ML20116J385

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Evaluation of Pressurized Thermal Shock for Beaver Valley Unit 1 Reactor Vessel
ML20116J385
Person / Time
Site: Beaver Valley
Issue date: 06/30/1996
From: Boyle D, Grendys P
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20116J366 List:
References
WCAP-14543, NUDOCS 9608130174
Download: ML20116J385 (51)
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Text

i WESTINGHOUSE NON PROPRIETARY CLASS 3 WCAP-14543 I

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EVALUA110N OF PRESSURIZED THERMAL SHOCK FOR THE BEAVER VALLEY UNIT 1 REACTOR VESSEL P. A. Grendys i

June 1996 Work Performed Under Shop Onler DROP-108 i

F.pd by Westinghouse Electric Corporation for the Duquesne Light Company Appro by t

D. E. Boyle, Managerj/

Reactor Equipment &'Matenals Engineering WESTINGHOUSE ELECTRIC CORPORATION Systems and Major Projects Division P.O. Bo); * (5 Pittsburgh, Pennsylva. 4 15230-0355 C 1996 Westinghouse Electric Corporation All Rights Reserved 9608130174 960802 PDR ADOCK 05000334 P

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PREFACE j

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'Ihis report has been technically reviewed and ve n d by:

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E. Terek h

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TABLE OF CONTENTS Section Iitif East LIST OF TABLES

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LIST OF FIGURES.................................................. y t

1.0 INTRODUCTION

1 2.0 PRESSUR r7FD THERMAL SHOCK...................................

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3.0 METHOD FOR CALCULATION OF RTm.......

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4.0 VERIFICATION OF PLANT-SPECIFIC MATERIAL PROPERTIES.............

5 5.0 NEUTRON FLUENCE METHODOLOGY AND RESULTS................... 11 i

1 6.0 DETERMINATION OF RT VALUES FOR ALL BELTLINE REGION m

MATERIALS.................................................... 14 7.0 CONCLUS IONS.................................................. 16

8.0 REFERENCES

................................................... 17 i

APPENDIX A A-0 Determination of Transition Temperature Shifts (ARTm) from Hyperbolic Tangent Curve Fitting Methodt APPENDIX B B-0 Determination of Margin Term for Plate B6903-1 fmm Industry Data Scatter

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LIST OF TABLES i

t IAhlt Title Pass i

1 Beaver Valley Unit 1 Reactor Vessel Beltline Materials Average Cu and Ni Values.........................................................

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2 Interpolation of Chemistry Factors from Regulatory Guide 1.99, Revision 2 f

Position 1.1.....................................................

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3 Calculation of Chemistry Factors Using Credible Surveillance Capsule Data.........

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Beaver Valley Unit 1 Reactor Vessel Beltline Region Material Properties Used in Calculations..................................................... 10 j

5 Beaver Valley Unit 1 Surveillance Capsule Fluence Reevaluation Results I1 I

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6 Capsule Neutron Fluence (10" n/cm, E > 1.0 MeV) Projections................. 12 2

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Capsule I.ead Factor Projections....................................... 12 l

8 Best Estimate Maximum Fluence (10" n/cm, E > 1.0 MeV) for the Beaver 2

Valley Unit 1 Reactor Vessel Beltline Region Materials....................... 13 9

RTm Calculations for the Beaver Valley Unit 1 Beltline Region Materials 15 i

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a LIST OF FIGURES Eigut T.itls P. ass 1

Identification and Location of Beltline Region Materials for the Beaver Valley Unit i Reactor Vessel..............................................

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RTm versus EFPY of Operation for Beaver Valley Unit i Limiting Material -

Lower Shell Plate B6903-1.......................

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SECTION

1.0 INTRODUCTION

A limiting condition on reactor vessel integrity known as Pressurized Thennal Shock (IrrS) may occur during a severe system transient such as a Loss-Of-Coolant-Accident (LOCA) or a steam line break.

i Such transients may challenge the integrity of a reactor vessel under the following conditions:

sevese overcooling of the inside surface of the vessel wall followed by high repressurnation; significant degradation of vessel material toughness caused by radiation embrittlement; and the presence of a critical-size defect in the vessel wall.

In 1985, the Nuclear Regulatory Commission (NRC) issued a formal ruling on PTS. It established screening criteria on pressunzed water reactor (PWR) vessel embrittlement as measured by the nil-ductility reference temperature, termed RTm.N RTm screening values were set for beltline axial welds, forgings or plates, and beltline circumfenential weld seams for the end-of-license plant operation. All PWR vessels in the United States have been required to evaluate vessel embrittlement in accordance with the criteria through end of license. The NRC recently amended its regulations for light water nuclear power plants to change the procedure for calculating radiation embrittlement. 'Ihe revised FTS Rule was published in the Federal Register, May 15,1991 with an effective date of June 14,1991.2 This amendment makes the procedure for calculating RTm values consistent with the methods given in Regulatory Guide 1.99, Revision 2m, The purpose of this report is to determme the RTm values for the Beaver Valley Unit I reactor vessel to address the revised FTS Rule. Section 2.0 discusses the Rule and its requirements. Section 3.0 provides the methodology for calculating RTm. Section 4.0 provides the reactor vessel beltline region material properties for the Beaver Valley Unit I reactor vessel. The methodology and resulting neutron fluence values used in this analysis are presented in Section 5.0. The results of the RTm calculations are presented in Section 6.0. The conclusions and references for the FTS evaluation follow in Sections 7.0 and 8.0, respectively.

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SECTION 2.0 PRESSURI7Fn THERMAL SHOCK De PTS Rule requires that th: PTS submittal be updated whenever there are changes in core loadings, surveillance measurements or other information that indicates a significant change in projected RTm values. The Rule outlines regulations to address the potential for PTS events on pressurized water reactor vessels in nuclear power plants that are operated with a license from the United States Nuclear Regulatory Commission (USNRC). FTS events have been shown from operating experience to be transients that result in a rapid and severe cooldown in the primary system coincident with a high or increasing primary system pressure. De FTS concem arises if one of these transients acts on the beltline region of a reactor vessel where a reduced fracture resistance exists because of neutron irradiation. Such an event may result in the propagation of flaws postulated to exia near the inner wall surface, thereby potentially affecting the integrity of the vessel.

De Rule establishes the following requirements for all dornestic, operating PWRs:

All plants must submit projected values of RTm for reactor vessel beltline material by giving values for time of submittal, the expiration date of the operating license, and the projected expiration date if a change in the operating license or renewal has been requested. His assessment must be submitted within six months after the effective date of this Rule if the value of RTm for any material is projected to exceed the screening criteria. Otherwise, it must be submitted with the next update of the pressure-temperature limits, or the next reactor vessel surveillance capsule report, or within five years from the effective date of this Rule change, whichever comes first. Dese values must be calculated based on the methodology specified in j

this rule. De submittal must include the following:

1) the bases for the projection (including any assumptions regarding core loading patterns),

and

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2) copper and nickel content and fluence values used in the calculations for each beltline material. (If these values differ from those previously submitted to the NRC, justification must be provided.)

