-01RI Structural Integrity Associates, InYCurve C -Core Critical, All Components

-BL .... N16 --BH I- --FWN -10CFR50 ....CDPN1300120011001O00900700UE--P 0VA-04003002001000050 100 150 200 250Minimum Reactor Vessel Metal Temperature

(°F)300Figure B-10: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 200°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-43 of B-43F0306-01R 1

S ' Structural Integrity Associates, IncY File No.: 1001527.304 li No.: 1400365CALCULATION PACKAGE Quality Program:

[] Nuclear [] Commercial PROJECT NAME:Plant Hatch Unit 1 &2 P-T Curve Evaluation CONTRACT NO.:P0: SNC19354-0010, Rev. 1 CONTRACT:

19354, Rev. 4CALCULATION TITLE:Hatch Unit 1 P-T Curve Calculation for 38 and 49.3 EFPYDocument Affected Project Manager Preparer(s)

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Revision Description ApprovalSintrs&De Revision Pages __________

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& DateSintrs&De 0 1 -45 Initial Issue Responsible EngineerA-i -A-3 R. GnagneB-i -B-43 D. V. Sommerville 12/30/2011 12/30/2011 Responsible VerifierG. Licina12/30/2011 D. V. Sommerville 12/30/2011 117 Citations for References Responsible Engineer[1] and [2] have beenupdated to show citation D.V. Sommerville M. Qinfor NRC approved 9/19/2013 9/19/2013 versions.

Citation forReference

[10] has been Responsible verifierupdated to show currentrevision.

Reference

[10] D. V. Sommerville was revised for the same 9/19/2013 reason as identified abovefor References

[1] and[2]. No technical changes are made for thisrevision.

Page 1 of 46F0306-01IRI V' Structural Integrity Associates,/Inc.Y File No.: 1001527.304Project No.: 1001527CALCULATION PACKAGE Quality Program:

[] Nuclear LI] Commercial CALCULATION TITLE:Hatch Unit 1 P-T Curve Calculation for 38 and 49.3 EFPYDocument Affected Project Manager Peae~)&Cekrs Reiin PgsRevision Description Approval Prepaurers)

& C atekrsRevision__Pages

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Signature

& DateSintrs&De 2 6, 7, 9, 11 -34, Revised to incorporate Responsible Engineer37 -46 updated fluence data 7 '¢A-I -A-3 to address NRC condition B-1 -B-43 for SIR-05-044-Rev.

1-Aregarding lowest service D. V. Sommerville temperature.

9/10/2014 D. V. Sommerville forC. J. Oberembt9/10/2014 Responsible VerifierD. V. Sommerville 9/10/20 14Page 2 of 46F0306-O1R 1

VStructural Integrity Associates, IncYTable of Contents

1.0 INTRODUCTION

...........................................................................

62.0 METHODOLOGY

..........................................................................

63.0 ASSUMPTIONS...........................................................................

124.0 DESIGN INPUTS.......................14 5.0 CALCULATIONS

.........................

.................................

i.............

155.1 Pressure Test (Curve A)...........................................................

155.2 Normal Operation

-Core Not Critical (Curve B)...............................

165.3 Normal Operation

-Core Critical (Curve C)....................................

1

76.0 CONCLUSION

S............................................................................

1

77.0 REFERENCES

.............

...............................................................

18APPENDIX A : P -T CURVE INPUT LISTING ..............................................

A-iAPPENDIX B : SUPPORTING CALCULATIONS

..........................................

B-iFile No.: 1001527.304 Revision:

2Page 3 of 46F0306-01R1 Structural Integrity Associates, IncYList of TablesTable 1 : Summary of Minimum Temperature Requirements for P-T Limit Curves...................

11Table 2: HNP-1 Beitline Region, Curve A, for 38 EFPY ...............................................

19Table 3: HNP-1 Beitline Region, Curve A, for 49.3 EFPY .............................................

20Table 4: HNP-1 Bottom Head Region, Curve A, for All EFPY ........................................

21Table 5: HNP-1 Non-Beltline Region, Curve A, for All EFPY... .....................................

21Table 6: HNP-1, Beltline Region, Curve B, for 38 EFPY and 100°F/hr Thermal Transient

.........

22Table 7: HNP-1, Beltline Region, Curve B; for 49.3 EFPY and 100°F/hr Thermal Transient

.......23Table 8: HNP-1, Beitline Region, Curve B, for 38 EFPY and 200°F/hr Thermal Transient

.........

24Table 9: HNP-1, Beitline Region, Curve B, for 49.3 EFPY and 200°F/hr Thermal Transient

......25Table 10: HNP-1 Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient...

26Table 11: HNP-1 Bottom Head Region, Curve B for All EFPY and 200°F/hr Thermal Transient...

27Table 12: HNP-1 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient

.. 28Table 13: HNP- 1 Non-Beltline Region, Curve B, for All EFPY and 200°F/hr Thermal Transient

..29Table 14: HiNP-1, Beltline Region, Curve C, for 38 EFPY and 100°F/hr Thermal Transient.........

30Table 15: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 100°F/hr Thermal Transient

.....31Table 16: H-NP-1, Beltline Region, Curve C, for 38 EFPY and 200°F/hr Thermal Transient.......32 Table 17: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 200°F/hr Thermal Transient

.....33Table 18: HNP-1 Bottom Head Region, Curve C for All EFPY and 100°F/hr Thermal Transient...

34Table 19: HNP-1 Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient...

35Table 20: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 100°F/hr Thermal Transient

.. 36Table 21: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient

.. 36File No.: 1001527.304 Page 4 of 46Revision:

2F0306-01R1 Structural Integrity Associates, Inc.eList of FiguresFigure 1: INP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPY.......................

37Figure 2: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 49.3 EFPY ...............

.....38Figure 3: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 1000F/hr....39 Figure 4: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 100°F/hr

.. 40Figure 5: TNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 2000F/hr....41 Figure 6: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 2000F/hr .. 42Figure 7: J-NP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 100OF/hr.........

43Figure 8: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and lOO°F/hr......44 Figure 9: HNP-1 P-T Curve C (Normal Operation

-. Core Critical),

38 EFPY and 200°F/hr.........

45Figure 10: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 200°F/hr.....46 File No.: 1001527.304 Revision:

2Page 5 of 46F0306-01R1 VStructural Integrity Associates,

1.0 INTRODUCTION

This calculation develops pressure-temperature (P-T) limit curves for the beltline, bottom head, and non-beitline regions of the Hatch Nuclear Plant, Unit 1 (HNP-1) reactor pressure vessel (RPV). The P-Tcurves are developed for 38 and 49.3 effective full power years (EFPY) of operation, and for 100OF/hrand 200°F/hr thermal transients.

The P-T curves are prepared using the methods documented in theBoiling Water Reactor Owner's Group (BWROG) Licensing Topical Reports (LTRs), "Pressure Temperature Limits Report Methodology for Boiling Water Reactors"

[ 1] and "Linear Elastic FractureMechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles forPressure-Temperature Curve Evaluations"

[2]. These LTRs satisfy the requirements of 1OCFR50Appendix G [3] and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel(B&PV) Code,Section XI, Non-mandatory Appendix G [4].2.0 METHODOLOGY A full set of P-T curves, applicable to the following plant conditions, are prepared:

1. Pressure Test (Curve A),2. Normal Operation

-Core Not Critical (Curve B), and3. Normal Operation

-Core Critical (Curve C).For each plant condition above, separate curves are provided for each of the following three regions ofthe RPV as well as a composite curve for the entire RPV:1. The beltline region,2. The bottom head region,3. The non-beltline region,4. Composite curve (bounding curve for all regions)In some cases, a region may contain more than one component which is considered for development ofthe associated P-T curve. For HINP-1, the curve for each vessel region identified above is composedfrom the bounding P-T limits determined for the following components:

1. Beltline:

a. Beltline shellb. Water level instrument (WLI) nozzle, N162. Non-beltline

a. Feedwater (FW) nozzleb. 10CFR50 Appendix G limits [3]3. Bottom Head:a. Bottom head penetrations (in-core monitor housings, control rod drive housings)

b. Core DP nozzleConsequently, separate curves are prepared for each component considered for each region then abounding curve is drawn from the individual curves.File No.: 1001527.304 Page 6 of 46Revision:

2F0306-01R1 Structural Integrity Associates,

/nc?Complete sets of P-T curves, as identified above, are provided for a 100 °F/hr and 200 °F/hr thermaltransient at 38 and 49.3 EFPY of operation.

The methodology for calculating P-T curves, described below, is taken from Reference

[1] unlessspecified otherwise.

Additional guidance regarding analysis of WLI nozzles is taken from Reference

[2].The P-T curves are calculated by means of an iterative procedure, in which the following steps areperformed:

Step 1: A fluid temperature, T, is assumed.

The P-T curves are calculated considering a postulated flaw with a 6:1 aspect ratio that extends '1/4 of the way through the vessel wall. The temperature at the postulated flaw tip is assumed equal to the coolant temperature.

Step 2: The static fracture toughness, K10, is computed using the following equation:

K1c 33.2 + 20.734 .e°°2(r-AT)

(1)Where: K10 = the lower bound static fracture toughness (ksi'lin).

T = the metal temperature at the tip of the postulated 1/4 through-wall flaw (0F).ART = the Adjusted Reference Temperature (ART) for the limitingmaterial in the RPV region under consideration

(°F).Step 3: The allowable stress intensity factor due to pressure, Kip, is calculated as:Kzp -(2)Where: K1ip the allowable stress intensity factor due to membrane(pressure) stress (ksi'Iin).

Ki0 the lower bound static fracture toughness calculated in Eq. (1)(ksi\Iin).

Kit the thermal stress intensity factor (ksi Win) from through wallthermal gradients.

SF =the ASME Code recommended safety factor, based on the reactorcondition.

