ML13295A451

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WCAP-17651-NP, Rev. 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis.
ML13295A451
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Issue date: 02/28/2013
From: Long E J
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PNP 2013-028 WCAP-17651-NP, Rev. 0
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ATTACHMENT 3WESTINGHOUSE WCAP-17651-NP REVISION 0PALISADES NUCLEAR POWER PLANT REACTOR VESSELEQUIVALENT MARGINS ANALYSIS44 pages follow Westinghouse Non-Proprietary Class 3WCAP-17651-NP February 201Revision 0Palisades Nuclear Power PlantReactor Vessel Equivalent Margins AnalysisWestinghouse 3

WESTINGHOUSE NON-PROPRIETARY CLASS 3WCAP-17651-NP Revision 0Palisades Nuclear Power Plant ReactorVessel Equivalent Margins AnalysisElliot J. Long*Materials Center of Excellence IFebruary 2013Reviewer:

Gordon Z. Hall*Major Reactor Component Design & Analysis IJ. Brian Hall*Materials Center of Excellence IApproved:

Frank C. Gift*., ManagerMaterials Center of Excellence I*Electronically approved records are authenticated in the electronic document management system.Westinghouse Electric Company LLC1000 Westinghouse DriveCranberry

Township, PA 16066, USA© 2013 Westinghouse Electric Company LLCAll Rights Reserved WESTINGHOUSE NON-PROPRIETARY CLASS 3 iiTABLE OF CONTENTSL IS T O F T A B L E S .......................................................................................................................................

iiiL IST O F F IG U R E S .....................................................................................................................................

ivLIST OF ACRONYMS AND ABBREVIATIONS

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

vEX EC U T IV E SU M M A RY ..........................................................................................................................

v iI IN T R O D U C T IO N ........................................................................................................................

I-I2 M ETH O D D ISC U SSIO N .............................................................................................................

2-12.1 ASME SECTION XI., APPENDIX K METHODOLOGY

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2-12.2 REGULATORY GUIDE 1.161 METHODOLOGY

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

2-33 ACCEPTANCE CRITERIA

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

3-I3.1 LEVEL A AND B SERVICE LOADINGS

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

3-13.2 LEVEL C SERVICE LOADINGS

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3-23.3 LEVEL D SERVICE LOADINGS

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3-34 EQUIVALENT MARGINS ANALYSIS INPUTS ...................................................................

4-I5 EQUIVALENT MARGINS ANALYSIS EVALUATIONS

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5-15.1 APPLIED J-INTEGRAL CALCULATIONS

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5-15.2 MATERIAL FRACTURE TOUGHNESS PROPERTIES

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5-25.3 FLAW EVALUATION RESULTS ...................................................................................

5-36 C O N C L U SIO N S ..........................................................................................................................

6-17 RE FE RE N C E S .............................................................................................................................

7-1WCAP-1765 I-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3iiiLIST OF TABLESTable 4-1 Palisades RV Beltline Geometry and Design ...............................................................

4-1Table 4-2 Palisades RV Beltline Predicted Upper-Shelf Energy at 42.1 EFPY ...............................

4-2Table 4-3 List of Transients Evaluated in the EMA .........................................................................

4-2Table 4-4 Fracture Toughness Margin Factors from Reference 7 ....................................................

4-3Table 4-5 Level A and B l00F/hr Cooldown Transient

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4-3Table 4-6 Level C 400°F/hr Cooldown Transient

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4-4Table 4-7 Level D 600°F/hr Cooldown Transient

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4-4Table 5-1 Palisades US and LS Plate EOLE USE Calculation with Consideration of Charpy TestSpecim en O rientation

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

5-4Table 5-2 Applied J-Integral and Material J-Resistance at 0. ]-Inch Crack Extension for AllT ran sien ts .........................................................................................................................

5-5Table 5-3 Available Margins on Pressure Load for Level A and B l00F/hr Cooldown Transient.5-6 WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3ivLIST OF FIGURESFigure 1-1 Palisades Reactor Vessel with Locations for EMA ..........................................................

1-2Figure 2-1 D efinition of A SM E O rientations

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

2-4Figure 5-1 Applied J-Integral versus Crack Extension for Circumferential Flaw -I/4t,L evel A and B ..................................................................................................................

5-7Figure 5-2 Applied J-Integral versus Crack Extension for Circumferential 1/10t Flaw,L evels C and D ................................................................................................................

5-8Figure 5-3 Base Metal Fracture Toughness at t/4 CVN = 47.5 ft-lb -Variation with Temperature..

5-9Figure 5-4 Base Metal Fracture Toughness at t/1 0 CVN = 46.1 ft-lb -Variation withT em perature

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

5-10Figure 5-5 Base Metal Fracture Toughness at t/ 10 CVN = 46.1 ft-lb vs. Measured High-Sulfur V-50 Plate Data -Variation with Temperature

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

5-11Figure 5-6 Weld Metal Fracture Toughness at t/4 CVN = 49.6 ft-lb -Variation withT em peratu re ...................................................................................................................

5-12Figure 5-7 Weld Metal Fracture Toughness at t/l 0 CVN = 47.9 ft-lb -Variation withT em perature

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

5-1 3Figure 5-8 Circumferential Flaw J-Integral versus Crack Extension

-t/4, Level A and B, BaseMaterial with Comparison of the Measured High-Sulfur V-50 Plate Data ....................

5-14Figure 5-9 Circumferential Flaw J-Integral versus Crack Extension

-t/4, P=2.75 ksi 100l F/hrC ooldow n, B ase M etal ...................................................................................................

5-15Figure 5-10 Circumferential Flaw J-Integral versus Crack Extension

-t/4, Level A and B,W eld M aterial .................................................................................................................

5-16Figure 5-11 Circumferential Flaw J-Integral versus Crack Extension

-t/4, P=2.75 ksi I 00°F/hrC ooldow n, W eld M etal ..................................................................................................

5-17Figure 5-12 Circumferential Flaw i-Integral versus Crack Extension

-t/10, Levels C and D,B ase M etal .....................................................................................................................

5-18Figure 5-13 Circumferential Flaw J-Integral versus Crack Extension

-t/10, Levels C and DL oads, W eld M etal .........................................................................................................