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The RTm screening criteria for the reactor vessel beltline region is:

270'F for plates, forgings, axial welds; and 300*F for circumferential weld material.

The following equations must be used to calculate the RTm values for each weld, plate or forging in the reactor vessel beltline:

Equation 1:

RTm = I + M + ARTm Equation 2:

A RTm = CF

  • f '"-"' 4 0 All values of RTm must be verified to be bounding values for the specific reactor vessel. In doing this each plant should consider plant-specific information that could affect the level of embrittlement.

Plant-specific PTS safety analyses are required before a plant is within three years of reaching the screening criteria, including analyses of altematives to minimize the FTS concem.

NRC approval for operation beyond the screening criteria is required.

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SECTION 3.0 METHOD FOR CALCULATION OF RTm In the PTS Rule, the NRC Staff has selected a conservative and uniform method for determining plant-specific values of RTm at a given time. For the purpose of comparison with the screening 1

1 criteria, the value of RTm for the reactor vessel must be calculated for each weld and plate or forging in the beltline region as follows.

j RTm = I + M + ARTm, where ARTm = CF

Initial reference temperature (RTm) in T of the unurmanted material M = Margin to be added to cover uncertainties in the values of initial RT, copper anJ nickel contents, fluence, and calculational procedures, per Regulatory Guide 1.99, Revision 2, in *F.

M = margin = 2 o,2 +,,2, 9 o, = 0*F when I is a measured value o, = 17'F when I is a generic value For plates and forgings:

o, = 17T when surveillance capsule data is not used o, = 8.5T when surveillance capsule data is used For welds:

03 = 28T when surveillance capsule data is not used ca = 14*F when surveillance capsule data is used o3 not to exceed 0.5*ARTm 1

i FF =

fluence factor = f S-*'* 0, where f = Neutron fluence (10 n/cm E>1.0 MeV) at the clad / base metal interface 2

CF = Chemistry Factor in 'F from the tablestri for welds and base metals (plates or forgings). If plant-specific surveillance data from two or more surveillance capsules has been deemed credible per Regulatory Guide 1.99, Revision 2, it should be considered in the calculation of the chemistry factor.

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SECTION 4.0 VERIFICATION OF PLANT-SPECIFIC MATERIAL PROPERTIES Before performing the pressurized thermal shock evaluation, a review of the latest plant-specific material properties for the Beaver Valley Unit I vessel beltline region was performed. The beltline region of a reactor vessel, per ASTM E185-82W is "the irradiated region of the reactor vessel (shell meerial including weld regions and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions that are predicted to experience sufficient neutron damage to warrant consideration in the selection of the surveillance material". Figure 1 identifes and indicates the location of all beltline region material for the Beaver Valley Unit I reactor vessel.

Material property values were MW from material test certifications from the original fabrication as well as the additional material chemistry tests performed as part of the surveillance capsule testing m

program. De average copper and nickel values were calculated by the Duquesne Light Company for each of the beltline region materials using all of the available matenal chemistry information."

his data was submitted to the NRC in response to Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Interrity. Table 1 presents these average Cu and Ni weight percent values.

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CIRCUMFERENTIAL SEAMS VERTICAL SEAMS 270*

86607-2 19-7148

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144.0" B6607-1 2

19-714A

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c 11-714 n

270' 20-71 87203-2 15'

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g n

20-714A 90'.

86903-1 Figure 1 Identification and Location of Beltline Region Materials for the Beaver Valley Unit 1 Reactor Vessel 6

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l TABLEI Beaver Valley Unit 1 Reactor Vessel Beltline Materials Average Cu and Ni Values Beltline Region Material Cu wt %

Ni wt %

Intermediate Shell Plate B6607-1 0.14 0.62 Intermediate Shell Plate B6607-2 0.14 0.62 lower Shell Plate B6903-1 (surveillance program) 0.20 0.54 Lower Shell Plate B7203-2 0.14 0.57 Intermediate Shell lang. Welds 19-714A/B 0.263 0.632 Heat #305424 tower Shell long. Welds 20-714A/B 0.338 0.606 Heat #305414 Circumferential Weld 11-714 0.278 0.071 Heat #90136 w

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TABLE 2 Interpolation of Chemistry Factors from Regulatory Guide 1.99, Revision 2, Position 1.1 Material Ni, wt %

Chemistry Factor, 'F Intermediate Shell Pigg 0.60 100

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0.62 100.5

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Given Cu wt % = 0.14 0.80 105 Intermediate Shell Plate 0.60 100 0.62 100.5 Given Cu wt % = 0.14 0.80 105 Lower Shell Plate 0.40 125 0

0.54 141.8 Given Cu wt % = 0.20 0.60 149 lower Shell Plate 0.40 91 B7203-2 0.57 98.7 Given Cu wt % = 0.14 0.60 100 Inter. Shell long. Welds 0.60 181.2 0.632 186.3 Given Cu wt% = 0.263 0.80 213.2 Lower Shell tene.

0.60 206.2 Welds 20-714A/B

,,3 Given Cu wt% = 0.338 0.80 237.2 Cire Weld 11-714 0.00 121.4 0.071 127.0 Given Cu wt% = 0.278 0.20 137.2 9

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TABLE 3 Calculation of Chemistry Factors Using Credible Surveillance Capsule Data Material Capsule Capsule f FF ART,

FF* A RT, FF2 Lower Shell Plate B6903-1 V

0.316 0.684 128.1 87.6 0.467 (Longitudinal)

U 0.690 0.8 %

118.9 106.5 0.803 W

0.915 0.975 147.7 144.0 0.95i Lower Shell Plate B6903-1 V

0.316 0.684 137.8 94.2 0.467 (Transverse)

U 0.690 0.8%

131.8 118.1 0.803 W

0.915 0.975 179.9 175.4 0.951 Sum:

725.9 4.442 163.4 Weld Metal V

0.316 0.684 158.0 108.1 0.468 U

0.690 0.8%

164.6 147.5 0.803 W

0.915 0.975 185.8 181.2 0.951 Sum:

436.7 2.221 1%.6 dU l r.5:

f = fluence (10" n/cm". Obtamed from recent fluence reevaluation presented in Secuon 5.0 of this report (documented in WCAP-14554m).