For hydrostatic and leak test conditions (i.e., P-T CurveA), SF = 1.5. For normal operation, both core non-critical andcore critical (i.e., P-T Curves B and C), 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 rateof temperature change is 25°F/hr or less).File No.: 1001527.304 Page 7 of 46Revision:

2FO306-01R1 VStructural Integrity Associates, IncYFor Curve B and Curve C calculations, K1t is computed in different ways based on theevaluated region. For the beitline, with the exception of nozzles, and bottom head regions, Kitis determined using the following equation:

K1, =O0.953 x10-3**CR. t25 (3)Where: CR = the cooldown rate of the vessel (°F/hr).t= the RPV wall thickness (in).For the FW nozzle, K1t is obtained from the stress distribution output of a plant specific finiteelement analyses (FEA). A polynomial curve-fit is determined for the through-wall stressdistribution at the bounding time point. The linear elastic fracture mechanics (LEFM) solutionfor K1t is:K1 ,no0.06C,0.57 2 c1 0.48 +2 0.33 ~31(4Where: a =/1/4 through-wall postulated flaw depth, a = 1/4 t (in).t = thickness of the cross-section through the nozzle at the limitingpath near the inner blend radius (in).Cot,Clt,

= thermal stress polynomial coefficients, obtained from a curve-Czt,C3t fit of the extracted stresses from a transient FEA.The thermal stress polynomial coefficients are based on the assumed polynomial formofo'(x) =Co +C1.x +C2* x2 + C3*. x3.In this equation, "x" represents the radial distance ininches from the inside surface to any point on the crack face.For the WLI nozzle, the nozzle assembly consists of an insert attached to the RPV with apartial penetration weld. The nozzle material is not ferritic and does not need to be specifically evaluated.

However, the effect of the penetration on the adjacent shell must be considered.

Reference

[2, Equation 8-2] provides the following simplified solution for the thermal stressintensity factor due to a 1 00°F/hr thermal ramp transient:

Ki1-ramp

= 874,

+t.)-]-20.715 (5)Where: Ki-ramp = the K1t (thermal stress intensity factor from through wall thermalgradients) for a WLI nozzle subjected to 1 00°F/hr thermal transient (ksi\/in).

ct = the instrument nozzle material coefficient of thermal expansion atthe highest thermal ramp temperature (in/in/°F).

tv = the vessel thickness (in).tn = the nozzle thickness (in).File No.: 1001527.304 Page 8 of 46Revision:

2F0306-01RI VStructural Integrity Associates, IncYLarger heat-up/cool-down rates are conservatively considered by scaling the stress intensity factor obtained using Eq. (5) by the ratio of the desired heat-up/cool-down rate to 100 °F/hr.Since the P-T curves are applicable to all Level A/B events, the bounding Level A/B events,for each region and component, identified from the vessel and nozzle thermal cycle diagrams[7], are considered when calculating the Kit above.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 asfollows:Pallow -M m .R (6)Where: Pailow = the allowable RPV internal pressure (psig).Kip = the allowable stress intensity factor due to membrane(pressure) stress, as defined in Eq. (2) t = the RPV wall thickness (in).Mm = the membrane correction factor for an inside surface axial flaw:Mm =1.85 for /t< 2Mm = 0.926 "It for 2 <.It < 3.464Mm =3.21 for "It >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.K .tPolw= (7)SCF. Mm

• R,Where: SCF = conservative stress concentration factor to account for bottomhead penetration discontinuities; SCF = 3.0 per Reference

[1].Paiiow, K1p, t, Mm and Ri are defined in Eq. (6).The bottom head region methodology for calculating the allowable pressure shown in Eq. (7)above is applied for the thicker shell portion of the HNP-1 bottom head. It is noted that theCore DP nozzle at HNP-1 penetrates a section of the bottom head in which the shell is 3 3/16"thick. Use of Eq. (7) to treat the effect of the penetration would be excessively conservative.

Preliminary calculations showed that this approach produced a bottom head curve whichbounded the entire vessel. Consequently, the effect of the Core DP nozzle penetration isconsidered in a manner similar to the FW nozzle, as described below.File No.: 1001527.304 Page 9 of 46Revision:

2F0306-01R1 Structural Integrity Associates, Inc.PFor the FW nozzle the allowable pressure is determined from a ratio of the allowable andapplied stress intensity factors.

The applied factor can be determined from a FEA thatdetermines the stresses due to the internal pressure on the nozzle and RPV. The methodology for this approach is as follows:p K1p "refaltlow, -(8)Where: Pref = RPV internal pressure at which the FEA stress coefficients (Eq.(9)) are determined (psi).KIp-app --the applied pressure stress intensity factor Pallow and K1p are defined as in Eq. (6)..The applied pressure stress intensity factor is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from a FEA and the LEFMsolution given in Eq. (4):KIp.app=

-p 0.448/-i-12p

+ 0.393(- C~ 9Where: a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in).t = thickness of the cross-section through the limiting nozzle innerblend radius corner (in).C~,l,= pressure stress polynomial coefficients, obtained from a curve-C~,~ fit of the extracted stresses from a FEA.For the WLI nozzle, the nozzle .material is not ferritic and does not need to be specifically evaluated.

However, the effect of the penetration on the adjacent shell must be considered.

The allowable pressure is determined from the ratio of the allowable and applied stressintensity factors given in Equation

8. The applied stress intensity factor, for a 1000 psig loadcase, is calculated generically as follows [2, Equation 8-1]:KI Pressure

=2.9045IR tF.+ +/-t,, 1-4.434 (10)-L. ]"Where: KI-pressure

=generic Kip-app for the WLI nozzle (ksi'lin).

R = RPV nominal inside radius (in).tv and tn are described as in Eq. (5).The allowable pressure for the WLI nozzle is then calculated using Eq. (8), similar to the FWnozzle.File No.: 1001527.304 Page 10 of 46Revision:

2F0306-01IRI Structural Integrity Associates, Inc.*Step 5: Steps 1 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 1,300.psig. This value bounds expected pressures.

Step 6: Table 1 below summarizes the minimum temperature requirements contained in 10OCFR50, Appendix G [3, Table 1], which are applicable to the material highly stressed by the mainclosure flange bolt preload (non-beltline curve). SI also includes additional minimumtemperature requirements for bolt-up as shown in Table 1 below.Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves.Maximum of: ASME Appendix G [4]P<O P RTNDT,max, requirements A

• 60 0F [1],* TSDMP > 20% Ph RTNDT,max

+ 90 0FASEpeniG[4 requirements Maximum of: ASME Appendix G [4]*< %hRTNDT,max, requirements B

• 60 0F [1],* TSDM _______________

P> 20% Ph RTNDT, max + 120 0FASEpeniG[4 requirements Maximum of: ASME Appendix G [4]P<OhRTNDT, max + 60 0F, requirements

+ 40 °F* 60 0F [1],C

• TSDMMaximum of: ASME Appendix G [4]P > 20% Ph

• RTNDT, max + 160 0F, requirements

+ 40 0F* TISHT______________

___wnHere:t~h iS me pre-servlce nyUorotes

pressure, 1~on psigRTNBT,ma, is the maximum RTNoT of the vessel materials highly stressed by the bolt preload.TSDM is the temperature used in the shutdown margin evaluation Tlisfrr is the temperature at which the full in-service hydrotest pressure is allowed per Curve ANote that the minimum bolt-up temperature of 60°F, is used here, consistent with the positiongiven in Reference

[1]. Further, some utilities specifically request that the minimum moderator temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-uptemperature requirement; therefore, it is also included in Table 1 above. However, to address theNRC condition regarding lowest service temperature in Reference

[1 ], the minimum temperature is set to 76 0F, which is equal to the RTNDT, max + 60 0F. This value is consistent with theFile No.: 1001527.304 Revision:

2Page 11 of 46F0306-01IR1 V Structural Integrity Associates, Inc.'previous minimum temperature limits developed in [11], and is higher than the minimum bolt-uptemperature specified in [ 12].Step 7: Uncertainty in the RPV pressure and metal temperature measurements is incorporated byadjusting the P-T curve pressure and temperature using the following equations:

TpTr = T +UT (11)PP-r = -PH- UP (12)Where: Tp-T = The allowable coolant (metal) temperature (0F).UT = The coolant temperature instrument uncertainty (0F).PP-j = The allowable reactor pressure (psig).P11 = The pressure head to account for the water in the RPV (psig).Can be calculated from the following expression:

PIH= p"Ah.p = Water density at ambient temperature (lb/in3).Ah = Elevation of full height water level in RPV (in).Up = The pressure instrument uncertainty (psig).Steps 1 through 7, above, are implemented for all components, in all regions, for each heat-up/cool-down rate, and at all EFPY.3.0 " ASSUMPTIONS The 10OCFR5 0 Appendix G [3] and AsME Code [4] requirements and methods are considered to besupported in their respective technical basis documentation; therefore, the assumptions inherent in theASME B&PV Code methods utilized for this evaluation are not specifically identified and justified inthis calculation.

Only those assumptions specific to this calculation are identified and justified here.The following assumptions are used in preparation of the HNP- 1 P-T curves:.1. The bounding ART for the beltline materials is used in the calculation of the WLI nozzle curve.This assumption is conservative since the WLI nozzle is located near the upper limit of thebeltline region and the cumulative fluence at this location is substantially lower than for thebeitline location corresponding to the peak fluence.

Use of a fluence representative of thelocation in the beltline shell corresponding to the WLJ nozzle location would result in an ART,local to the WLI nozzle, which is lower than used in the present evaluation.

Since the fluence atthe WLI nozzle location is not specifically provided in the available fluence analysis

results, thepeak beltline value is used in this calculation.

Conservatism can be removed from the P-Tcurves by considering a WLI nozzle fluence in the ART calculation

[5], which would result in alower ART used in the WLI nozzle beltline curve.2. The full-vessel height is used in the calculation of the static head contributed by the coolant inthe RPV.This assumption is conservative in that the static head at the non-beltline regions is slightly lowerthan that of the bottom head curve; however, the difference in static head is small; therefore, theFile No.: 1001527.304 Page 12 of 46Revision:

2F0306-01RI Structural Integrity Associates, IncYadded complexity in considering different static head values for each region of the vessel is notconsidered beneficial.

3. The FW nozzle is the bounding non-beltline component of the RPV.This assumption is made because:a. The geometric discontinuity caused by the nozzle penetration in the RPV shell causes a stressconcentration which results in larger pressure induced stresses than would be calculated inthe shell regions of the RPV.b. The FW nozzle experiences more severe thermal transients than most of the other nozzlesbecause of the feedwater injection temperature which causes larger thermal stresses than areexperienced in the shell region of the RPV.c. Although some other nozzles can experience thermal transients, which Would cause thermalstresses larger than those calculated for the shell regions of the RPV, and some nozzles arelarger diameter than the FW nozzle, which could result in a slightly larger K1p, the combinedstresses from the applied thermal and pressure loads are considered to bound all other non-beltiline discontinuities.