5-19WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3VLIST OF ACRONYMS AND ABBREVIATIONS ASME American Society of Mechanical Engineers B&PV Boiler and Pressure VesselCD cooldownCE Combustion Engineering CEOG Combustion Engineering Owners GroupCFR Code of Federal Regulations CVN Charpy V-notchEFPY effective full-power yearsEMA equivalent margins analysisEOLE end-of-license extension FSAR Final Safety Analysis ReportHU heatupIS intermediate shellJ-R fracture toughness resistance LS lower shellL-T lateral-transverse MnS manganese-sulfide NRC U.S. Nuclear Regulatory Commission RG Regulatory GuideRRVCH replacement reactor vessel closure headSF structural factorSIF stress intensity factorT-L transverse-lateral US upper shellUSE upper-shelf energyWCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3viEXECUTIVE SUMMARYThis report presents the methodology and results of the upper-shelf equivalent margins analysis (EMA)for the three Palisades Nuclear Power Plant reactor vessel materials with end-of-license-extension (EOLE) upper-shelf energy (USE) levels below the 50 ft-lb limit of 10 CFR 50, Appendix G. Materials with EOLE USE levels below 50 ft-lb are required to be evaluated, per paragraph IV.A.I.a of 10 CFR 50,Appendix G, for equivalent margins of safety specified in ASME Code Section XI, Appendix K.The two Palisades reactor vessel beltline materials and one extended beltline material that drop below the50 ft-lb limit were identified in WCAP-17341-NP, Revision 0 and WCAP-17403-NP,.

Revision 1,respectively.

These reports concluded that upper shell plate D-3802-3 in the extended

beltline, and lowershell plate D-3804-1 and intermediate to lower shell circumferential weld 9-112 (Heat #27204) in thetraditional
beltline, are predicted to drop below the 50 ft-lb limit required per 10 CFR 50, Appendix G atEOLE, which corresponds to 42.1 effective full-power years (EFPY). In WCAP-17403-NP, Revision 1, amethodology was proposed that could demonstrate acceptance to the 10 CFR 50, Appendix G 50 ft-lblimit for upper shell plate D-3802-3.
However, Palisades has elected to perform the EMA on this materialdue to the risk that it may fall below the 50 ft-lb limit if future operation includes higher flux levels.All three Palisades reactor vessel beltline and extended beltline regions with predicted Charpy upper-shelf energy levels falling below 50 ft-lb at EOLE were found to be acceptable for equivalent margins of safetyper the ASME Code Section XI.Service Level A and B Transients Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/4-thickness location for normal Level A and B load conditions, basedon the Regulatory Guide 1. 161 fracture toughness methodology.

This limiting material passed the flaw extension and stability criteria of ASME Section XIAppendix K.The equivalent margins analysis for the plate materials are acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for Service Level A and Btransients.

Service Level C Condition Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/10-thickness location for the service Level C load condition, based onthe Regulatory Guide I. 161 fracture toughness methodology.

This limiting material passed the flaw extension and stability criteria of ASME Section XIAppendix K.The equivalent margins analysis for the plate materials are acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for the Service Level C transient.

WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3viiService Level D Condition Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/10-thickness location for the service Level D load condition, based onthe Regulatory Guide 1.161 fracture toughness methodology.

This limiting material passed the flaw extension and stability criterion of ASME Section X1,Appendix K.The equivalent margins analysis for the plate materials is acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for the Service Level D transient.

WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 31-11 INTRODUCTION An upper-shelf energy (USE) evaluation was performed for the Palisades reactor vessel (RV) beltlinematerials in WCAP-17341-NP, Revision 0 (Reference I) and for the extended beltline materials inWCAP-17403-NP, Revision 1 (Reference 2). These reports concluded that materials in three locations

-upper shell plate D-3802-3 in the extended

beltline, and lower shell plate D-3804-1 and intermediate tolower shell circumferential weld 9-112 (Heat #27204) in the traditional beltline

-are predicted to dropbelow the 50 ft-lb limit required per 10 CFR 50, Appendix G (Reference

3) at end-of-license extension (EOLE), which corresponds to 42.1 effective full-power years (EFPY). In WCAP- 17403-NP, Revision 1,a methodology was proposed that could demonstrate acceptance to the 10 CFR 50, Appendix G 50 ft-lblimit for upper shell plate D-3802-3.
However, Palisades has elected to perform the equivalent marginsanalysis (EMA) on this material due to the risk that it may fall below the 50 ft-lb limit if future operation includes higher flux levels.Reactor vessel materials with USE levels below 50 ft-lb are required to be evaluated, per paragraph IV.A.I.a of 10 CFR 50, Appendix G (References 3 and 4), for equivalent margins of safety specified inthe American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) CodeSection XI, Appendix K (Reference 5). This summary report provides the methodology and results of theupper-shelf EMA of the Palisades reactor vessel limiting materials for 42.1 EFPY. Figure 1-1 shows thelocations of interest for this analysis in the Palisades reactor vessel.Section 2 of this report discusses the methodologies used to complete the Palisades EMA. Section 3identifies the acceptance criteria for the EMA with consideration of the various service loadings including Levels A, B, C, and D. Section 4 provides the inputs necessary to complete the EMA. while Section 5documents the EMA evaluations.

The conclusions of this report are documented in Section 6.WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 31-2WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-2LOOP IDJILETaiLOOP 1BINLETaiLOOP 2A LOOP 2 LOOPINLETr2 OUTLET02 INLETA120' Igo, 240,I IL ower Shell PlateFigure 1-1 Palisades Reactor Vessel with Locations for EMAWCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 32-12 METHOD DISCUSSION 2.1 ASME SECTION XI, APPENDIX K METHODOLOGY ASME Section XI, Appendix K (Reference

5) specifies the methodology to be used to evaluate theequivalent margins for low upper-shelf materials.

Reference 5 contains different postulated flaw depths,locations, and orientations, as well as the applied J-integral and stability criteria.

These are brieflydescribed here.Applied SIF Calculation for Axial and Circumferential Flaws with Pressure LoadingFor an axial flaw of depth a, the stress intensity factor (SIF) due to internal pressure is calculated with astructural factor (SF) on pressure using procedure in Article K-4000 in Reference 5.Applied SIF for Axial and Circumferential Flaws with Thermal LoadingFor an axial or circumferential flaw of depth a, the S1Fs due to radial thermal gradients for cooldownrates up to 100°F/hr are calculated using procedure in Article K-4000 in Reference 5.The SIFs for all other thermal design transients are computed using the stress distributions from the actualdesign transients analyzed in this EMA. The procedure from ASME Section X1, Appendix A (Reference

6) employing the cubic polynomial coefficients are also used.Effective Flaw Depth and Applied J-Integrals The effective flaw depth for small-scale yielding (aj) is used and the applied J-integrals are calculated again using the procedure in Reference 5.The calculation of a J-integral due to applied loads accounts for the material's elastic-plastic behavior of astress-strain curve.Postulated Flaws for Level A and B Service LoadingsThe postulated flaw is an interior semi-elliptical surface with a depth of one-quarter of the vessel wallthickness and an aspect ratio (length over depth) of 6:1. Orientation of the flaw is assumed to be asfollows:tbasea° -= 4where,ao = postulated initial flaw depth, inchestbase = thickness of the base or weld material, inchesWCAP- 1765 1-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 32-2For weld materials, the major axis of the flaw is to be oriented along the weld line.For base materials, both axial and circumferential orientations are to be considered.

All the postulated flaws are oriented in the radial direction.