FF = fluence factor = f""***

  • ARTmvalues obtained from hyperbolic tangent curve-fined Charpy V-notch curves. See Appendix A of this report.

CF = E(FF

2 A summary of the pertinent chemical and mechanical properties of the beltline region plates and weld materials of the Beaver Valley Unit I reactor vessel are given in Table 4. Chemistry Factor (CF) and Initial RTm (I) values are also presented in Table 4.

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TABLE 4 Beaver Valley Unit 1 Reactor Vessel Beltline Region Material Properties Used in Calculations l

Material Cu wt %

Ni w" %

Chemistry Factor. 'F"'

Initial RTm,r, 'F Intermediate Shell Plate B6607-1 0.14 0.62 100.5 43 Intermediate Shell Plate B6607-2 0.14 0.62 100.5 73 Lower Shell Plate B6903-1 0.20 0.54 141.8 27 Lower Shell Plate B6903-1 163.4 27 Using S/C Data (RG 1.99, Pos. 2.1) lower Shell Plate B7203-2 0.14 0.57 98.7 20 i

Intermediate Shell long. Welds 19 714A/B 0.263 0.632 186.3

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Heat #305424 Intermediate Shell Long. Welds 19-714A/B 1%.6

-56 Using S/C Data (RG 1.99, Pos. 2.1) lower Shell long. Welds 20-714A/B 0.338 0.606 209.1

-56 Heat #305414 CL-..fas.tial Weld Il-714 0.278 0.071 127.0

-56 Heat #90136

,LV.JL (a) Chemistry Factor calculated per Tables I and 2 of 10 CFR 50.61 and Regulatory Guide 1.99, Revision 2 Position 2.1.

(b) Initial RT,,,, values of the plate amaterials are measured while the weld materials have generic values.

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SECTION 5.0 NEUTRON FLUENCE METHODOLOGY AND RESULTS i

This section provides the results of the neutron dosimetry evaluation. Included is an update of the i

dosimetry evaluation for Capsules V, U, and W. This update is based on current state-of-the-art methodology and nuclear data including recently released neutron transport and dosimetry cross-section libraries derived from the ENDF/B-VI database. This report provides a consistent up-to-date j

r.eutan exposure database for use in evaluating the material properties of the Beaver Valley Unit I reactor vessel. The complete Beaver Valley Unit 1 fluence reevaluation is documented in WCAP-14554t71. The results of the updated dosimetry evaluation for each of the survei' lance capsules removed to date are presented in the following table.

TABLE 5 Beaver Valley Unit 1 Surveillance Capsule Fluence Reevaluation Results 1 r7 Capsule Capsule lead Faceo-Capsule Fluence Uncenanty EFPY (10 n/cm, E>l.0 MeV) 2 V

1.65 0.316 8%

1.16 U

l.10 0.690 8%

3.58 W

l.10 0.915 9%

5.92 s

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k Additicnally, the updated capsule fluence values and lead factors for the capsules remaining in the reactor vessel are presented in Tables 6 and 7 respectively.

I TABLE 6 Capsule Neutron Fluence (10" n/cm, E > 1.0 MeV) Projections'3 2

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EPPY Capsule X Capsule Y Capsule T Capsule Z Capsule S 10.8 (EOC 10) 2384 1.589 1.084 1.084 0.8626 12 2.544 1.723 1.217 1.244 0.9441 14 2.822 1.956 1.450 1.522 1.086 16 3.101 2.188 1.683 1.801 1.228 18 3379 2.421 1.915 2.079 1369 20 3.658 2.654 2.148 2358 1.511 22 3.936 2.886 2381 2.636 1.653 24 4.215 3.119 2.613 2.915 1.795 26 4.493 3352 2.846 3.193 1.936 27.1 (EOL) 4.646 3.480 2.974 3346 2.014 TABLE 7 Capsule lead Factor ProjectionsM EFPY Capsule X Capsule Y Capsule T Capsule Z Capsule S 10.8 (EOC 10) 1.73 1.16 0.79 0.79 0.63 12 1.71 1.16 0.82 0.84 0.64 14 1.69 1.17 0.87 0.9) 0.65 16 1.66 1.17 0.90 0.97 0.66 18 1.64 1.18 0.93 1.01 0.67 20 1.63 1.18 0.96 1.05 0.67 22 1.62 1.19 0.98 1.08 0.68 24 1.61 1.19 1.00 1.11 0.68 26 1.60 1.19 1.01 1.13 0.69 27.1 (EOL) 1.59 1.19 1.02 1.15 0.69 12

The calculated peak fast neutron fluence (E > 1.0 MeV) values at the inner surface of the Beaver Valley Unit I reactor vessel are presented in Table 8. Fluence values are projected for each of the reactor vessel beltline region materials.

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TABLE 8

.Best Estimate Maximum Fluence (10" n/cm, E > 1.0 MeV) for the 2

Beaver Valley Unit 1 Reactor Vessel Beltline Region Materialsm EFPY lower Shell Lower Shell Cucumf. tial Intermediate Shell Intermediate Shell Plates lengitudinal Weld Plates longitudinal Welds Welds 10.8 (EOC 10) 1.376 c.2726 1376 1376 0.2726 12 1.478 03009 1.478 1.485 03009 14 1.655 03500 1.655 1.675 03500 16 1.833 03991 1.833 1.865 03991 18 2.010 0.4482 2.010 2.055 0.4482 20 2.188 0.4973 2.188 2.244 0.4973 22 2365 0.5464 2365 2.434 0.5464 24 2.543 0.5955 2.543 2.624 0.5955 26 2.721 0.6446 2.721 2.814 0.6446 27.1 (EOL) 2.818 0.6716 2.818 2.919 0.6716

)

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SECTION 6.0 DE'IERMINATION OF RTm VALUES FOR ALL BELTLINE REGION MATERIALS Using the prescribed FTS Rule methodology, RT values were generated for all beltline region m

l materials of the Beaver Valley Unit I reactor vessel for fluence values at the present time (10.8 EFPY), and end-of-license. The end-of-license EFPY was calculated to be 27.1 EFPY. The FTS Rule requires that each plant assess the RTm values based on plant specific surveillance capsule data whenever:

Plant-specific surveillance data has been deemed credible as defm' ed in Regulatory Guide 1.99, Revision 2, and RTm values change significantly. (Changes to RTm values are considered significant if the value determined with RTm quations (1) and (2), or that using capsule data, or both, exceed e

the screening criteria prior to the expiration of the operating license, including any renewed term, if applicable, for the plant.)

