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Attachment 1, Structural Integrity Associates, Inc., Report No. 0901132.401, Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis
	ML110060693
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Site:	Palisades
Issue date:	04/20/2010
From:	Griesbach T, Marthandam V; Entergy Nuclear Palisades, Structural Integrity Associates
To:	; Office of Nuclear Reactor Regulation
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	0901132.401
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ATTACHMENT 1 STRUCTURAL INTEGRITY ASSOCIATES, INC.

REPORT NO. 0901132.401 EVALUATION OF SURVEILLANCE DATA FOR WELD HEAT NO. W5214 FOR APPLICATION TO PALISADES PTS ANALYSIS 178 pages follow

Report No. 0901132.401 Revision 0 Project No. 0901132 April 2010 Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis Preparedfor:

Entergy Nuclear Corp.

Palisades Nuclear Power Plant Preparedby.

Structural Integrity Associates, Inc.

San Jose, California Preparedby: Date: 4/20/2010 Timothy . Griesbach Preparedby:

\/V/1 A 4 AA Date: 4/20/2010 Vikram Marthandam Reviewed by: Date: 4/20/2010 Clark Oberembt Approved by: Date: 4/20/2010 Timothy J. Griesbach

REVISION CONTROL SHEET Document Number: 0901132.401

Title:

Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis PTS Analysis Client: PalisadesN clear Corp.

Entergy SI Project Number: 0901132 Quality Program: N Nuclear El Commercial Section Pages [Revision [ Date [ Comments 1.0 1 0 4/20/2010 Initial Issue 2.0 1-2 3.0 2-6 4.0 6-12 5.0 13 -23 6.0 23 - 29 7.0 29 8.0 30-33 Appendix A Al - A2 Appendix B B1 -1B7 Appendix C C1 - C22 Appendix D D1 - D19 Appendix E El - E27 Appendix F F1 - F24 Appendix G G1 - G23 Appendix H H1 -1H6 Appendix I I1 - 14 1- t t t

EXECUTIVE

SUMMARY

This evaluation was performed as part of a review of the Palisades Pressurized Thermal Shock (PTS) re-evaluation. A previous analysis performed for the Palisades vessel in 2000 determined that the PTS screening criteria limit of 270'F for weld heat No. W5214 would not be reached until January 2014. That evaluation was based on the fluence projections and weld material chemistry for weld heat No. W5214 available at that time; no credit was given for surveillance data to improve the RTPTS projection. In the fall of 2009 it became apparent to Entergy that new information was available that could affect the RTNDT of the limiting Palisades vessel beltline material. The new data included revised fluence calculations and a total of eleven irradiated surveillance capsules that contain Charpy V-notch data for weld heat No. W5214. This report examines the updated fluence calculations performed by Westinghouse and all the available surveillance data relevant to the Palisades reactor pressure vessel weld heat No. W5214. Using the revised fluences and chemistry factors based on the refitted surveillance data for this weld heat, this re-evaluation shows that the projected date to reach the PTS screening criteria limit using the surveillance weld data would be approximately April 2017 or later.

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Table of Contents Section Page 1.0 INT ROD U C TIO N ................................................................................................................ 1 2.0 APPLICA B ILITY ........................................................................................................ 1 3.0 METH OD O LO GY .......................................................................................................... 2 4.0 DATA EVALUATION RESULTS ............................................................................... 6 5.0 DATA CREDIBILITY ASSESSMENT AND FLUENCE EVALUATION ................. 13 6.0 DISCU SSIO N ............................................................................. ..... 23 7.0

SUMMARY

AND CONCLUSIONS ........................................... 29 8.0 RE F E REN C E S .................................................................................................................. 30 APPENDIX A: CEOG DETERMINATION OF BEST-ESTIMATE CHEMISTRY FOR WELD HEAT NUM BER W5214 ........................................................... ........ A-1 APPENDIX B: EXCERPT FROM GENERIC LETTER 92-01 AND RPV INTEGRITY ASSESSMENT NRC/INDUSTRY WORKSHOP ON RPV INTEGRITY ISSUES .............B-1 APPENDIX C: PALISADES SUPPLEMENTAL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 .................................................. C-1 APPENDIX D: INDIAN POINT 2 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 .............................. D-1 APPENDIX E: INDIAN POINT 3 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 ................ E-1 APPENDIX F: H. B. ROBINSON 2 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 .............................. F-1 APPENDIX G: CVGRAPH TANH CURVE-FITS FOR W5214 SURVEILLANCE WELD D A T A .......... ................................. ............................................................. G-1 APPENDIX H: CALCULATION OF TIME-WEIGHTED AVERAGE TEMPERATURES FOR SURVEILLANCE CAPSULES CONTAINING WELD HEAT NO. W5214 ............... H-1 APPENDIX I: LISTING OF DESIGN INPUTS FOR WELD HEAT NO. W5214 SURVEILLANCE DATA RE-EVALUATION ................................................. . ... I-1 Report No. 0901132.401, Rev. 0 ii StructuralIntegrity Associates, Inc.

List of Tables Table Page Table 1: Results of all W5214 Surveillance Data with Reported Fluence and Vendor Shift Results ........................................................................................ . . . 1 0 Table 2: Summary of Revised Capsule Fluences and Time-Weighted Average Temperatures for Surveillance'Capsules Containing Weld Heat No. W5214 .............................. 11 Table 3: Summary of Revised (Refitted) Surveillance Capsule Results for Weld Heat No.

W 52 14 ............................................................................................. 12 Table 4: Test Specimens Contained in Palisades Capsules SA-60-1 and SA-240-1 ............... 15 Table 5: Evaluation of Palisades Surveillance Data Results for Weld Heat No. W5214 ..... 17 Table 6: Evaluation of all Surveillance Capsule Results Containing Weld Heat No.

W 52 14 ........................................................................................ . . . 18 Table 7: Scatter in Fit to all Surveillance Capsule Results Containing Weld Heat No.

W 52 14 .................................................................... ................ . . . .19 Table 8: History of Time-Weighted Operating Temperature for Palisades ...................... 20 Table 9: Correlation Monitor Material HSST Plate 02 Calculation of Fitted CF ............... 21 Table 10: Correlation Monitor Material HSST Plate 02 Calculation of Measured - Predicted Scatter ............................................................................................... 2 2 Table 11: Calculated and Projected Fluence Values at 600 Weld Location ..................... 23 Table 12: Limiting Fluence Determination for Current Licensing Basis (Case 1)................ 25 Table 13: Limiting Fluence Determination for Revised Best-Estimate CF Value (Case 2)......25 Table 14: Limiting Fluence Determination for Case 4a .......................................... 26 Table 15: Limiting Fluence Determination for Case 4b ........................................... 26 Table 16: Interpolation of PTS Limit Date Based on Current Licensing Basis and Revised F lu en ce .............................................................. ............................... 2 7 Report No. 0901132.401, Rev. 0 iii StructuralIntegrity Associates, Inc.

Table 17: Interpolation of PTS Limit Date Based on Limiting Fluence for Case 4b ............. 28 Table 18: Projected Maximum Fluence and Estimated PTS Limit Dates for Palisades Weld W52 14 ........... ................................................................................... 2 9 List of Figures Figure Page Figure 1. Best Fit to Data for all W5214 Surveillance Data with Reported Fluence and V endor Shift V alues .............................................................................. 34 Figure 2. Palisades Supplemental Surveillance Data (W5214) with Revised Fluence and Refitted Shift (Case 4a) ..................................................................... 35 Figure 3. Best Fit for all W5214 Surveillance Data with Revised Fluence and Refitted Shift (Case 4b) .................................................... 36 Figure 4. Plot of Residual vs. Fast Fluence for A533B-1 HSST-01/HSST-02 CMM with Companion Materials, the Overall 2-Sigma Scatter is 50'F [24] .................... 37 Figure 5: Projected Peak Fluence at 60' Weld Location (from [18]) and RTPTs Limit Dates...38' I Report No. 0901132.401, Rev. 0 iv StructuralIntegrity Associates, Inc.

EVALUATION OF SURVEILLANCE DATA FOR WELD HEAT NO. W5214 FOR APPLICATION TO PALISADES PTS ANALYSIS

1.0 INTRODUCTION

The Palisades Nuclear Plant submitted to NRC a Pressurized Thermal Shock (PTS) evaluation in 2000 that projected the value for RTPTS, or maximum Adjusted Reference Temperature (ART) of the limiting vessel weld or plate, based on the calculated fluences and material properties available at that time [ 1]. The limiting vessel beltline material was determined to be weld heat No. W5214, and the projected ART value was based on the method in the PTS Rule given in 10CFR50.61, Paragraph (c)(1) [2] using the best estimate chemistry for this weld, the corresponding chemistry factor, CF, and the fluence values from the vessel fluence evaluation in WCAP-15353 [3]. These inputs to the PTS Rule equations were used to calculateRTPTS, and the Palisades vessel was projected to reach the screening criterion limit of 27 0 'F for the limiting weld in January 2014.

Since the time that the previous PTS evaluation was performed for the Palisades vessel, ten years have passed and more data and information are available now to update the projected RTNDT value for the limiting Palisades vessel beltline material. In particular, this evaluation considers all the available surveillance data for weld heat No. W5214 that can be used to refine the projected RTNDT in accordance with 10CFR50.61, Paragraph (c)(2) [2]. This evaluation is being updated now because there is new information that changes the projected values of RTPTS for the Palisades vessel.

The new information was generated by performing a survey of all relevant surveillance data for weld heat No. W5214. Eleven irradiated surveillance capsule reports were found containing this weld, and the Charpy data contained in these capsules was compiled and refitted consistently using the CVGRAPH hyperbolic tangent curve-fitting methodology [4]. Also, the eleven capsule fluence values have been updated (over time) by Westinghouse using their NRC approved fluence methodology for implementing the Regulatory Guide 1.190 benchmarking procedure [5]. All data was evaluated in accordance with the PTS Rule approach to determine the shift values, fitted CF from the surveillance data, scatter from the mean predicted shift, and credibility of the data. It was determined that this new evaluation provides the most technically complete and sound assessment for the Palisades weld heat No. W5214 and allows for more accurate life projections of the limiting material in the Palisades vessel. The latest W5214 life projection provides improvement (i.e.,. more time) from the previous prediction to reach the PTS screening criterion limit.

2.0 APPLICABILITY This evaluation is applicable to the Palisades Reactor vessel PTS analysis relative to intermediate shell axial welds 2-112A/B/C fabricated from weld heat No. W5214 [1]. The results of this evaluation are used to revise the RTpTs projection to determine the maximum fluence, or Report No. 0901132.40 1, Rev. 0 1 ~Structural Integrity Associates, Inc.

equivalent date, to reach the PTS screening criteron of 270'F for the limiting axial weld at the 600 azimuthal location. Evaluation of other beltline region materials was not performed at this time because they are not projected or expected to exceed the PTS screening criterion over the next several years. A complete PTS analysis for all of the vessel beltline materials will be performed at a later time per 10CFR50.61.

3.0 METHODOLOGY 3.1 Charpy TANH Curve-Fitting Method All Charpy data has been re-evaluated to assure that the Charpy curve fits and the 30 ft-lb shift values from the surveillance capsule reports are performed in a consistent manner. The general shape of Charpy test data (energy versus temperature, or lateral expansion versus temperature) is that of an "S", generally with definable lower and upper shelves and a connecting region between the shelves called the transition region. The hyperbolic tangent (TANH) function has been used for some time as a simple statistical curve-fit tool to describe this "S"-shaped response [25].

Other functional relationships could have been used to produce a similar shape (e.g., an error function), but the benefit of the TANH function is that the curve fit parameters defining the "S" shape have physical meaning relative to what is generally evaluated from the test results. As a result, the hyperbolic TANH curve fitting of Charpy V-notch (CV) impact energy data has been a standard practice within the industry.

The TANH model used for modeling Charpy V-notch curves is given by Equation (1) [25]:

Cv = A + B tanh [(T - T,) / C] (1)

where, Cv = Charpy V-notch impact energy T = test temperature A = the mean energy level between the upper and lower shelves B = the + or - deviation from the mean energy level To = a parameter that represents the mid-energy transition temperature C = the + or - deviation of the intercepts of the tangent to the transition of To and the upper and lower shelves The lower shelf (A - B) was fixed at 2.2 ft-lb, and the upper shelf (A + B) was fixed in accordance with standard practice for applying hyperbolic tangent fits to Charpy V-notch data

[24].

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3.2 Fluence Analysis Method The surveillance capsule fluence values were re-evaluated by Westinghouse using the DORT neutron transport calculation method which has been benchmarked to meet the criteria in NRC -

Regulatory Guide 1.190 [5], shows close agreement between calculations and neutron dosimetry measurements, and has been approved for use by NRC. The capsule fluence values were provided as design inputs by Westinghouse [ 18].

3.3 10CFR50.61 (PTS Rule) Embrittlement Prediction Methods The PTS Rule in 10CFR50.61 [2] provides two methods for determining the reference temperature. The first method considers only the copper and nickel chemistry, fluence, and initial RTNDT of the weld, plate, or forging material in the reactor vessel beltline. For those beltline materials, Equation .(2) is used to determine the adjusted RTNDT for comparison to the PTS screening criteria limits.

RTNDT = Initial RTNDT + ARTNDT + Margin (2) where ARTNDT is the mean value of the transition temperature due to irradiation, and must be calculated using the Equation (3):

ARTNDT = (CF) f (0.28-0.10 log f) (3) where CF (0 F) is the chemistry factor, which is a function of the copper and nickel content. CF is determined by using Table 1 (from 10CFR50.61) for welds and by using Table 2 (from 10CFR50.61) for base metals (plates and forgings). "Wt % copper" and "Wt % nickel" are the best-estimate values for the material, which will normally be the mean of the measured values for a plate or forging. For a weld, the best estimate values will normally be the mean of the measured values for a weld deposit made using the same weld wire heat number as the critical vessel weld. For weld heat number W5214, the best-estimate chemistry, as determined by the industry best-estimate results from the CEOG report [20], is Cu = 0.213 wt%, Ni = 1.007 wt%.

The best-estimate chemistry values for the C-E fabricated welds are shown in Appendix A. The corresponding chemistry factor for this weld heat is CF = 230.73°F. This value for best-estimate nickel content varies slightly from the value used previously in the PTS submittal (Ni = 1.01%)

[ 1]. It is noted that the basis for the best estimate Cu and Ni values came from the CEOG report

[20] which is considered to be the industry standard for the C-E fabricated welds, but Palisades chose to round up the nickel content from 1.007% to 1.01% in the 1998 RAI response to Generic Letter 92-01 [19]. For the current analysis we have also used the CEOG determined actual.

nickel best estimate chemistry which gives a CF value of 230:73°F for comparison to a CF value of 231.08'F for the rounded up nickel content.

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The Initial RTNDT for weld heat No. W5214 is determined from the generic value of-56°F for C-E fabricated Linde 1092 flux type welds [31], andthe margin term is determined from Equation 4:

Margin = 2 1o I A(4)

A where cy, is the standard deviation for the initial RTNDT. If the generic mean Initial RTNDT value for a Linde 1092 weld is used, then cy, = 170 F [2]. The (1-sigma) standard deviation for ARTNDT, aA, is 28°F for welds, so the margin term for this case is 65.5°F.

Using this approach to determine the RTPTs at the screening criteria limit for axial welds (i.e.,

270'F) yields a maximum allowable fluence at the 60' azimuthal weld location of:

RTPTS = 270'F = Initial RTNDT + ARTNDT + Margin = -56 + ARTNDT + 65.5-F (5)

ARTNDT = 260.5-F = (CF) f(0. 2 8 -0.10 log ) -= (230.73) f(0. 28 -0.10 log f) (6) and f= 1.595x10' 9 n/cm 2 (7)

The second method for determining the chemistry factor and the RTNDT states that, "To verify that RTNDT for each vessel beltline material is a bounding value for the specific reactor vessel, licensees shall consider plant-specific information that could affect the level of embrittlement.

This information includes but is not limited to the reactor vessel operating temperature and any related surveillance program results." Surveillance program results means any data that demonstrates the embrittlement trends for the limiting beltline material, including but not limited to data from test reactors or from surveillance programs at other plants with or without surveillance program integrated per 10 CFR Part 50, appendix H. This is the case for Palisades; eleven previously tested surveillance capsules are now available that contain the limiting vessel weld heat No. W5214. The axial weld in the Palisades vessel made from weld heat No. W5214 was determined to be the limiting vessel beltline material [1].

Results from the plant-specific surveillance program must be integrated into the RTNDT estimate if the plant-specific surveillance data has been deemed credible as judged by the following (

criteria [2]:

(A) The materials in the surveillance capsules must be those which are the controlling materials with regard to radiation embrittlement, (B) Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions must be small enough to permit the determination of the 30-foot-pound temperature unambiguously, (C) Where there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values must be less than 28TF for welds and 170 F for base metal. Even if the range Report No. 0901132.401, Rev. 0 4 W1StructuralIntegrity Associates, Inc.

in the capsule fluences is large (two or more orders of magnitude), the scatter may not exceed twice those values (i.e., 56°F),

(D) The irradiation temperature of the Charpy specimens in the capsule must equal the vessel wall temperature at the cladding/base metal interface within 25°F, and (E) The surveillance data for the correlation monitor material in the capsule, if present, must fall within the scatter band of the data base for the material.

Surveillance data deemed credible according to these criteria must be used to determine a material-specific value of CF for use in Equation (2). A material-specific value of CF is determined from Equation (8) [19].

CF (8)

[fags - 0z=M where "n" is the number of surveillance data points, "Ai" is the measured value of AT30 from the Charpy specimens, and "f'"is the fluence for each surveillance capsule data point.

If there is clear evidence that the copper and nickel content of the surveillance weld differs from the vessel weld (i.e. differs from the average for the weld wire heat number associated with the vessel weld and the surveillance weld), the measured values of AT30 must be adjusted for differences in copper and nickel content by multiplying them by the ratio of the chemistry factor for the vessel material to that for the surveillance weld [2].

For cases in which the results from a credible plant-specific surveillance program are used, the value of CA to be used in the margin term of Equation (4) is 14'F for welds; this is called a reduced margin term. The value of GA need not exceed one-half of ARTNDT [2].

The use of results from the plant-specific surveillance program method may result in a RTNDT that is higher or lower than that determined from the first (chemistry table) method. If the resulting RTNDT from using the surveillance data gives a higher value it must be used. If the resulting RTNDT from using the surveillance data givesa lower value it may be used.

NRC provided additional guidance for evaluation and use of surveillance data in Reference 19.

The guidance provides examples of Case 4 that may be used for evaluating the Palisades related surveillance data, as shown in Appendix B. Two cases are considered, Case 4a considers surveillance data from the plant of interest, and Case 4b for use of surveillance capsule data from both the plant of interest and also from its sister plants containing the same weld heat.