Postulated Flaws for Levels C and D Service LoadingsThe postulated flaw is an interior semi-elliptical surface with a depth of 1/10 of the base metal wallthickness plus the cladding thickness (with a total depth not exceeding I inch), a surface length ofsix times the depth, and the flaw plane oriented in the radial direction.

tbasea° = 10 + tctadwhere,tclad = thickness of the cladding, inchesFor weld materials, the adequacy of the upper-shelf toughness with a flaw's major axis oriented along theweld of concern is evaluated.

For the base materials, the adequacy of the upper-shelf toughness with a flaw's major axis oriented alongaxial and circumferential directions is evaluated.

The toughness properties for the corresponding orientations are used.Flaws of various depths, ranging up to the maximum postulated depth, shall be analyzed to determine themost limiting flaw depth.WCAP- 17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 32-32.2 REGULATORY GUIDE 1.161 METHODOLOGY Material Fracture Toughness PropertyThe material J-integral resistance property as a function of flaw extension is a conservative representation for the RV material beltline region. As the actual beitline J-integral fracture resistance material properties for the Palisades RV are not available, U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide(RG) 1.161 (Reference 7, Section 3) is used. Regulatory Guide 1.161 has been developed to providecomprehensive guidance acceptable to the NRC staff for evaluating reactor pressure vessels when theCharpy USE falls below the 50 ft-lb limit of Appendix G to 10 CFR Part 50. The analysis methods in theregulatory position are based on methods developed for the ASME Code,Section XI, Appendix K(Reference 5). The NRC staff has reviewed the analysis methods in Appendix K and finds that they aretechnically acceptable but are not complete, because Appendix K does not provide information on theselection of transients and gives very little detail on the selection of material properties.

In RG 1.161,specific guidance is provided on selecting transients for consideration and on appropriate materialproperties to be used in the analyses.

The material fracture toughness J-resistance is provided inReference 7 and is expressed as:IR = (MF)Ci(Aa)c2 exp[C3(Aa)c4]where,= J-integral fracture resistance for the material, in-lb/in2MFAa= margin factor (see Table 4-4)= amount of ductile flaw extension, inchesCI, C2, C3, C4, =material constants used to describe the power-law fit to the J-integral resistance curve for the materialBase MetalC1= exp[-2.44

+ 1.13

  • In CVN -0.00277
  • T]C2 = 0.077 + 0.116
  • In C1C3 = -0.0812 -0.0092
  • In CoC4= -0.409Weld MetalC1= exp[-4.12

+ 1.49

  • In CVN -0.00249
  • T]C2=0.077 +0.116* In C,WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 32-4C3 = -0.0812 -0.0092

  • In C1C4 = -0.5Per RG 1.161, the Charpy v-notch upper-shelf energy (CVN) value should be matched to the properorientation of the plate material (see Figure 2-1). Therefore, for axial flaws, the CVN value for the lateral-transverse (L-T) "strong" orientation in the vessel wall should be used. Similarly, for circumferential flaws, the CVN value for the transverse-lateral (T-L) "weak" orientation should be used. See Section 5.1for additional details.Also, with consideration of plate materials, the J-R model described in this section is developed formaterials with high fracture toughness.

For plate material with sulfur content less than 0.018 wt. %, the J-R model may be used. For plate material with sulfur content greater than 0.0 18 wt. %, the model may beused if it can be justified as conservative or a material-specific justification can be made based on otherdata. See Section 5.2 for additional details.'WEAK" DIRECTION ASME TRANSVERSE ASTM T-LRPV CIRC. FLAWASME LONGITUDINAL ASTM L-TRNV AXIAL FLAWFigure 2-1 Definition of ASME Orientations WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 33-13 ACCEPTANCE CRITERIAThe ASME Code forms the basis for the requirements of Appendix G to 10 CFR Part 50. The acceptance criteria for the low-USE locations in the RV beltline materials are established in the ASME Code SectionXI, Appendix K, Article K-2000 (Reference

5) and are summarized here.3.1 LEVEL A AND B SERVICE LOADINGSFlaw Extension Criterion The applied J-integral evaluated at a pressure 1.15 times the accumulation pressure (as defined in theplant-specific overpressure protection report),

with a structural factor of I on thermal loading for theplant-specific heatup (HU) and cooldown (CD) conditions, shall be less than the J-integral of the materialat a ductile flaw extension of 0. 1 inch.J1(a,, 1.15Pa, CD or HU) < 10.1where JI is the applied J-integral with:ta =- + 0.1 in4where,Pa = accumulation pressure as defined in the plant-specific overpressure protection report, but not exceeding

1. I times the design pressure, ksiHU = heatupCD = cooldownJO. I= the J-integral resistance at a ductile flaw extension of 0.1 inch., in-lb/in2Flaw Stability Criterion Flaw extensions at pressures up to 1.25 times the accumulation pressure shall be ductile and stable, usinga structural factor of I on thermal loading for the plant-specific HU and CD conditions.

1(1.25 P,, CD or HU) should be in ductile tearing mode and stableThe flaw stability criterion is evaluated using:* The J-integral due to applied loads for the postulated flaw in the vessel should satisfy theequilibrium equation for the stable flaw extension:

J = JRWCAP-17651I-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 33-2In the preceding equation:

i = J-integral due to applied loadsJR = J-integral resistance to ductile tearing for the materialThe applied J-integral should satisfy the stability criterion for the following ductile tearingequation.

Under increasing load, stable flaw extension will continue as long as remainsless than aiR8a0i]< mJRaa- aaIn the preceding equation:

aj = partial derivative of applied J-integral with respect to flaw depth, a, withOaconstant loada. = slope of the J-resistance curveOaThe above requirements for flaw extension and stability for Level A and B service loadings are satisfied as discussed in Section 5 of this report.3.2 LEVEL C SERVICE LOADINGSFlaw Extension Criterion The applied J-integral, with a structural factor of I on loading, shall be less than the J-integral of thematerial at a ductile flaw extension of 0.1 inch.J, (a,, Pa, CD or HU) < Jo.1where Ji is the applied J-integral with:a, = ao + 0.1 inFlaw Stability Criterion Flaw extensions shall be ductile and stable, similar to Level A and B service loadings, with a structural factor of 1 on loading.The preceding requirements for flaw extension and stability for Level C service loadings are satisfied asdiscussed in Section 5 of this report.WCAP-1765 1-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 33-33.3 LEVEL D SERVICE LOADINGSFlaw Stability Criterion The total flaw depth after stable flaw extension shall be less than or equal to 25 percent of the vessel wallthickness and the remaining ligament shall not be subject to tensile instability.

This requirement for flaw stability for Level D service loadings is satisfied as discussed in Section 5 ofthis report.Tensile instability occurs only when the applied J-integral slope exceeds that of the material curve and theflaw continually grows per RG 1.161 and Appendix K of the ASME B&PV Code. As shown in Section 5of this report for the Palisades EMA, flaws are stable with adequate margins.