As presented in Table 2, chemistry factor values for the Beaver Valley Unit I beltline region materials based on average copper and nickel weight percent were calculated using Tables 1 and 2 from 10 CFR 50.61. Additionally, chemistry factor values based on credible surveillance capsule data were calculated per Regulatory Guide 1.99, Revision 2, Position 2.1 (Table 3). Table 4 pmsents all of the chemistry factor and initial RT, values used in the FTS calculations. Table 9 provides a summary of the RTm values for all beltline region material for 10.8 and 27.1 EFPY.

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TABLE 9 RTm Calculations for the Beaver Valley Unit 1 Beltline Region Materials Material CF f

FF I

M ARTm RTm Current Time 10.8 EFPY Inter. Shell Plate B6607-1 100.5 1376 1.089 43 34 109.4 186.4 Inter. Shell Plate B6607-2 100.5 1376 1.089 73 34 109.4 216.4 lauer Shell Plate B6903-1 141.8 1376 1.089 27 34 154.4 215.4 using SC data 163.4 1376 1.089 27 29.l*

177.9 234.0

~

(RG Pos. 2.1)

Lower Shell Plate B7203-2 98.7 1376 1.089 20 34 107.5 161.5 Inter. Shell long. Welds 1863 0.2726 0.646

-56 65.5 1203 129.8 19-714A/B using S/C data 1%.6 0.2726 0.646

-56 44 127.0 115.0 (RG Pos. 2.1)

Lower Shell lang. Welds 209.1 0.2726 0.646

-56 65.5 135.0 144.5 20-714A/B Circumferential Weld 11-714 127.0 1376 1.089 56 65.5 1383 147.8 End-of Life (27.1 EFPY)

Inter. Shell Plate B66071 100.5 2.919 1.284 43 34 129.1 206.1 Inter. Shell Plate B6607-2 100.5 2.919 1.284 73 34 129.1 236.1 lower Shell Plate B6903-1 141.8 2.818 1.276 27 34 180.9 241.9 using SC data 163.4 2.818 1.276 27 29.l*

208.4 2643 (RG Pos. 2.1)

Lower Shell Plate B7203-2 98.7 2.818 1.276 20 34 125.9 179.9 1

4 Inter. Shell Long. Welds 1863 0.6716 0.888

-56 65.5 165.5 175.0 19-714A/B I

l using SC data 1%.6 0.6716 0.888

-56 44 174.7 162.7 l

(RG Pos. 2.1) 4 Lower Shell Long. Welds 209.1 0.6716 0.888

-56 65.5 185.8 195 3 20-714A/B i

i Circumferential Weld 11-714 127.0 2.818 1.276

-56 65.5 162.0 171.5 I

  • Determined to be 29.l*F from 1o band ofindustry data scatter'3 See Appendix B.

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SECTION

7.0 CONCLUSION

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As shown in Table 9 all RTm values remain below the NRC PTS screening criteria values using fluence values for the present time (10.8 EFPY) and end-of-license (27.1 EFPY). A plot of RTm values versus EFPY of Operation, shown in Figure 2, illustrates the available margin for the Beaver Valley Unit I reactor vessel beltline region materials. Lower Shell Plate B6903-1 is the limiting Beaver Valley Unit I reactor vessel beltline region material.

RTPTS vs. EFPY of Operation 30 300

[6

- wrw

--g g _mism CD 5

i-100 (E

100

)

M PTS Semoning CHieda

--- Lamer shot Mate 30003-1 30003-1 using SC Dela to 8 EPPY 27.1 EPPY EFPY of Operation Figure 2 RTm versus EFPY of Operation for Beaver Valley Unit 1 Limiting Material - Lower Shell Plate B6903-1 16

SECTION

8.0 REFERENCES

1.

10 CFR Part 50.61, " Analysis of Potential Pressurized Hermal Shock Events," July 23,1985.

2.

10 CFR Part 50.61, " Fracture Toughness Requirements for Protection Against Pressurized

' Dermal Shock Events," May 15,1991. (PTS Rule) 3.

Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials,"

U.S. Nuclear Regulatory Commission, May 1988.

4.

ASTM E185-82, " Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels", E706 (IF).

5.

WCAP-8457, "Duquesne Light Company Beaver Valley Unit No.1 Reactor Vessel Radiation Surveillance Program", J. A. Davidson, et al., October 1974.

6.

" Beaver Valley Power Station Reactor Vessel Dr.ta, Unit 1", RVDATA3.XLS, Ted Huminski, Duquesne Light Company,11/9/95 7.

WCAP-14554, Beaver Valley Unit 1 Fluence Reevaluation, S. L. Anderson, dated June 1996.

8.

" Beaver Valley 1 Reactor Vessel PTS Analysis", prepared by Timothy J. Griesbach, reviewed by Brian F. Beaudoin, ATI Consulting, dated 12/12/95.

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APPENDIX A Reevaluation of the Charpy V-Notch Transition Temperature Shifts (ARTm) using Hyperbolic Tangent Curve Fitting Methods

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De limiting material of interest in the Beaver Valley Unit I reactor vessel is lower shell plate B6903-1, heat mtmber C6317-1. His plate is also the Beaver Valley Unit I surveillance program base material. Both longitudinal (LT) and transverse (TL) orientated specimens from this plate material were tested in the unirradiated and irradiated conditions. The irradiated data was obtained from specimens removed and tested from Capsules U, V, and W (References A-2 through A-5).

Position 2.1 of Regulatory Guide 1.99, Revision 2l^* has been used to evaluate the projected level of embrittlement in this plate from a best-fit of the measured Charpy V-notch test data. A reevaluation of the Charpy test data was performed using the CVGRAPH program'^*, which calculated a hyperbolic tangent (TANH) curve-fit of the data. De hyperbolic tangent function is commonly used to mathematically describe the Charpy test results according to the following equation. (See Figure 1 of this Appendix.)

CVN = A + B ranh [(T-To/ CJ (1)

J where CVN is the Charpy V-notch energy, (A - B) is the asymptotic lower shelf energy, (A + B) is the asymptotic upper shelf energy, To is the mid-transition temperature corresponding to A, and C is the measure of the slope of the transition region.

j Eight sets of data were considered he impact energy versus temperature values were obtained and tanh coefficients determmed for curve-fits to each of the data sets. De fitted results for the base material are shown in Figures 2 through 5 for the transverse data and Figures 6 through 9 for the longitudinal data. He calculated Tw and AT, temperatures are given in Table A-1.

e A-1

TABLE A-1 Calculated T, and ATw Values from the TANH Curve-Fits Capsule Orientation T, (*F)

Calculated AT,(*F) l Unitradiated TL 18.1 I

V TL 155.9 137.8 f

U TL I49.8 131.7 W

TL 198.0 179.9 Uni: radiated LT 3.4 V

LT 124.8 128.",

U LT 115.4 118.9 W

LT 1445<

147.8 l

The Beaver Valley Unit I surveillance weld is heat number 305424, which is same material as the i

intermediate shell axial welds in the reac%r vessel. The weld material was tested in the unirradiated and irradiated conditions. The irrsdiated data was obtained from specimens removed and tested frem Capsules U, V, and W (References A-2 through A-5). 'Ihe impact energy versus temperature values were obtained and tanh coefficients determined for curve-fits to the data. "Ihe results for the Beaver Valley Unit I surveillance weld are shown in Figures 10 through 13 of this appendix. The calculated T, and AT, values are presented in the following table.