4. Application of a SCF = 3.0 to the membrane pressure stress in the bottom head bounds the effectof the bottom head penetrations on the stress field in this region of the vessel.Bottom head penetrations will create geometric discontinuities into the bottom head hemisphere resulting in high localized stresses.

This effect must be considered in calculating the stressintensity factor from internal pressure.

Rather than performing a plant specific

analysis, SIapplies a conservative SCF for a circular hole in a flat plate subjected to a uniaxial load to themembrane stress in the shell caused by the internal pressure.

The assumption of SCF -- 3.0 isconservative because:a. It applies a peak SCF to the membrane stress which essentially, intensifies the stress throughthe entire shell thickness and along the entire crack face of the postulated flaw rather thanintensifying the stress local to the penetration and considering the stress attenuation awayfrom the penetration,

b. Review of SCFs for circular holes in plates subjected to an equi-bi-axial stress state as wellas SCFs for arrays of circular holes in shells, shows that the SCF is likely closer to 2-2.5rather than 3.0.Consequently, the method utilized by SI is expedient, as intended, and conservatively bounds theexpected effect of bottom head penetrations because a bounding SCF is used and applied as amembrane stress correction factor.5. ASME XI, Non-mandatory Appendix G, Paragraph G-22 14.3 [4] is used to calculate the thermalstress intensity factor for heat-up / cool-down rates greater than 100 °F/hr.The ASME Code [4] acknowledges that this methodology is conservative when applied to heat-up / cool-down rates greater than 100 0F/hr; therefore, the results obtained using this method forthe 200 0F/hr heat-up / cool-down rate are conservative.

Conservatism can be removed, ifFile No.: 1001527.304 Page 13 of 46Revision:

2F0306-01RI Structural

Integrit, Associates, Inc?necessary, by solving the thermo-elastic problem for the stresses in the vessel shell thencalculating the stress intensity factor using the plant specific stress distribution.

4.0DESIGN INPUTSThe design inputs, also included in Appendix A, used to develop the HNP-1 P-T curves are discussed below:1. Limiting RTNDT and ART [5]:Non-beltline:

Non-beltline:

Bottom Head:Beltline:

• 38 EFPY:49.3 EFPY:2. Shutdown Margin Temperature

[9]:3. RPV Dimensions*.[6]:

Full vessel height:RPV inside radius:RPV shell thickness:

Bottom head inside radius:Bottom head shell thickness:

4. Heat-up / Cool-down Rates [8]:5. Nozzle Stress Intensity Factors [1I0]:FW Nozzle:1 ksi Pressure:

100 °F/hr:200 °F/hr:450°F shock:WLI Nozzle:1 ksi Pressure:

100 °F/hr:200 °F/hr:40 *F (bounding value for non-belItline region, excluding bottom head)16 0F (bounding value for materials highly stressed by bolt preload)10 0F116.3 OF129.0 °F68 0F836.75 inches(Used to calculate maximum water head during pressure test andconservatively applied for normal operation as well)110.375 inches5.375 inches110.5 inches3.188 inches (in region with Core DP penetration) 6.813 inches (in region with CRD9 penetrations) 100 0F/hr200 0F/hr76.6 ksi-in°511.5 ksi-in°523.1 ksi-in°565.3 ksi-in°571.6 ksi-in0517.4 ksi-in0534.8 ksi-in05File No.: 1001527.304 Revision:

2Page 14 of 46F0306-01IRI Structural Integrity Associates, Inc.YCore DP Nozzle:1 ksi Pressure:

32.3 ksi-in°5100 °F/hr: 1.73 ksi-in°5200 °F/hr: 3.46 ksi-in°56. Design Pressure

[7]:, 1250 psig7. Pre-service Hydro-test pressure

[7]: 1563 psig(Taken as 1.25 *Design pressure

= 1563 psig)8. Instrument uncertainties

[8]:Pressure:

0 psigTemperature:

0*F5.0 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 Nuclear QA program.

Four cases areevaluated, corresponding to two EFPY values (38 and 49.3) and two cool-down rates (100 and 200°F/hr). P-T limits are calculated from 0 to 1300 psig. Supporting calculations for all curves areincluded in Appendix B.Because BWR operation is typically along the saturation curve, the limiting K1t for the FW nozzle isscaled to reflect the worst-case step change due to the available temperature difference between thesaturation temperature at a given pressure and the 100 0F feedwater temperature.

It is recognized that atlow temperatures, the available temperature difference is insignificant, which could result in a near zeroKit. Therefore, a minimum K1u is calculated for both the 1000F/hr and 2000F/hr cool-down rates; scalingof the non-beltline

/ feedwater nozzle Kit based on the available temperature difference is not allowedbelow the minimum Kit corresponding to the cool-down rate, being evaluated.

The composite P-T curves are extended below 0 psig to -14.7 psig based on the evaluation documented in Reference

[13], which demonstrates that the P-T curves are applicable to negative gauge pressures.

Since the P-T curve calculation methods used do not specifically apply to negative values of pressure, the tabulated results start at 0 psig. However, the minimum RPV pressure is -14.7 psig.5.1 Pressure Test (Curve A)The minimum bolt-up temperature of 760F minus instrument uncertainty (0°F) is applied to all regionsas the initial temperature in the iterative calculation process.

The static fracture toughness (Kit) iscalculated for all regions using Eq. (1). The resulting value of K1t, along with a safety factor ofl .5 isused in Eq. (2) to calculate the pressure stress intensity factor (K1p). The allowable RPV pressure iscalculated for the beltline, bottom head and Non-Beltline regions 'using Eq. (6, 7, and 8), as appropriate.

For the non-beltline region (feedwater nozzle / upper vessel),

the additional constraints specified in Step6 of Section 2.0 are applied.

Final P-T limits for temperature and pressure are obtained from Eq. (12and 13), respectively.

File No.: 1001527.304 Page 15 of 46Revision:

2F0306-01RI VStructural Integrity Associates, Inc.YSince the thermal stress intensity factor is taken as zero for Curve A, the cool-down rates do not affectthe results for Curve A.Values for the composite beltline region curves for 38 and 49.3 EFPY are listed in Table 2 and Table 3,respectively.

Additionally, more detailed data for the composite beltline are provided in Appendix B.Data for the composite bottom head region curve for all EFPY is listed in Table 4. Data for thecomposite non-beltline (feedwater nozzle / upper vessel) region curve, including the 10OCFR50Appendix G [4] limits, for all EFPY is listed in Table 5. The data for each region is graphed, and theresulting composite Curve A for 38 and 49.3 EFPY are provided in Figure 1 and Figure 2, respectively.

Additional data and curves for each region are included in Appendix B.5.2 Normal Operation

-Core Not Critical (Curve B)The minimum bolt-up temperature of 76°F minus coolant temperature instrument uncertainty (00F) isapplied to all regions as the initial temperature in the iterative calculation process.

The static fracturetoughness (Kic) is calculated for all regions using Eq. (1). The thermal stress intensity factor (K1t) iscalculated for the beltline plate and bottom head regions using Eq. (3), for the FW nozzle using Eq. (4),and for the WLI (N16) nozzle using Eq. (5).The resulting values of Kit and Kit, along with a safety factor of 2.0, are used in Eq. (2) to calculate thepressure stress intensity factor (K1p). The allowable RPV pressure is calculated for the beltline, bottomhead, and non-beltline regions using Eq. (6, 7, and 8), as appropriate.

For the non-beltline (FW nozzle /upper vessel) region, the additional constraints specified in Step 6 of Section 2.0 are applied.

Final P-Tlimits for temperature and pressure are obtained from Eq. (12 and 13), respectively.

The data resulting from each P-T curve calculation is tabulated.

Values for the composite beltlineregion with a 100°F/hr cool-down rate at 38 and 49.3 EFPY are listed in Table 6 and Table 7,respectively.

Values for the composite beltline region with a 200°F/hr cool-down rate at 38 and 49.3EFPY are listed in Table 8 and Table 9, respectively.

Data for the bottom head region with 1 00°F/hrand 200°F/hr cool-down rates are listed in Table 10 and Table 11, respectively.

Data for the FW nozzle/ upper vessel region with 100°F/hr and 200°F/hr cool-down rates are listed in Table 12 and Table 13,respectively.

The data for each region is graphed, and the resulting composite Curve B for 38 and 49.3EFPY with a 1O00F/hr cool-down rate are provided in Figure 3 and Figure 4, respectively.

The resulting composite Curve B for 38 and 49.3 EFPY with a 200°F/hr cool-down rate are provided in Figure 5 andFigure 6, respectively.

Additional data and curves for each region are included in Appendix B.File No.: 1001527.304 Page 16 of 46Revision:

2F0306-01R1 Structural.lIntegrity Associates, IncY5.3 Normal Operation

-Core Critical (Curve C)The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, withseveral exceptions.

The initial evaluation temperature is calculated as the limiting non-beltline RTNDTthat is highly stressed by the bolt preload (in this case, that of the closure flange region: 16 0F perSection 3.0) plus 60°F, resulting in a minimum critical temperature of 76 °F. When the pressureexceeds 20% of the system hydrostatic test pressure (20% of 1,563 psig =313 psig), the P-Tlimits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20%of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for thehydrostatic pressure test. The final Curve C values are taken as the absolute maximum between theregions of the beitline, the bottom head, and the non-beitline.

The data resulting from each P-T curve calculation is tabulated.

Values for the composite beltllneregion with a 100°F/hr cool-down rate at 38 and 49.3 EFPY are listed in Table 14 and Table 15,respectively.

Values for the composite beltline region with a 200°F/hr cool-down rate at 38 and 49.3EFPY are listed in Table 16 and Table 17, respectively.

Data for the bottom head region with 100°F/hrand 200°F/hr cool-down rates are listed in Table 18 and Table 19, respectively.

Data for the non-beltline (FW nozzle / upper vessel) region with 100°F/hr and 200°F/hr cool-down rates are listed inTable 20 and Table 21, respectively.