Therefore, crack growth orstability is not an issue.WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 34-14 EQUIVALENT MARGINS ANALYSIS INPUTSThe following material property inputs, vessel design data, and transient data were used in the EMA ofthe three Palisades reactor vessel materials with predicted EOLE USE values below 50 ft-lb. The twomaterials in the traditional beltline region, lower shell plate D-3804-1 and intermediate to lower shellcircumferential weld 9-112 (Heat #27204) have EOLE USE values below 50 ft-lb. Though it can beshown by the methodology documented in WCAP-17403-NP that the extended beltline region material, upper shell plate D-3802-3.

remains above 50 ft-lb at EOLE, Palisades has elected to perform the EMAon this material with consideration of the possibility of future operation at higher flux levels. Table 4-1documents the Palisades reactor vessel geometry.

Table 4-2 contains the unirradiated, EOLE I/10T, andEOLE 1/4T USE for the three Palisades reactor vessel materials.

Unit pressure load through-wall stressprofiles for axial and hoop stresses were used in all the pressure SIF calculations.

Design transients for allLevel A and B transients were considered in addition to the 100°F/hr CD transient specified inReference 5; see Table 4-3. ASME Code Section D material properties for yield strength and modulus ofelasticity are from Reference 8.Level A and B transients with a 1000F/hr cooldown rate, Level C transients with a 400°F/hr cooldownrate, and Level D transients with a 600°F/hr cooldown rate were used in the EMA. These transient definition points are also listed in Tables 4-5 through 4-7. Finally, cladding effects for the Levels C and Dload levels were conservatively ignored because the temperatures at evaluation points are above thecladding stress free temperature of 4007F (Reference 9).The Palisades Final Safety Analysis Report (FSAR) subsection 4.2.2 lists and describes RV design basistransients;

however, further information is needed to conduct a transient stress analysis.

Therefore, toaccommodate this need, the Design Specification for the Replacement Reactor Vessel Closure Head(RRVCH) for Palisades Nuclear Generation

Station, DS-ME-04-10, Revision 3 (Reference
10) was usedto obtain temperature vs. time and pressure vs. time RV design basis transient data. Design Specification DS-ME-04-10 contains one additional transient (steam line rupture) that was not included in the originaldesign basis transients for the reactor vessel. The steam line rupture transient is conservatively included inthe EMA. Additional transients from RG 1.161 are also evaluated.

Table 4-1 Palisades RV Beitline Geometry and DesignParameter ValueO')Base Metal Inside Diameter (Di) 172.7 inBase Metal Inner Radius 86.35 inBase Metal Wall Thickness (t) 8.79 inCladding Thickness 0.25 in 2)Material Specification SA-302 Gr. B Modified PlateAccumulation Pressure (Pacc) 2.750 ksiNotes:I. Reactor vessel beltline geometry values were obtained from WCAP-15353

-Supplement 2-NP (Reference I1).2. Cladding and cladding effects were conservatively ignored in the various stress analyses performed for Palisades as partof the EMA.WCAP-1765 1-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 34-2WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-2Table 4-2 Palisades RV Beltline Predicted Upper-Shelf Energy at 42.1 EFPYReactor Vessel Material" 1' Projected EOLE USE(2)Unirradiated Location Heat Number USE"' (ft-lb) At 1/10t (ft-lb) At 1/4t (ft-lb)LS Plate D-3804-1 C-1308- 13, 72 46.1 48.2Using CVGraphRefitted Initial C-1281 62.2 47.5 50.1US Plate USED-3802-3' 4)Using 95% Shear C-1281 59 46.6 47.5Initial USEIS to LS Circumferential Weld 9-112 27204 84 47.9 49.6Notes:1. Reactor vessel material information, heat numbers, and unirradiated initial USE values were taken from WCAP-17341-NP (Reference I) for LS plate D-3804-1 and IS to LS circumferential weld 9-112 and from WCAP-17403-NP (Reference

2) for US plate D-3802-3.

This information is consistent with P-PENG-ER-006 (Reference 12).2. The projected EOLE USE values at 1/4t were taken from WCAP-17341-NP for LS Plate D-3804-1 and IS to LScircumferential weld 9-112 and from WCAP-17403-NP for US plate D-3802-3.

The projected EOLE USE values at 1/10twere calculated for the EMA using the methodology described in RG 1.99, Revision 2 (Reference 13), which isequivalent to the methodology used in the previous reports.3. The heat number for LS plate D-3804-1 has also been reported as C-1308A.4. Using the methodology proposed in WCAP-17403-NP, it can be demonstrated that US Plate D-3802-3 meets the 50 ft-lblimit of 10 CFR 50, Appendix G. However, Palisades has elected to perform the EMA on this material due to the risk thatit may fall below the 50 ft-lb limit if future operation includes higher flux levels.Table 4-3 List of Transients Evaluated in the EMANumber Transient Description Load LevelI Plant HU at 100°F/hr A2 Plant CD at 100°F/hr A3 Plant Loading Change, 5% Full Load/Minimum A4 Plant Unloading Change, 5% Full Load/Minimum A5 Plant Load Change, 10% Full Load Step, Step Increase, T,.Id A6 Plant Load Change.,

10% Full Load Step, Step Decrease, T,,Id A7 Plant Load Change, 10% Full Load Step, Step Increase, Th.t A8 Plant Load Change, 10% Full Load Step, Step Decrease, Th., A9 Plant Loading Change, 15% Full Load/Min A10 Plant Unloading Change, 15% Full Load/Min AII Loss of Primary Coolant Flow, TCold B12 Loss of Primary Coolant Flow, Th., B13 Reactor Trip or Loss of Load, ToId B14 Reactor Trip or Loss of Load, Th., BWCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 34-3Table 4-3 List of Transients Evaluated in the EMA (cont.)Number Transient Description Load Level15 Reactor Trip, Loss of Load, or Loss of Primary Coolant Flow, Tsurgenow B16 Safety Valve Operation, Tinlet B17 Safety Valve Operation, Toutlet B18 Steam Line Rupturetl) D19 RG 1.161 Cooldown at 100°F/hr B20 RG 1.161 Cooldown at 400°F/hr C21 RG 1.161 Cooldown at 600°F/hr DNotes:I. This design transient is conservatively bounded by the Regulatory Guide (Reference

7) transient for LevelD loads.Table 4-4 Fracture Toughness Margin Factors from Reference 7Metal Levels A, B, and C Level DBase 0.749 1Welds 0.629 1Table 4-5 Level A and B 100IF/hr Cooldown Transient Time (sec) Pressure (ksi) Fluid Tnuid (IF)0 2.75 5332,800 2.75 4563,600 2.75 4335,400 2.75 3837,200 2.75 3339,000 2.75 28310,800 2.75 233WCAP- 17651I-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 34-4Table 4-6 Level C 4000F/hr Cooldown Transient Time (see) Pressure (ksi) Fluid Tfl0id (IF)0 2.25 5331,197 1.3 400Table 4-7 Level D 600IF/hr Cooldown Transient Time (sec) Pressure (ksi) Fluid Tnuid (IF)0 2.25 533798 1.3 400WCAP- 1765 1-NP February 2013WCAP- 17651I-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-15 EQUIVALENT MARGINS ANALYSIS EVALUATIONS 5.1 APPLIED J-INTEGRAL CALCULATIONS For the Level A and B service load conditions, the Palisades EMA has considered a total of 17 designtransients from the Palisades FSAR, along with the 100°F/hr, 400'F/hr and 600°F/hr cooldown ratetransients provided in Reference

7. The typical through-wall thermal stress, shown in Figure 5-1, wascomputed analytically at inside surface, mid-wall, and outside surface locations.