TABLE A-2 1

Calculated T, and ATm Values from the TANH Curve-Fits Capsule T ('F)

Calculated AT (*F)

Unirr=Amiad

-66.0 i

V 91.8 157.8 U

98.4 164.4 W

l19.6 185.6 i

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REFERENCES.

A-1.

" Beaver Valley 1 Reactor Vessel MS Analysis", prepared by Timothy J. Griesbach, reviews.d by Brian F. Beaudoin, ATI Consulting, dated 12/12/95.

A-2, WCAP-8457, "Duquesne Light Company Beaver Valley Unit No.1 Reactor Vessel Radiatiori Surveillance Program", J. A. Davidson, et al., October 1974.

A-3.

WCAP-9860, " Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Prc,,r.cn", S. E. Yanichko, et al., January 1981.

A-4.

WCAP-10867, " Analysis of Capsule U from the Duquesne Light Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program", R. S. Boggs, et al., September 1985.

A-5.

WCAP-12005, " Analysis of Capsule W from the Duquesne Light Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program", S. E. Yanichko, et al., November 1988.

A-6.

Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials",

May 1988.

A-7.

CVGRAPH, Charpy V-Notch Curve-Fitting Routine, Version 4.0, developed by ATI Consulting, March 1995.

O i

A-3 i

I i-i B/C 1

45

)

RESPONSE = A+ B Tanh C

N A

~~-

uc 3

I I

)

.C

+C TO TEM.P ERATURE, T i

i i

i l

Figure 1. Hyperbolic Tangent (TANH) CVN Curve

1 Beaver Valley Unit 1 - Base Metal /TL (Unirr)

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 16J509 on 12-12-1995 Page1 Coefficients of Curve 1 A = 43.49 B = 4l29 C = 93 M 1D = 49.68 F uation is: CVN = A + B ' l tanh((T - TO)/C) ]

4 Upper Shelf Energy: 84.78 Temp at 30 ft-ils 181 Temp. at 50 ft-lbs 64.4 lower Shelf Energy: 22 Fixed Material: PLATE SA533B1 Heat Number: 08317-1 Orientation TI, Capsule: Unirr Total Fluence: 0.0 300 cn 250

,C

~

laN am N

1:$

4 150 a>c m

100 z

[

o

>o

/

50 P;/

a D

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant BV1 Cap; Unirr Material PLATE SA533B1 Ori: TI, Heat f: 06317-1 Charpy V-Notch Data l

Temperature input CVN Energy Computed CVN Energy Differential 1

-100 4

538

-138

-100 25 538

-2B8

-100 45 538

- 118 l

-100 5

538

-38 l

-50 135 10M 2E2

-50 6

10M

-4B7

-50 11 1037 12

- Data continued on next page "

Figure 2. Unirradiated Charpy V-Notch Data (TL Orientation)

Beaver Valley Unit 1 - Base Metal /TL (Unirr) l I

Page2 l

Material PLATE SA533B1 Heat Number. m317-1 Orientation TL Capsule Unirr Total Fluence 0.0 Charpy V-Notch Data (Continued)

Temperature input CVN Energy Computed CVN Energy Differential

-50 11 10B7

.12

-50 11 10E7 J2 l

10 33 2638 6.11 10 40 2638 1111 10 285 2638 131 10 285 2638 ISI 10 20 2638

-638 40 465 3921 728 40 34 3921

-521 l

40 36 3921

-321 40 33 3921

-621 40 41 3921 L78 40 31 3921

- 8 21 11 0 65 67M

-2M 11 0 64 67M

-3M 110 63.5 67M

-354 110 77 67M 9.95 160 765 77.73

-123 160 76 77.73

-L73 160 825 77.73 4.76 160 82 77.73 426 160 795 77.73 176 210 83 8223

.76 210 825 8223 26 210 75 8223

-723 1

210 82 (E23

-23 SUM of RESIDUAIS = -2flS j

i b

l 1

Beaver Valley Unit 1 - Base Metal /TL (V) f I

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 16059J on 12-12-1995 l

Page1 Coefficients of Curve 2 A : 422 B = 40 0 = 10033

% = 1875 Fquation is CVN : A + B * [ tanh((T - W)/C) ]

Upper Shelf Energy: 8221 Temp. at 30 ft-lbs 155B Temp at 50 ft-lbs 2072 Imer Shelf Energy: 22 Fixed j

Material PLATE SA533B1 Heat Number. 06317-1 Orientation TL j

Capsule: V Total Fluence 336E18 a00 I

m 250 O

l>

x 200 h

te L

150 ec N

100 Z

0 jwo yo

/

50 b

3 o

-300

-200

-100 0

100 200 300 400 500 800 Temperature in Degrees F Data Set (s) Plotted Plant BV1 Cap V Material: PLATE SA533B1 Ori: TL Heat f. 06317-1 Charpy V-Notch Data Temperature input CVN Energy Computed CVN Energy Differential 0

25 4D6

-156 75 16 5 938 6S1 100 16 14J IB9 150 30 US1 2DB 150 285 US1 2

200 355 4736

-11E 200 42 4736

-536

= Data continued on c st page **

Figure 3. Capsule V Charpy V-Notch Data (TL Orientation)

Beaver Valley Unit 1 - Base Metal /TL (V)

Page2 Materiah PLATE SA533B1 Heat Number. G317-1 Orientation: TL Capsule V Total Fluence :ll6D8 Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 210 43 5103

-E03 220 66 54.73 1126 250 77 6433 12fi6 300 755 7453

.96 350 735 7939

-5S9 SUM of PEDUAIS = 397 O

e

'l

Beaver Valley Unit 1 - Base Metal /TL (U)

CVCRAPH 4.0 Hyperbolic Tangent Curve Printed at 16:35'09 on 12-12-1995 Page1 l

Coefficients of Curve 3 A = 41B9 B = 39.49 C = 1272 TO = 188.67 F uation is CVN : A + B ' l tanh((T - 1D)/C) ]

4 Upper Shelf Energy: 81.19 Temp. at 30 ft-lbs 149B Temp. at 50 ft-lhe 215B lower Shelf Energy: 22 Fixed Material: PIATE SA533B1 Heat Number: G317-1 Orientation TL Capsule U Total Fluence: 6.90E18 30o cn aso Q

~

laA am N

kD a

150 Oc N

100 Z

cs.