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Also, if there is clear evidence that the copper or nickel content of the surveillance weld differs from that of the vessel weld, i.e., differs-from the average of the weld wire heat number associated with the vessel weld and the surveillance weld, the measured values of ARTNDT should be adjusted by multiplying them by the ratio of the chemistry factor of the vessel weld to that of the surveillance weld using the equation [19]:

Ratio Adjusted ART*. a ifTWO- C~r c

Measured ARTT(9 Pt CF. cf.(9)

Table According to the NRC guidance [19], further adjustment to the ARTNDT data from other sources is needed if there is a difference between the capsule temperature from the other plant and the plant of interest. A temperature correction of 10 F/0 F is made to the ARTNDT values to account for this difference; a positive temperature adjustment is made to capsules exposed to (time-Weighted average) temperatures below the mean vessel temperature, and a negative temperature adjustment is made to capsules exposed to (time-weighted average) temperatures above the mean vessel temperature. The mean vessel temperature for the Palisades vessel, using a time-weighted average for the plant operating cycles, is determined to be 535.2'F, as shown in Table 8.

Guidance from Reference 19, Case 4, "Surveillance Data from Plant and Other Sources," and 10CFR50.61, method 2 for inclusion of plant-specific surveillance data, has been applied to evaluation of the W5214 surveillance data as described in Section 5.0.

4.0 DATA EVALUATION RESULTS In 1998, Consumers Energy provided a response to a Request for Information from NRC regarding pressure vessel integrity for the Palisades vessel [26]. That response evaluated seven surveillance capsules containing weld heat No. W5214 which were available at that time (two capsules from H. B. Robinson 2, two capsules from Indian Point 2, and three capsules from Indian Point 3) and determined those data were not credible and, therefore, the data was not used to improve the projected RTPTs for the Palisades vessel. Since then, four more capsules containing this weld heat can be included in the analysis for use of surveillance data related to the Palisades limiting weld material. An evaluation of these data starts with the original capsule reports.

The new data survey was performed to gather all the unirradiated and irradiated capsule test results for the Palisades limiting weld material. The data from all related surveillance capsules containing weld heat No. W5214 were compiled and the results were reviewed for applicability to the Palisades vessel weld. New data were discovered in the process of compiling these capsule reports. For example, there are two capsules from the Palisades supplemental Report No. 0901 132.401, Rev. 0 6 StructuralIntegrity Associates, Inc.

surveillance program that were previously unreported (References 14 - 17). In addition, three capsules from the H. B. Robinson 2 surveillance program (References 12), two capsules from the Indian Point 2 surveillance program (References 6 - 8), and four capsules from the Indian Point 3 surveillance program (References 9, 10, 11 and 13) were compiled and the Charpy V-notch test results were reviewed. These reports include surveillance capsule fluences and comparisons between the unirradiated and irradiated Charpy V-notch curves to determine the ARTNDT (or AT 30) shifts. The reported fluence values from these capsule reports, the average of measured surveillance weld copper and nickel chemistries, and the (measured and reported) AT 30 shift results for these eleven capsules are shown in Table 1. The capsule reports are included in Appendix C (Palisades), Appendix D (Indian Point Unit 2), Appendix E (Indian Point Unit 3) and Appendix F (H. B. Robinson Unit 2). These are considered to be the reported data (or original data), with the exception of the Palisades capsule reports that were considered to be supplemental capsule test results.

It is useful to first combine these data without any adjustments for chemistry or irradiation temperature to determine the mean trend in irradiation damage behavior. The mean trend, or average chemistry factor, can be calculated directly from a least squares fit to the data using Equation (8). The least squares fit method was used and a best fit chemistry factor (CF) of 217.671F was determined from these data, as shown in Table 1. The results are plotted in Figure 1 and are shown here for information only. The scatter in the measured - predicted results show that the scatter exceeds the 28°F (1-sigma) margin for two out of eleven points, but these two points are within the 56°F (2-sigma) margin. The average copper content for these surveillance materials is Cu = 0.243 wt%, and the average nickel content for these surveillance materials is Ni

= 0.965 wt%. The predicted (average) chemistry factor for the surveillance specimens based on chemistry (from the PTS Rule Table 1) is CF = 234.37'F. The mean fit to the data shows that the CF value and the fitted trend for these data is well below that predicted by the PTS Rule method 1 (i.e., surveillance data not available).

4.1 Original and Re-evaluated Surveillance Capsule Fluence Westinghouse recalculated the capsule fluences from Palisades, Indian Point 2, Indian Point 3, and H. B. Robinson 2 using a consistent methodology to establish a common basis for the fluence values. This was an essential step so that all the surveillance capsule data could be evaluated properly for credibility and applicability to the Palisades vessel limiting weld material.

The revised fluence values for capsules containing weld heat No. W5214 are shown in Table 2

[ 18]. It is noted that there were changes in the fluences from the originally calculated fluence values (shown in Table 1), and the new calculated fluence results (shown in Table 2) that were used to re-evaluate all the relevant surveillance data. The same Westinghouse fluence methodology was used to calculate fluence in the wall of the Palisades vessel for prediction of

the vessel embrittlement.

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4.2 Surveillance Capsule Temperatures Surveillance capsule temperatures are necessary for the temperature corrections of the surveillance data when applying these data tothe plant of interest. Time-weighted average temperatures were determined for the Palisades, Indian Point 2, Indian Point 3, and H. B.

Robinson 2 capsules containing weld heat No. W5214. The data and method for determining the time-weighted average temperatures is given in Appendix H. The time-weighted average temperatures for the Indian Point Units 2 & 3 capsules were verified in Reference 33.

4.3 Original and Re-evaluated Charpy V-notch Surveillance Data The surveillance capsule test results for weld heat No. W5214 from the Palisades supplemental capsules SA-60-1 and SA-240-1 are provided in Appendix C. The supplemental capsules with this weld heat were irradiated for a number of cycles, and removed and tested; capsule SA-60-1 was removed at the end of cycle 13, and capsule SA-240-1 was removed at the end of cycle 14.

The specimens containing weld metal inserts were reconstituted to full size Charpy V-notch specimens. The capsule materials were tested by Framatome in 2001 [14, 15]. The unirradiated Charpy energy values for the weld metals are documented in a letter from John R. Kneeland to Matthew J. DeVan dated February 2, 1999 [16]. The baseline (unirradiated) curve and weld metal chemistry data for these specimens are also provided in Appendix C.

The surveillance capsule test results for weld heat No. W5214 from the Indian Point Unit 2 reactor surveillance capsule program are provided in Appendix D. The unirradiated data is contained in a Westinghouse report [8]. Southwest Research Institute tested two irradiated capsules, capsule Y [7] and capsule V [6]. The Indian Point 2 surveillance weld metal chemistry is also contained in these reports.

There are four irradiated surveillance capsules containing weld heat No. W5214 and one baseline test report for the Indian Point Unit 3 plant, as shown in Appendix E. The baseline capsule report from Westinghouse contains the unirradiated data and one chemistry measurement for the surveillance weld [9]. The results for the four irradiated capsules are also given in one Westinghouse (WCAP-16251-NP) report [13]. This WCAP report contains the surveillance weld Charpy V-notch test results and measured chemistry data for the Indian Point Unit 3 plant.

The surveillance capsule test results for weld heat No. W5214 from the H. B. Robinson Unit 2 reactor surveillance capsule program are provided in Appendix F. The unirradiated data is contained in a Westinghouse report [27]. There are three irradiated capsules from H. B.

Robinson Unit 2 which contain weld heat No. W5214, capsule T, capsule V, and capsule X. The Charpy V-notch test results from these three capsules are contained in one Westinghouse (WCAP-15805) report [12]. This WCAP report also documents the measured surveillance weld chemistry for H. B. Robinson Unit 2.

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These original Charpy V-notch energy data were refitted using the CVGRAPH 5.0 hyperbolic tangent curve-fitting method [4]. The data were carefully fitted to obtain the best TANH fits.

The CVGRAPH curve-fit results are shown in Appendix G from Reference 32. The results of the refitted and reanalyzed weld heat No. W5214 data for 30 ft-lb shift (AT 30) are shown inTable

3. These refitted Charpy data results have been verified for use in the new credibility evaluation

[32].

The results presented here are considered to be "new data" because of the updated fluences and refitted AT 30 values and because several additional capsules containing weld heat No. W5214 were uncovered in this survey that had not been previously evaluated together with the other data. The results from these new data were evaluated for applicability to the prediction of the RTPTs value for weld heat No. W5214 per 10CFR50.61 [2] and the NRC guidance shown in Appendix B [19].

An evaluation of the credibility for the use of these data for the Palisades limiting weld is given in Section 5.0.

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Table 1.

Results for all W5214 Surveillance Data with Reported Fluence and Vendor Reported Shift Results Reported Reported Predicted Measured -

Capsule %Cu(a) %Ni(a) CF (F) Fluence (b) FF ARTndt ARTndt Predicted (n/cmA2) (F) (F) ARTndt (F)

SA-60-1 0.307 1.045 266.5 1.61E+19 1.13 259 246.3 12.7 SA-240-1 0.307 1.045 266.5 2.60E+19 1.26 280.1 273.4 6.7 HB2 T 0.34 0.66 217.7 3.87E+19 -1.35 288.15 293.6 -5.5 HB2 V 0.34 0.66 217.7 5.30E+18 0.82 209.32 179.1 30.3 HB2 X 0.34 0.66 217.7 4.49E+19 1.38 265.93 300.5 -34.6 IP2 V 0.20 1.03 226.3 5.59E+18 0.84 204 182.3 21.7 IP2 Y 0.20 1.03 226.3 5.89E+18 0.85 195 185.4 9.6 IP3 T 0.16 1.12 206.2 2.63E+18 0.64 151.6 138.6 13.0 IP3 Y 0.16 1.12 206.2 6.92E+18 0.90 172 195.2 -23.2 IP3 Z 0.16 1.12 206.2 1.04E+19 1.01 229.2 220.1 9.1 IP3 X 0.16 1.12 206.2 8.74E+18 0.96 193.2 209.4 -16.2 Average = 0.243 0.965 Table CF = 234.37°F Best fit CF = 217.67°F (a) Measured capsule weld materials Cu and Ni values obtained from [6, 12, 13, 14, 15, 20, 26]

(b) Reported capsule fluence values from [6, 7, 12, 13, 28]

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Table 2.

Summary of Revised Capsule Fluences and Time-Weighted Average Temperatures for Surveillance Capsules Containing Weld Heat No. W5214 Surveillance Time-Weighted Fluence (a)

Reactor Capsule Average Temperature (E > 1 MeV)

Designation (OF) [n/cm 2]

Palisades SA-60-1 535.0 [from Table 8] 1.50E19 Palisades SA-240-1 535.7 [from Table 8] 2.38E19 H. B. Robinson 2 T 547 [12] 3.87E19 H. B. Robinson 2 V 547 [12] 5.30E18 H. B. Robinson 2 X 547 [12] 4.49E19 Indian Point 2 V 524 [12] 4.92E18 Indian Point 2 Y 529.1 [from App. H] 4.55E18 Indian Point 3 T 539.4 [from App. H] 2.63E18 Indian Point 3 Y 539.5 [from App. H] 6.92E18 Indian Point 3 Z 538.9 [from App. H] 1.04E19 Indian Point 3 X 539.7 [from App. H] 8.74E18 (a) Revised capsule fluence values from Reference 18.

Report No. 0901132.40 1,Rev. 0 11 RRStructural IntegrityAssociates, Inc.

Table 3.

Summary of Revised (Refitted) Surveillance Capsule Results for Weld Heat No. W5214 Unirradiated Irradiated Revised Upper Shelf Capsule (Refitted) (Refitted) (Refitted) Energy T30 (F)(a) T30 (F)(a) AT 30 (F) (ft-lbs)(a)

SA-60-1 -60.1 198.9 259 54.5 SA-240-1 -60.1 220 280.1 52.5 HB2 T -85.8 203.3 289.1 60.5 HB2 V -85.8 123 208.8 70.5 HB2 X -85.8 179.8 265.6 79.8 IP2 V -65.4 132.1 197.5 76 IP2 Y -65.4 128.5 193.9 66.5 IP3 T -63.8 86 149.8 90.5 IP3 Y -63.8 107.3 171.1 69 IP3 Z -63.8 164.5 228.3 76 IP3 X -63.8 128.7 192.5 75 (a) Charpy TANH curve-fit parameters, T30 values and plots are shown in Appendix G [32]

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5.0 DATA CREDIBILITY ASSESSMENT AND FLUENCE EVALUATION The purpose of this evaluation is to apply the credibility requirements in 10CFR50.61 to the Palisades, H.B Robinson Unit 2, Indian Point Unit 2, and Indian Point Unit 3 surveillance capsule data and to determine if the surveillance capsule data is credible and can be used to improve the RTNDT predictions for the limiting vessel weld heat No. W5214.

10CFR50.61 describes general procedures acceptable to the NRC staff for calculating the effects of neutron, radiation embrittlement of low-alloy steels currently used for light-water-cooled reactor vessels. 10CFR50.61 provides two methods for calculating the adjusted reference temperature of the reactor vessel beltline materials. The first method is described in paragraph (c)(1). The second method is described in paragraphs (c)(2) and (c)(3). The procedures in paragraphs (c)(2) and (c)(3) can only be applied when two or more credible surveillance data sets become available. These tests of surveillance data credibility are also stated in Section 3.3.

NRC provided additional guidance for evaluation and use of surveillance data in Attachment 3 of Reference 19. The evaluation presented herein is organized like Case 4 from this guidance.

document, the case for plants with surveillance data for their plant and from other sources.

5.1 Credibility Evaluation:

Criterion 1: The materials in the surveillance capsules must be those which are the controlling materials with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR 50, "Fracture Toughness Requirements" as follows:

"the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material and regard to radiation damage."

The Palisades reactor vessel consists of the following beltline region materials [ 1, 31]:

" Intermediate Shell, Axial Welds 2-112 A/B/C, material heat No. W5214,

" Lower Shell, Axial Welds 3-112 A/B/C, material heat No. W5214 and 34B009,

" Intermediate to Lower Shell, Circumferential Weld 9-112, material heat No. 27204,

" Intermediate Shell, Plate D-3803-1, material heat No. C-1279,

" Intermediate Shell, Plate D-3803-2, material heat No. A-0313,

" Intermediate Shell, Plate D-3803-3, material heat No. C-1279, Report No. 0901132.401, Rev. 0 13 StructuralIntegrity Associates, Inc.

Lower Shell, Plate D-3804-1, material heat No. C-1308A,

Lower Shell, Plate D-3804-2, material heat No. C-1308B,

" Lower Shell, Plate D-3804-3, material heat No. B-5294.

The Palisades reactor vessel was designed and fabricated in accordance with the ASME Boiler and Pressure Vessel Code,Section III, 1965 Edition, including all addenda through Winter 1965

[21]. The Palisades reactor vessel surveillance program was originally developed with the intent to comply, where possible, with the guidance of ASTM E 185-66, "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors" [22]. At the time that the Palisades surveillance capsules were built, 10 CFR50 Appendices G and H did not exist.

5.1.1 Descriptionof OriginalPalisadesSurveillance Capsule Program ASTM E 185-66 [22] describes the requirements for test specimens. ASTM E 185-66 requires the base metal specimen be from "...one heat with the highest initial ductile-brittle transition temperature", also known as the nil-ductility transition temperature (NDTT). Drop weight tests of Palisade's beltline samples identified five of the plates in contention for the highest initial NDTT at -30'F. The base material from shell plate D-3803-1 was selected over the other base metal specimens for the capsule base metal because it had the highest initial RTNDT temperature

[31]. ASTM E 185-66 requires a sample to represent one vessel weld if a weld occurs in the irradiated region. The original Palisades surveillance weld specimens were fabricated with the same procedure used to fabricate the reactor vessel axial welds, and were fabricated with a similar filler wire and fluxes as the reactor vessel beltline welds. However, the original Palisades surveillance capsules did not contain limiting axial weld heat No. W5214.

5.1.2 Descriptionof Supplemental Surveillance Capsules SA-60-1 and SA-240-1 At the end of Cycle 11, the Palisades surveillance capsule program was augmented to contain two supplemental surveillance capsules, designated as SA-60-1 and SA-240-1, installed in the capsule holders located on the core support barrel. The new surveillance capsules, SA-60-1 and SA-240- 1, included welds fabricated with weld wires of identical heats to those of the Palisades reactor vessel beltline welds. Surveillance capsule SA-60-1 and SA-240-1 contained test specimens from the following material heat No.'s: W5214, 34B009, 27204, and standard reference material HSST-02. All of these materials are the same heats as the materials used to fabricate portions of the reactor vessel that surround the active core and adjacent regions of the reactor vessel.

Table 4 provides a tabulation of the specimens included in the Palisades supplemental surveillance capsules SA-60-1 and SA-240- 1.

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Table 4.

Test Specimens Contained in Palisades Capsules SA-60-1 and SA-240-1 Material Description Tension Standard Charpy V- 18 mm Charpy Notch Impact V-Notch Inserts Weld Metal W5214 --- 42 (39)*

Weld Metal 34B009 --- --- 36 (39)*

Weld Metal 27204 3 12 36 Correlation Monitor --- 12 ---

Material, HSST Plate 02 (Heat No. A1195-1)

number of specimens in SA-60-1 capsule [15]

Capsules SA-60-1 and SA-240- 1 were removed from the Palisades reactor vessel at the end of cycles 13 and 14, respectively. Twelve Charpy V-notch specimens made from weld heat No.

W5214 were tested in capsule SA-60-1 [15], and twelve Charpy specimens from heat No.

W5214 were tested in capsule SA-240-1 [14]. Twelve Charpy V-notch specimens made from the HSST-02 correlation monitor material were tested from capsule SA-240-1 [14].

Because weld heat No. W5214 in the supplemental capsules matches the limiting axial welds, Criterion 1 is met for the Palisades reactor vessel.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determinatioA of the 30 ft-lb temperature and upper shelf energy unambiguously.

Criterion 2 is satisfied if the Charpy energy data for the surveillance capsules containing weld heat No. W5214 can be fitted to determine the 30 ft-lb temperature (T 30) and upper shelf energy (USE) unambiguously. An accurate determination of the 30 ft-lb shift (AT30) values is the reason these data were re-evaluated. The TANH curve fit method provides an accurate and reproducible determination of these values and can be used to establish the T30 and USE values for a given Charpy data set [24]. Unirradiated and irradiated Charpy energy versus temperature data for the weld metal were fitted and plotted using the CVGRAPH hyperbolic tangent curve fitting program [4]. The Charpy energy fitted results for the eleven surveillance capsules, including the calculated 30 ft-lb temperatures and upper shelf energy values, are shown in the Appendix G and summarized in Table 3. Based on engineering judgment by looking at the fitting parameters and the plots, the scatter in the data is small enough, and the correlation coefficients are high enough, to permit the determination of the 30 ft-lb temperature and upper shelf energy of the surveillance weld materials unambiguously. Hence, Criterion 2 is met for all the surveillance capsules evaluated here which contain weld metal heat No. W5214.