Typical axial through-wall stress distributions for the vessel during a heatup transient, shown in Figure 5-2, were used in thisEMA. The associated vessel wall metal temperatures, required for the applied J-integral evaluation andthe material fracture toughness resistance (J-R), were also used.The applied J-integral values for the circumferential flaws for all Level A and B service level conditions are shown in Figure 5-1. These figures show the peak J-integral values during each transient as a functionof crack extension starting from the 1/4-thickness flaw. These calculations used a structural margin of1.25 for pressure loading and I for thermal loading, as required by Reference 5.Figure 5-2 shows the applied J-integral values at 1/10-thickness flaws, with a structural margin of I forpressure and thermal loadings, for circumferential flaws under Level C and D conditions.

All applied J-integral values shown in Figure 5-1 and Figure 5-2 are applicable for both the weld and basemetals because flaws are considered circumferential.

Only circumferential base metal flaws areconsidered in this analysis, because only the "weak" orientation USE is projected to drop below 50 ft-lbsas described below.The measured initial USE value for the Palisades Nuclear Power Plant LS plate D3804-1 is 110 ft-lb inthe longitudinal direction.

Similarly, US plate D3802-3 has an initial USE value of 91 ft-lb in thelongitudinal direction per P-PENG-ER-006 (Reference 12). The estimated transverse values for the LSand US plates are 72 and 59 ft-lb. respectively, which were reduced by 35 percent to approximate thetransverse direction per NUREG-0800, Revision 2 Branch Technical Position MTEB 5-3 (Reference 14).Table 5-1 documents the calculation of the end-of-license-extension (EOLE) USE with consideration ofthe Charpy testing direction for Palisades.

Data were obtained from WCAP-1734 1-NP and WCAP-17403-NP for the LS and US plates, respectively.

The table shows that for the longitudinal "strong" direction, both plates exhibit an EOLE USE value per10 CFR 50, Appendix G above 50 ft-lb. When the initial longitudinal USE value is reduced to 65 percentper MTEB 5-3 to approximate the transverse "weak" direction, both plates drop below the 50 ft-lb limit.Therefore, only circumferential flaws are postulated in the two plates, because the EOLE USE in thelongitudinal "strong" direction is above the 10 CFR 50, Appendix G limit. As stated previously in Section2.2, the CVN value should be matched to the proper orientation of the plate material.

Therefore, for axialflaws, the CVN value for the lateral transverse (L-T) "strong" orientation in the vessel wall will be used.Similarly, for circumferential flaws, the CVN value for the transverse-lateral (T-L) "weak" orientation will be used. Therefore, only circumferential base metal flaws are considered in this analysis.

WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-2The applied J-integral values shown in Figure 5-1 and Figure 5-2 are used in the flaw evaluations.

Table5-2 summarizes the maximum circumferential applied J-integrals for all design, 100°F/hr, 400°F/hr, and600°F/hr transients.

5.2 MATERIAL FRACTURE TOUGHNESS PROPERTIES The estimated base material fracture toughness properties for the 1/4- and 1/10-thickness locations areshown in Figure 5-3 and Figure 5-4, respectively using the high-toughness

/ low-sulfur model from RG1.161. The corresponding material toughness values for the weld material are shown in Figures 5-6 and 5-7, also using the model from RG 1.161. These figures show the toughness values at different metaltemperatures ranging from 300'F to 600'F, over which the vessel wall metal temperatures vary during thetransients.

These include the USE levels considered for the materials at the flaw location and a flawextension of up to 1 inch.Per P-PENG-ER-006, the sulfur content of US plate D-3802-3 is 0.029 wt. %. Similarly, for LS plateD-3804-1, the sulfur content is 0.024 wt. %. The Palisades plates have a sulfur content greater than thehigh-toughness model limit of 0.018 wt. % specified in RG 1.161. The J-R model in RG 1.161 has anupper limit in sulfur because J-R data for plates with high sulfur content are scarce and the available datashowed low toughness, flat J-R curves, and a size effect. The most data available for a high-sulfur A-302B plate are for the V-50 plate in NUREG/CR-5265 (Reference 15). This plate has a reported sulfurcontent of 0.021 and 0.025 wt. % with USE values of 44 to 51 ft-lb, averaging around 48 ft-lb at the 1/4Tlocations in the T-L (weak) orientation.

This USE is comparable to the EOLE projection for the Palisades high-sulfur plates.The V-50 plate was unusual in that it had a test specimen size effect that has not been observed in otherRV material J-R curves and is unique to the V-50 plate. A high content of manganese-sulfide (MnS)inclusions and banded regions of microstructure, are believed to be the causes of the unusual specimensize effect observed.

Conservatively, the lowest J-R curve test data from this testing program is plotted inFigure 5-5, which is from a 6T size specimen and is considerably lower than test data for the IT J-R.which is the standard size specimen typically used. In addition, the manufacturing practices used toproduce this extremely low-toughness V-50 plate are not representative of those used in the Palisades RV.The V-50 plate is A-302 B plate with a nickel content of 0.23 wt. % while the Palisades plates are SA-302B Modified, which means that they have at least 0.4 wt. % nickel. Nickel was added to increasetoughness.

Therefore, the J-R curve test data from the V-50 plate data can be conservatively viewed as theworst possible case and can be compared to the J-applied values from this evaluation.

Adjusting the 180'F6T plate V-50 J-R curve data to 600'F using the ratio of the RG 1.161 correlation, the 600'F data can beapproximated as shown in Figure 5-5.High-sulfur A-302 B Modified plate J-R data are available in NUREG/CR-6426 (Reference 16).However, the weak-direction Charpy USE value is 64 ft-lb, which is above the 10 CFR 50, Appendix Glimit of 50 ft-lb. This further validates that the V-50 plate was an anomaly and can be considered a veryconservative lower bound of the available high-sulfur A-302 B plate J-R data. The J-applied in thePalisades SA-302 B Modified plate remains below the measured very conservative lower-bound V-50 A-302 B plate J-R data.WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-35.3 FLAW EVALUATION RESULTSThe flaw stabilities for various material, flaw location, and service load levels are shown in Figure 5-8through Figure 5-13. Figure 5-8 shows the applied J-integral and material J-resistance for circumferential flaws in base metal at the 1/4-thickness location for Level A and B design transients.