O so r

b U

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap.:U Material PLATE SA533B1 Ori: TL Heat f. 2317-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 50 11 1022

.77 78 20 1399 6

100 16 17B9

-139 150 28 30.04

-2.04 150 32 30.04 1.95 17 5 34 37.46

-146 200 42 452

-32

- Data continued on next page "

Figure 4. Capsule U Charpy V-Notch Data (TL Orientation)

Beaver Valley Unit 1 - Base Metal /TL (U)

Page2 Material PIATE SA533B1 Heat Number. G317-1 Orientation TL Capsule U Total Fluenm 6.90E16 Charpy V-Notch Data (Continued)

Temperatum Input CVN Energy Computed CVN Energy Diffemntial 250 65 5939 5S 300 69 695

-5 350 7/

75.4 159 400 76 7&44

-144 450 80 7 9.91 DB SUM of RESIDUAIS = 145 O

e

u 4

Beaver Valley Unit 1 - Base Metal /TL (W)

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 16:35D9 on 12-12-1995 Page1 Coefficients of Curve 4 A = 31J2 B = 28.92 C = 482 TO = 199.9 Equation is CVN = A + B ' I tanh((T 'm)/C) }

Upper Shelf Energy: 60D4 Temp. at 30 ft-lbs 198 Temp. at 50 ft-lk 237.4 lower Shelf Energy: 22 Fixed Material PLATE SA553B1 Heat Number: G317-1 Orientation: TL Capsule: W Total Fluen : 9J5DB 300 m

2so

.c l5 200 m

bD L

150 ecw 100 1

0 y

a 5"

(

a) 0

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted j

Plant: BV1 Cap: Y gria Py_TQgBy0ri: TL Heat f. m317-1 Temperature input CVN Energy Computed CVN Energy Differential 76 19 253 16.46 125 15 4E7 1032 l

175 18 1738 S1 180 18 1931

-131 200 29 3L18

-?_18 200 25 3tl8

-6.18 210 40 37D9

?.9

= Data continued en next page "

Figure 5. Capsule W Charpy V-Notch Data (TL Orientation)

\\

Beaver Valley Unit 1 - Base Metal /TL (W)

Page2 Material: PLATE SA533B1 Heat Numben m317-1 Orientation: TL Capsule i Total Fluenz 9J5E18 Charpy V-Notch Data (Continued)

Temperature input CVN Energy Computed CVN Energy Differential 225 50 44.95 5.04 250 55 53E1 138 300 59 59J5

-J5 400 62 60.03 L96 450 55 60.04

-5.04 SUM of REDUAIS : 2134 e

9 I

l i

Beaver Valley Unit 1 - Base Metal /LT (Unirr)

CVCRAPH 4D Hyperbolic Tangent Curve Printed at 165524 on 12-12-1995 Page1 Coefficients of Curve !

A = 6&93 B = 6&73 C = 8176

% = 525 F uation is CVN = A + B ' [ tanh((T - W)/C) ]

4 Upper Shelf Energy: 135B7 Temp. at 30 ft-lbs -14 Temp. at 50 ft-lbs 28 Imer Shelf Energy: 239 Fired Materiah PLATE SA533B1 Heat Number: 06317-1 Orientation LT Capsule Unirr Total Fluena: 0.0 30u m

250

.D Ia%

am h

t:e L

150 c) d N

r 100 a

U o

V W

D

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap: Unirr Materiah PLATE SA533B1 Ori: LT Heat f. 06317-1 Charpy V-Notch Data Temperature input CVN Energy Computed CVN Energy Diffe.mntial

-50 10 12B2

-2B2

-50 8

12m

-4B2

-50 21 12E BJ7 10 445 37.71 6.78 10 50 37.71 1228 10 20 37.71

-17.71 60 71 74B9 2]

= Data continued on next page "

Figure 6. Unirradiated Charpy V-Notch Data (LT Orientation)

i i

Beaver Valley Unit 1 - Base Metal /LT (Unirr)

Page2 Material PLATE SA533B1 Heat Numben 2317-1 Orientation: LT Capsule Unirr Total Fluence 0.0 Charpy V-Notch Data (Continued)

Temperature input CVN Energy Computed CVN Energy Differential 60 90 7439 15.1 60 54 74 5

-20M 100 1015 10118

-128 l

100 103 10118

-18 l

100 107 10118 3E1 l

210 134 132B3 136 1

210 1335 132E3 A6 1

210 1315 132E3

-1.13 300 131 13531

-431 300 137 13531 128 300 136 13531 E8 SUM of REDUAIS =.72

'r D

Beaver Valley Unit 1 - Base Metal /LT (V)

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 16fh24 on 12-12-1995 Page1 Coefficients of Curve 2 A = 602 B = SBE5 C = 89.99 1D = 17/.42 F uation is CVN : A + B ' [ tanh((T - TO)/C) 1 4

Upper Shelf Energy:1195 Temp at 30 ft-lbs 124B Temp. at 50 ft-lbs 1605 lower Shelf Energy: 22 Fixed Material PLATE SA533B1 Heat Number 06317-1 Orientation: LT Capsuie V Total Fluence 3.16D8 30o u,

2so C

~

lax 2m Ne L

150 a)

M O

N AF" 100 2;>

/o 0

50 o

1 o

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap:V Material PLATE SA533B1 Ori: LT Heat f. 06317-1 i

Charpy V-Notch Data Temperature input CVN Energy Computed CVN Energy Differential 75 13 1332

.12 103 14 5 20

-55 100 335 20 13.4 9 150 445 435

.99 1'

200 58 7J25

-1725 250 1235 100 2149 300 1055 11227

-&7/

" Data continued on next page "

Figure 7. Capsule V Charpy V-Notch Data (LT Orientation)

Beaver Valley Unit 1 - Base Metal /LT (V)

Page2 Material: PLATE SA53381 Heat Number. 06317-1 Orientation LT Capsule V Total Fluence 3.16ElB Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 350 11 3 117 2

-42 SUM of RESIDUAIS = 429 i

9

Beaver Valley Unit 1 - Base Metal /LT (U)

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 16ffr24 on 12-12-1995 Page1 Coefficients of Curve 3 A : 5523 B = 53D3 C = 106.02 E = 17032 Fquation is CVN : A + B ' l tanh((T 'ID)/C) l Upper Shelf Energy: 10826 Temp. at 30 ft-lbs 115.4 Temp. at 50 ft-ils 1593 Imer Shelf Energy: 2.2 Fixed Material PLATE SA533B1 Heat Number G317-1 Orientation LT Capsule U Total Fluence 6.90DB 30u en 250