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Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Position 2 (surveillance data available) normally should be less than 28°F for welds and 17'F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fails this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition in ASTM E185.

The functional form of the least squares method as described in paragraph (c)(2) of 10CFR 50.61 will be utilized. A best-fit line is generated for this data to determine if the scatter of the ARTNDT values about this line is less than 28°F for weld metal heat No. W5214.

The Palisades limiting weld metal will be evaluated for credibility. This weld is made from weld heat No. W5214. This weld metal is also contained in the Indian Point Unit 2, Indian Point Unit 3, and H. B. Robinson Unit 2 surveillance programs. Since the welds in question utilized data from other surveillance programs, the recommended NRC methods for determining creditability will be followed. Of the recommended methods, Case 4 most closely represents the situation listed above for the Palisades surveillance weld metal.

Case 4a CredibilityAssessment - Palisades W5214 Data Only The data most representative for the Palisades limiting vessel weld are the supplemental surveillance capsules containing weld heat No. W5214 since the irradiation environment of the surveillance capsules and the reactor vessel are the same. The data requires the least adjustment.

An adjustment can be made for the difference between the chemistry of the capsule specimens (CF = 266.5'F) and the best estimate chemistry of the vessel (CF = 230.73°F) using the ratio procedure. The updated fluence and ratio adjusted shift values were used to calculate a new least-squares fitted chemistry factor. The Palisades capsule data are shown in Table 5 along with the fitted solution (i.e., mean shift prediction) result, and the comparison of the measured -

predicted scatter from the fitted CF of 198.8°F. A plot of the measured AT 30 vs. fluence results for the Palisades supplemental capsule weld (W5214) is shown in Figure 2 along with the +- lCY

,bounds for credible data scatter. The data clearly fall within the 1-sigma scatter band for credible surveillance data and the margin term can be reduced when using credible data.

Based on criterion 3, the Palisades surveillance data is credible since the scatter is less than 28°F for both of these surveillance capsules.

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Table 5.

Evaluation of Palisades Surveillance Data Results for Weld Heat No. W5214 Weld Heat No. W5214 Surveianc Palisades Revised ARTndt (F) Predicted Measured -

Capsule Cu Ni Table CF Fluence Refitted Adjusted to AlRTndt, Predicted Number (wt%) , (wt%) (F) (n/cnA2) FF ARTndt (F) Vessel CF (F) (F) ARTndt (F)

SA-60-1 0.307 1.045 266.5 1.50E+19 1.11 259.0 224.2 221.13 3.11 SA-240-1 0.307 1.045 266.5 2.38E+19 1.23 280.1 242.5 245.30 -2.80

. . ... .. . . . .Fitted

. . . . . . . ..... .... CF [ 8 "8F Case 4b CredibilityAssessment - All W5214 Surveillance Capsule Data Following the guidance in Case 4 [19], the data from all sources should also be considered. For weld heat No. W5214 there are a total of eleven surveillance capsules from Palisades, Indian Point Unit 2, Indian Point Unit 3, and H.B. Robinson Unit 2. Since data are from multiple sources, the data must be adjusted first for chemical composition differences and then for irradiation temperature differences before determining the least-squares fit.

For a credibility determination, the measured and refitted T30 shift data for all the relevant plant data was normalized to the mean chemistry factor of the vessel (230.73°F) using the ratio procedure and then to the mean operating temperature (535.2°F) for the Palisades vessel (see Table H-7). The fitted CF value, shown in Table 6, is determined to be 227.74 0 F for this case.

The results for (measured - predicted) scatter for all the W5214 surveillance data results are shown in Table 7. The results for all the surveillance capsule data are plotted in Figure 3 along with the +/- 2cy scatter bands. The scatter in the measured- predicted values exceeds 28°F (1-sigma) for a few points. Four of the measured - predicted ARTNDT values are outside the 1-sigma band of 28°F, but all data points are within the 56'F (2-sigma) scatter band for welds.

According to 10CFR50.61 paragraph (c)(2)(iv), the use of results from the plant-specific surveillance program may result in an RTNDT that is higher or lower than that determined from the chemistry of the weld and a chemistry factor using the tables. If the CF value is higher, it must be used for vessel RTPTS predictions, if the CF value is lower, it may be used.

The chemistry factor from paragraph (c)(1) is 230.73°F, and the adjusted chemistry factor using the Palisades surveillance capsule data is 227.74°F. It is noted that per NRC guidance that it is possible to use a lower value of chemistry factor based upon all sources of surveillance capsule data with a full margin term (i.e., 56°F) if the data is credible in all other ways but the scatter.

In summary, the (measured - predicted) scatter for all the W5214 weld data is within the acceptable range of 56°F for a wide range of fluence. For this case, the surveillance capsule fluence ranges between 2.63x1018 n/cm 2 to 4.49x1019 n/cm 2 . Therefore, the weld data meets this criterion, and the Palisades surveillance program weld metal chemistry factor to be used for determining RTPTS and RTNDT is 227.74°F in combination with a full (2-sigma) margin term.

Report No. 0901132.401, Rev. 0 17 Vj~ StructuralIntegrity Associates, Inc.

Table 6.

Evaluation of all Surveillance Capsule Results Containing Weld Heat No. W5214 Measured Ratio Chem. &

Table Revised Fluence Irrad. (Refitted) Adjusted Temp. Adj.

Capsule %Cu %Ni CF (F) Fluence Factor Temp. ARTndt ARTndt ARTndt FFA2 AT30 x FF (n/cmA2) FF Ti (F) (F) (F) (F)

SA-60-1 0.307 1.045 266.5 1.50E+19 1.11 535.0 259 224.2 224.0 1.237 249.186 SA-240-1 0.307 1.045 266.5 2.38E+19 1.23 535.7 280.1 242.5 243.0 1.522 299.830 HB2T 0.34 0.66 217.7 3.87E+19 1.35 547 289.1 306.4 318.2 1.820 429.263 HB2V 0.34 0.66 217.7 5.30E+18 0.82 547 208.8 221.3 233.1 0.677 191.749 HB2X 0.34 0.66 217.7 4.49E+19 1.38 547 265.6 281.5 293.3 1.906 404.943 IP2 V 0.20 1.03 226.3 4.92E+18 0.80 524.0 197.5 201.4 190.2 0.643 152.544 IP2Y 0.20 1.03 226.3 4.55E+18 0.78 529.1 193.9 197.7 191.6 0.610 149.601 IP3 T 0.16 1.12 206.2 2.63E+18 0.64 539.4 149.8 167.6 171.8 0.405 109.400 IP3 Y 0.16 1.12 206.2 6.92E+18 0.90 539.5 171.1 191.5 195.8 0.804 175.543 IP3 Z 0.16 1.12 206.2 '1.04E+19 1.01 538.9 228.3 255.5 259.2 1.022 262.003 IP3 X 0.16 1.12 206.2 8.74E+18 0.96 539.7 192.5 215.4 219.9 0.926 211.596

_ SUM 11.573 2635.658 Vessel Best Estimate CF = 1230.73°F Mean Vessel T = 535.2 0 F I -- I Least Squares Fitted CF = 227.74°F J Itdlm IsUr,.dcp.Ule Well ll]dUl1iaIS t.Iu dlIu Imi1VdlUS ti.llU1 110111 [O, ,i, 114? JD, LU, zOJ (b) Fluence values obtained from Reference18 I I IIS (c) Time-weighted average temperatures obtained from References 23 and 33 and Appendix H J(d) Refitted Charpy V-notch shift data obtained from Reference 32 and Appendix G II Report No. 0901132.40 1, Rev. 0 18 R2StructuralIntegrity Associates, Inc.

Table 7.

Scatter in Fit to all Surveillance Capsule Results Containing Weld Heat No. W5214 Irrad. Revised Fluence Adjusted Predicted Adjusted-Capsule Temp. Fluence Factor ARTndt ARTndt Predicted Ti (F) (n/cmA2) FF (F) (F) (F)

SA-60-1 .535 1.50E+19 1.11 224.0 253.31 -29.27 SA-240-1 535.7 2.38E+19 1.23 243.0 281.00 -38.00 HB2 T 547 3.87E+19 1.35 318.2 307.23 10.97 HB2 V 547 5.30E+18 0.82 233.1 187.34 45.75 HB2 X 547 4.49E+19 1.38 293.3 314.44 -21.14 IP2 V 524 4.92E+18 0.80 190.2 182.69 7.48 IP2 Y 529.1 4.55E+18 0.78 191.6 177.83 13.77 1P3 T 539.4 2.63E+18 0.64 171.8 145.01 26.81 IP3 Y 539.5 6.92E+18 0.90 195.8 204.23 -8.48 IP3 Z 538.9 1.04E+19 1.01 259.2 230.24 28.92 IP3 X 539.7 8.74E+18 0.96 219.9 219.14 0.76 Note: four of the eleven (measured - predicted) data points exceed the 1 standard deviation of 28'F for credible data for welds. All eleven (measured - predicted) data points fall within 2 standard deviations of 56°F for welds.

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I- Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.

The Palisades supplemental surveillance capsules SA-60-1 and SA-240-1 were located in the reactor vessel between the core barrel and the vessel wallopposite the center of the core. These supplemental surveillance capsules were installed in the capsule holders located on the core support barrel. Table 8 provides a history of the time-weighted temperature for the Palisades supplemental surveillance capsules and reactor vessel wall.

Table 8.

History of Time-Weighted Operating Temperature for Palisades Operating Cycle Cycle Average Surveillance Time Weighted Cycle Length(a) Vessel Capsule Capsule Avg. T Number (EFPD) Temp.(b) Removed (OF)

(OF) 1 371.7 523 2 440.1 529 3 342.5 534 4 321.0 536 5 386.7 536 6 326.7 536 7 362.5 536 8 366.1 537 9 292.5 534 10 349.7 534 11 421.9 533 12 399.3 534 13 419.6 536 SA-60-1 535.0 14 449.3 537 SA-240-1 535.7 15 401.3 537 16 444.3 537 17 493.1 537 18 472 537 19 459.2 537 Time Weighted 20 499.8 537 Vessel Avg. T 21 519.2 537 (OF) 22 498.8 537 535.2 (a) Cycle length (EFPD) values obtained from Reference 23 (b) Cycle average vessel temperatures obtained from Reference 28 Report No. 0901132.401, Rev. 0 20 R2StructuralIntegrityAssociates, Inc.

The location of the specimens with respect to the reactor vessel beltline assured that the reactor vessel wall and the specimens have experienced equivalent operating conditions such that the temperatures did not differ by more than 25°F. Therefore, this criterion is satisfied for the Palisades capsules.

The Indian Point Unit 2 and Indian Point Unit 3 average surveillance capsule temperatures have been also reviewed and updated. The H. B. Robinson Unit 2 average capsule temperature was confirmed by the utility. The time-weighted average temperature values for these capsules are listed in Table 2, and the method for calculating these temperatures is given in Appendix H.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band for that material.

The Palisades supplemental surveillance capsules, SA-60-1 and SA-240- 1, both contain standard reference material HSST02 plate. Plots of the Charpy energy versus temperature for the irradiated condition of correlation monitoring material (HSST Plate 02, Heat A 1195-1) from SA-60-1 and SA-240-1 are documented in BAW-2341 Rev 2 [15] and BAW-2398 [14], respectively. Charpy energy versus temperature for the unirradiated correlation monitoring material (HSST Plate 02, Heat Al 195-1) is taken from NUREG/CR-6413, ORNL/TM-13133 [24]. Tables 9 and 10 provide the updated calculation of (measured - predicted) scatter versus fast fluence in the correlation monitor material (HSST 02) data. Figure 4 (from Reference 24) shows that the measured scatter band for the correlation monitor materials is 50'F.

Table 9.

Correlation Monitor Material HSST Plate 02 Calculation of Fitted CF Capsule Fluence Fluence Factor ARTNDT(c) FF

ARTNDT FF2 (X 1019) (a) (FF) (b) (OF)

SA-60-1 1.5 1.112 113.7 126.4344 .1.2365 SA-240-1 2.38 1.234 140.9 173.871 1.5223 Sum 300.305 2.7588 CF Surveillance weld = I (FF x RTNDT) Y- (FF2 )= 300.305/2.7588 = 108.853 Slope of best fit line is 108.853 Notes:

(a) Calculated fluence (x 1019 n/cm2 , E>1.0 MeV)

(b) FF = fluence factor = f(o.28-o.*1ogf)

(c) Irradiated values of 30 ft-lb Transition Temperature From BAW-2341 Rev 2 and BAW-2398 [15, 14]

Report No, 0901132.401, Rev..O 21 R StructuralIntegrity Associates, Inc.

Table 10.

Correlation Monitor Material HSST Plate 02 Calculation of Measured - Predicted Scatter Capsule Fluence Fluence Factor ARTNDT(C) Predicted (Measured -

(X 1019) (a) (FF) (b) ARTNDT Predicted) ARTNDT SA-60-1 1.5 1.112 113.7 121.044 -7.344 2.38 1.234 140.9 134.324 6.575 /

SA-240-1 Where predicted ARTNDT = (slope best fit)*(Fl uence Factor)

Slope of best fit line is 108.853 Notes:

(a) Calculated fluence (x 1019 n/cm2 , E>1.0 MeV)

(b) FF = fluence factor = f(o.28-o.1*Iogf)

(c) Irradiated values of 30 ft-lb Transition Temperature From BAW-2341 Rev 2 and BAW-2398 [15, 14]

Table 10 shows that the scatter in these data is less than 50'F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM-13133 [24]. Thus, criterion 5 is satisfied for the correlation monitor materials.

5.2 Palisades Vessel Fluence Evaluation Fluence in the Palisades vessel beltline has been tracked to manage the PTS issue. The fluence projections are important to be able to predict the future levels of embrittlement in the vessel beltline materials. Calculations of the neutron exposure of the Palisades reactor pressure vessel were previously completed and documented in WCAP-15353, Revision 0 [3]. That evaluation, along with the benchmarking method, was submitted for review by the NRC Staff and the methodology and the final results were approved as part of the PTS evaluation in 2000 [1]. The previous evaluation determined that the peak fluence at the clad-to-base-metal interface at the 600 limiting axial weld was 1.158x101 9 n/cm 2 (E > 1 MeV) at the end of Cycle 14 (i.e., October 1999)

[34]. Since then, ten more years of plant operation has occurred and, as a result, the vessel has accumulated additional fluence. Recently, Westinghouse provided an updated fluence assessment for the Palisades vessel beltline region that includes cycle specific analysis for additional -

operating cycles for which the design has been finalized and operations are known (Cycles 15 through 21) and projections for future operation based on the best available knowledge as a function of EFPY and estimated calendar dates [18]. The calculated and projected neutron fluence values for the limiting 60' weld location are given in Table 11. Note: the cycle specific projections for the designs of Cycles 21 and beyond were provided by Entergy and include an assumed load factor of 95% for future plant operation [ 18].

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Table 11.

Calculated and Projected Fluence Values at 600 Weld Location [181 End of Estimated Cumulative Neutron Fuel Calendar Time Fluence @ 60*

Cycle Date (EFPY) n/cm 2 (E> 1 MeV) 14 October 1999 14.4 1.158E+19 15 March 2001 15.5 1.196E+19 16 March 2003 16.7 1.240E+19 17 September 2004 18.0 1.282E+19 18 April 2006 19.3 1.326E+19 19 September 2007 20.6, 1.369E+19 20 March 2009 22.0 1.419E+19 21 October 2010 23.4 1.472E+19 22 April 2012 24.7 1.520E+19 23 October 2013 26.1 1.571E+19 24 April 2015 27.4 1.619E+19 25 October 2016 28.8 1.670E+19 26 April 2018 30.2 1.721E+19 6.0 DISCUSSION The results for the surveillance capsules containing weld heat No. W5214 have been re-evaluated for applicability to the Palisades vessel. The refitted Charpy data results have been incorporated along with updates to the average capsule irradiation temperatures, corrections to account for chemistry differences, and results of the revised fluence calculations for the capsules and for the Palisades vessel have been included. Four cases are considered for prediction of the date to reach the PTS screening criteria limit.

The first case is Position 1 of the PTS Rule using the current licensing basis method and considering the revised fluence calculations and projections, as shown in Table 11. The chemistry factor for the weld heat No. W5214 was based on best-estimate Cu = .213%, Ni =

1.01%, and a CF = 231.08'F. The maximum fluence limit was calculated to be 1.584x10 9 n/cm 2 according to the embrittlement prediction method when surveillance data is not available. That prediction of RTNDT shift is shown in Table 12, and the corresponding date to reach the PTS screening criteria limit of 270'F for axial welds is March 2014 using the fluence interpolation given in Table 16. The current licensing basis date to reach the PTS screening criteria date is Report No. 0901132.401, Rev. 0 23 Structural Integrity Associates, Inc.

January 2014 as given in Reference 1. It has been determined that the Palisades plant is still operating within that licensing basis.

The second case follows Position 1 of the PTS Rule but considers that the actual best-estimate chemistry for- weld heat No. W5214 has slightly lower nickel as determined by the CEOG report in 1998 [20]. This evaluation was performed after the initial PTS submittal in 1995 and, using this information, the revised Ni = 1.007% which gives a new value of CF = 230.73 0 F. It is permitted under the PTS Rule in 10CFR50.61 to use the best-estimate values for Cu and Ni, however there is only a slight difference in the maximum fluence to reach the PTS screening criteria limit (i.e.,

1.595x10 1 9 n/cm 2) as shown in Table 13. The projected date to reach that limit using the interpolated fluence projections is July 2014 as shown in Table 16. Although this case does not show much additional margin from the January 2014 date, it is provided here to show that there is still slightly more time to be gained within the Position 1 approach of the PTS Rule method before the vessel reaches the 270'F screening criteria limit.

The third case considered plant-specific surveillance data from the Palisades supplemental capsules containing weld heat No- W5214. This case is labeled as Case 4a per the guidance document for use of surveillance data [19]. The Case 4a credibility assessment calculated a fitted chemistry factor of 198.8°F from the two Palisades capsule data points., The data were deemed to be credible based on meeting all the credibility criteria including scatter within the 1-sigma (i.e.,

28°F) scatter bounds. The limiting fluence for the vessel for this case is shown in Table 14. Using these results and a reduced margin term to account for credible data, the projected date to reach the PTS screening criteria limit would be beyond 2034 for the limiting vessel weld heat No. W5214, as shown in Table 18. Note: It is likely that some other beltline material would become limiting if this case was used for weld heat No. W5214. However, this case demonstrates that surveillance data can provide significant improvement in determining the effects of embrittlement on the limiting vessel beltline weld material.

The fourth case, permitted under the PTS Rule, is to use all sources of surveillance data that match the limiting weld heat No. W5214. This is designated as Case 4b, and the credibility assessment determined the fitted CF = 227.74°F. The data meet credibility criteria 1, 2, 4, & 5, and the scatter of the (measured - predicted) data was within 2-sigma (i.e., 56°F) such that it can be considered to be credible data for the chemistry factor, however the margin term, CYA, cannot be reduced in half.