The data for each region is graphed, and the resulting composite Curve C for 38 and 49.3 EFPY with a 100°F/hr cool-down rate are provided in Figure 7 and Figure 8,respectively.

The resulting composite Curve C for 38 and 49.3 EFPY with a 200°F/hr cool-down rateare provided in Figure 9 and Figure 10, respectively.

Additional data and curves for each region areincluded in Appendix B.Note that the Beltline Region curves for the 200 0F/hr thermal transient at 38 and 49.3 EFPY shown inTables 16 and 17 and Figures 9 and 10 exhibit negative pressures at the lower end of the curve. This isnon-realistic and essentially indicates a higher minimum temperature for this region than for the otherregions of the RPV. Since these curves are not intended for normal operation and are intended only todisposition out-of-specification thermal transients these results do not pose any operational difficulties.

6.0 CONCLUSION

S P-T curves are developed for JINP-1 using the methodology, assumptions, and design inputs defined inSections 2.0, 3.0, and 4.0. P-T curves are developed for the beltline, bottom head, and non-beltline

regions, considering a 100 0F/hr and 200 *F/hr thermal transient at 38 and 49.3 EFPY, for the following plant conditions:

Pressure Test (Curve A), Normal Operation

-Core Not Critical (Curve B), and NormalOperation

-Core Critical (Curve C). Tabulated pressure and temperature values are provided for allregions and EFPYs in Tables 2 through 21. The accompanying P-T curve plots are provided in Figures1 through 10.File No.: 1001527.304 Page 17 of 46Revision:

2F0306-0 1RI VStructural Integrity Associates, Inc.Y

7.0 REFERENCES

1. Structural Integrity Associates Report No. SIR-05-044, Revision 1-A, "Pressure-Temperature LimitsReport Methodology for Boiling Water Reactors,"

June 2013, SI File No. GE-10Q-401.

2. Structural Integrity Associates Report No. 0900876.40 1, Revision 0-A, "Linear Elastic FractureMechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzlesfor Pressure-Temperature Curve Evaluations,"

May 2013.3. 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. 2008).4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix G, "Fracture Toughness Criteria for Protection Against Failure,"

2001 Edition including the 2003 Addenda.5. Structural Integrity Associates Calculation No. 1001527.301, Rev 1, "Hatch Unit 1 RPV MaterialSummary and ART Calculation."

6. General Electric Drawing No. E-234-270, Revision 3, "General Arrangement Elevation for: 218"I.D. BWR," SI File No. 100 1527.208.

7. General Electric Drawing No. I135B9990, "Nozzle Thermal Cycles (Feedwater),"

SI File1001527.211.

8. Design Input Requests:

a. DIR, Revision 2, "Revised P-T Curves for Plant Hatch Units 1&2," SI File No.1001527.201.

b. DIR, Revision 0, "Hatch Units 1 and 2 P-T Curve Revisions,"

SI File No. 1400365.200.

9. General Electric Document No. GE-NE-BI1 10069 1-01R1, "Plant Hatch Unit 1 RPV Surveillance Materials Testing and Analysis,"

March 1997, 51 File No. 1001527.202.

10. Structural Integrity Associates Calculation No. 1001527.303, Revision 1, "Feedwater, Water LevelInstrument, and Core DP Nozzle Fracture Mechanics Evaluation for Hatch Unit 1 and Unit 2Pressure-Temperature Limit Curve Development.

11. General Electric Document No. GE-NE-B1 100827-00-01, "Plant Hatch Units 1 & 2 RPV PressureTemperature Limits License Renewal Evaluation,"

March 1999, SI File No. 1400365.202.

12. NRC Docket No. 50-321, "Edwin I. Hatch Nuclear Plant Unit No. 1, Amendment to FacilityOperating License,"

Amendment No. 59, License No. DPR-57, ADAMS Accession No.ML0 12950436, SI File No. 1400365.202.

13. SI Calculation No. 1400365.30 1, Rev. 0, "Hatch RPV Vacuum Assessment."

File No.: 1001527.304 Page 18 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table 2: HNP-I Beltline Region, Curve A, for 38 EFPY°F psi76.0 0.076.0 365.298.8 415.1114.4 465.0126.3 514.9135.9 564.8144.0 614.7150.9 664.6157.0 714.5162.4 764.5167.3 814.4171.8 864.3175.8 914.2179.6 964.1183.1 1014.0186.4 1063.9189.5 1113.8192.4 1163.7195.2 1213.6197.8 1263.5200.2 1313.5202.6 1363.4File No.: 1001527.304 Page 19 of 46Revision:

2F0306-01RI Structural Integrity Associates, IncTable 3:HINP-1 Beltline Region, Curve A, for 49.3 EFPY.A 9. .-76.76.0103.3120.9133.9144.2152.7160.0166.4172.0177.1181.7185.9189.8193.4196.7199.9202.9205.7208.3210.8213.2psi0.0345.8394.5443.2491.9540.6589.3638.0686.6735.3784.0832.7881.4930.1978.81027.41076.11124.81173.51222.21270.91319.6File No.: 1001527.304 Revision:

2Page 20 of 46F0306-01 RI Structural Integrity Associates, lncYTable 4: HNP-1 Bottom Head Region, Curve A, for All EFPYOF psi76.0 0.076.0 1226.178.7 1274.281.2 1322.483.6 1370.5Table 5: HNP-Z Non-Beltline Region, Curve A, for All EFPYP-T Curve P-T CurveTemperature Pressure°F psi76.0 0.076.0 312.6106.0 312.,6106.0 934.2109.5 982.6112.7 1031.0115,7 1079.3118.6 1127.7121,3 1176.1123.9 1224.4126.3 1272.8128.6 1321.2File No.: 1001527.304 Page 21 of 46Revision:

2F0306-01RI

~jStructural Integrity Associates, Inc.YTable 6: HNP-1, Beitline Region, Curve B, for 38 EFPY and 100°F/hr Thermal Transient OF psi76.0 0.076.0 144.9104.2 193.8122.1 242.7135.2 291.6145.6 340.5154.2 389.4161.6 438.3168.0 487.2173.6 536.1178.7 585.0183.4 633.9187.6 682.8191.5 731.7195.1 780.6198.5 829.5201.6 878.4204.6 927.3207.4 976.2210.1 1025.1212.6 1074.0215.0 1122.9217.3 1171.8219.5 1220.7221.6 1269.6223.6 1318.5File No.: 1001527.304 Page 22 of 46Revision:

2F0306-01IRI Structural Integrity Associates, Inc.YTable 7: HNP-I, Beltline Region, Curve B, for 49.3 EFPY and 100°F/hr Thermal Transient

°F psi76.076.0110.3130.4144.7155.9164.9172.6179.3185.2190.4195.2199.5203.5207.2210.7213.9216.9219.8222.5225.1227.5229.8232.0234.2236.20.0130.4179.8229.2278.6328.0377.4426.8476.2525.6575.0624.4673.8723.2772.6822.0871.4920.8970.21019.61069.01118.41167.81217.21266.61316.0File No.: 1001527.304 Revision:

2Page 23 of 46F0306-01 RI Sj1~ tructural Integri~t Associates, IncYeTable 8: HNP-1, Beltline Region, Curve B, for 38 EFPY and 200°F/hr Thermal Transient

°F psi76.076.0104.5122.5135.8146.2154.8162.2168.6174.3179.4184.1188.3192.2195.8199.2202.4205.3208.2210.8213.3215.7218.0220.2222.3224.3226.3228.20.023.372.9122.6172.3222.0271.6321.3371.0420.6470.3520.0569.6619.3669.0718.6768.3818.0867.6917.3967.01016.61066.31116.01165.71215.31265.01314.7File No.: 1001527.304 Revision:

2Page 24 of 46F0306-01 RI Structural Integrity Associates,

/ncYTable 9: HNP-I, Beltline Region, Curve B, for 49.3 EFPY and 200°F/hr Thermal Transient

°F psi76.0 0.076.0 8.8109.9 57.3129.9 105.9144.1 154.5155.2 203.1164.2 251.6171.9 300.2178.6 348.8184.4 397.3189.7 445.9194.4 494.5198.8 543.0202.8 591.6206.5 640.2209.9 688.7213.1 737.3216.1 785.9219.0 834.5221.7 883.0224.3 931.6226.7 980.2229.0 1028.7231.2 1077.3233.4 1125.9235.4 1174.4237.4 1223.0239.2 1271.6241.1 1320.2File No.: 1001527.304 Page 25 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table 10: HNP-I Bottom Head Region, Curve B for All EFPY and 100°F/hr Thermal Transient

• a.e*

• U76.76.079.683.086.289.292.094.797.399.7102.0104.2psi0.0813.9863.8913.8963.71013.61063.61113.51163.51213.41263.31313.3File No.: 1001527.304 Revision:

2Page 26 of 46F0306-01 RI

~jjStructuraIiIntegrity Associates, IncYTable 11: HNP-1 Bottom Head Region, Curve B for All EFPY and 2000F/hr Thermal Transient

..- e u°F psi76.076.079.683.086.289.292.094.797.299.6101.9104.1106.2108.30.0715.7765.6815.4865.2915.1964.91014.81064.61114.41164.31214.11264.01313.8File No.: 1001527.304 Revision:

2Page 27 of 46F0306-01I R1 Structural Integrity Associates, IncTable 12:HINP-1 Non-Beltline Region, Curve B, for All EFPY and 100°F/hr Thermal Transient OF psi76.0 0.076.0 198.284.6 236.491.8 274.597.9 312.6136.0 312.6136.0 724.2139.0 773.5141.8 822.9144.4 872.2146.8 921.5149.2 970.9151.4 1020.2153.6 1069.6155.6 1118.9157.6 1168.3159.4 1217.6161.2 1266.9163.0 1316.3File No.: 1001527.304 Page 28 of 46Revision:

2F0306-01RI Structural Integrity Associates, lnc~eTable 13: HNP-I Non-Beltline Region, Curve B, for All EFPY and 20O°F/hr Thermal Transient

°F psi76.0 0.076.0 198.284.6 236.491.8 274.597.9 312.6136.0 312.6136.0 724.2139.0 773.5141.8 822.9144.4 872.2146.8 921.5149.2 970.9151.4 1020.2153.6 1069.6155.6 1118.9157.6 1168.3159.4 1217.6161.2 1266.9163.0 1316.3File No.: 1001527.304 Page 29 of 46Revision:

2F0306-01RI Structural Integrity Associates, Inc.eTable 14: HNP-1, Beitline Region, Curve C, for 38 EFPY and i00°F/hr Thermal Transient 976.76.0125,1149.3165.6177.9187.7195.9203.0209.1214.6219.6224.1228.2232.1235.6238.9242.0245.0247.7250.3252.8255.2257.5259.6261.7263.7psi0.0109.3157.8206.2254.7303.1351.6400.0448.5497.0545.4593.9642.3690.8739.2787.7836.1884.6933.1981.51030.01078.41126.91175.31223.81272.31320.7File No.: 1001527.304 Revision:

2Page 30 of 46F0306-01 RI

$j~tructural Integrity Associates, Inc.*Table 15: HNP-1, Beltline Region, Curve C, for 49.3 EFPY and 1000F/hr Thermal Transient OF psi76.076.0133.5159.6176.6189.3199.4207.8215.0221.3226.9231.9236.4240.6244.5248.1251.4254.5257.5260.3262.9265.4267.8270.1272.3274.3276.30.0102.8151.5200.1248.8297.5346.1394.8443.5492.2540.8589.5638.2686.9735.5784.2832.9881.6930.2978.91027.61076.31124.91173.61222.31271.01319.6File No.: 1001527.304 Revision:

2Page 31 of 46F0306-01R1 Structural Integrity Associates, Inc.eTable 16: HNP-1, Beltline Region, Curve C, for 38 EFPY and 200°F/hr Thermal Transient

°F psi76.0 0.076.0 -12.3125.6 36.9149.9 86.1166.3 135.4178.6 184.6188.4 233.8196.6 283.0203.7 332.3209.9 381.5215.4 430.7220.4 480.0224.9 529.2229.0 578.4232.8 627.6236.4 676.9239.7 726.1242.8 775.3245.7 824.6248.5 873.8251.1 923.0253.6 972.3256.0 1021.5258.2 1070.7260.4 1119.9262.5 1169.2264.5 1218.4266.4 1267.6268.2 1316.9NOTE: See the discussion in Section 5.3 regarding the negative pressure in this table.File No.: 1001527.304 Page 32 of 46Revision:

2F0306-01 RI Structural Integrity Associates, IncTable 17: HNP-1, Beitline Region, Curve C, for 49.3 EFPY and 2000F/hr Thermal Transient "F76.076.0134.0160.2177.3190.0200.1208.5215.7222.0227.6232.6237.2241.4245.2248.8252.2255.3258.3261.0263.7266.2268.6270.8273.0275.1277.1279.0280.9psi0.0-18.830.680.0129.4178.9228.3277.7327.2376.6426.0475.5524.9574.3623.8673.2722.6772.1821.5870.9920.4969.81019.21068.71118.11167.51217.01266.41315.8NOTE: See the discussion in Section 5.3 regarding the negative pressure in this table.File No.: 1001527.304 Revision:

2Page 33 of 46F0306-01RI Structural Integrity Associates,

/ncYeTable 18: HNP-1 Bottom Head Region, Curve C for All EFPY and 100°F/hr Thermal Transient 976.076.083.690.195.9101.1105.8110.1114.1117.8121.2124.4127.4130.2132.9135.4137.9140.2142.4144.5psi0.0450.5498.8547.2595.6643.9692.3740.7789.1837.4885.8934.2982.51030.91079.31127.71176.01224.41272.81321.1File No.: 1001527.304 Revision:

2Page 34 of 46F0306-01 R1 Structural Integrity Associates, lnc:Table 19: HNP-I Bottom Head Region, Curve C for All EFPY and 200°F/hr Thermal Transient e°F psi76.076.083.690.195.9101.1105.8110.2114.1117.8121.2124.4127.4130.3132.9135.5137.9140.2142.4144.6146.6148.50.0352.3400.7449.2497.6546.0594.4642.9691.3739.7788.1836.6885.0933.4981.91030.31078.71127.11175.61224.01272.41320.9File No.: 1001527.304 Revision:

2Page 35 of 46F0306-01 R1

~Structural Integrity Associates, Inc.*Table 20:tINP-1 Non-Beltline Region, Curve C, for All EFPY and 100°F/hr Thermal Transient

°F psi76.076.098.0112.1122.6130.9137.9217.0217.00.097.6140.6183.6226.6269.6312.6312.61563.0Table 21: HNP-1 Non-Beltline Region, Curve C, for All EFPY and 200°F/hr Thermal Transient

• F psi76.076.098.0112.1122.6130.9137.9217.0217.00.097.6140.6183.6226.6269.6312.6312.61563.0File No.: 1001527.304 Revision:

2Page 36 of 46F0306-01R 1

Structural Integrity Associates, Inc.'Curve A -Pressure Test, Composite Curves-Bei .... Bottom Head--- Non-Beltline 13001200110010009008004.E1150300200100I0Minimum Reactor Vessel Metal Temperature

(°F)Figure 1: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPYFile No.: 1001527.304 Revision:

2Page 37 of 46F0306-01R1 Structural Integrity Associates, Curve A -Pressure Test, Composite Curves-Beltline

---

Bottom Head -- -- Non-Beltline

-==,Overall 1300 -____I__I I110'- ____-I I _11o 800... I___ I -_t, I, I!,I'94 0 0 -I- --- ........

-.... ..... .... .. .......-... ..300 -~ -' -i!--!_ _ _ _+/- _ _ _ _200 1.......M inim um............

B olt-Up..

....-

........Teprtre=7 0100, -Minimm RIPrssr i-1. piFieN. 0052.0 Page 3=of 4Revison:F030-OII Structural Integrity Associates, Inc.Curve B -Core Not Critical, Composite Curves-Be...n --Bottom Head -- -Non-Beltline

-=,,Overall

-K....1300120011001000900* 8000.E-I 500El#.400300200100Minimum Reactor Vessel Metal Temperature (0F)Figure 3: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and IOO°F/hrFile No.: 1001527.304 Revision:

2Page 39 of 46F0306-01 RI VStructural Integrity Associates,/lnc.?

Curve B -Core Not Critical, Composite Curves-Beiti.e.---Bottom Head---- Non-Beltline m===Overall 130012001100900800700tE-1 500&- 4003002001000Minimum Reactor Vessel Metal Temperature

('F)Figure 4: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 1O00FfhrFile No.: 1001527.304 Revision:

2Page 40 of 46F0306-01 RI Structural Integrity Associates, lncYCurve B -Core Not Critical, Composite Curves-....n --Bottom Head --1 Non-Beitline

-==Overall 1300120011001000900a.*1ES500&" 40030001!;0 2(X)Minimum Reactor VesselI Metal Temperature

(*F)Figure 5: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 41 of 46F0306-01RI jjStructural Integrity Associates, IncYCurve B -Core Not Critical, Composite Curves-eilie-- -- Bottom Head -- -- Non-Beltline m===Ove rail1300120011001000900800 ....7010 *E-. 500Si3002001000Minimum Reactor Vessel Metal Temperature

(=F)Figure 6: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 42 of 46F0306-01IRI Structural Integrity Associates, IncYCurve C -Core Critical, Composite Curves-....ne --Bottom Head -- -- Non-Beitline

-.mmOverall 1300120011001O00900,6" 6003002001000Minimum Reactor Vessel Metal Temperature

(°F)Figure 7: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 10O°F/hrFigure 7: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 1000F/hrFile No.: 1001527.304 Revision:

2Page 43 of 46F0306-01R1 Structural Integrity Associates, Inc.YCurve C -Core Critical, Composite Curves-Bei....---Bottom Head -- -- Non-Beltline

-Overall13001200110010009000.gi70EA- 4o03002001000Minimum Reactor Vessel Metal Temperature

(@F)Figure 8: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 100°F/hrFile No.: 1001527.304 Revision:

2Page 44 of 46F0306-01RI Structural Integrity Associates, Inc.YCurve C -Core Critical, Composite Curves-....ne -- Bottom Head -- -- Non-Beitline i,,,,,Overall 130012001110010001900OMinimum Bolt-Temperature

=7Minimum BeltliTemperature

= 5Minimum RP\Pressure

= -14.7a.SE-,Sg800700op l ! anI!940FI __ aI aVe Ipsig jiaaaIIaIaIIIIIIII I* i /I A, Iiii,iiii'i, .../600400-.. ......300200100 ,0520025030o+/-_Minimum Reactor Vessel Metal Temperature (0F)Figure 9: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 200°F/hrFile No.: 1001527.304 Revision:

2Page 45 of 46F0306-01RI Structural Integrity Associates, IncYeCurve C -Core Critical, Composite Curves-Bei..ne---Bottom Head -- -- Non-Beitline

-Overall1300120011001000900J 6004..E"1 500&" 4003002001000Minimum Reactor Vessel Metal Temperature

('F)Figure I0: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 20O°F/hrFigure 10: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 2000F/hrFile No.: 1001527.304 Revision:

2Page 46 of 46F0306-01I RI Structural Integrity Associates, Inc5APPENDIX A:P -T CURVE INPUT LISTINGFile No.: 1001527.304 Revision:

2Page A-i1 of A-3F0306-01 RI jjStructural Integrity Associates, Inc~eTable A-i: HINP-I Stress Intensity Factors for Feedwater and WLI Nozzles 1131Feedwater 76.6 65.3 11.5 23.1WLI 71.6 N/A 17.4 34.8Core DP 32.3 N/A 1.7 3.5Notes:1. K1 in units of ksi-in0s2. 200 "F/hr results are scaled from 100 "F/hr assuming response is linearTable A-2: HNP-I P-T Curve Input ListingGeneral Parameters English Unit System for Tables and Plots0 Temperature Instrument Uncertainty Adjustment

(°F)0 Pressure Instrument Uncertainty Adjustment (psig)62.4 Water Density (lbm/ft3)836.75 Full-Vessel Water Height (in)1.5 Safety Factor for Curve A2 Safety Factor for Curves B and C76 Bolt-up Temperature