The corresponding results for the NRC Regulatory Guide 100°F/hr cooldown transient are shown in Figure 5-9. The J-applied remains below even the conservative temperature-adjusted V-50 plate J-R data. Figure 5-8compares the J-R data using the high-toughness, low-sulfur model of RG 1.161, along with the measuredV-50 plate J-R data, to the J-applied calculated in this analysis.

For the weld metal, Figure 5-10 and Figure 5-11 show the applied J-integral and material J-resistance results for the Level A and B transients for the circumferential flaws, and the corresponding NRCRegulatory Guide I 00°F/hr cooldown transient.

For Level C and D loads, circumferential flaw versus crack extension results are shown Figure 5-12 forbase metal and in Figure 5-13 for the weld metal. The J-applied curves for Levels C and D are essentially flat, indicating very small flaw extension.

The J-applied curves are also well below the JR curves,indicating stable flaw extension.

Table 5-2 lists the minimum material fracture toughness J-resistance as calculated per RG I. 161 at a peakmetal temperature of 610'F, which is observed at the 1/4-thickness locations.

All transients that haveapplied J-integral values with the crack tip at significantly lower temperatures than 610'F are well belowthe J-resistance listed, indicating that the EMA criteria are met.Maximum available equivalent margins were computed for the Level A and B governing transient with100lF/hr cooldown rate at accumulation pressure levels by iteration.

The maximum structural marginfactors that result in the J-applied values equal to the material J-resistance at 0.1-inch crack extension ascalculated per RG 1.161 are listed in Table 5-3. This evaluation indicates that the minimum structural margin available for the base material is 2.874 (with circumferential flaws). For the weld material withthe circumferential flaws, the minimum structural margin available is 2.490. All these cases have theirstructural factors well above the minimum requirement of 1.15 (Reference 5).The flaw extension figures demonstrate that:The NRC Regulatory Guide 100°F/hr cooldown transient with the accumulation pressure levelsgoverns the Level A and B transients.

All cases considered are acceptable with the applied J-integral values at 0.1-inch crack extensions below the material J-resistance (Ji. )required by Reference 5.WCAP- 17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-4WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-4Table 5-1 Palisades US and LS Plate EOLE USE Calculation with Consideration of Charpy TestSpecimen Orientation 1/4T EOLE Projected Projected Charpy Reactor Vessel Wt.% Fluence Unirradiated USE EOLE USEOrientation Material Cu (x 10'9 n/cm2, USE (ft-lb) Decrease

(-LbUE > 1.0 MeV) (%) (ft-lb)US Plate D-3802-3 0.25 0.0902 19.5 73 LS Plate D-3804-1 0.19 2.024 1100) 33 74US Plate D-3802-3 0.25 0.0902 59 19.5 47.5 2LS Plate D-3804-1 0.19 2.024 72 33 48.2Notes:I. Measured longitudinal-direction initial USE values from P-PENG-ER-006.

All other data are taken from WCAP-17341-NP and WCAP-17403-NP for the LS and US plates, respectively.

2. Data are taken from WCAP-17341-NP and WCAP-17403-NP for the LS and US plates, respectively, and summarized inTable 4-2.WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-5Table 5-2 Applied J-Integral and Material J-Resistance at 0.1-Inch Crack Extension for All Transients Load Circumferential Base JR Weld JRNumber Transient Description Level a/t Japplied (in-lb/in

2) (in-lb/in
2) (in-lb/in 2)1 Plant HU at 1000F/hr A 49.12 Plant CD at I00°F/hr A 106.43 Plant Loading Change, 5% Full Load/Minimum A 47.94 Plant Unloading Change, 5% Full Load/Minimum A 104.75 Plant Load Change, 10% Full Load Step, Step Increase, Tcold A 55.26 Plant Load Change, 10% Full Load Step, Step Decrease, Twid A 49.57 Plant Load Change, 10% Full Load Step, Step Increase, Th., A 53.38 Plant Load Change, 10% Full Load Step, Step Decrease, Th., A 52.59 Plant Loading Change, 15% Full Load/Min A 48.21/4 601 46210 Plant Unloading Change, 15% Full Load/Min A 68.111 Loss of Primary Coolant Flow, Tcold B 53.512 Loss of Primary Coolant Flow, Thor B 90.313 Reactor Trip or Loss of Load, Tcold B 48.114 Reactor Trip or Loss of Load, Th., B 90.115 Reactor Trip, Loss of Load, or Loss of Primary Coolant Flow, Tsurgetlow B 86.516 Safety Valve Operation, Tinlet B 69.717 Safety Valve Operation, Toutlet B 96.619 RG 1.161 Cooldown at 100°F/hr B 181.520 RG 1.161 Cooldown at 400°F/hr C 163.81/10 783 70821 RG 1.161 Cooldown at 600°F/hr D 304.8WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-6Table 5-3 Available Margins on Pressure Load for Level A and B 100°F/hr Cooldown Transient Base Material Weld MaterialCircumferential Flaw Circumferential FlawTime J-applied J0.1 Material J-applied J.01 Material(sec) SF (in-lb/in

2) (in-lb/in
2) SF (in-lb/in
2) (in-lb/in 2)0 3.106 699 699 2.760 527 5282,800 2.874 776 776 2.490 578 5803,600 2.882 807 807 2.490 600 6015,400 2.963 885 885 2.549 653 6537,200 3.102 975 975 2.659 711 7119,000 3.272 1,076 1,076 2.797 776 77710,800 31.69 1,188 1,188 27.05 847 848Minimum SF 2.874 2.490WCAP-1765 1-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-7WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-7100300Applied J-Integral-Circumferential Flaw, Level A & B, a/t=-1/4t, SF=1.25 -2-3---4100..........

14.........