Use of Case 4b for the Palisades vessel is acceptable because the (measured - predicted) scatter in the weld data is within the acceptable range of 56°F for a wide range of fluence. The limiting fluence for Case 4b is 1.685x1019 n/cm2 (E > 1 MeV) as shown in Table 15. Table 17 interpolates the vessel fluence and shows the projected date to reach the screening criteria limit is April 2017, a difference of three years compared to the first case using the current licensing basis and Position 1 approach. A summary of the four cases considered in this analysis is given in Table 18.

Report No. 0901132.401, Rev. 0 24 StructuralIntegrity Associates, Inc.

Table 12.

Limiting Fluence Determination for Current Licensing Basis (Case 1)

FLUENCE= 1.584E+19 n/cm2 f= 1.584 f FACTOR= f^(0.28-0. 1*@LOG(f))

= 1.1270 CHEM FACTOR= 231.08 OF ARTNDT= 260.5 "F RTNDTO= -56.0 °F MARGIN= 65.5 °F 0

TOTAL RTNDT= 270.0 F Table 13.

Limiting Fluence Determination for Revised Best-Estimate CF Value (Case 2) 2 FLUENCE= 1.595E+19 n/cm f= 1.595 f FACTOR= fA(0.28-0.1*@LOG(f))

= 1.1289 CHEM FACTOR = 230.73 OF ARTNDT= 260.5 °F RTNDTO= -56.0 °F MARGIN= 65.5 OF TOTALRTNDT= 270.0 °F Report No. 0901132.401, Rev. 0 25 R StructuralIntegrityAssociates, Inc.

Table 14.

Limiting Fluence Determination for Case 4a FLUENCE= 5.438E+19 n/cm2 f= 5.438 f FACTOR= fA(0.28-0.1*@LOG(f))

- 1.4185 CHEM FACTOR= 198.8 °F ARTNDT= 282.0 OF RTNDTO= -56.0 OF MARGIN= 44.0* OF TOTALRTNDT= 270.0 OF

reduced margin term based on credible surveillance data Table 15.

Limiting Fluence Determination for Case 4b FLUENCE= 1.685E+19 n/cm 2 f= 1.685 f FACTOR= fA(0.28-0.1*@LOG(f))

= 1.1437 CHEM FACTOR= 227.74 OF ARTNDT= 260.5 OF RTNDTO= -56.0 *F 0

MARGIN= 65.5 F TOTALRTNDT= 270.0 oF Report No. 0901132.40 1, Rev. 0 26 V StructuralIntegrity Associates, Inc.

Table 16.

Interpolation of PTS Limit Date Based on Current Licensing Basis and Revised Fluence Neutron Date Fluence @ 600 n/cm 2 (E > 1 MeV)

November 2013 1.571E+19 December 2013 1.574E+19 January 2014 1.577E+19 February 2014 1.579E+19 March 2014 1.582E+19" April 2014 1.585E+19 May 2014 1.588E+19 June 2014 1.591E+19 July 2014 1.594E+19**

August 2014 1.596E+19 September 2014 1.599E+19 October 2014 1.602E+19 November 2014 1.605E+19 December 2014 1.608E+19 January 2015 1.611E+19 February 2015 1.613E+19 March 2015 1.616E+19 April 2015 1.619E+19

Maximum fluence limit = 1.584x10'9 n/cm 2 for current licensing basis material case, CF = 231.08'F

- Maximum fluence limit = 1.595x10' 9 n/cm 2 for revised best-estimate weld, CF = 230.73'F Report No. 0901132.401, Rev. 0 27 Strucural Integrity Associates, Inc.

Table 17.

Interpolation of PTS Limit Date Based on Limiting Fluence for Case 4b Neutron Date Fluence @ 600 n/cm 2 (E > 1 MeV)

November 2016 1.670E+19 December 2016 1.673E+19 January 2017 1.676E+19 February 2017 1.679E+19 March 2017 1.682E+19 April 2017 1.685E+19*

May 2017 1.688E+19 June 2017 1.691E+19 July 2017 1.694E+19 August 2017 1.697E+19 September 2017 1.700E+19 October 2017 1.703E+19 November 2017 1.706E+19 December 2017 1.709E+19 January 2018 1.712E+19 February 2018 1.715E+19 March 2018 1.718E+19 April 2018 1.721E+19

Maximum fluence limit = 1.685x101 9 n/cm 2 for Case 4b using revised fluence and W5214 surveillance data CF = 227.74°F and full (2-sigma) margin term Report No. 0901132.401, Rev. 0 28 V StructuralIntegrity Associates, Inc.

Table 18.

Projected Maximum Fluence and Estimated PTS Limit Dates for Palisades Weld W5214 Case No. CF IRTNDT Fluence FF DRTNDT Margin RTPTS Est. PTS Date

(*F) (*F) (109 n/cm2) (*F) (*F) (TF)

(1) Current LB w/revised 231.08 -56 1.584 1.1270 260.5 65.5 270 March 2014 fluence (2) Current LB w/revised 230.73 -56 1.595 1.1289 260.5 65.5 270- July 2014 fluence and revised CF value 4a 198.80 -56 5.438 1.4185 282 44 I 270 > 2034*

4b 227.74 -56 1.685 1.1437 260.5 65.5 270 April 2017

Other beltline materials will likely become more limiting and will affect this date _

Case 1 - Current licensing basis CF value for W5214 weld and revised fluence calculation Case 2 - CEOG best estimate chemistry and CF value for W5214 weld and revised fluence calculation Case 4a - Use of credible Palisades W5214 surveillance data and revised fluence with reduced margin term Case 4b - Use of all W5214 surveillance data and revised fluence with full margin term 7.0

SUMMARY

AND CONCLUSIONS The results for all available surveillance capsules containing weld heat No. W5214 have been evaluated for applicability to the Palisades limiting Vessel weld. Updates to the surveillance capsule fluences and the projected fluence in the Palisades vessel were also reviewed and included in these analyses. The methods of 10CFR50.61 were applied including options for considering the effects of surveillance data on the projected RTNDT values. Using Position 1 of the PTS Rule (without the use of surveillance data) shows a projected date to reach the PTS screening criteria limit as late as July 2014. However, use of the weld heat No. W214 surveillance data can improve the projections of embrittlement and significantly changes the date to reach the screening criteria limit. Since weld heat no. W5214 is currently identified as the limiting material, the projections using Case 4a with the credible Palisades supplemental surveillance data show that the PTS screening criteria limit of 270'F would not be reached until after 2034; however, other vessel beltline materials would become limiting and that would change that date. For Case 4b, the surveillance data for weld heat No. W5214 were shown to be credible for determination of the CF value, but the scatter in the data would not permit a reduction in the margin term. However, use of the fitted chemistry factor for Case 4b with the revised fluence projections and the full margin term provides a better determination of the vessel embrittlement prediction for the limiting vessel weld. Using all the, available weld heat No.

W5214 surveillance data, a CF value of 227.74°F was determined for Case 4b and a projected date to reach the screening criteria limit of approximately April 2017 was estimated using the "updated fluence projections from Westinghouse.

Report No. 0901 132.401, Rev. 0 29 StructuralIntegrity Associates, Inc.

8.0 REFERENCES

1. Letter from Darl S. Hood (USNRC) to Nathan Haskall (Palisades), "Palisades Plant -

Reactoiý Vessel Neutron Fluence Evaluation and Revised Schedule for Reaching Pressurized Thermal Shock Screening Criteria (TAC No. MA8250)," November 14, 2000. (SI File No.

0901025.206).

2. Code of Federal Regulations, Title 10, Part 50, Section 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," U. S. Nuclear Regulatory Commission. (SI File No. 0901025.201).

3. Westinghouse Report, "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation,"

WCAP-15353, Rev. 0, January, 2000. (SI File No. 0901025.203).

4. CVGRAPH Version 5.0.2, Hyperbolic Tangent Curve-Fitting Program, Developed by.ATI Consulting, 2000.

5. Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," U. S. Nuclear Regulatory Commission, March 2001.

6. SWRI Report, "Reactor Vessel Material Surveillance Program for Indian Point Unit No. 2 Analysis of Capsule V," SWRI Project No. 17-2108, October 1988. (SI File No.

0901132.201).

7. SWRI Report, "Reactor Vessel Material Surveillance Program for Indian Point Unit No. 2 Analysis of Capsule Y," SWRI Project No. 02-5212, November 1980. (SI File No.

0901132.202).

8. Westinghouse Report, "Consolidated Edison Co. Indian Point Unit No. 2 Reactor Vessel Radiation Surveillance Program," WCAP-7323, May 1969. (SI File No. 0901132.203).

9. Westinghouse Report, "Consolidated Edison Co. of New York Indian Point Unit No. 3 Reactor Vessel Radiation Surveillance Program," WCAP-8475, January 1975. (SI File No.

0901132.204).

10. Westinghouse Report, "Analysis of Capsule T from the Indian Point Unit No. 3 Reactor Vessel Radiation Surveillance Program," WCAP-9491, April 1979. (SI File No.

0901132.205).

Report No. 0901132.401, Rev. 0 30 StructuralIntegrity Associates, Inc.

11. Westinghouse Report, "Analysis of Capsule Y from the Power Authority of the State of New York Indian Point Unit 3 Reactor Vessel Radiation Surveillance Program," WCAP-10300, March 1983. (SI File No. 0901132.206).

12. Westinghouse Report, "Analysis of Capsule X from the Carolina Power & Light Company H. B. Robinson Unit 2 Reactor Vessel Radiation Surveillance Program," WCAP-15805, March 2002. (SI File No. 0901132.207).

13. Westinghouse Report, "Analysis of Capsule X from Entergy's Indian Point Unit 3 Reactor Vessel Radiation Surveillance Program," WCAP- 16251-NP, Revision 0, July 2004. (SI File No. 0901132.208).

14. Framatome ANP Report, "Test Results of Capsule SA-240-1 Consumers Energy Palisades Nuclear Plant - Reactor Vessel Material Surveillance Program," BAW-2398, May 2001. (SI File No. 0901132.209).

15. Framatome ANP Report, "Test Results of Capsule SA-60-1 Consumers Energy Palisades Nuclear Plant - Reactor Vessel Material Surveillance Program," BAW-234 1, Revision 2, May 2001. (SI File No. 0901132.210).

16. Letter from J. Kneeland to M. J. DeVan dated February 2, 1999, Enclosure. (SI File No.

0901132.211).

17. Westinghouse Report, "Neutron Fluence Analysis for Palisades Surveillance Capsule SA-240-1," CPAL-01-009, April 30, 2001. (SI File No. 0901132.212).

18. Email Transmittal from Stanwood L. Anderson (Westinghouse) to Timothy Griesbach,

Subject:

Revised Fluence Values for Design Inputs to PTS Evaluation, April 15, 2010. (SI File No. 0901132.223)

19. "Generic Letter 92-01 and RPV Integrity Assessment," NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. (SI File No. 0901132.213).

20. "Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best Estimate Copper and Nickel Content," Combustion Engineering Owners Group, CEOG Task, 1054, CE NPSD- 1119, Rev. 01, July 1998. (SI File No. 0901025.204)

21. ASME Boiler and Pressure Vessel Code,Section III, 1965 Edition, including all addenda through Winter 1965, American Society of Mechanical Engineers.

Report No. 0901132.401, Rev. 0 31 V StructuralIntegrityAssociates, Inc.

22. ASTM E185-66, "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors."

23. Design Input Record from Thomas Allen (Entergy) to Timothy Griesbach (SIA) for basis/reference for adjusting the Palisades Cycle 1 through 12's cycle length expressed as Effective Full Power Day (EFPD) & unadjusted cycle lengths and operating dates, Attachments LAR of 2-21-2000, and EA-DOR-09-01, Rev. 0, April 15, 2010. (SI File No.

0901132.224)

24. ORNL Report, "Analysis of the Irradiation Data for A302B and A533B Correlation Monitor Materials," Oak Ridge National Laboratory, NUREG/CR-6413, ORNL/TM- 13133, April 1996.

25. EricksonKirk, M. A., EricksonKirk, M. T., Rosinski, S., Spanner, J., "A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data," Journal of Pressure Vessel Technology, Volume 131, June 2009. (SI File No. 0901132.225)

26. Haskell (Consumers Energy) to NRC, "Docket 50-255 -License DPR-20 -Palisades Plant Response to Request for Additional Information Regarding Reactor Pressure Vessel Integrity (TAC No. MA0560)," September 8, 1998. (SI File No. 0901132.217)

27. Westinghouse Report, "Carolina Power & Light Co. H. B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program," WCAP-7373, January 1970. (SI File No. 0901132.218)

28. "Evaluation of Palisades Nuclear Plant Reactor Pressure Vessel Through the Period of Extended Operation," Constellation Nuclear Services Report, CNS-04-02-0 1, Rev. 1, June 2004. (SI File No. 0901132.219)

29. "Estimation of EDYS for IP2 Reactor Vessel Head by 2R17 and 2R18," Entergy Nuclear Calculation Number FCX-00538, 7/20/05. (SI File No. 0901132.220)

30. Entergy Nuclear Calculation Number IP3-CALC-RV-03720, Rev. 2, Page 7 of 8. (SI File No. 0901132.221)

31. RVID2, NRC Reactor Vessel Integrity Database, U. S. Nuclear Regulatory Commission, Version 2.0.1, 2000.

32. "Determination of 30 ft-lb Shift (AT30) Values for the Palisades Reactor Vessel Heat No.

W5214," Structural Integrity Associates Calculation No. 0901132.301, Rev. 0, 4/15/10.

(SI File No. 0901132.301)

Report No. 0901132.40 1, Rev. 0 32 StructuralIntegrity Associates, Inc.

33. "Verification of the Time Weighted Average Temperatures for Indian Point Units 2 and 3 Vessel Weld Surveillance Capsules," Structural Integrity Associates Calculation No.

0901132.302, Rev. 0, 4/15/10. (SI File No. 0901132.302)

34. Letter from Nathan Haskall (Palisades) to U. S. Nuclear Regulatory Commission, "Reply to Request for Additional Information Regarding Reactor Pressure Vessel Neutron Fluence Evaluation (TAC No. MA8250)," July 6, 2000. (SI File No. 0901132.226).

Report No. 0901132.401, Rev. 0 33 StructuralIntegrity Associates, Inc

400.00 350M0 .-.- __ ________

I ----------------- _____I-- ~ -- - ~ * * *-.--I . -- . - - -- -

250.00

__- __P I-

- -----.. I--____.........

IL . 11171_

,,1, 111 ... 77

_ ~ ---- T PAL -.- ~ -~F 200 . _oo

... 0-- __ _I_

- I . - -- .I 1 F 20.OE002.E+940+1 IP3__

IP3 __ _ ____- 17 . ___ ___ __

.- 0 90112.41..ev.. Si ra l i J PI P i --------

0.00................._.........__

10.E002.0+940E ...................... . .______ ____ ___ 9 ___

7l e c } ------

Figue ] Bes Fi toDataforallV¢524 Srveilaae Dta wt/ epoted luece ad Vnde SBet Vlue o.~~--- 4 tuurlItedyAsoiteI CF0217.4671ev Report N(

350.00 250-00 - i j .. . ..... .. i SA-L 4"-0-i

- -*iii .. . !*

200.00 S40- ii 150.00 Best Fit CF= 198.8F 100.00 50.00 0.00 O.OOE+00 2.OOE+19 4.00E+19 FkenMe (n/cmz)

Figure 2. Palisades Supplemental Surveillance Data (W5214) with Revised Fluence and Refitted Shift (Case 4a)

Report No. 0901132.401, Rev. 0 35 V StructuralIntegrity Associates, Inc.

400.00 350.00 300.00 25000 U.

200.00 C

150.00 100.00 50.00 0.00 0.OOE+00 2-O0E+19 400E+ 19 Oluence (n/cmz)

Figure 3. Best Fit for all W5214 Surveillance Data with Revised Fluence and Refitted Shift (Case 4b)

Report No. 0901132.401, Rev. 0 36 V Stwutural Integrity Associates, Inc.

100,

- -- Two Sigma 50F.

o A5330-1 HSST01/02 CMM 80 a Plate Materials x WIteld Malertals 60 a Forging Materials

40. 4o xx x AX 20 0 13 ScoI20 -

o~Oooo o:

0 A 0- U ° --°-- ,,, 0 o) 0*93 x --..----- 0 amu o 0 .* *. ,,o I a x ao x. 0 o DA 8 mu a-0)E

-0xX x X x.ox

-80 ._4__-

s -

x 6AX 0 _ *0 13 x t

-10 0. . . . . - .. . . . .. . .. . ..

1100E+17 1.00E+18 1.00E+lg 1.00E+20 Fluence, E > I MeV [n/cm t j Figure 4. Plot of Residual vs. Fast Fluence for A533B-1 HSST-01/HSST-02 CMM with Companion Materials, the Overall 2-Sigma Scatter is 50'F [24].

Rep ort No. 0901132.401, Rev. 0 StructuralIntegrity Associates, Inc.

2.000E+19 -I I I Case 2 Case 4b 1.800E+19 - July 2014 Aril 2017 1.600E+19 - . . .....-.-. Case 1 S1.400E+19 Case I'

,arch 014 1-200E+19 -

A W

C4, 1.OOOE+19 _

E C 8.000 E+18 S 6.000E+18 _

4.OOOE+18 _

Note: Case 4a (not shown) would extend beyond 2034 2.000E+18 -

O.O00E+00 Figure 5. Projected Peak Fluence at 600 Weld Location (from [18]) and Revised RTpTs Limit Dates Report No. 0901132.401, Rev. 0 38 StructuralIntegrityAssociates, Inc.

APPENDIX A CEOG DETERMINATION OF BEST-ESTIMATE CHEMISTRY FOR WELD HEAT NUMBER W5214 (from CE NPSD-1119, Rev. 1 [201)

Report No. 0901132.401. Rev. 0 A-1 ,

J 01ruuMaurw liggwgrigy MW~UUldlVb, I1IC.

Table 5 (contlnmaD Ont Estimate Caoper and Ncelby HRea Number SMg Nmmber 2SrILr, S Nkk*M S IM&l 59n 0.1m5 0.057 wu* own 6329... ........ 0.704 odmoo O-W 0.o6o obac s!#l! ,mam Co. w M 83640 0.09 o.09 m=Ople me w 83642 0.046 0.0oo simple mes 83648 0.042 0.136 3W&p nwwa 83650 0.0415 0.08 weighted me=a 83653 0.042 0.102 !mibaed aum 860543 0.214 0.046 MiE rame 86034B.956 0.213 0.052 mm. of lndume sm dm am00 0.054 0.151 !Mois!d Mmoa 88112 0.045 0.200 sp mean 88114 .0.043 0.189 sknpll m=a 89476 0.022 0.071 sknae m=a 89.33 0.046 0.059 sknol mea 90069 0.040 0.071 weiined me ..