(°F)16 ART of Closure Flange Region (°F)10 Default Temperature Increment for Tables (0F)50 Default Pressure Increment for Composite Tables (psig)Beltline Parameters 116.3 Adjusted Reference Temperature, 38 EFPY (°F)129.0 Adjusted Reference Temperature, 49.3 EFPY (0F)110.375 Vessel Radius (in)5.375 Vessel Thickness (in)100 Heat-up / Cool-down Rate (°F/hr)200 Heat-up / Cool-down Rate (°F/hr)Generic Type of Static Pressure Head AdditionN/A Specific Water Height for Static Pressure Head Addition (in)Generic Type of Temperature Increment for Tables5 Specific Temperature Increment for Tables (°F)File No.: 100 1527.304 Page A-2 of A-3Revision:

2F0306-01RI Structural Integrity Associates,

/nc*P- uv nputsInstrument Nozzle Parameters 116.3 Adjusted Reference Temperature, 38 EFPY (OF)129.0 Adjusted Reference Temperature, 49.3 EFPY ('F)110.375 Vessel Radius (in)5.375 Vessel Thickness (in)See Table Applied Pressure Stress Intensity Factor (ksi*in^0.5)

A-i Applied Thermal Stress Intensity Factor (ksi*in^0.5) 7.70E-06 Coefficient of Thermal Expansion (in!/in/'F) 1000 Reference Pressure (psig)Generic Type of Static Pressure Head AdditionN/A Specific Water Height for Static Pressure Head Addition (in)Generic Type of Temperature Increment for Tables5 Specific Temperature Increment for Tables (*F)Bottom Heai10110.56.81251002003GenericN/AGeneric5Non-Beltline 40See TableA-iYes1005501000GenericN/AGeneric5d Parameters Adjusted Reference Temperature

(°F)Vessel Radius (in)Vessel Thickness (in)Heat-up / Cool-down Rate (°F/hr)Heat-up / Cool-down Rate (°F/hr)Stress Concentration FactorType of Static Pressure Head AdditionSpecific Water Height for Static Pressure Head Addition (in)Type of Temperature Increment for TablesSpecific Temperature Increment for Tables (°F)(Feedwater Nozzle) Parameters Adjusted Reference Temperature

(°F)Applied Pressure Stress Intensity Factor (ksi* in^0.5)Applied Thermal Stress Intensity Factor (ksi*in^0.5)

Minimum Thermal Stress Intensity Factor (ksi*in^0.5)

Scale KIT based on Saturation Temperature?

Minimum Transient Temperature

(°F)Maximum Transient Temperature

(*F)Reference Pressure for Thermal Transient (psig)Type of Static Pressure Head AdditionSpecific Water Height for Static Pressure Head Addition (in)Type of Temperature Increment for TablesSpecific Temperature Increment for Tables (°F)File No.: 1001527.304 Revision:

2Page A-3 of A-3F0306-01RI jjStructural Integrity Associates, Inc.*APPENDIX B:SUPPORTING CALCULATIONS File No.: 1001527.304 Revision:

2Page B-I of B-43F0306-01RI

~jStructoral Integrity Associates, Inc.*Table B-I: HNP-1, Beltline Region, Curve A Calculations, for 38 EFPY-A

• I°ksi*in^0.5

°ksi*inAO.5

-IFps'76.076.086.096.0106.0116.0126.0136.0146.0156.0166.042.542,544.547.050.153.858.463.970.879.189.228.328.329.731.333.435.938.942.647.252.759.576.076.086.096.0106.0116.0126.0136.0146.0156.0166.00.0611.9642.9680.8727.0783.5852.5936.81039.71165.51319.0File No.: 1001527.304 Revision:

2Page B-2 of B-43F0306-01R I

Structural Integrity Associates, Inc.tTable B-2: HNP-1, WLI (N16) Nozzle Beltline Region, Curve A Calculations, for 38 EFPY-A U -- -ksiifl^O.5

-IFpsi76.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.042.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.928.328.329.731.333.435.938.942.647.252.759.567.877.990.2105.376.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.00.0365.2384.3407.6436.1470.9513.4565.3628.7706.1800.6916.21057.21229.51440.0File No.: 1001527.304 Revision:

2Page B-3 of B-43F0306-0tRI Structural Integrity Associates, Inc.YTable B-3: HNP-1, Beitline Region, Curve A Calculations, for 49.3 EFPY-A U -Gageiiiii Fl idiiiTemprtr°ksi*inAO.5

°ksi*inAO.5 P- Crvpsi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.926.926.927.428.028.629.330.030.931.832.833.935.236.538.039.741.643.645.948.351.154.257.561.276.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.00.0580.5591.9604.5618.5633.9650.9669.8690.6713.6739.0767.1798.2832.5870.4912.4958.71009.91066.51129.01198.11274.51358.9File No.: 1001527.304 Page B-4 of B-43Revision:

2F0306-01RI Structural Integrity Associates, Inc.Table B-4: HNP-I, WLI (N16) Nozzle Beitline Region, Curve A Calculations, for 49.3 EFPY-A F --°F psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.326.926.927.428.028.629.330.030.931.832.833.935.236.538.039.741.643.645.948.351.154.2,57.561.265.469.974.980.586.693.4100.976.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.00.0345.8352.9360.7369.2378.7389.2400.8413.7427.8443.5460.8479.9501.0524.4550.2578.7610.3645.1683.6726.2773.2825.2882.7946.21016.31093.91179.61274.31379.0File No.: 1001527.304 Revision:

2Page B-5 of B-43F0306-01 RI Structural Integrity Associates, Inc.*Table B-5: HNP-1, Bottom Head Region, Curve A Calculations, All EFPYA .-°ksi *inA0.5 °ksi*inA0.5 psi76.0 110.8 73.9 76.0 0.076.0 110.8 73.9 76.0 1226.181.0 119.0 79.3 81.0 1318.686.0 128.0 85.3 86.0 1420.9File No.: 1001527.304 Revision:

2Page B-6 of B-43F0306-01RI j§StructuraI Integrity Associates, Inc.eTable B-6: HNP-I, FW Nozzle / Non-Beitline, Curve A Calculations, All EFPY76.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0°ksi*inA0.5 75.875.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7°ksi*inA0.5 50.550.552.955.558.261.264.568.071.876.080.585.390.696.3102.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0psi0.0629.5660.3693.8730.0769.3811.8857.9907.8961.81020.41083.81152.51227.01307.6File No.: 1001527.304 Page B-7 of B-43Revision:

2F0306-01RI Structural Integrity Associates, Inc.?Table B-7: HNP-1, Beitline Region, Curve B Calculations, for 38 EFPY and 100°F/hr ThermalTransient

..* a a76.76.076.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0°ksi*inA0.5 42.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3°ksi*inAO.5 18.018.019.120.321.823.726.028.832.236.341.447.655.264.476.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0psi0.0379.0402.2430.6465.3507.7559.4622.6699.9794.2909.31050.01221.81431.7File No.: 1001527.304 Revision:

2Page B-8 of B-43F0306-01IRI Structural Integrity Associates,

/nc.YTable B-8: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 38 EFPY and100°F/hr Thermal Transient

• SS *- 9 D°F ksi*inA0.5

°ksi*inAO.5 psi76.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.042.542.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.9185.5219.212.512.513.614.816.318.220.523.326.730.835.942.149.758.970.284.1100.976.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.00.0144.9159.2176.7198.1224.2256.0295.0342.5400.6471.5558.1663.9793.2951.01143.81379.3File No.: 1001527.304 Revision:

2Page B-9 of B-43F0306-01RI Structural Integrity Associates, IncYtTable B-9: HNP-I, Beltline Region, Curve B Calculations, for 49.3 EFPY and 100°F/hr ThermalTransient

..* .UGage fluid P-T Curve P-T CurveTemperature K1Temperature Pressure°F °ksi*in^0.5

°ksi*in^0.5 76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.917.017.017.417.818.318.819.320.020.621.422.223.224.225.326.628.029.531.233.135.137.439.942.745.849.253.057.261.876.76.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0psi0.0355.4364.0373.4383.9395.5408.3422.4438.0455.3474.3495.4518.7544.4572.9604.3639.1677.5719.9766.8818.6875.9939.21009.21086.51172.01266.51370.8File No.: 1001527.304 Revision:

2Page B-1l0 of B-43F0306-01RI Structural Integrity Associates, Inc.~Table B-I0: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 49.3 EFPY and100°F/hr Thermal Transient

-Sp **

• e-ksi~in^O.5 "ksi~inAO.5 psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.3163.8177.5192.7209.411.511.511.912.312.813.313.814.515.115.916.717.718.719.821.122.524.025.727.629.631.934.437.240.343.747.551.756.361.467.073.280.087.696.076.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.00.0130.4135.7141.5148.0155.1163.0171.6181.3191.9203.6216.6231.0246.8264.3283.7305.1328.7354.9383.7415.7450.9489.9533.0580.6633.3691.4755.7826.7905.3992.01087.91193.91311.0File No.: 1001527.304 Revision:

2Page B- 11 of B-43F0306-01RI Structural Integrity Associates, Inc.YTable B-Il: HNP-I, Bottom Head Region, Curve B Calculations, for All EFPY and 100°F/hrThermal Transient

• e. e U-/-°ksi*inAO.5

°ksi*in^0.5 "1-psi76.076.081.086.091.096.0101.0106.0110.8110.8119.0128.0138.0149.0161.2174.649.649.653.758.263.268.774.881.576.076.081.086.091.096.0101.0106.00.0813.9883.3960.01044.81138.41242.01356.4File No.: 1001527.304 Revision:

2Page B-12 of B-43F0306-01RI Structural Integrity Associates, lnc.*Table B-12: HNP-I, FW Nozzle / Non-Beitline, Curve B Calculations, for All EFPY and 100°F/hrThermal Transient

... 9 F°ksi*inAO.5

°ksi*inAO.5

°F psi76.076,080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.075.875.879.383.287.491.996.7102.0107.8114.0120,7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.832.117.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.00.0198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-13 of B-43F0306-01RI Structural Integrity Associates,

/InCYTable B-13: HNP-I, Beltline Region, Curve B Calculations, for 38 EFPY and 200°Ffhr ThermalTransient