,O I$

200 x

te k

150 ecw o

100

>u

.A Su_

M U

l

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plottal Plant BV1 Cap.: U Material: PLATE SA533B1 Ori.: LT Heat f: 06317-1 Charpy V-Notch Data Temperature input CVN Energy Computed CVN Energy Differential 50 8

I? 13

-433 78 25 18.01 6.98 100 20 24.44

-4.44 150 53 4 5.18 7B1 200 58 69E9

-11E9 250 91 B&96 2D3 300 111 99B1 11.18

= Data continued on next page "

Figure 8. Capsule U Charpy V-Notch Data (LT Orientation)

Beaver Valley Unit 1 - Base Metal /LT (U)

Page2 7

)

Material: PLATE SA533B1 Heat Number. 06317-1 Orientation LT Capsule U Total Fluence 690E18 Charpy V-Notch Data (Continued)

Temperature input C'H Energy Computed CVN Energy Differential 400 99 106B9

-739 1

SUM of RESIDUAIS = -J4 1

e 5

1 i

i i,

i i

a

(

i

Beaver Valley Unit 1 - Base Metal /LT (W)

CVGRAPH 4D Hyperbolic Tangent Curve Printed at 165524 on 12-12-1995 Page1 Coefficients of Curve 4 A = 59J5 B = 56.95 C = 74f/

W = 1862 Equation is CVN = A + B ' I tanh((T - W)/C) ]

Upper Shelf Energy: 116.11 Temp. at 30 ft-lbs 1443 Temp at 50 ft-lbs 1742 Imer Shelf Energy: 22 Fixed Material PIATE SA533B1 Heat Number. OS317-1 Orientation LT Capsule: W Total Fluence: 935E18 300 u) 250 4

IaN 200 h

t:e 4

150 asc m

j u 100 s

o J

so J

a-

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap: W ggPgT(gBy0ri: LT Heat f: G317-1 l

Temperatum Input GW Energy Computed GW Energy Diffemntial 100 15 1235 2S4 150 33 3332

-2 175 50 5053

-53 200 69 69 2

-2 300 115 111DI 3.98 400 112 115.75

-3.75 SUM of RESIDUAIS = 1.48 Figure 9. Capsule W Charpy V-Notch Data (LT Orientation)

Beaver Valley Unit 1 - Weld Metal (Unirr)

CVCRAPH 4D Hyperbolic Tangent Curve Printed at 17:16:33 on 12-12-1995 Page1 i

Coefficients of Curve 1 A = fn73 B = 5353 C = 53B8 1B = -3725 Fquation is CVN = A + B ' l tanh((T - 1D)/C) ]

Upper Shelf Energy: 10926 Temp. at 30 ft-lbs -65.9 Temp. at 50 ft-lbs -433 lower Shelf Energy: 22 Fixed Material ELD Heat Number. 305424 Orientation-Capsule Unirr Total Fluence: OB 3m 1

en 250

.o I

1 ag am i

x 1-em 150 e

c o

n N

-L B

100 g

n i

o so o

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap Unirr Material ELD Ori.:

Heatf.305424 Charpy V-Notch Data Temperature input CVN Energy Computed CVN Energy Diffemntial

-150 2

3B1

-131

-150 4

331 18

-150 25 3B1

-131

-60 26 34B2

-832

-60 37 3432 237

-60 27 34B2

-7B2

'.5 75 683 639

- Data continued on next page "

Figure 10. Unirradiated Charpy V-Notch Weld Data

Beaver Valley Unit 1 - Weld Metal (Unirr)

Page2 Material WELD lient Number: 305424 Orientation-Capsule Unirr Total Fluence 0.0 Charpy V-Notch Data (Continued)

Temperatun input CVN Energy Computed CVN Energy Diffenntial

-25 88 683 1929

-25 77 683 869 0

88 8826

-26 0

665 8826

-21.76 0

80 8&26

-826 100 1085 108 S 3

-13 100 100 10 & 6 3

-BE3 100 117 5 108E3 826 210 1035 109 5

-5.75 210 122 10925

!?.74 210 11 0 1093

.74 SUM of Rl!SIDUAIS = -4B i

i A-J

Beaver Valley Unit 1 - Weld Metal (V)

CVGRAPH 4.0 Hyperbolic Tangent Curve Printal at 17:1633 on 12-12-1995 Page1 Coefficients of Curve 2 A = 4556 B = 4336 C = 10918 1B = 132B1 Equation is CVN = A + B ' [ tanh((T - TO)/C) J Upper Shelf Energy: 8893 Temp at 30 ft-lbs 91.7 Temp at 50 ft-lbs 144 lower Shelf Energy: 22 Fixed Material: ELD Heat Number: 315424 Orientation-Capsule: V Total Fluence: 116D8 30o m

250

,o IaN 2m N

tm 4

150 a>c M

100 z

o d

)

O o

m 0

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap:V Material: ELD Ori:

Heat f: 305424 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0

5 92

-42 75 29 2453 4.46 100 30.5 3191

-141 100 37 3191 4DO 125 37 4147

-5.47 150 535 5234 115 150 525 5234

.15

" Data antinued on next page "

Figure 11. Capsule V Charpy V-Notch Weld Data

l l

Beaver Valley Unit 1 - Weld Metal (V) i Page2 Material WDD Heat Number. 305424 Orientation-Capsule V Total Fluenx 116D8 Charpy V-Notch Data (Continued)

Temperatum Input CVN Energy Computed CVN Energy Differential 200 71.5 6933 P_16 250 75 7936

-4B6 300 90 85.06 4.93 350 87 8734

-34 400 875 8829

.79 SUM of RESIDUAIS = -1.12 l

O l

Beaver Valley Unit 1 - Weld Metal (U)

CVCRAPH 4D flyperbolic Tangent Curve Printed at 17:16:33 on 12-12-1995 Page1 Coefficients of Curve 3 A = 465 B = 443 C = 14138

11) = 15175 Equation is CVN = A + B ' I tanh((T - 11))/C) ]

Upper Shelf Energy: 903 Temp at 30 ft-lbs 9&4 Temp at 50 ft-lbs 164S lower Snelf Energy: 22 Fired Material: WELD Heat Number. 305424 Orientation:

Capsule U Total Fluence 6.90E18 300 rn 250

,C IaN 2m N

te L

150 Cc N

100 2

s D

j

/t y

O

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plottal Plant: BV1 Cap;U Material TELD Ori:

Heat f. 305424 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0

10 1124

-124 50 19 18.79 2

78 32 24 3 719 78 28 24B 339 100 30 3042

,42 150 34 4532

-1132 150 42 4532

-332

= Data continued on next page "

Figure 12. Capsule U Charpy V-Notch Weld Data

Beaver Valley Unit 1 - Weld Metal (U)

Page2 Material YllD Heat Number. 305424 Orientation-Capsule U Total Fluence 6.90E18 Charpy V-Notch Data (Continued)

Temperature loput CVN Energy Computed CVN Energy Differential 200 67 60.5 6.49 200 58 605

-25 250 80 7P.73 726 300 80 mm

-m 400 86 -

8&l6

- 2.16 SUM of PEIDUAIS = 2.48 1

i O

e

._y

Beaver Valley Unit 1 - Weld Metal (W)

CVGPAPH 4.0 Hyperbolic Tangent Curve Printed at 17d6:33 on 12-12-1995 Page1 Coefficients of Curve 4 A = 423 B = 403 C = 107.92 W = 153B Equation is CVN = A + B ' l tanh((T - %)/C) )

Upper Shelf Energy: 8?.41 Temp at 30 ft-Its 1195 Temp. at 50 ft-lbs 174.7 lower Shelf Energy: 22 Fixed Material TELD fient Number: 305424 Orientation:

Capsule i Total Fluence 915E18 300 m

250

,C IoN 2m N

bD L

150 0c N

z D

Y

^

so a

V o

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set (s) Plotted Plant: BV1 Cap: FCharh*yNMh dan

    • b Temperature Input CVN Energy Computed CVN Energy Differential 25 15 895 6.04 76 27 1754 9.45 125 30 3134

-134 125 24 3134

-734 150 35 4039

-5B9 150 47 4039 63 200 43 5&49

-15.49

- Data continued on next page =

Figure 13. Capsule W Charpy V-Notch Weld Data l

l 1

Beaver Valley Unit 1 - Weld Metal (W)

Page2 Material WBS Heat Numben 305424 Orientation-Capsule W Total Fluence: 915D8 Charpy V-Notch Data (Continued)

Temperatum Input CVN Energy Computed CVN Energy Differential 210 73 61.48 1151 250 80 7036 933 300 83 77.4 559 400 72 8158

-958

~

SUM of REIDUAIS = 72

=

0 I

i i

i i

I APPENDIX B Determination of Margin Term for Plate B6903-1 from Industry Data Scatter of Embrittlement Data for Vessel Plate Materials l

I O

i i

l l

1 4

B-0

i iI in the original development of the Regulatory Guide 1.99, Revision 2154, embrittlement trend curves, 51 weld data points and 126 base metal data points existed in the database. Scatter in the predicted l

Charpy T shiAs versus the actual measured T, shift data was observed to be different between weld 3

2 l

material and base metal material; the regression analyses performed at that time yielded mean residual l

errors of 28'F for welds and 17'F for base materials. 'Iherefore, this'was the basis for the margin t

term in Regulatory Guide 1.99, Revision 2. However, much new surveillance capsule data has been generated since the development of Regulatory Guide 1.99, Revision 2, and this study examined the

{,

scatter in the available surveillance database for base metal matenals.

!i

{,

Around 200 data points now exist for shift in plates and forgings from commercial reactor surveillance j

capsule programs. These data have been gathered for inclusion in the new EPRI PREP 4 database, and curve fits to the new data have been performed by ATI Consulting. Updated fluence values were also a

j used from the Westinghouse surveillance capsule neutron fluence reevaluation *21 I

f l

1 j

The actual measured versus predicted (Regulatory Guide 1.99, Revision 2) shift values were calculated j

and a statistical analysis performed to determine the scatter (i.e. sigma) for the overall data set. 'Ihe j

combined plot showing the residual (actual minus predicted) scatter in the base metal data is shown in

)

Figure 14. These data show more scatter than the original data set used to develop the Regulatory a

j Guide 1.99, Revision 2, margin term. The residual scatter in the original 126 base metal data points l

varied from -50 to +50*F, with a 1-sigma value of 17'F while the residual scatter of the 194 data points shown in Figure 10 varied from -98 to +60*F, with a 1-sigma value of 29.I'F. The residual 1

]

scatter of these data are denized in the histogram shown in Figure 15. Additionally, the residual data distribution shows a characteristic nonnal distribution with a mean at -10.95'F. 'Iherefore, this shows that the current Regulatory Guide 1.99, Revision 2, equations for predicting ART, in base metals tends to overpredict the amount of shift by approximately ll*F.

Furthermore, from the amount of scatter obserted in all base metal data, actual data shift values falling within 1-sigma (i.e. 29.I'F) of the best-fit prediction would be determined to be credible by the Regulatory Guide 1.99, Revision 2, definition. 'Ihe maximum scatter in these data is -27.5'F, which is well within 1-sigma of the scatter of all base metal data. A mean plus 1-sigma line is shown on the plot in Figure 14. It is noted that all of the Beaver Valley Unit I plate data fall within this upper bound line indicating that the data are credible.

B-1

'Iherefom, this mean plus 1-sigma bounding relation was used to predict the RTm in the limiting lower shell plate B6903-1 from the Beaver Valley Unit I reactor vessel. The margin term to be used in calculating RT was reduced from a (2-sigma) value of 34'F to a (1-sigma) value of 29.l'F.

m

REFERENCES:

B-1.

Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials",

May 1988.

i B-2.

WCAP-14044, " Westinghouse Surveillance Capsule Neutron Fluence Reevaluation", E. P.

Lippincott, April 1994.

s b

B-2

l I

o I

~$

  • \\

o I

O O ll $

a D

D bl

-8 C

I D

N li l

E E

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l C

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D I

O m m U

U h

U D

I l

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$c T

9 D

U D @D CD l OD

.8 D

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A O

fl D

D 1

t gD D

j D

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D 00 jQ O m

k 0

g U

U U

D D lD gg O

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1 m

D O

D 5

i lU D

Dg D

_o D

6 i

CD D O lN D

O gjD D GD D

D D b D

2 lO a

gg 0

g JD D

iI D

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0 f

El] @Q30 0D D

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fD Dk

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i khk@f@@g I

I I

l i

I l

I U) 3Pu.ngp (pal 3fPaki-lon;3Y) lonplsey

i 1

35 R

30

-I r + 1 cr Mean Residual = -10.95 *F 25 M = 29J *F 2

5 E 20 R

5 E

15 o

l u

l I

l 3

E 10 aE i

5 I

0

-100 60 20 0

20 40 60 80 i

Residual (Actual-Predicted) ARTer(*F) i i

Figure l$

Histogram Showing Calculated Scatter in Base Metal Data i

)

1

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