90(t1 0.035 0.079 kmile mean 90077 0.036 0.057 shoole rmea

.. 099 0.197 0.060 simple Cu. tr wie Ni 90130 C.044 0.133 simple me=

90136 0269 0.070 weitýW mean 90144 0.042 0.075 simple mean 90146 0.039 0.082 weighted mean 90209 0.044 0,126 simple mean 9565 0.213 0.052 HI. W04SB/9565 data A8746 0.150 0.13 Avg. Ca wih bare wire dm tcNi:Ni BOLA 0.027 0.913 simple mean HODA 0.027 0.947 simpe man W5214 w/N1200 0.21. 1.007 coil wgt'd Cu. Ni200 BE See Repow" CE NPSD- 1039. Rev 02 for method of dctennination.

.45 Ca¢m"am EnWW*q*,W*W, OevamV, ckXFVD-11IW. ~ 91 Cdpp.*U to 1"S. C.AMd" Eftif g toe ~ 1:419 Report No. 0901132.401, Rev. 0 A-2 R StructuralIntegrity Associates, Inc.

APPENDIX B EXCERPT FROM GENERIC LETTER 92-01 AND RPV INTEGRITY ASSESSMENT NRC/INDUSTRY WORKSHOP ON RPV INTEGRITY ISSUES Report No. 0901132.401, Rev. 0 B-1 I StructuralIntegrity Associates, Inc.

REQUIREMENTS AND RECOMMENDATiONS IN 10 CFR 50.61 & RG 1.99 REV. 2 Per I0CFR 50.61 (c)(2) 7To verify that RTNDT for each vessel beltrine maeflal 13 a bounding value for the Spew. reactor vessel. licensees shell consider plant-specific information that could affect the leveh of embciement. This ko'matlon Includes but is not limited to the ,eactor vesale OpMOfVg temperaiue md any rleded sovellnce pfogrem results.

Per Footnote 5:

6 Surveillance program results means any data that de o-strates the embrbtl4emer trends for the limitingi beltlne material, including but not limited to data from test reactors or from surveilance program at othe plants with or without srvreiHance program Integrated per 10 CFR Part 50, Appendix H.

Per RG 1.99 Rev. 2 Position 2.1 and 10 CFR 5.61(c)(2)(iXB):

"ifthere Is dleor evidence that the copperor nickel content of the surveillanceweld differs from that of the vaseweld, i.e., diff from the average for the we"d wire heat number associated with the vessel weld and the, surveillance weld, the measuredvalues of AdRTsPT should be adjustedby muWti Iylng them by the ratdo of the chenisty fco for the vessel weld to that for the survefth oo wel/r Table CF 1,f Of. ,*RT p r tNo Adjusted 0RTJ ( TrcuaB, CFIgi A i, Report No. 0901132.401, Rev. 0 B-2 Structurallntegrity Associates, Inc.

IRRADIATION ENVIRONMENT ADJUSTMENTS

Irradiation temperature and fluence are first order environmental variables In assessing bradfaffon damage Other variables are believed to be less significant contributors Must account for differences in temperature between surveillance specimens and vessel 4* Sats~s have shown that for temperatures near 550 'F, a I 'F decrease In Irradiation temperature will result In approximately a I OF Increase In ART~n, Report No 0901132.401. Rev. 0 J

B-3 u ategrity Associates, Inc.

lk> 01ruGful-al

RECENT ISSUES ON USE OF SURVEILLANCE DATA S~ "Beet4it lineW through survelUance data (plot of ARTND. vs.

fluence) must go through otigin

Using a CF detrmilned from nonicredible surveillance data

Correcting for chemical compo*oiton (ratio procedure)

Correcting for Irradiation environment (temperature)

Appropriate chemical compositton for multipte surveiflance capsules from a single source (i.e., mean vatue for all capeules from that source) 0 Appropriate rormatizing parameters for surveillanco data when assessing credibility (ie., mean of survelllance data) and determining CF (i.e., best esEmaet of ves"l)

Report No . 0901132.401, Rev. 0 B-4 . ,...,.. gnU.. A nnnnM#nt. ~nn 41 U u aIO giiyffuy t10 tuaw, fiii,

CASE 4: SURVEILLANCE DATA FROM PLANT AND OTHER SOURCES Surveillance data (Weld metal)

. Mr, : Ad.At ART ca"9NOSS Vendiori rwmd.

TT 0 ~ T 1""

M*( o 6=o1pl~u va P100 A - W 0=014 I $MO &M 210" 116W0 Nant B - I1)2 . 5I00 O07 i 124.0 1280 MintS- BaW- C4 0*7500W 0.36 M.020-tan Cl-I W 0.33 OA7 S5.0 0*3_ IVA 2 -...

PlMant C

2 B5W 0.43 OJY N&6.0 6A99 *.0 *21.0 PtM. t Wx... 0,66 88 ... ,021 166. 1,72.1 Ptmn X *2 WwMl 10.24 10.961 536. 1.40 M&0.0 237.0 Vessel being analyzd is Ptlnt*X Best estimate chemistry for heat (Weld metal) 0.34% Cu, 0.68% NI -* Table CpV0SI1 Chem. 220.6SF Credibility assessment- Using Plant "X" data on~y No temperature adjustment needed DetermiIne Surveillance CF for Plant X data only (214.11T)

Wad. FU0o teoued predwot Cepsur. Cui W1 Temp. (1ART~ PIE~td Plant 1 0x24 10.8 .00 0 I6O 140., 24.7 IPlant x -2 6 0.24 .68 5.0 1.40 1 240 -43S Data are ciredible since st.altw; Is less than o&(29*F) for all surveillance spectmens Report No. 0901132.401, Rev. 0 B-5

StructuralIntegrity Associates, Inc.

CASE 4: SURVEILLANCE DATA FROM PLANT AND OTHER SOURCES (cont'd)

Determination of CF - Plant "X* date only No temperature adjustment. needed Adjust measured RTNOT to cOemical composition of VESSEL Table CFsurv" chem. a MI Determine Surveillance CF No temperature adjustment needed Surveillance CF = 259.0*F Final Result assuming RTNOT(U) - -7.0F; M - 49.8; F 0.8745 RTNoT -7.0 + 49.8 4 (259.0 0.8745) 269.20F Report No. ()901132.401, Rev. 0 B-6 *e .. ,.a,,

k> guylify ->DUL'Idiva, mu.

CASE 4: SURVEILLANCE DATA FROM PLANT AND OTHER SOURCES (cont'd)

Credibility assessment - All data Data adjusted to mean chemlcal comp. of surveillance capsules Cu a 0.31%

Ni = 0.67%

Data adjisted to mean temperature of surveillance capsules Temp. - BS0T Determine Surveillance CF (218.4F)

IrrtL flu Ac.usted Ajrnt T Pmdcted (Adjusted -

Capsule Cu NJ Tamq. 3 using Rato and ART Predlotd)

('F) ~ ramporatute (550'f T 6T, Plat A - 1 0,37 0*,0 W8.0 0,79 19t.0 203.1 7.71 PMWnt B -I 0.33 0.6? 66N.0 0.107 12M.0 94.1 31.9 Plant B - 2 0.3s 0.6? 681.0 0.96 202.5 209.6 .7.1, Plant C - 1 0.33 0.67 556.0 0.830 18s= 207.0 -24.8 Plant C -2 0.33 I087 656A0 0.N8 221l0 216,4 4.5 Pant X- 1 0.24 0.0, 63K*0 0.281 172,n1 142.0 294 IAMAtX-2 0.24 OM 536.0 1.94-0 1 257.6 260L0 Data are not Credible since scafter Is greater than cA (28"i=) for several surveillance specimens

.Report 1No. 0901132.401. I Rev. 0 B-7 MuralIntegrity Associates, Inc.

ak->

APPENDIX C PALISADES SUPPLEMENTAL MATERIALS SURVEILLANCE PROGRAM RESULTS FORWELD NO. W5214 Report No. (0901132.401,J Rev. 0 C-1 utegrity Associates, Inc.

W> ifulflufal

BAW-2398 May 2001 Test Results of Capsule SA-240-1 Consumers Energy Palisades Nuclear Plant

- Reactor Vessel Material Surveillance Program --

by M. J. DeVan.

FTI Document No. 77-2398-00 (See Section 7 for document signatures.)

Prepared for Consumers Energy Prepared by Framatome ANP, Inc.

3315 Old Forest Road P. 0. Box 10935 Lynchburg, Virginia 24506-0935

'FRAMATMEAKNP YIF

Executive Summary This report describes the results of the tests performed on the specimens contained in the second supplemental reactor vessel surveillance capsule (Capsule SA-240-1) from the Consumers Energy Palisades Nuclear Plant. The objective of the program is to monitor the effects of neutron irradiation on the mechanical properties of the reactor vessel materials by testing and evaluation of Charpy impact specimens.

Supplemental Capsule SA-240-1 was removed from the Palisades reactor vessel at the end-of-cycle 14 (EOC-14) for testing and evaluation. The test specimens included modified 18mM Charpy V-notch inserts for three weld metals fabricated with weld wire heats W5214, 34B009, and 27204 and standard Charpy V-notch specimens fabricated from the correlation monitor plate material, HSST Plate 02. The weld metal Charpy inserts were reconstituted to full size Charpy V-notch specimens. The reconstituted weld metals along with HSST Plate 02 material were Charpy impact tested. The results of these tests are presented in this document.

ii ARAMATOME ANp

Table 3-2. Chemical Composition of Palisades Capsule SA-240-1 Surveillance Materials Chemical Composition, wt%

Weld Metal Weld Metal Weld Metal Correlation Monitor Plate Element W5214aa) 34B009(a) 27204'b) Heat No. A1195-1*c)

C 0.094 0,110 0.142 0.23 Mn 1.161 1.269 1.281 1.39 P 0,009 0.012 0.009 0.013 S 0.012 0.016 0.008 0.013 Si 0.252 0.181 0.217 0.21 Ni 1.0451" 1.121 (bI 1.067 0.64 Cr 0.040 0.040 0.071 ---

Mo 0.510 0.543 0.525 0.50 Cu 0.30710) 0 . 1 8 5(b) 0.194 0.17 191 (a) AEA Technology analysis.

(b) Analysis provided by Consumers Energy. DO' (c) ORNL analysis.111]

3-4 FRAMATOME ANP

Table 4-3. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal W5214 Test Impact Lateral Shear Specimen Temperature, Energy, Expansion, Fracture, I1D OF ft-lbs rmil %

2AL1 70 14 9 0 2AH3 125 15.5 6 20 AW5 175 24.5 15 10 2AJI 200 13 10 40 AU4 200 26.5 15 35 2AL3 225 25 11 50 AP1 250 40 26 65 AU5 300 54.5 47 95 2AES 350 49 42 95 2AK5 400 50.5* 35 100 AP5 450 52.5* 45 100 AS2 500 54.5* 43 100

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.J'jT 4-7 -RAMATOME ANP

Table 4-6. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. A1195-1 Test Impact Lateral Shear Specimen Temperature, Energy, Expansion, Fracture, ID OF ft-lbs mril %

02D2-10 70 6.5 4 0 02D2-13 125 15.5 10 20 02D2-23 175 27.5 24 30 02D2-17 200 26 19 35 02D2-2 200 44.5 29 55 OCD2-22 225 44.5 30 55 02D2-19 240 54 40 70 02D2-8 250 70 50 80 02D2-5 300 83* 66 100 02D2-15 350 82.5* 72 100 02D2-24 400 89.5* 67 100 02D2-11 500 82.5* 65 100

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.t[71 4-10 4RAMATOME ANP

Table 4-11. Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-240-1 Surveillance Materials Material Hyperbolic Tangent Curve Fit Coefficients Description Absorbed Energy Lateral Extpansion Percent Shear Fracture Weld Metal A: 27.4 A: 22.8 A: 50.0 W5214 B: 25.2 B: 21.8 B: 50.0 C: 111.6 C: 83.5 C: 72.5 TO: 208.1 TO: 231.7 TO: 223.2 Weld Metal A: 29.8 A: 22.9 A: 50.0 34B009 B: 27.6 B: 21.9 B: 50.0 C: 111.7 C: 88.0 C: 109.8 TO: 176.6 TO: 184.3 TO: 192.6 Weld Metal A: 28.0 A: 25.6 A: 50.0 27204 B: 25.8 B: 24.6 B: 50.0 C: 145.7 C: 169.2 C: 118.4 TO: 215.3 TO: 225.9 TO: 210.1 Correlation A: 43.3 A: 35.8 A: 50.0 Monitor Plate, B: 41.1 B: 34.8 B: 50.0 HSST Plate 02 C: 75.3 C: 83.1 C: 75.9 (Heat No. A1195-1) TO: 211.8 TO: 222.2 TO: 206.5 4-15 fFRAMATOME ANP

Table 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-240-1 Surveillance Materials 30 ft-lb Transition Temperature, 50 ft-lb Transition Temperature, 35 mi Lateral Expansion Material FT OF Transition Temperature, 'F Upper-Shelf Energy, ft-lb Description Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated Decrease Weld Metal -60.2 O 219.9 280.1 -17.4(1) 372.7 390.1 -29.61" 284-3 313 9 102.7'al 52.5 50.2 W5214 Weld Metal -82.0(21 177.4 259.4 -45.0(') 280.8 325.8 -51.6(> 238.6 290.2 113.9(a) 57.4 56.5 34B009 Weld Metal -41.20) 226.6 267.8 -6.1 ) 399.7 405.8 Not 293.7 --- 108.41") 53.8 54.6 27204 available.

HSST Plate 02 45.7(c) 186.6 140.9 78.3(c) 224.2 145.9 Not 220.3 --- 120.3"e 84.4 35.9 Heat No A1195-1 available.

I-.

(a) Data reported in AEA Technology Report AEA-TSD-0774. 1 91 (b) Data reported in CE Report No. TR-MCC-189.[' 8 (c) Data reported in NUREG/CR-6413.t" 0

1 I I { I I I I I I

Figure 4-2. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal W5214 100 75

' 50 LL 25 0

0 100 200 300 400 500 600 Temperature, F

= 100 E

e0 80 2 60 x 40 ..... .... .... ...... . ........ -- - - - I........

41 l ,

S20 0J 0 100 200 300 400 500 600 Temperature, F 120 T3,EF: +6.

T50: +372.7F 100 I T30: +219.9F CvLJSE: 52.5 t-l 80 I 601-CL)

.E 401 20 0

Material: Weld Metal Heat Number, W5214 0

0 100 200 300 400 500 600 Temperature, F 4-18 f,

Figure 4-5. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Correlation Monitor Plate Material (HSST Plate 02), Heat No. A1195-1 100 or 75 U

'I 50 IL U

4) 25 a) 0 0 100 200 300 400 500 600 Temperature, F 100 80 60 Uj 40 .................... .................................

20 0

0 100 200 300 400 500 600 Temperature, F 120 T 3 .MLE: +220.3 F Tao: +224.2 F Tso:, +186.6F 100 F CvUSE: 84.4 fl-l U) 80

.4)

U 60 wC

'I U

a.

40

Material: HSST Plate 02 Orientation: Longitudinal SHAat NumhAr: At 195-1 0

0 100 200 300 400 500 600 Temperature, F gA 4-21 I' FRAMATOME ANP

6.0 Summary of Results The investigation of the post-irradiati on test results of the materials contained in the second supplemental surveillance capsule, Capsule SA-240-1 removed from the Consumers Power Company Palisades reactor vessel, led to the following conclusions:

1. Observation of the Capsule SA-240-1 thermal monitors indicated that the irradiated test specimens were exposed to a maximum irradiation temperature less than 558 0F,

2. Thirty-six pre-machined irradiated 18mm Charpy inserts were successfully reconstituted and machined to Type A Charpy impact specimens. The reconstituted Charpy specimens were subsequently impact tested.

3. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal W5214 increased 280.1*F and 390.1'F, respectively. In addition, the CVUSE for this material decreased 48.9%.

4. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal 34B009 increased 259.4°F and 325.8'F, respectively. In addition, the CVUSE for this material decreased 49.6%.

5. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal 27204 increased 267.8'F and 399.7°F, respectively. In addition, the CUSE for this material decreased 50.4%.

6. The correlation monitor plate demonstrated similar behavior with an increase in the 30 ft-lb and 50 ft-lb transition temperatures of 140.9°F and 145.9°F, respectively.

The percent decrease in the CRUSE for this material is 29.8%.

6-1 IFRAMATOMEANP

2] BAW-2341, Revision 2 May 2001 21 El El a

Test Results of Capsule SA-60-1 Consumers Energy Palisades Nuclear Plant El -- Reactor Vessel Material Surveillance Program --

by M. I. DeVan I

Li Li a

FTI Document No. 77-2341-02 (See Section 7 for document signatures.)

Li B

Prepared for I Consumers Energy K]

Prepared by Eli Framatome ANP, Inc.

3315 Old Forest Road LI P. 0. Box 10935 Lynchburg, Virginia 24506-0935 K]

Li fRAMATOME ANP

Executive Summary LI This report describes the results of the test specimens from the first supplemental capsule S(Capsule SA-60-1) of the Consumers Energy Palisades Nuclear Plant as part of their reactor vessel surveillance program. The objective of the program is to monitor the effects of neutron irradiation on the mechanical properties of the reactor vessel materials by testing and evaluation H of Charpy impact specimens.

Supplemental Capsule SA-60-1 was removed from the Palisades reactor vessel at the end-of-cycle 13 (EOC-13) for testing and evaluation. The capsule contents were removed from Capsule SA-60-1 for testing and examination. The test specimeins included modified 18mm Charpy V-notch inserts for three weld metals fabricated with weld wire heats W5214, 34B009, and 27204 and standard Charpy V-notch specimens fabricated from the correlation monitor plate material, HSST Plate 02. The weld metal Charpy inserts were reconstituted to full size Charpy V-notch specimens. The reconstituted weld metals along with HSST Plate 02 material were Charpy impact tested.

Following the initial Charpy V-notch impact testing, the laboratory performed a calibration of the temperature indicator used in the Palisades Capsule SA-60-1 testing. The results of the laboratory calibration indicated the instrument was out-of-tolerance. Based on the results of this calibration test, the laboratory revised the Charpy impact test temperatures accordingly. Revision 1 corrects the test temperatures for the Supplemental Capsule SA-60-1 reconstituted weld metal Charpy V-notch impact specimens and the HSST Plate 02 Charpy V-notch impact specimens.

Revision 2 provides an update to the hyperbolic tangent-curve fits of the Charpy impact curves by restraining the upper-shelf energy.. For these curve fits, the lower-shelf energy was fixed at 2.2 ft-lbs for all cases, and for each materials the upper-shelf energy was fixed at the average of 2 all test energies exhibiting 100% shear, consistent with ASTM Standard E 185-82.