15-16--- 17--------------------------------------

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

1'30-2.75k si 100OF/h rC,2.12.32.4Flaw Depth a (in)2.52.6Figure 5-1 Applied J-Integral versus Crack Extension for Circumferential Flaw -1/4t, Level A and BWCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-8WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-8Applied J-Integral Curve -Circumferential Flaw, Level C & D, a = 1/10t, SF=1400 [Transient#

I-Load Level C--- Load Level D300200.S" 100 --------------------------

0 I I II0.8 0.9 1 1.1 1.2 1.3 1.4Flaw Depth a (in)Figure 5-2 Applied J-Integral versus Crack Extension for Circumferential 1/10t Flaw, Levels C and DWCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-9WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-9RG 1.161 Fracture Toughness JR, Base Metal, MF=0.749 at t/4 CVN=47.5 ft-lbs -Variation with Temperature 40003500 -200--- 300-4003000 ---500-600C25002000150050000 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1Crack Extension Aa (in)Figure 5-3 Base Metal Fracture Toughness at t/4 CVN = 47.5 ft-lb -Variation with Temperature Note: JR = J-resistance, CVN = Charpy V-notchWCAP- 17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-10WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-10RG 1.161 Fracture Toughness JR for Base Metal with MF=1 at t/10 CVN=46.1 ft-lbs -Variation with Temperature 400035003000250020001500n1000VW 5000-00.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9Crack Extension Aa (in)Figure 5-4 Base Metal Fracture Toughness at t/10 CVN = 46.1 ft-lb -Variation with Temperature WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-11RG 1.161 Fracture Toughness JR for Base Metal with MF=1 at t110 CVN=46.1 ft-lbs -Variation with Temperature CCCoCo0)C0)0I-LL400035003000250020001500100050000 0.1 0.2 0.3 0.4 0.5Crack Extension Aa (in)0.6 0.7 0.8 0.91Figure 5-5 Base Metal Fracture Toughness at t/10 CVN = 46.1 ft-lb vs. Measured High-Sulfur V-50 Plate Data -Variation with Temperature WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-12WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-12RG 1.161 Fracture Toughness JR for Weld Metal with MF=0.629 at t/4 CVN=49.6 ft-lbs -Variation with Temperature Annn -Ternperature

°F)J-2003500 --- -300-4003000 ---500-600S250020001 5 0 0 .....01" 0000 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1Crack Extension Aa (in)Figure 5-6 Weld Metal Fracture Toughness at t/4 CVN = 49.6 ft-lb -Variation with Temperature WCAP- 17651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 51Figure 5-7 Weld Metal Fracture Toughness at t/10 CVN = 47.9 ft-lb -Variation with Temperature WCAP- 1765 I-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-14WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-14Circumferential Flaw Stability, Base Metal LevelA & B, a/t=1/4t, SF=1.2514001300120011001000900800700a..600600I-- JR Base 1/4t 430F-JR Base 1/4t 530F-JR Base 114t 610F--da=01"Line 0 6T V-50 plate data at 18OFA GT V-50 plate data adusted to GOOFI!II4003002001000IAA A A IAmAA A------------------------------------------------------

I2.12.72.22.32.4Flaw Depth a (in)2.52.6Figure 5-8Circumferential Flaw J-Integral versus Crack Extension

-t/4, Level A and B, Base Material with Comparison of the Measured High-Sulfur V-50 Plate DataNote: The limiting transients 2, 4, and 17 are shown.WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-15Circumferential Flaw Stability

-Base Metal, P=2.75ksi 100F/hr Cooldown, a/t=1/4t, SF=1.251800-Japplied T=533F1600 -Japplied T=480F0 -Japplied T=460F-Japplied T=313F1400 -= JR Base T=533F O-JR Base T=480F 01200 -JR Base T=460F O-JR BaseT=313F,

--da=0.1" Line1000E- 8006004000200 000 ,1 1 _ __ i -2.1 2.2 2.3 2.4 2.5 2.6 2.7Flaw Depth a (in)Figure 5-9 Circumferential Flaw J-Integral versus Crack Extension

-t/4, P=2.75 ksi 1000F/hr Cooldown, Base MetalWCAP-1765 1-NPFebruary 2013Revision 0

WF~ST1NGHOT NF NON..PRAPPTPTADV C'I A CC 2WESTINGHOUSE NON-PROPPIETAR-01 A CC I5-16i'41400130012001100100090080070060050040030020010002.1Circumferential Flaw Stability, Weld Metal LevelA & B, a/t=-1/4t, SF=1.25---2--4--- JR Weld 400F-JR Weld 500F-JR Weld 610F-L- da=O.1"Line 22I-2.2 9'0, Flaw Depth a (in)Figure 5-10 Circumferential Flaw J-Integral versus Crack Extension

-t/4, Level A and B, Weld MaterialNote: The limiting transients 2, 4, and 17 are shown.W~AP1 7t~ L.\TT3WCAP- 1 -765 1 -NT PFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-17WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-171400130012001100100090900=800.'700" 600.500440030020010002.100Circumferential Flaw Stability, Weld Metal, P=2.75ksi 10OF/hr Cooldown,,

a/tIl/4t, SF=1.25Tranient

  1. JIJapplied T=533F OJapplied T=456F 0-Japplied T=364F= JR Weld 533F= JR Weld 456F-JR Weld 364F--da = 0.1" Line000000000n9IUII2.20002.30002.4000Flaw Depth a (in)2.50002.60002.7000Figure 5-11 Circumferential Flaw J-Integral versus Crack Extension

-t/4, P=2.75 ksi 100°F/hr

Cooldown, Weld MetalWCAP-17651-NP February 2013Revision 0

WESTIN211OUSE NoN, pkOP'R'ETARI, CLASS 31800 C'rcIJnJIerentiaj'pjaW Stabil'ty

-Baselaný Metal,'Figure &1I2 circumfereta Flaw J14ntegrai versus Crack Extension "09U~ Levels Cad0,Bs eaFebruary201Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 35-19WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-19nI..180016001400120010008006004002000Circumferential Flaw Stability

-Weld Metal, Level C & D, a = 1/10t, SF=1Transient

  1. -Level C Load--- -Level D LoadJRWeld t/10 400F 0-JR Weld tV10 500F-JR Weld t/10 610OF--daO0.1"0i00i00.80.9 1 1.1 1.2 1.3Flaw Depth a (in)1.4Figure 5-13 Circumferential Flaw J-Integral versus Crack Extension

-t/10, Levels C and D Loads, Weld MetalWCAP-1 7651-NPFebruary 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 36-16 CONCLUSIONS The Palisades reactor vessel beltline and extended beltline regions with predicted Charpy upper-shelf energy levels falling below 50 ft-lb at the EOLE period were evaluated for equivalent margins of safetyper the ASME Code Section X1 (References 5, 6, and 18) and found to be acceptable.

The minimumstructural margin available for the limiting reactor vessel material (intermediate to lower shellcircumferential weld 9-112 [Heat #27204])

of 2.490 (circumferential flaws) occurs during a Service LevelA and B transient using the toughness model of RG 1. 161. The equivalent margins analyses for the platematerials, lower shell plate D-3804-1 and upper shell plate D-3802-3, are bounded by the conservative test data reported in NUREG/CR-5265.

Use of the conservative V-50 plate data from NUREG/CR-5265 for the Palisades plate materials with sulfur content greater than the 0.018 wt. % limit specified inRegulatory Guide 1. 161 shows that the applied J-integral values are acceptable.