• SS *~ 9Gage Fluid P-T curve P-T CurveTemperature Temperature Pressure°F ksi*inAO.5 76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.042.542.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3°ksi*inA0.5 14.814.815.315.916.517.117.918.719.520.521.622.824.125.627.229.031.033.235.638.241.244.448.052.056.461.3"F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0psi0.0306.6317.6329.8343.3358.2374.7392.9413.0435.3459.9487.0517.1550.3586.9627.5672.3721.8776.5836.9903.8977.61059.21149.41249.11359.3File No.: 100 1527.304Revision:

2Page B-14 of B-43F0306-01 RI1 Structural Integrity Associates, IncYTable B-14: HNP-I, WLI (N16) Nozzle Beitline Region, Curve B Calculations, for 38 EFPY and2000F/hr Thermal Transient

.e* e F°F ksi*in^0.5

°ksi*inA0.5 0Fpsi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.042.542.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3146.0157.9171.0185.5201.5219.2238.83.83.84.34.95.56.16.87.68.59.510.611.813.114.616.218.020.022.124.527.230.233.437.041.045.450.255.661.568.175.383.492.2102.076.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.00.023.330.137.645.955.165.276.488.8102.5117.7134.4152.9173.3195.9220.9248.4278.9312.6349.8391.0436.5486.7542.3603.6671.5746.4829.3920.91022.11133.91257.51394.1File No.: 100 1527.304Revision:

2Page B-15 of B-43F0306-01R1 Structural Integrity Associates, Inc,Table B-15: HNP-I, Beltline Region, Curve B Calculations, for 49.3 EFPY and 2000F/hr ThermalTransient

• a9 e*

• FGage Fluid P-T Curve P-T CurveTemperature K11Temperature Pressure°F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0°ksi*inA0.5 40.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1°ksi*in^0.5 13.813.814.214.615.115.616.116.817.418.219.120.021.022.123.424.826.328.029.931.934.236.839.542.646.049.854.058.663.776.76.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0psi0.0283.0291.6301.0311.5323.1335.9350.0365.6382.9401.9423.0446.3472.0500.5531.9566.7605.1647.5694.4746.2803.5866.8936.81014.21099.61194.11298.51413.8File No.: 1001527.304 Revision:

2Page B-16 of B-43F0306-01RI Structural Integrity Associates, IncYeTable B-16: HNP-I, WLI (N16) Nozzle Beltline Region, Curve B Calculations, for 49.3 EFPY and200°F/hr Thermal Transient

..- 9 93=°ksi*inA0.5 "ksi*inAO.5 psi76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.040.440.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.1151.3163.8177.5192.7209.4228.02.82.83.23.64.04.65.15.76.47.28.09.010.011.112.413.815.317.018.920.923.225.728.531.635.038.843.047.652.658.364.571.378.987.396.676.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.00.08.814.119.926.333.441.350.059.670.382.095.0109.3125.2142.7162.0183.4207.1233.2262.1294.0329.3368.3411.3459.0511.6569.7634.0705.0783.5870.3966.21072.11189.21318.7File No.: 1001527.304 Revision:

2Page B- 17 of B-43F0306-01 R1 Structural Integrity Associates, Inc.Table B-17: HNP-1, Bottom Head Region, Curve B Calculations, for All EFPY and 200°F/hrThermal Transient a **

• UGage FluId P-T Curve P-T CurveTemperature Temperature Pressure76.76.081.086.091.096.0101.0106.0111.0°ksi*inAO.5 110.8110.8119.0128.0138.0149.0161.2174.6189.5°ksi*inAO.5 43.943.947.952.557.463.069.075.883.276.76.081.086.091.096.0101.0106.0111.0psi0.0715.7785.1861.8946.61040.31143.81258.31384.7File No.: 1001527.304 Revision:

2Page B-I18 of B-43F0306-01RI j7Structural Integrity Associates,

/nc,5Table B-18: HNP-I, FW Nozzle / Non-Beltline, Curve B Calculations, for All EFPY and 200°F/hrThermal Transient

.e* 9 U°F ksi*in^0.5

°ksi*inA0.5 psi76.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.075.875.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.826.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.00.0198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B- 19 of B-43F0306-01Rt Structural Integrity Associates, IncTable B-19: HNP-I, Beltline Region, Curve C Calculations, for 38 EFPY and 100°F/hr ThermalTransient O°ksi*inA0.5

°ksi*inAO.5

°Fpsi36.0 37.4 15.5 76.0 0.036.0 37.4 15.5 76.0 321.146.0 38.3 15.9 86.0 331.656.0 39.4 16.5 96.0 344.366.0 40.8 17.2 106.0 359.976.0 42.5 18.0 116.0 379.086.0 44.5 19.1 126.0 402.296.0 47.0 20.3 136.0 430.6106.0 50.1 21.8 146.0 465.3116.0 53.8 23.7 156.0 507.7126.0 58.4 26.0 166.0 559.4136.0 63.9 28.8 176.0 622.6146.0 70.8 32.2 186.0 699.9156.0 79.1 36.3 196.0 794.2166.0 89.2 41.4 206.0 909.3176.0 101.6 47.6 216.0 1050.0186.0 116.8 55.2 226.0 1221.8196.0 135.3 64.4 236.0 1431.7File No.: 1001527.304 Page B-20 of B-43Revision:

2F0306-01 RI Structural Integrity Associates, Inc.YTable B-20: HNP-I, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 38 EFPY and100°F/hr Thermal Transient Gage Fluid P-T Curve P-T CurveTemperature Temperature Pressure36.36.046.056.066.076.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.0°ksi*inAO.5 37.437.438.339.440.842.544.547.050.153.858.463.970.879.189.2101.6116.8135.3157.9185.5219.2°ksi*inA0.5 10.010.010.411.011.712.513.614.816.318.220.523.326.730.835.942.149.758.970.284.1100.976.76.086.096.0106.0116.0126.0136.0146.0156.0166.0176.0186.0196.0206.0216.0226.0236.0246.0256.0266.0psi0.0109.3115.7123.6133.2144.9159.2176.7198.1224.2256.0295.0342.5400.6471.5558.1663.9793.2951.01143.81379.3File No.: 1001527.304 Revision:

2Page B-21 of B-43F0306-01RI S~tructural Integrity Associates, IncYeTable B-21:. HNP-I, Beltline Region, Curve C Calculations, for 49.3 EFPY and 100°F/hr ThermalTransient 36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0°ksi*inA0.5 36.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9°ksi*inAO.5 15.015.015.215.415.615.816.116.316.717.017.417.818.318.819.320.020.621.422.223.224.225.326.628.029.531.233.135.137.439.942.745.849.253.057.261.8°F76.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0psi0.0310.5314.4318.6323.3328.5334.3340.6347.7355.4364.0373.4383.9395.5408.3422.4438.0455.3474.3495.4518.7544.4572.9604.3639.1677.5719.9766.8818.6875.9939.21009.21086.51172.01266.51370.8File No.: 1001527.304 Revision:

2Page B-22 of B-43F0306-01R 1

Structural Integrity Associates, Inc:Table B-22: HNP-I, WLI (NI6) Nozzle Beitline Region, Curve C Calculations, for 49.3 EFPY and1O00F/hr Thermal Transient "F"ksi'inA0.5 "ksi'inA0.5 "Fpsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.19.59.59.79.910.110.310.610.811.211.511.912.312.813.313.814.515.115.916.717.718.719.821.122.524.025.727.629.631.934.437.240.343.747.551.756.361.476.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0102.8105.1107.8110.7113.9117.4121.3125.6130.4135.7141.5148.0155.1163.0171.6181.3191.9203.6216.6231.0246.8264.3283.7305.1328.7354.9383.7415.7450.9489.9533.0580.6633.3691.4755.7826.7File No.: 1001527.304 Revision:

2Page B-23 of B-43F0306-01 RI j§Structural Integrity Associates, Inc:~216.0221.0226.0231.0236.0151.3163.8177.5192.7209.467.073.280.087.696.0256.0261.0266.0271.0276.0905.3992.01087.91193.91311.0Table B-23:HNP-I, Bottom Head Region, Curve C Calculations, for All EFPY and 100°F/hrThermal Transient Temperature II*F °ksi*inA0.5 36.0 68.136.0 68.141.0 71.746.0 75.851.0 80.356.0 85.261.0 90.766.0 96.771.0 103.476.0 110.881.0 119.086.0 128.091.0 138.096.0 149.0101.0 161.2106.0 174.6::Temperature Pesr°ksi*inAO.5 OF psi28.3 76.0 0.028.3 76.0 450.530.1 81.0 481.632.1 86.0 516.134.4 91.0 554.236.8 96.0 596.339.6 101.0 642.842.6 106.0 694.245.9 111.0 751.149.6 116.0 813.953.7 121.0 883.358.2 126.0 960.063.2 131.0 1044.868.7 136.0 1138.474.8 141.0 1242.081.5 146.0 1356.4File No.: 1001527.304 Revision:

2Page B-24 of B-43F0306-01R 1

Structural Integrity Associates,/Inc.:

Table B-24: HNP-1, FW Nozzle / Non-Beltline, Curve C Calculations, for All EFPY and 100°F/hrThermal Transient e36.36.040.044.048.052.056.060.064.068.072.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0°ksi*inAO.5 52.352.353.955.757.559.661.864.166.769.572.575.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.8°ksi*inA0.5 psi20.49.810.310.811.412.012.713.514.315.316.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0168.0172.0176.0180.0184.0188.0192.0196.0200.0204.00.097.6103.8110.6118.1126.5135.7145.8157.1169.5183.1198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-25 of B-43F0306-01RI Structural

Integrit, Associates, Inc."Table B-25: HNP-I, Beitline Region, Curve C Calculations, for 38 EFPY and 200°F/hr ThermalTransient

-9. D°ksi*inA0.5

°ksi*inAO.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.037.437.437.838.338.839.440.140.841.642.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.312.312.312.512.813.013.313.614.014.414.815.315.916.517.117.918.719.520.521.622.824.125.627.229.031.033.235.638.241.244.448.052.056.461.376.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.00.0248.7253.7259.2265.2271.9279.3287.5296.6306.6317.6329.8343.3358.2374.7392.9413.0435.3459.9487.0517.1550.3586.9627.5672.3721.8776.5836.9903.8977.61059.21149.41249.11359.3File No.: 1001527.304 Revision:

2Page B-26 of B-43F0306-01IRI Structural Integrity Associates, Inc.:Table B-26: HNP-1, WLI (N16) Nozzle Beltline Region, Curve C Calculations, for 38 EFPY and2000F/hr Thermal Transient GaeFli°ksi*inAO.5 "ksi*in^0.5 P-T CurveTemperature "FP-T CurvePressurepsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.037.437.437.838.338.839.440.140.841.642.543.444.545.747.048.550.151.853.856.058.461.063.967.270.874.779.183.989.295.1101.6108.8116.8125.6135.3146.0157.9171.01.31.31.51.72.02.32.63.03.43.84.34.95.56.16.87.68.59.510.611.813.114.616.218.020.022.124.527.230.233.437.041.045.450.255.661.568.176.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0-12.3-9.3-5.9-2.22.06.511.617.123.330.137.645.955.165.276.488.8102.5117.7134.4152.9173.3195.9220.9248.4278.9312.6349.8391.0436.5486.7542.3603.6671.5746.4829.3920.9File No.: 1001527.304 Revision:

2Page B-27 of B-43F0306-01 RI Structural Integrity Associates, Inc.e216.0221.0226.0231.0185.5201.5219.2238.875.383.492.2102.0256.0261.0266.0271.01022.11133.91257.51394.1File No.: 1001527.304 Revision:

2Page B-28 of B-43F0306-01R1 Structural Integrity Associates, InC*:Table B-27: HNP-I, Beltline Region, Curve C Calculations, for 49.3 EFPY and 200°F/hr ThermalTransient

e. 9°F oksi*inAO.5

°ksi*inA0.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140,111.811.812.012.212.412.612.913.213.513.814.214.615.115.616.116.817.418.219.120.021.022.123.424.826.328.029.931.934.236.839.542.646.049.854.058.663.776.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0238.1242.0246.2251.0256.1261.9268.2275.3283.0291.6301.0311.5323.1335.9350.0365.6382.9401.9423.0446.3472.0500.5531.9566.7605.1647.5694.4746.2803.5866.8936.81014.21099.61194.11298.51413.8File No.: 100 1527.304Revision:

2Page B-29 of B-43F030-01R 1

Structural Integrity Associates, IncYTable B-28: HNP-1, WLI (N16) Nozzle Beitline Region, Curve C Calculations, for 49.3 EFPY and200°F/hr Thermal Transient Temprtr°ksi*inA0.5

°ksi~inA0.5 P °FCrvP-T CurvePressurepsi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.036.436.436.837.137.638.038.539.139.740.441.142.042.943.945.046.347.749.250.952.754.857.059.662.365.468.872.576.781.286.391.998.0104.8112.4120.7129.9140.10.80.81.01.21.41.61.92.12.42.83.23.64.04.65.15.76.47.28.09.010.012.413.815.317.018.920.923.225.728.531.635.038.843.047.652.676.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.0156.0161.0166.0171.0176.0181.0186.0191.0196.0201.0206.0211.0216.0221.0226.0231.0236.0241.0246.0251.00.0-18.8-16.5-13.9-11.0-7.8-4.2-0.34.08.814.119.926.333.441.350.059.670.382.095.0109.3125.2142.7162.0183.4207.1233.2262.1294.0329.3368.3411.3459.0511.6569.7634.0705.0File No.: 100 1527.304Revision:

2Page B-30 of B-43F0306-01RI Structural Integrity Associates, IncYe216.0221.0226.0231.0236.0241.0151.3163.8177.5192.7209.4228.058.364.571.378.987.396.6256.0261.0266.0271.0276.0281.0783.5870.3966.21072.11189.21318.7File No.: 1001527.304 Revision:

2Page B-31I of B-43F0306-01 R1 S~tructural Integrity Associates, Inc.tTable B-29: HNP-1, Bottom Head Region, Curve C Calculations, for All EFPY and 200°F/hrThermal Transient 9OF ksi*in^0.5

°ksi*in^0.5 psi36.036.041.046.051.056.061.066.071.076.081.086.091.096.0101.0106.0111.068.168.171.775.880.385.290.796.7103.4110.8119.0128.0138.0149.0161.2174.6189.522.522.524.326.428.631.133.836.840.243.947.952.557.463.069.075.883.276.076.081.086.091.096.0101.0106.0111.0116.0121.0126.0131.0136.0141.0146.0151.00.0352.3383.5418.0456.0498.1544.7596.1652.9715.7785.1861.8946.61040.31143.81258.31384.7File No.: 1001527.304 Revision:

2Page B-32 of B-43F0306-01RI Structural Integrity Associates, lnc.YTable B-30: HNP-1, FW Nozzle / Non-Beitline, Curve C Calculations, for All EFPY and 2000F/hrThermal Transient

-.- 9°F ksi*inAO.5

°ksi*inA0.5 psi36.036.040.044.048.052.056.060.064.068.072.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.052.352.353.955.757.559.661.864.166.769.572.575.879.383.287.491.996.7102.0107.8114.0120.7128.0135.9144.4153.7163.8174.6186.4199.2213.0228.0244.2261.8280.814.69.810.310.811.412.012.713.514.315.316.317.518.820.221.723.425.327.429.732.234.937.941.244.848.753.157.862.968.674.781.588.896.8105.576.076.080.084.088.092.096.0100.0104.0108.0112.0116.0120.0124.0128.0132.0136.0140.0144.0148.0152.0156.0160.0164.0168.0172.0176.0180.0184.0188.0192.0196.0200.0204.00.097.6103.8110.6118.1126.5135.7145.8157.1169.5183.1198.2214.9233.3253.5275.8300.3327.3356.9389.5425.2464.4507.4554.5606.0662.4724.1791.4865.0945.41033.11128.81233.11346.7File No.: 1001527.304 Revision:

2Page B-33 of B-43F0306-01RI jjStructural Integrity Associates, Inc.Curve A -Pressure Test, All Components

-BL ....-N16 -- -- BH -.-FWN -* OCFR50 ....CDPN1300120011001000900hiu 0*140030020010000-I ____ ________

________

_______100 150 200 250Minimum Reactor Vessel Metal Temperature

(*F)50300Figure B-I: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 38 EFPYNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-34 of B-43F0306-01R I

Structural Integrity Associates, Inc.YCurve A -Pressure Test, All Components

-BL .... N16 --BH -- --FWN 10CFR50 ....CDPN1300120011001000900.~800p70'UlUIE 0iU-4003002001000050 100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-2: HNP-1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 49.3 EFPYNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-35 of B-43F0306-01RI Structural Integrity Associates, lncYCurve B -Core Not Critical, All Components

-BL .... N16 --- BH --.-FWN -. 1OCFR50O....CDPN 1300120011001000{906Il6006Il500SI4003002001000 50}100 150Minimum Reactor Vessel Metal Temperature

(°F)200250Figure B-3: HNP-I P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 100OF/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-36 of B-43F0306-01R1 Structural Integrity Associates, Inc.YCurve B -Core Not Critical, All Components

-BL ....-N16 --- BH -- -FWN -- 10CFRSO0....CDPN 1300- __1200 ~--11001000 ...900I=ED300 +200- _-1000o0 50100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-4:HINP-1 P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and100°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-37 of B-43F0306-01R 1

~jjStructural Integrity Associates, Inc.eCurve B -Core Not Critical, All Components

-BL .... N16 --BH -- --FWN -* OCFRSO ....CDPN1300O-12001100 -,...1000900 -.:800S700j ÷600 ---U400 ...300: I I" I: l i* I___ I I *-ii;, 4/:17II!/IIIIIIIFii tI i÷__IIIII__~1~IIIIII'I/2001! ItI/ ltll1004 4 ~-~----------~-

,o i2500 4---50300100 150 200Minimum Reactor Vessel Metal Temperature

(*F)Figure B-5: HNP-1 P-T Curve B (Normal Operation

-Core Not Critical),

38 EFPY and 200°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-38 of B-43F0306-01RI Structural Integrity Associates, lnc.eCurve B -Core Not Critical, All Components

-BL ....-N16 --BH --.--FWN -, 1OCFR50 ....CDPN1300120011001O00900Ip76Ie,0@16oE400~300200 I1000o40100 150 200Minimum Reactor Vessel Metal Temperature (0F)*25050300Figure B-6: HNP-I P-T Curve B (Normal Operation

-Core Not Critical),

49.3 EFPY and200°F/hrNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-39 of B-43F0306-01RI Sj~tructural Integrity Associates, Curve C -Core Critical, All Components

-BL .... N16 --- BH --.-FWN -. 10CFR50 ....CDPN1300120011001000900S800b700S600~5004-4003002001000050100 150 200Minimum Reactor Vessel Metal Temperature

(*F)250300Figure B-7: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 100°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-40 of B-43F0306-01RI V$tructural Integrity Associates, InceCurve C -Core Critical, All Components

-BL .... N16 -- -- BH -.-FWN IOCFRSO ....CDPN1300120011001000900.~800p700Els00U-4003002001000 4-0100 150 200Minimum Reactor Vessel Metal Temperature

(*F)50250300Figure B-8: HNP-1 P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 1000F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-41 of B-43F0306-01RI Structural Integrity Associates, IncYtCurve C -Core Critical, All Components

-BL ....-N16 --BH -.-FWN -. 1OCFR50 ... CDPN1300120011001000900.~800p 700:; 6006Ew504OO3002001000i °- I100 150 200Minimum Reacto Vessel Metal Temperature I*F)300Figure B-9: HNP-I P-T Curve C (Normal Operation

-Core Critical),

38 EFPY and 200°F/hrNote: BL is Beltline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-42 of B-43F0306-01RI Structural Integrity Associates, InYCurve C -Core Critical, All Components

-BL .... N16 --BH I- --FWN -10CFR50 ....CDPN1300120011001O00900700UE--P 0VA-04003002001000050 100 150 200 250Minimum Reactor Vessel Metal Temperature

(°F)300Figure B-10: HNP-I P-T Curve C (Normal Operation

-Core Critical),

49.3 EFPY and 200°F/hrNote: BL is Beitline, BH is Bottom Head, CDPN is Core Differential Pressure Nozzle, and FWN isFeedwater NozzleFile No.: 1001527.304 Revision:

2Page B-43 of B-43F0306-01R 1