F ii ARAMATOME ANP

Table 3-2. Chemical Composition of Palisades Capsule SA-60-1 Surveillance Materials Ii Chemical Composition, wt%

Weld Metal Weld Metal Weld Metal 27204(b) Correlation Heat No. Monitor Plate Al1i9541Ce)

Element W5214(a) 34B009(a)

C 0.094 0.110 0.142 0.23 L]

Mn 1.161 1.269 1.281 1.39 P 0.009 0.012 0.009 0.013 S 0.012 0.016 0.008 0.013 Si 0.252 0.181 0.217 0.21 Ni 1.045(o' 1.121(b) 1.067 0.64 Cr 0.040 0.040 0.071 ---

Mo 0.510 0.543 0.525 0.50 Cu 0 . 3 0 7 (b) 0.185(b) 0.194 0.17 (a) ABA Technology analysis.8 9

(b) Analysis provided by COnsumers Energy.

0 (c) ORNL analysis.'

Ll U

Li ILI 3-4 7 7 FRAMATOME ANP

P" Table 4.3. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal W5214 Test Impact Lateral Shear Specimen Temperature, Energy, Expansion, Fracture, ID OF ft-lbs mil %

AA2 74 10 4 0 AWl 129 24 15 5 AW2 154 23.5 15 15 2AF5 204 30 16 50 AL3 229 33.5 23 65 AA4 254 28 19 60 2AL6 279 43.5 35 80 2AE2 279 48.5 38 90

-2AH6 329 47.5 35 90 AR94 404 51.5* 43 100 2AH1 454 55* 47 100 AV4 479 57* 46 100 Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.15 i.

r 4-7 4- 7RAMATOME ANP

I U] Table 4-6. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. A1195-1 LI Test Impact Lateral Shear Specimen Temperature, Energy, Expansion, Fracture, LI I1D OF ft-lbs mil %

02D2-9 74 8 3 5 El 02D2-3 104 20.5 16 10 02D2-1 129 24.5 18 20 El 02D2-7 154 26.5 23 40 02D2-18 179 35.5 28 45

] OCD2-21 204 48.5 40 70 02D2-14 229 53.5 43 65 LI 02D2-16 229 51.5 43 70 a 02D2-4 02D2-6 02D2-12 254 279 329 73.5 85*

-87.5*

65 70 74 80 100 100 El 02D2-20 404 86.5* 77 100 El

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.15 El El El

[j LI C]

Li if] 4-10 AFRAMATOME ANP

Table 4-11. Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-60-1 Surveillance Materials F--

Material Hyperbolic Tangent Curve Fit Coefficients Description Absorbed Energy Lateral Expansion Percent Shear Fracture r Weld Metal A: 28.4 A: 25.0 A: 50.0 W5214 B: 26.2 B: 24.0 B: 50.0 C: 158.1 C: 160.0 C: 80.5 TO: 188.8 TO: 239.6 TO: 214.9 Weld Meta, A: 28.7 A: 25.3 A: 50.0 34BO09 B: 26.5 B: 24.3 B: 50.0 C: 123.8 C: 97.6 C: 89.6 TO: 161.8 TO: 196.4 TO: 179.6 2,

Weld Metal A: 27.6 A: 25.9 A: 50.0 27204 B: 25.4 B: 24.9 B: 50.0 C: 111.4 C: 101.8 C: 92.1 L.

TO: 201.4 TO: 214.4 TO: 187.1 I-Correlation A: 44.3 A: 41.3 A: 50.0 Monitor Plate, B: 42.1 B: 40.3 B: 50.0 L~.

HSST Plate 02 C: 95.1 C: 104.9 C: 85.2 (Heat No. Al195-1) TO: 193.0 TO: 208.6 TO: 183.7 L.

V U

U F-1~

L_

k-

ý4-15 4F-RAMATOME AN P

Table 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-60-1 Surveillance Materials 30 ft-lb Transition Temperature, 50 ft-lb Transition Temperature, 35 mil Lateral Expansion Material OF OF Transition Temperature, OF Upper-Shelf Energy, ft-lb Description eUnirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated Decrease Weld Metal -60.2(a) 198.8 259.0 -17.4(a) 375.6 393.0 -29.6(a) 310.1 339.7 102.7(a) 54.5 48.2 W5214 Weld Metal -82.0(a) 167.8 249.8 -45.0(o) 298.6 343.6 -51.6(a) 237.5 289.1 I13.9(a) 55.25 58.65 34B009 2

Weld Metal -41.2(b) 211.9 253.1 -6.1(') 355.6 361.7 Not 249.4 -- 108.4O() 53.0 55.4 27204 available.

HSST Plate 02 45.7(') 159.4 113.7 783P) 206.0 127-7 Not 187.9 -- 120.3() 86.3 34.0 Heat No A 1195-1 available.

(a) Data reported in AEA Technology Report AEA-TSD-0774. 8 6

(b) Data reported in CE Report No. TR-MCC-189.1 (c) Data reported in NUREG/CR-6413.' 0 0

3:

Figure 4-2. Charpy Impact Data for Irradiated Weld Metal W5214 100 or 75 50 U}

I-Ll 25 0

LI -100 0 100 200 Temperature, F 300 400 500 600 100 80

.2 60 x 40 it 20

-WI 0

-1CO00 0 100 200 300 400 500 600 Temperature, F 2

120 TqSMLE : +310.1 F 14.

Tso: +375.6 F 100 To: +198.8 F CvUSE: 54.5 ft-lb 80 60 w

... °°. 1..... ..... ... °. =... ....... * ..... . °.. °.. ..... .....

46 Co 40 Mater.a.:.Wel..Meta.

20 l

Heat Number: W5214 0-

-10 0 100 200 300 400 500 600 Temperature, F 4-18 4tRAMATOME ANP

I]

Figure 4-5. Charpy Impact Data for Irradiated Correlation Monitor Plate Material (HSST Plate 02), Heat No. A1195-1 ZI 100 75 LL 50 M

25 0

-100 0 100 200 300 400 500 600 Temperature, F 7

En 100 CF 80 60 Ck

'U

0. 40 cci 20 r--

0

-100 0 100 200 300 400 500 600 Temperature, F 2

L-120 T.SSMLE +5.

Tso: +206.0F 100 'T30: :1 59.4 GvU SE: 86.3 ft-l 80 I0 60 CL A

40 L.

20 a Material: HSST Plate 02 Orientation: Longitudinal Heat Number: A1195-1 0

-100 0 100 200 300 400 500 600 Temperature, F fAM E 4-21 '.FRAMATOMEAMP

Palisades Nuclear Plant - Weld/W5214 (Unirr)

CVGRAPH 4.0 Hyperbolic Tangent Curve Printed at 15:08:08 on 12-01-1995 Page I Coefficients of Curve I A 52.4 B 5029 C 99.19 TO -12.69 Equation is: CVN = A + B * [ tanh((T - TO)/C)- I Upper Shelf Energy: 102.7 Fixed Temp. at 30 ft-lbsr -60.2 Temp. at 50 ft-lbs. -17.4 Lower Shelf Energy: 2.1 Fixed Material: WELD Heat Number: W5214 Orientation: TI Capsule: Unirr Total Fluence: O.0 300--

250o Cn 200-150-z 5O0-Ho 5-- - - - - - -

t0L) I

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: PAL Cap,: Unirr Material: WELD OriL TL Heat f. W5214 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-110 11.8 14.5 -2.7

-80 33.9 22.69 112

-80 20.6 22.69 -2.09

-80 29.5 22.69 6.8

-40 47.9 38.89 9

-40 43.5 38.89 4.6

-40 29.5 38.89 -9.39

-40 4129 38.89 2.4 Data continued on next page

Palisades Nuclear Plant - Weld/W5214 (Unirr)

Page 2 Material: WELD Heat Number. W,5214 Orientation: TL Capsule: Unirr Total Fluence: 0.0 Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 0 64.19 58.8 5.39 0 39.09 58.8 -19.7 20 62.7 68.4 -5.7 20 60.5 66.4 -7.9 30 78.19 72.8 5.39 40 612 76,86 -15.66 60 87 83.82 3.17 60 75.19 83.82 -8.62 60 111.4 83.82 27.57 110 110,59 94.88 15.71 110 98.8 94.88 3.91 210 110.59 101.58 9.01 210 95.9 101.58 -5.68 300 97.4 102.51 -5.11 300 94.4 S02.51 SUM of RESIDUA -8.11 ALS = 10.77

APPENDIX D INDIAN POINT 2 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 Report No. 0901132.401, Rev. 0 D-1 Structural Integrity Associates, Inc.

cr Ir--

DATE:. SEP 2 9 1977, WNES c.t CONSOLIDATED EDISON CO.

INDIAN POINT UNIT NO. 2 REACTOR VESS2EL RADIATION SURVEILLANCE PROGRAM By S. E. Yanichko May 1969 IPP 106 Approved:

E. Landerman

\

Westinghouse Electric Corporation Nuclear Energy Systems Division Box 355 Pittsburgh, Pa. 15230

SECTION 4 POST-IRRADIATION TESTING Specimen capsules will be removed from the reactor only during normal refueling periods. The recommended schedule for removalof capsules is as follows:

Capsule Capsule Typ~e Identification Exposure Time I T (Replacement of ist Region)

II S (Replacement of 2nd Region)

I Z (Replacement of 4th Region)

II V 10 years I U I W Extra capsules for complementary I X testing or additional exposure II Y Each specimen capsule upon removal after radiation exposure will be trans-ferred to a post-irradiation test facility for disassembly of the capsule and testing of all specimens.

4.1 CHARPY V-NOTCH IMPACT TESTS The testing of the eight Charpy impact specimens from each of the IPP vessel plates, the weld and HAZ metal, and the correlation monitor material in the capsules can be -done singulary, making possible the performance of Charpy impact tests at five different temperatures, with three extra specimens to provide an optimum curve for each plate, The initial, Charpy specimen from the first capsule removed should be tested at room temperature. The impact energy value for this test temperature should be compared with pre-irradiation test data. The testing temperatures for the remaining specimen should then be appropriately raised or lowered. The test temperatures of 9

specimens from capsules exposed to longer irradiation periods should be determined by the test results for the previous capsule.

4.2 TENSILE TESTS The two tensile specimens per plate or weld from each of the capsules should be tested at room temperature and the approximate operating temperature of the reactor (550°F).

4.3 WEDGE OPENING LOADING TESTS The WOL specimens from each individual capsule should be tested at a temper-ature based on the transition temperature shift obtained from the associated Charpy impact specimens. A mean temperature of -200 oF plus the transition temperature shift should be the initial test temperature.

4.4 POST-IRRADIATION TEST EQUIPMENT

1. Milling machine or special cut-off wheel for opening capsules and dosimeter blocks.

2. Hot-cell tensile testing machine with:

a. pin-type adapter for pulling tensile tests

b. clevis and extensometer for pulling WOL specimens.

3. Hot-cell Charpy impact testing machine.

4. Nal scintillation detector and pulse height analyzer for gamma counting of the specific activities of the dosimeters.

10

TABLE 7 PRE-IRRADIATION TENSILE PROPERTIES FOR THE INDIAN POINT UNIT NO. 2 PRESSURE VESSEL PLATE MATERIAL AND WELD METAL Test 0.2% Yield Tensile Total Reduction' Plate Temp., Strength, Strength, Elongation In Area, No. oF psi psi B2002-1 Room 68,500 89,000 25.1 67.8 B2002-1 Room 65,850 87,800 25.3 67.4 B2002-1 200 61,550 79,900 24,1 68.6 B2002-1 200 .67,950 89,400 23.8 67.6 B2002-1 400 57,900 79,900 23.1 64.7 B2002-1 400 59,800 82,200 22.2 67.8 B2002-1 600 56,750 80,550 21.9 64.3 B2002-1 600 57.,750 85,700 22.9 64.2 B2002-2 Room 62,350 83,800 27.1 70.0 B2002-2 Room 66,750 90,500 28.2 69.6 B2002-2 200 63,650 84,450 24.8 70.5 B2002-2 200 63,200 83,800 25.5 67.3 B2002-2 400 53,800 77,900 23.1 68.5 B2002-2 400 52,650 73,150 22.4 67.6 B2002-2 600 53,500 78,800 22.7 64.4 B2002-2 600 54,700 81,450 24.7 64.4 B200.2-3 Room 65,650 87,300 27.6 67.3 B2002-3 Room 65,000 87,350 24.8 66.7 B2002-3 200 67,800 88,900 23.4 68.6 B2002-3 200 67,700 89,150 22.1 64.9 B2.002-3. 400 57,950 79,550 22, 3 68.7 B2002-3 400 55,350 77,100 23.2 64.9 B2002-3 600 57,750 83,850 24.9 68.2 B2002-3 600 58,350 86,500 24.9 64.7 Weld Room 64,500 80,700 28.5 73.9 Weld Room 65,000 81,000 26.9 71.5 Weld 200 63,450 76,100 28.4 72.9 Weld 200 61,050 75,200 25.2 73,0 Weld 400 57,550 75,000 22.9 68.1 Weld 400 58,300 75,800 22,6 69.6 Weld 600 56,650 79,800 24.4 62.0 Weld 600 56,650 79,200 24.0 66.9 21

1297-8 140 120 1-100

-J 80 z

L.U 60 40 00 20 0

0 t-1 I

-200 -100 0 100 200 300 TEMPERATURE (OF)

Figure 10.. Pre-irradiation Charpy V-Notch Impact Energy for the Indian Point Unit #2 Reactor Pressure Vessel Weld Metal 37

SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510, 6220 Culebra Road San Antonio, Texas 78284 REACTOR PROGRAM VESSEL MATERIAL FOR INDIAN POINT SURVEILLANCE UNIT NO, 2-ANALYSIS OF CAPSULE Y by E. B. Norris FINAL REPORT SwRI Project No. 02-5212 Prepared for Consolidated Edison Company of New York, Inc.

4 Irving Place New York, New York 10003 November 1980 U. S. Lindholm, Director Department of Materials Sciences

TABLE VTI CHARPY V-NOTCH LMPACT DATA IXDIAV P'OINT UNIT NO. 2 PRESLSRE VESSEL 'WELD METAL Lateral Spec. Temp. Energy Shear Expansion Condition No. (ft-lbs) *ý. Mils Baseline (a) -150 12.5 10ý 10

- 150 10.5 15 11

-100 35.0 25 29

-100 9.0 20 9

-100 18.0 C30 19

-80 13.0 20 12

-80 32.5 20 27

-80 26.0 20 23

-40 34.0 30 30

-40 35.5 35 31

-40 48.0 35 40 10 78.5 60 64 10 74.0 60 60 10 81.0 70 68 60 102.5 80 78 60 10..-0 85 82 60 100.0 85 80 110 1.12.5 99 88 110 108.5 90 87

110 108.3 98 88 160 115.5 100 90 160 113.0 100 92 160 120.0 100 93 210 121.0 100 92 210 1.23.5 100 91 210 117.5 100 92 Capsule Y W-17 747.5 nil 14 W-19 110 23.0 5 19 7-1-20 160 "O.0 25 34 W-21 190 47.3 50 43 W;-23 210 55 .-j

60 5.1

4-24 260 N"5Oo 51

" 18 300 61.0 00 45

J-22 350 67.0 100 52 (a) Not reported.

(b) Specimen anmber stamped on impac: side.

TABLE VIII CHARPY V-NOTCH DNPACT DATA CORRELATION MONITOR MATERIAL (SUPPLIED BY U. S. STEEL)

Lateral Spec. Temp. Laergy Shear Expanz ion Condit ion No. -L80 (ft-lbs) (m~ils)

(a)' -80 6 Baseline 4 2

-80 4 2 6

-60 8 3 6

-60 6, 3 6

-40 12 10 14

-40 10. 5 10

-20 6 5 7

-20 14 135 14

-20 13 15 14 0 22 30 22 0 18 25 18, 20 29 35 28 2O 23 35 23 36 45 33 40 26 45 26 60 36 50 40 60 33 45 35 80 67 100 .60 8o 50 70 48 100 68 98 60 100 62 85 58 Capsule Y R-60 40 5.0 nil 4 R-.5 7 74 26.0 5 2:

R-62 90 30.5 10 26 R-58 110 23.0 15 26 R-59 135 36.0 210 32 R-6 3 160 51.5 43 ti R-64 210 260 60.0 68.5 90 100 33 58 R-6 1 (a) Noc reported.

.'3

120

(

, 80 40 0

200 -100 0 100 200 300 *00 Temperature, deg F 120

so 0

4.10 -10 20cO 200 -,:0

~n~eratr~, e -.

60 S40 ep u, Code:

>_______________ zo//,,./0 f.

'-n A'rradiat~ed CEL .1>1

'. /* / ',.72 x 1013

/00 ,.:,, '(Z >' 1 .M-eV) 60

-20O0 - 100 0 iO0 200 300 4O0 Temperature, deg -

60

-7*

x 7 /

C,:de:

zoO 60 /"*~7

".nirradiaced Id/

CE ',"MeV C'

-20O -1^10 *00 "0 1 300 0 7.(eZz 'T * . e -7 F-JL.-KE-.;: C-NFT" .*.*.- -: .," ".Z .. T ...o --. --... . , ...-

.T.. o ....

~~C*~'; 4K F I M CTORV S MATERIAL SURVCEANCE ..:7" g 'PROGRAM FOR INDIAN POINT U*iTr NO. 2

,,. . ~t.,

{I A

MA ",.t4 FL:il. . , .,"- ..

I, .

i 4." .. ......... ' . . ...... . .,., . . ~J 3/4~A7" C.

Prjc for NPrepared

(.° i/.Consodated Edison Company of New York, In

'".4ff * -. :. 4lrning Place.,. :

4 i . 4ANew.York, NowYork 10003 4

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~q?'*.3.i 4 VSO5THVWYE ST RESEA-RCH I,N 1 TfS T yx~flr,,

fj7ýX REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FOR INDIAN POINT UNIT NO. 2

~1 ANALYSIS OF CAPSULE V FINAL REPORT SwRI Project No. 17-2108 Prepared for Consolidated Edison Company of New York, Inc.

4 Irving Place New York, New York 10003 October 1988 Written by Approved by F. A. Iddings B. T. Cross D. G. Cadena Director Mark Williams (Consultant) Department of NDE Science and Research Southwest Research Institute

I. A OF MOESULTS AND CONCLUSIONS

{The analysis of the fourth material surveillance capsule removed from the Indian Point Unit No. 2 reactor pressure vessel led to the following conclusions:

(1) Based on a calculated neutron spectral distribution, Capsule V received a fast fluence of 5.3 x 101 8 n/cm2 (E > 1 MeV) at its radial center line.

(2) The surveillance specimens of the core beltline plate materials experienced shifts in RTNDT (50 ft-lb. values) over the range of .79°F (Plate B2002-2) to 239°F (Weld) as a result of fast neutron exposure up to the 1987 refueling outage.

(3) The core beltline weld exhibited the largest shift in RTNDT and is projected to control the heatup and cooldown limitations throughout the design lifetime of the pressure vessel.

3.33 x 1018*

(4) From the previous capsule, Z, the estimated maximum neutron fluence of neutrons/cm2 (E > 1 MeV) was received by the vessel wall in 5.17 effective full power years (EFPY) through Cycle 5, which is equal to a fluence rate of 6.44 x 10170 per EFPY.