Palisades Plant-Specific EMA Comparison to CE-NPSD-993 CE-NPSD-993, Revision 0 (Reference

17) is a generic Combustion Engineering (CE) EMA that wascompleted in May 1995 for the Combustion Engineering Owners Group (CEOG). This report summarized that all CE reactor vessel materials with end-of-life USE values below 50 ft-lb would satisfy equivalent margins of safety to ASME Code Section I11, Appendix G with consideration of the generic designtransients and reactor vessel geometries assumed in that report. Therefore, based on the results of thisplant-specific EMA, the results of the CEOG report with consideration of the design transients and vesselgeometries for Palisades are confirmed.

Per CE-NPSD-993, the minimum acceptable USE value for plate materials in the longitudinal direction was 30 ft-lb for Level A and B transients.

Likewise, for the transverse direction, a value of 19.5 ft-lb wasconcluded to be the acceptable value for plate materials.

On a generic basis, weld materials need toexhibit at least 34 ft-lb for longitudinal welds and 19.5 ft-lb for circumferential welds to provideequivalent margins of safety for Level A and B transients.

The minimum acceptable USE values for LevelC and D transients were generically determined to be 30 and 19.5 ft-lb for plate materials in thelongitudinal and transverse directions, respectively.

Weld materials need to exhibit at least 30 ft-lb forlongitudinal and circumferential welds to provide equivalent margins of safety for Level C and Dtransients.

For Palisades, the predicted USE in the transverse "weak" direction at EOLE was 47.5 ft-lb forUS Plate D-3802-3.

The predicted USE does not drop below 50 ft-lb for the longitudinal "strong"direction plate data at EOLE. The predicted USE for intermediate to lower shell circumferential weld 9-112 (Heat #27204) material at EOLE was 49.6 ft-lb.Service Level A and B Transients Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/4-thickness location for normal Level A and B load conditions, basedon the Regulatory Guide 1. 161 fracture toughness methodology.

The applied J-integral values for the assumed 1/4-thickness inside-surface circumferential flawsin the base metal and circumferential flaws in the weld metal with a safety margin of 1.15 onpressure loading are within the material fracture toughness J-resistance at 0.1-inch crackextension.

WCAP-17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 36-2The assumed flaw is ductile and stable with crack extension with a safety margin of 1.25 onpressure loading.The equivalent margins analyses for the plate materials are acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for Service Level A and Btransients.

Service Level C Condition with 4001F/hr Cooldown Transient Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/10-thickness location for the Service Level C load condition, basedon the Regulatory Guide 1. 161 fracture toughness methodology.

The applied J-integral values for the assumed 1/10 base metal thickness inside-surface circumferential flaws in the base metal and circumferential flaws in the weld metal with asafety margin of 1.00 on loading are within the material fracture toughness J-resistance at0.1 -inch crack extension.

The assumed flaw is ductile and stable with crack extension with a safety margin of I onpressure loading.The equivalent margins analyses for the plate materials are acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for the Service Level C transient.

Service Level D Condition with 600°F/hr Cooldown Transient Intermediate to lower shell circumferential weld 9-112 (Heat #27204) is governing forEOLE USE margin at the 1/10-thickness location for the Service Level D load condition, basedon the Regulatory Guide 1.161 fracture toughness methodology.

The applied J-integral values for the assumed 1/10 base metal thickness inside-surface circumferential flaws in the base metal and circumferential flaws in the weld metal with asafety margin of 1.00 on loading are within the material fracture toughness J-resistance at0. 1-inch crack extension.

The total flaw depth after a stable flaw extension is well within 75 percent of the vessel wallthickness, with the remaining ligament stable for crack propagation.

The equivalent margins analyses for the plate materials are acceptable and bounded by theconservative test data reported in NUREG/CR-5265 in all cases for the Service Level D transient.

WCAP- 17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 37-17 REFERENCES

1. Westinghouse Report WCAP-17341-NP, Revision 0, "Palisades Nuclear Power Plant Heatup andCooldown Limit Curves for Normal Operation and Upper-Shelf Energy Evaluation,"

February2011.2. Westinghouse Report WCAP-17403-NP.

Revision 1, "Palisades Nuclear Power Plant ExtendedBeltline Reactor Vessel Integrity Evaluation,"

January 2013.3. Code of Federal Regulations, 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements,"

U.S. Nuclear Regulatory Commission, Washington D.C., Federal Register, Volume 77, No. 14,January 23, 2012.4. Code of Federal Regulations, 10 CFR Part 50.55a, "Codes and Standards,"

U.S. NuclearRegulatory Commission, Washington D.C., Federal Register, Volume 77, No. 14,January 23, 2012.5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Division I, Appendix K, "Assessment of Reactor Vessels with Low Upper ShelfCharpy Impact Energy Levels,"

2007 Edition Up to and Including 2008 Addenda.6. ASME B&PV Code,Section XI, Division 1, Appendix A, "Analysis of Flaws," 2012 Edition.7. Regulatory Guide 1.161, "Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less than 50 Ft-Lb," U.S. Nuclear Regulatory Commission, June 1995.8. ASME B&PV Code, Section 11, Part D, "Materials,"

2012 Edition.9. B. R. Ganta, D. J. Ayres, and P. J. Hijeck, "Cladding Stresses in a Pressurized Water ReactorVessel Following Application of the Stainless Steel Cladding, Heat Treatment and InitialService,"

presented at ASME Pressure Vessel and Piping Conference, San Diego, California, June 1991.10. Westinghouse Design Specification DS-ME-04-10,.

Revision 3, "Design Specification for aReplacement Reactor Vessel Closure Head (RRVCH) for Palisades Nuclear Generating Station,"

August 2006.II. Westinghouse Report WCAP-15353

-Supplement 2 -NP, Revision 0, "Palisades ReactorPressure Vessel Fluence Evaluation,"

July 2011.12. Combustion Engineering Report P-PENG-ER-006, Revision 0, "The Reactor Vessel GroupRecords Evaluation Program Phase II Final Report for the Palisades Reactor Pressure VesselPlates, Forgings, Welds and Cladding,"

Combustion Engineering, Inc., October 1995.13. Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials,"

U.S.Nuclear Regulatory Commission, May 1988.WCAP- 17651-NP February 2013Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS37-214. "Fracture Toughness Requirements,"

Branch Technical Position 5-3, Revision 2, Contained inChapter 5 of Standard Review Plan for the Review of Safety Analysis Reports for Nuclear PowerPlants: LWR Edition, NUREG-0800, March 2007.15. NUREG/CR-5265, "Size Effects on J-R Curves for A 302-B Plate," U.S. Nuclear Regulatory Commission, January 1989.16. NUREG/CR-6426, Volumes I and 2, "Ductile Fracture Toughness of Modified A 302 Grade BPlate Materials, Data Analysis,"

U.S. Nuclear Regulatory Commission, January andFebruary 1997.17. Combustion Engineering Report CE-NPSD-993, Revision 0, "Evaluation of Low Upper ShelfEnergy for Reactor Vessel Beltline Weld and Base Metal Materials for Combustion Engineering Nuclear Steam Supply Systems Reactor Pressure Vessels,"

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