At the end of Cycle 8 (8.6 EFPY) the neutron fluence was 4.45 x 1018 n/cm 2 giving 3.26 x 1017 n/cm 2 per EFFY for Cycles 6 through 8. This calculated value for the decrease in fluence per EFFY agrees well with the experimental value for the decrease in fluence rate; i.e., 50.6% vs. 48.9%. The use of a low leakage core loading pattern beginning with Cycle 6 did significantly reduce the fluence rate on the pressure vessel wall.

R rJ flevised from Capsule Z report using the latest plant sp~teii lead facto'rs.*

I-I

TABLE IV-5 CILARPY IhPACT DATA WITH PHOTOS OF FRACTURE FACES Da:e 2une 2, lS MA*E*IAL - (WELD)

SPECIMEN TEMP ENERGY LATERAL FRACTURE PHOTOGRAPH NO. OF Fr- LBS EXPANSION APPEARANCE I x W- 9 74 0 F 24.0 .019 0 W- 10 +130 26.5 .023 20

,v-1 +180 40.5 .035 40 4-2 +220 53.0 .048 65 W-13 +260 62.5 .05- 95

, T W-14 +300 76.0 .06. 95 W-16 +325 72.5 .065 95 W-15 +350 76.0 .067 100

_ __ _ _ __ __ I _ _ _ __ _ _

_______ ".. I i

I ______ ______

Iv-16

WELD METAL 160 '

-F---

/' 0 BASELINE

[3 A CAPSULE Y

+ CAPSULE V 120 In

'4- BO A

A A

zLiI 50 f t. lb.

40 00 30 ft.lb.

0 0 0

-200 -100 0 100 200 300 400 TEMPERATURE (deg F)

F

-~---- -

I .-- r 100 0 BASELINE CAPSULE Y

+ CAPSULE V 75 A A 50 A

EL& c

-J Lu 25 J Li 35 mi I 0

0 0

-200 -100 0 .100 200 300 400 I.. -,

TEMPERATURE (deg F)

F Figure IV-3. Radiation Response of Indian Point Unit No. 2 Weld Metal ci F~

IV-20

/ti Table IV-9 SUMLMARY OF RTNDT SHIFTS AND UPPER SHELF ENERGY REDUCTION (Cv)

FOR MATERIALS IN CAPSULE V

'~1 A. Sunmaryotnuezm~da*ARTNDTVamlforTTestSpm in Capue V Fluence Type of Neto 50 Ft-Lbs Measured ARTNDT (OF) 30 Ft-Lbs 35 milso Materia Weld 5.69E18 239 204 230 77 Ft-Lbs Plate B2002-2 4~.57E18 85 80 97 HAZ' 5.59E18 190 162 184 Correlation Monitor 4.57E18 104 108.

B. Decrease in Upper ShelfEnergy (Cv)

Initial Shelf Capsule V*°* Cv Material Ft-lb Ft-lb Ft-lb % Decrease B2002-2 117 111 6 5 Weld Metal 118 75 43 36 HAZ 100 98 2 (nil) 2 Correlation Monitor 118 70 48 41 035 mil + 20°F included in table.

"The upper shelf energy for this capsule was below 77 ft lbs.

` Average of 3 Charpy measurements at f 100% ductile failure.

Fl Ii IV-23

TABLE IV-11(Cont'd) f' SUTMMARY OF CHEMISTRY VALUES FOR INDIAN POINT UNIT NO. 2 MATERIALS Makru, ,Source of Data W Ni W%

Plat B202-3 WCAP 7328 (.14)* (.57)0 Capsule-Z: Cv Specimen 3-33 .30 .64 Capsule-Z: Cv Specimen 3-38 .27 .59 Capsule-Z: Tensile Specimen 3-5 .23 .58 Capsule-Y: Cv Specimen 3-41 .21 Capsule-Y: Cv Specimen 3-45 .22 Capsule-Y: Tensile Specimen 3-6 (.11)

Capsule-Y: Tensile Specimen 3-7 (.10)A --

Capsule-T: CT Specimen 3-2 .27 --

Capsule-T: Cv Specimen 3-3 .23 --

Capsule-T: Tensile Specimen 3-1 (.09)I-Average .25 .60 HAZ Capsule-V: Cy Specimen H-16 .08 1.2 Capsule-V: CvSpecimen H-12 .06 1.2 Capsule-Y: Cv Specimen H.21 .15 -

Capsule-Y: CvSpecimen H-23 .20 -.

Average .12 1.2 weld Capsule-V: CXv Specimen W-13 .23 1.02 Capsule-V: Cv Specimen W-12 .20 1.06 Capsule-V: Tensile Specimen W-3 .20 (.69)*

Capsule-V: Cv Tebsile Specimen W-4 (.12)0 1.00 Capsule-Y: Cv.Specimen W.17 .19 --

Capsule-Y: Cv Specimen W-19 .22 Capsule-Y: Tensile Specimen W-5 .18 Capsule-Y: Tensile Specimen W-6 .20 -

Average .20 1.03 Correlation Monitor Capsule-V: Cv Specimen R-56 ..20 .18 Capsule-V: Cv Specimen R-52 .18 .27 Capsule-Z: Cv Specimen R-33 .35 .28 Capsule-Z: Cv Specimen R-36 .31 .27 Capsule-Z: Cv Specimen R-40 .21 .21

- Capsule-Y: Cv Specimen R-60 .17 -

Capsule-Y: Cv Specimen R-62 .19 Capsule-T: Cv Specimen R-2 .25 Average .23 .24

Values in parentheses discarded because of excessive deviation or were WCAP values.

Surveillance specimen WCAP values not used since chemical analyses were adailable.

IV-27

APPENDIX E INDIAN POINT 3 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 Report No. 0901132.401, Rev. 0 E-1 StructuralIntegrityAssociates, Inc.

Westinghouse Class 3 U

CONSOLIDATED EDISON CO. OF NEW YORK INDIAN POINT UNIT NO. 3 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM S. E. Yanichko J. A. Davidson January 1975 APPROVED:

J.'%N hiios ~

a Work Performed Under INT 106 WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems Division P. 0. Box 355 Pittsburgh, Pennsylvania 15230

SECTION 3 PREIRRADIATION TESTING 3-1. CHARPY V-NOTCH TESTS Charpy V-Notch impact tests were performed on the vessel plates at various temperatures from -100 to 210'F to obtain full Charpy V-Notch transition curves (refer to tables3-1 and 3-2, and to figures 3-1 thru 3-5). Charpy V-Notch impact tests were performed on weld metal and HAZ metal at various temperatures ranging from -1,50 to 160'F. The results are reported *,-:table 3-3 and in figures 3-6 and 3-7, respectively. The Charpy V-Notch impact data for the correlation monitor material are shown in table 3-4 and figure 3-8.

3-2. ENSILE TESTS Tensile tc. s were performed on the shell plates and on weld material at room temperature, 300 and r,(OO0 F, respectively. The results are shown in table 3-5 and in figures 3-9 through 3-14.

3-3. DROPWEIGHT NDTT TESTS Dropweight NDTT tests (ASTM E208) were performed on each plate by the fabricator. The NDTT obtL.,ied on each plate follows:

Plate Temperature B2802-1 -50OF B2802-2 -500 F B2802-3 -40OF B2803-3 -10O F 3-1

(Wk- AWrt-7 TABLE 3-3 PREIRRADIATION CHARPY V-NOTCH IMPACT DATA FOR THE INDIAN POINT UNIT NO. 3 REACTOR PRESSURE VESSEL WELD METAL AND WELD HEAT AFFECTED ZONE MATERIAL Weld Metal Weld Heat-Affected Zone Test Lateral Test Lateral Temp Energy Shear Expansion Temp. Energy Shear Expansion oF FT-LBS % Mils 0F FT-LBS % Mils

-1 50 5.0 5 2 -150 4,0 0 2

-150 2,0 5 2 -150 6.0 5 1

-150 4,5 9 4 -150 14.0 , 9 11

-100 29.0 20 22 -125 16.0 9 14

-100 18.0 18 16 -125 7.0 5 8

-100 25.5 23 23 -125 34.0 14 28

-50 35.0 40 34 -100 48.5 20 35

-50 33.0 47 30 -100 59.0 25 40

-50 32.5 40 30 -100 30.0 18 20

-35 78.0 64 66 -50 30.0 29 22

-35 69.5 67 56 -50 62.5 40 44

-35 54.5 40 47 -50 60.0 36 44

-20 87.0 77 69 10 111.0 85 79

-20 82.0 77 63 10 51.5 47 48

-20 89.0 81 74 10 83.0 62 62 10 100.0 81 78 60 142.0 100 90 10 105.0 82 '81 60 127.0 100 82 10 113.5 100 85 60 121.5 100 91 60 115.0 100 89 160 111.0 100 81 60 119.0 100 84 160 125.0 100 85 60 121.5 100 90 160 143.0 100 88 160 124.0 100 88 160 125.0 100 89 160 112.0 100 90 3-9

8328-10 160 140 120 100 r9 80 CD 60 00 -

20--

0i-

-200 -100 0 100 200 300 TEMPERATURE (OF)

Figuie 3-6. Preirradiation Charpy V-Notch Impact Energy for the Indian Poit No. 3 Reactor Pressure Vessel Weld Metal 3-10

TABLE A-1 CHEMICAL COMPOSITION OF THE INDIAN POINT UNIT NO. 3 REACTOR VESSEL MATERIALS Chemical Composition (wt-%)

Lower Shell Intermediate Shell Course Plate Course Plate As-Deposited Element B2802-1 B2802-2 B2802-3 B2803-3 Weld Metal C 0.22 0.19 0.20 0.22 0.08 Mn 1.41 1.33 1.32 1.30 1.18 P 0.010 0.015 0.011 0.012 0.019 S 0.023 0.019 0.025 0;024 0.016 Si 0.28 0.21 0.26 0.28 0.17 Ni 0.50 0.53 0.49 0.52 1.02 Cr 0.08 0.09 0.08 0.08 0.04 Mo 0.46 0.48 0.50 0.45 0.53 Cu 0.18 0.20 0.19 0.24 0.15 Al 0.036 .0.027 0.042 0.03 <0.01 V <0.01 <0.01 <0.01 <0.01 <0.01 Sn 0.014 0.017 0.014 <0.01. 0.007 Cb <0.01 <0.01 <0.01 <0.01 <0.01 Zr <0.01 <0.01 <0.01 <0.01 <0.01 Ti <0.01 <0.01 <0.01 <0.01 <0.01 All other elements (except Fe) were <0.01%.

A-2

Westinghouse Non-Proprietary Class 3 WCAP-16251-NP July 2004 Revision 0 Analysis of Capsule X from Entergy's Indian Point Unit 3 Reactor Vessel Radiation Surveillance Program

Westinghouse

WESTINGflOUSE NON-PROPRIETARY CLASS 3 WCAP- 16251-NP, Revision 0 Analysis of Capsule X from Entergy's Indian Point Unit 3 Reactor Vessel Radiation Surveillance Program T.J. Laubham J. Conermann S.L. Anderson July 2004 Approved:a Ghergurd(ich, Manager Reactor Component Design & Analysis Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355

ix EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance Capsule X from Indian Point Unit 3. Capsule X was removed at 15.5 EFPY and post irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the recently released neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI data-base. Capsule X received a fluence of 0.874 x 10 9 n/cm2 after irradiation to 15.5 EFPY. The peak clad/base metal interface vessel fluence after 15.5 EFPY of plant operation was 5.86 x 1018 n/cm 2.

This evaluation lead to the following conclusions: 1) The measured 30 ft-lb shift in transition temperature values of the lower shell plate B2803-3 contained in capsule X (longitudinal & transverse) are greater than the Regulator), Guide 1.99, Revision 2, predictions. However, the shift values are less than the two sigma allowance by Regulatory Guide 1.99, Revision 2. 2) The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule X is less than the Regulatory Guide 1.99, Revision 2, prediction. 3) The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate B2802-2 contained in capsule X (longitudinal) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2. 4) The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Indian Point Unit 3 surveillance program are in good agreement with the Regulatory Guide 1.99, Revision 2 predictions. 5) All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (27.1 EFPY) as required by I OCFR50, Appendix G [2]. 6) The Indian Point Unit 3 surveillance data from the lower shell plate B2803-3 was found to be credible. This evaluation can be found in Appendix D.

Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.

1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule X, the fourth capsule removed and tested from the Indian Point Unit 3 reactor pressure vessel, led to the following conclusions:

The Charpy V-notch data presented in WCAP-8475r3 j, WCAP-9491 [4, WCAP-l103O00[5, and WCAP- 1 818516] were based on hand-fit Charpy curves using engineering judgient. However, the results presented in this report are based on a.re-plot of all applicable capsule data using CVGRAPH, Version 5.0.2, which is a' hyperbolic tangent curve-fitting program. Appendix C presents the CVGRAPH, Version 5.02, Charpy V-notch plots and the program input data.

Capsule X received an average fast neutron fluence (E> 1.0 MeV). of 0.874 x 10 9 n/cm 2 after 15i5 effective full power years (EFPY) of plant operation.

Irradiation of the reactor vessel lower shell plate B2803-3 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),

resulted in an irradiated 30 ft-lb transition temperature of 191.6°F and an irradiated 50 ft-lb transition temperature of 223.8°F. This results in a 30 ft-lb transition temperature increase of 159.6°F and a 50 ft-lb transition temperature increase of 161.7°F for the longitudinal oriented specimens. See Table 5-9.

Irradiation of-the reactor vessel lower shell plate B2803-3 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 216.5°F and an irradiated 50 ft-lb transition temperature of 327.4°F. This results in a 30 ft-lb transition temperature increase of 158.2°F and a 50 ft-lb transition temperature increase of 217.9°F for the longitudinal oriented specimens. See Table 5-9.

Irradiation of the weld metal (heat number W5214) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 128.5°F and an irradiated 50 ft-lb transition temperature of 196.8'F. This results in a 30 ft-lb transition temperature increase of 193.2°F and a 50 ft-lb transition temperature increase of 242.8°F. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B2802-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 98.1 'F and an irradiated 50 ft-lb transition temperature of 145.0°F. This results in a 30 ft-lb transition temperature increase of 152.6°F and a 50 ft-lb transition temperature increase of 166.5°F for the longitudinal oriented specimens. See Table 5-9.

The average upper shelf energy of the lower shell plate B2803-3 (longitudinal orientation) resulted in an average energy decrease of 24 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 81 ft-lb for the longitudinal oriented specimens. See Table 5-9.

Summary of Results

1-2 The average upper shelf energy of the lower shell plate B2803-3 (transverse orientation) resulted in an average energy decrease of 16 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 52 ft-lb for the longitudinal oriented specimens. See Table 5-9.

The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 46 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 74 ft-lb for the weld metal specimens. See Table 5-9.

The average upper shelf energy of the intermediate shell plate B2802-2 (longitudinal orientation) resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 105 ft-lb for the longitudinal oriented specimens. See Table 5-9.

A comparison, as presented in Table 5-10, of the Indian Point Unit 3 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 21'1 predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values of the lower shell plate B2803-3 contained in capsule X (longitudinal & transverse) are greater than the Regulatory Guide 1.99, Revision 2, predictions. However, each shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.

- The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule X is less than the Regulatory Guide 1.99, Revision 2, prediction.

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell plate B2802-2 contained in capsule X (longitudinal) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.

- The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Indian Point Unit 3 surveillance program are in good agreement with the Regulatory Guide 1.99, Revision 2 predictions.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (27.1 EFPY) as required by IOCFR50, Appendix G [2]

Summary of Results

2 INTRODUCTION This report presents the results of the examination of Capsule X, the fourth capsule removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on the Indian Point Unit 3 reactor pressure vessel materials under actual operating conditions.

The surveillance program for tile Indian Point Unit 3 reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-8475, "Consolidated Edison Co. of New York Indian Point Unit No. 3 Reactor Vessel Radiation Surveillance Program"J3U.' The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM El185-62, "Recornmended Practice for Surveillance Tests on Structural Materials for Nuclear Reactors." Capsule X was removed from the reactor after 15.5 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy \-notch impact and tensile, surveillance specimens was performed.

This report summarizes the testing of and the post-irradiation data obtained from surveillance capsule X removed from the Indian Point Unit 3 reactor vessel and discusses the analysis of the data.

Introduction

4-3 Table 4-1 Chemical Composition (wt%) of the Indian Point Unit 3 Reactor Vessel Surveillance Materials (Unirradiated)(a, Intermediate Shell Plate Lower Shell Plate Element B2802-1 B2802-2 B2802-3 B2803-3 Weld Metal (b)

C 0.22 0.19 0.20 0.22 0.08 Mn 1.41 1.33 1.32 1.30 1.18 P 0.010 0.015 0.011 0.012 0.019 S 0.023 0.019 0.025 0.024 0.016 Si 0.28 0.21 0.26 0.28 0.17 Ni 0.50 0.53 0.49 0.52 1.02 (1'.21){c' Cr 0.08 0.09 0.08 0.08 0.04 Mo 0.46 0.48 0.50 0.45 0.53 Cu 0.18 0.20 0.19 0.24 0.15 (0.166)1c)

Al 0.036 0.027 0.042 0.03 <0.01 V <0.01 <0.01 <0.01 <0.01 <0.01 Sn 0.014 0.017 0.014 <0.01 0.007 Cb <0.01 <0.01 <0.01 <0.01 <0.01 Zr <0.01 <0.01 <0.01 <0.01 <0.01 Ti <0.01 <0.01 <0.01 <0.01 <0.01 Notes:

(a) Data obtained from WCAP-1 1815 and duplicated herein for completeness.

(b) Weld wire Heat Number W5214, Flux Type Linde 1092, and Flux Lot Number 3692. Surveillance weldment has the same heat and flux as the nozzle shell longitudinal weld seams 1-042A, B & C.

(c) Results of chemical analysis performed on irradiated Charpy V-notch Specimen W-15 from Capsule Y.

Description of Program

5-4 The average upper shelf energy of the intermediate shell plate B2802-2 (longitudinal orientation) resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 105 ft-lb for the longitudinal oriented specimens. See Table 5-9.

A comparison, as presented in Table 5-10, of the Indian Point Unit 3 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2ý" predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values of the lower shell plate B2803-3 contained in capsule X (longitudinal & transverse) are greater than the Regulatory Guide 1.99, Revision 2, predictions. However, each shift value is less than the two sigmia allowance by Regulatory Guide 1.99, Revision 2.

- The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule

'X is less than the Regulatory Guide 1.99, Revision 2, predictions

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell plate B2802-2 contained in capsule X (longitudinal) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.

The-measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Indian Point Unit 3 surveillance program are in good agreement with the Regulatory Guide 1.99, Revision 2 predictions.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the extended life of the vessel (27.1 EFPY) as required by IOCFR50, Appendix G [2]

The fracture appearance of each irradiated Charpy specimen from the various surveillance Capsule X materials is shown in Figures 5-13 through 5-16 and shows an increasingly ductile or tougher appearance with increasing test temperature.

The load-time records for individual instrumented Charpy specimen tests are shown in Appendix B.

The Charpy V-notch data presented in WCAP-8475[3 ], WCAP-9491 14), WCAP-l10 3 0 0 )52,and WCAP-11 81 5[6l were based on hand-fit Charpy curves using engineering judgment. However, the results presented in this report are based on a re-plot of all applicable capsule data using CVGRAPH, Version 5.0.2, which is a hyperbolic tangent curve-fitting program. This, report also shows the composite plots that show the results from the previous capsule. Appendix C presents the CVGRAPH, Version 5.02, Charpy V-notch plots and the program input data.

Testing of Specimens firom Capsule X

5-8 Table 5-3 Charpy V-notch Data for the Indian Point Unit 3 Surveillance Weld Metal Irradiated to a Fluence of 0.874 x 1019 ncm2 (E> 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number FC ft-lbs Joules mils mm %

W42 75 24 9 12 5 0.13 20 W41 125 52 49 66 36 0.91 50 W43 125 52 24 33 19 0.48 40 W48 150 66 35 47 26 0.66 45 W47 200 93 37 50 30 0.76 70 W44 250 121 67 91 52 1.32 95 W45 300 149 72 98 56 1.42 98 W46 350 177 75 102 57 1.45 100 Testing of Specimens fi'om Capsule X

5-12 Table 5-7 Instrumented Charpy Impact Test Results for the Indian Point Unit 3 Surveillance Weld Metal Irradiated to a Fluence of 0.874 x' 1019 nlcm 2 (E>I.0 MeV)

Charpy Normalized Energies Yield Time to Time to Fast 2

Test Energy E, (ft-lb/in ) Load Yield Max. Max. Fract. Arrest Yield Flow Sample Temp. Charpy Max. Prop. PV tcrv Load t41 Load Py Load Stress Stress No. ("F) (ft-lb) ED/A E,,/A Ep/A (lb) (msec) Pý.1 (Ib) (msec) (Ib) P, (ib) ov (ksi) (ksi)

W42 75 9 73 36 36 3426 0.14 3696 0.16 3687 0 114 119 W41 125 49 395 226 169 3411 0.15 4363 0.52 4288 617 114 129 W43 125 24 193 68 126 334] 0.14 4109 0.22 4058 1.313 111 124 W48 150 35 282 .184 98 3416 0.14 4449 0.42 4417 1141 114 131 W47 200 37 298 150 148 3371 0.14 4260 0.37 4222 1713 112 127 W44 250 67 540 227 . 313 3486 0.14 4432 .0.50 4251 2819 116 132 W45 300 72 580 218 362 3329 0.14 4303 0.50 3029 2501 1I1 127 W46 350 75 604 221 383 3285 0.14 4309 0.51 n/a n/a 109 126 Testing of Specimens from Capsule X

5-15 Table 5-10 Comparison of the Indian Point Unit 3 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Temperature Shift Decrease Material Capsule Fluence(d) Predicted Measured Predicted Measured 9 2 (OF) ()) ( (%))

(x 10' n/cm , (OF) ( b E > 1.0 MeV)

Lower Shell Plate T 0.263 101.9 139.4 24 12 B2803-3 Z 1.04 161.6 167.8 33.5 22 (Longitudinal) X 0.874 153.9 159.6 32 23 Lower Shell Plate T 0.263 101.9 105.9 24 16 B2803-3 Y 0.692 143.5 148.9 30 25 Z 1.04 161.6 157.9 33.5 18 (Transverse) X 0.874 153.9 158.2 32 24 Surveillance T 0.263 131.3 151.6 22 30 Program Y 0.692 185.0 172.0 27 43 Weld Metal Z 1.04 208.3 229.2 31 37 X 0.874 198.4 193.2 29 38 Intermediate Shell Plate B2802-2 X 0.874 146.2 152.6 30 16 (Longitudinal)

Notes:

(a) Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material.

(b) Calculated using measiured Charpy data plotted using CVGRAPH, Version 5.0.2 (See Appendix C)

(c) Values are based on the definition of upper shelf energy given in ASTM El 85-82.

(d) The fluence values presented here are the calculated values, not the best estimate values.

Testing of Specimens from Capsule X

" 5-23 N

SURVgILLANCE WELD MATERIAL CVGRAPH 5.0,2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:31 PM Data Sct(s) Plotted Curve Plant Capsule Material Ori. Heat #

Indian Point 3 UNIRR SAW NA W5214 2 Indian Point 3 T SAW NA W5214 3 Indian Point 3 Y SAW NA W5214 4 Indian Point 3 z SAW NA W5214 5 Indian Point 3 x SAW NA W5214 300y 250---

200

150 .

uJ z

>100 .

50

0

.- 300 -2010 -100 0 100 200 300 400 500 600 Temperature In Deg F o Set I r Set2 0 Set3 1, Set4 Set5 Results Curve. Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 2,2 120. 0 .0 -64, 7 .0 -46.0 .0 2 2.2 84. 0 -36.0 86. 9 151.6 130. 6 176. 6 3 2.2 69.0 -51.0 107. 3 172.0 164.2 210.2 4 2.2 76.0 -44, 0 164.5 229.2 218.7 264. 7

.5 2.2 74.0 -46.0 128. 5 193.2 196. 8 242. 8 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Indian Point Unit 3 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

15.-24 SURVEILLANCE WELD MATERIAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 04:11 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

I Indian Point 3 UNIRR SAW NA W5214 2 Indian Point 3 T SAW NA W5214 3 Indian Point 3 Y SAW NA W5214 4 Indian Point 3 z SAW NA W5214 5 Indian Point 3 X SAW NA W5214 200 150 E

0 50 0 -

-300 300 600 Temperature in Deg F 0 Set I 0 Set3 6 Set4 Results Curve Fluence LSE USE d-USE T @35 d-T @35

.0 90. 8 .0 -59.3 .0 2 .0 80. 3 -10.5 113.3 172.6 3 .0 65.6 -25. 2 145.0 204.3 4 .0 73.5 -17.3 187.8 247. 1 5 .0 62.1 -28.7 184.6 243.9 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature rfor Indian -Point nijnt Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-25 SURVEILLANCE WELD MATERIAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 03:57 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. H-eat #

1 Indian Point 3 UNIRR SAW NA W5214 2 Indian Point 3 T SAW NA W5214 3 Indian Point 3 Y SAW NA W5214 4 Indian Point 3 z SAW NA W5214 5 Indian Point 3 x SAW NA W5214 125 100 3..

0 75 0

'I, 0

20 50 . .

0~

25 0 -"--= -

-300 -2010 -100 0 100 200 300 400 500 600 Temperature in Deg F o Set I 0 Set2 0 Set3 A Set4 Set 5 Results Curve Fiuence LSE USE d-USE ,r @so d-T @50

.0 100.0 .0 -47.8 .0 2 .0 100.0 .0 124.0 171.8 3 .0 100.0 .0 132,6 180.4 4 .0 100.0 .0 147.5 195.3 5 .0 100.0 .0 144.5 192.3 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Indian Point Unit 3 Reactor Vessel Weld Metal of S ecimenc frorn Ca SUIC X

C-0 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Appendix C

UNIRRADIATED (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:26 PM Page 1 Coefficients of Curve 1 A = 61.1 B = 58.9 C = 47.03 TO = -37.11 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))j Upper Shelf Energy= 120.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-64.7 Deg F Temp@50 ft-lbs=-46.0 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: UN[RR Fluence: n/cmA2 300 250 200 0

1.

150 w

z

> 100 50 0 -=

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-150.00 5. 00 3, 16 19. 8.4

-150. 00 2. 00 3. 16 -1. 16

-150. 00 4. 50 3.16 1. 34

-100. 00 29. 00 9. 80 19. 20

-100. 00 18. 00 9. 80 8. 20

-100. 00 25, 50 9. 80 15. 70

-50. 00 35. 00 45. 35 -10. 35

-50. 00 33, 00 45. 35 -12. 35

- 50. 00 32, 50 45. 35 -12. 85 C-45

UNIRRADIATED (WELD)

Page 2 Plant: Indian Point 3 Material: SAW - Heat: W5214 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-35. 00 78 6o 63. 74 14. 26

- 35. 00 69. 50 63. 7'4 5. 76 3-5. 00 54. 50 63. 74 -9.24

-20. 00 87. 00 81. 63 5. 37

-20. 00 82. 00 81. 63 .37

-20. 00 89. 00 81. 63 7. 37

10. 00 100. 00 106. 00 -6. 00

10. 00 105. 00 106. 00 -1. 00

10. 00 113. 50 106. 00 7. 50

60. 00 115. 00 118. 14 -3.14

60. 00 119. 00 118. 14 86

60. 00 121. 50 118 14 3 36 160, 00 124. 00 1-19. 97 4. 03 160. 00 125. 00 119. 97 5. 03 160. 00 112. 00 119. 97 -7.97 Correlation Coefficient -. 981 C-46

CAPSULE T (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:26 PM Page 1 Coefficients of Curve 2 A = 43.1 B = 40.9 C = 87.09 TO = 115.75 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=84.0(Fixed) Lower 'Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=86.9 Deg F Temp@50 ft-lbs=130.6 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: T Fluence: n/cm^n2 300 1 1 r-~~

250

-200 0

0 U-S150 z

> 100-50 Lf.

JI 0 --. I - -

-300 -200 -100 0 100 200 30 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

.06 13. 00 7.56 5. 44

70. 00 17.50 23. 39 -5. 89 110. 00 48.00 40. 40 7. 60 150. 00 55. 50 58, 40 -2. 90 150. 00 53. 00 58. 40 -5. 40 165. 00 66. 00 64. 04 1. 96 210. 00 78. 00 75. 58 2. 42 300. 00 90. 50 82. 83 7. 67 Correlation Coefficient = .979 C-51

CAPSULE Y (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:26 PM

,4 Page 1 Coefficients of Curve 3 A = 35.6 B = 33.4 C = 90.16 TO = 122.54 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=69.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs--107.3 Deg F Tempp@50 ft-lbs=164.2 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: Y Fluence: n/cmA2 300 250 200 0

.LL 150 U-,

w z

> 100 U

so 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

25. 00 20. 00 9.08 10.92

72. 00 19. 50 18, 62 . 88 125. 00 31. 00 36.51 -5. 51 125. 00 29. 50 36.51 -7. 01 150. 00 49. 00 45. 47 3. 53 200. 00 67. 50 58. 84 8. 66 300. 00 69. 50 67. 72 1 .78 400. 00 68. 50 68. 86 - 36 Correlation Coefficient = .960 C-54

.CAPSULE Z (WELD)*

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:26 PM Page I Coefficients of Curve 4 A = 39.1 B = 36.9 C = 97.52 TO = 188.96 D = 0.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=76.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=164.5 Deg F Temp@50 ft-lbs=218.7 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: Z Fluence: n/cm^2 300

(

250 +

0 200 0.

LL 150 7-w z

100 4.-

50 A 0 ----- - i i .. I -~- --.

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 10 00 12.45 -2. 45 150. 00 21 00 25. 10 -4. 10 150. 00 44. 00 25. 10 18. 90 175. 00 26. 00 33. 85 -7. 85 200. 00 33. 00 43. 26 10. 26 225. 00 57. 00 52, 15 4. 85 300.00 75. 00 69. 14 5. 86 400. 00 77 .00 75. 04 1. 96 Correlation Coefficient = .929 C-57

CAPSULE X (WELD)

CVGRAPH 5,0.2 Hyperbolic Tangent Curve Printed on 04/02/2004 02:36 PM Page 1 Coefficients of Curve 5 A = 38.1 B = 35.9 C = 118.98 TO = 155.76 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))l Upper Shelf Energy=74.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 ft-lbs=128.5 Deg F Temp@50 ft-lbs= 196.8 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: X Fluence: n/cmA2 300 250

0) 200 0

LL 150 z

100 F, 50- S*

A~7~

QW

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

75. 00 9. 00 16. 89 -7. 89 125.00 49. 00 29. 02 19. 98 125. 00 24. 00 29. 02 -5 .02 150. 00 35. 00 36. 36 -1 36 200. 00 37. 00 50. 87 -13 87 250. 00 67. 00 61. 78 5. 22 300. 00 72. 00 68. 16 3. 84 350. 00 75. 00 71. 36 3. 64 Correlation Coefficient = .906 C-60

APPENDIX F H. B. ROBINSON 2 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM RESULTS FOR WELD NO. W5214 Report No. 0901132.401, Rev. 0 F-1 V StructuralIntegrityAssociates, Inc.

~)pri&tL.Cy L U

CAROLINA POWER AND LIGHT CO.

H. B..ROBINSON UNIT NO. 2 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM By-S. E. Yanichko January 1970 Work Performed Under CPL-106 Approved:

E. Landerman Westinghouse Electric Corporation Nuclear Energy Systems Box 355 Pittsburgh, Pennsylvania 15230 14

40 7cý 2-3 TABLE 4 PRE-IRRADIATION CHARPY V-NOTCH IMPACT DATA FOR THE CPL H. B. ROBINSON UNIT NO. 2 REACTOR PRESSURE VESSEL WELD METAL AND WELD HEAT AFFECTED ZONE METAL Weld MeLal lleat Affected Zone Test Ls teral Test Lateral Specimen Temp Energy Shear Expansion Specimen Te' ep

(°F) Energy Shear Expansion No. (ft-lb) (%) (mils) No. (°F) (ft-lb) () (nmils)

W25 -150 19.0 29 16 1128 -150 1.1.0 10 12 W26 -150 10.0 23 9 1129 -150 31.0 18 29 W27 -150 30.0 29 25 1130 -150 34.0 18 3o W34 -150 3.0 9 2 W35 -150 34.5 26 28 1125 -100 39.5 29 30 W36 -150 2.0 9 2 1126 -1.00 42.0 37 34 1127 -100 41.0 - 34 30 W28 -100 .38.0 30 34 W29 -100 29.0 23 19 1131 - 50 42.5 34 35 W30 -100 25.0 20 22 1[32 - 50 60.0 45 50 1133 - 50 37.5 32 30 W31' - 50 21.0 25 20

-W32 - 50 54.5 36 49 1134. - 20 75.0 42 61 W33 - 50 36.5 30 31 1035 - .20 86.0 61, 62 1136 - 20 45.0 34 37 W37 10 73.5 64 62 W38 10 68.0 61 58 H37 10 83.0 81 67 W39 10 65.5 59 57 1138 10 119.0 90 81.

H39 10 94.0 77 70 W40 60 97.0 90 80 W41 60 99.0 91 80 H40 60 116.0 100 88 W42 60 116.0 94 88 H41 60 111.5 100 87 H42 60 110.0 95 87 W43 110 97.0 95 74 W44 110 104.0 100 85 H43 110 117.0 100 93 W45 100 107.5 98 89 H44 110 140.0 100 83 H45 110 119.0 100 86 W46 210 112.0 100 90 W47 210 111.0 100 91 B46 210 130.0 100 89 W48 210 115.0 100 83 .47 .210 134.0 100 86 1148 210 123.0 100 84 18

1179-5 130 120 --

0 100 H-0

.80 LLI 60 z 0 LU 40 00 0 0

20 0 0

0

-200 -100 0 100 200 300 TEMPERATURE (OF)

Figure 10. Pre-Irradiatlon Charpy V-Notch Impact Energy for the CPL H. B. Robinson Unlit 2 Reactor Pressure Vessel Weld Metal 32 I.

f) 1z; -? I , 6 Q-'ý

. -. r . 1 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-15805 Analysis of Capsule X-from the Carolina Power & Light Company K.B. Robinson Unit 2 Reactor Vessel Radiation Surveillance Program T. J. Laubham E. P. Lippincott J. Conermann MARCH 2002 Prepared by the Westinghouse Electric Company for the Carolina Power & Light Company Approve d:

C. H. Boyd, Mainager Equipment & Materials Technology Westinghouse Electric Company LLC Nuclear Services Division P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355

Viii EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance capsule X from H.B.

Robinson Unit 2. Capsule X was removed at 20.39 EFPY and post irradiation mechanical tests of the Charpy V-notch and tensile specimens was performed, along with a fluence evaluation based methodology and nuclear data including recently released neutron transport and dosimeriy cross-section libraries derived from the ENDF/B-VI database. The calculated peak clad base/metal vessel fluence after 20.39 EFPY of plant operation was 2.76 x 1019 n/cm 2 and the surveillance Capsule X calculated fluence was 4.49 x 1019 n/cm2 , A brief summary of the Charpy V-notch testing results can be found in Section 1 and the updated capsule removal schedule can be found in Section 7. A supplement to this report is a credibility evaluation, which can be found in Appendix D, that shows the H.B. Robinson Unit 2 surveillance weld data, while including all surveillance data for weld heat W5214, is credible. Of the three surveillance plates, only intermediate shell plate W 10201-5 was found to be credible.

Analysis of H.B. Robinson Unit 2 Capsule X

1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance capsule X the fourth capsule to be removed from the H.B. Robinson Unit 2 reactor pressure vessel, led to the following conclusions: (General Note: Temperatures are reported to two significant digits only to match CVGraph output.)

The capsule received an average fast neutron calculated fluence (E > 1.0 MeV) of 4.49 x 10'9 n/cm 2 after 20.39 effective full power years (EFPY) of plant operation.

Irradiation of the reactor vessel intermediate shell plate W 10201-4 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction of the plate'(longitudinal orientation), to 4.49 x 1019 n/cm 2 (E> 1.0MeV) resulted in a 30 ft-lb transition temperature increase of 104.730 F and a 50 ft-lb transition temperature increase of 98.68'F. This results in an irradiated 30 ft-lb transition temperature of 86.55*F and an irradiated 50 ft-lb transition temperature of 116.041F for the longitudinally oriented specimens Irradiation of the weld metal Charpy specimens to 4.49 x 1019 n/cm2 (E> 1.0MeV) resulted in a 30 ft-lb transition temperature increase of 265.93IF and a 50 ft-lb transition temperature increase of 251.741F. This results in an irradiated 30 ft-lb transition temperature of 179.640 F and an irradiated 50 ft-lb transition temperature of 211.38 0F.

0 Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens to 4.49 x 1019 n/cm 2 (E >

1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 210.13 0 F and a 50 ft-lb transition temperature increase of 216.5 91F. This results in an irradiated 30 ft-lb transition temperature of 100.471F and an irradiated 50 ft-lb transition temperature of 150.541F.

Irradiation of the correlation monitor material Charpy specimens to 4.49 x 10" n/cm 2 (E ý>1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 125.2 1F which resulted in an irradiated 30 ft-lb transition temperature of 188.151F. The tested specimens did not reach the 50 ft-lb transition temperature.

The average upper shelf energy of the intermediate shell plate Wi10201-4 (longitudinal orientation) resulted in an average energy decrease of 1 ft-lb after irradiation to 4.49 x 1019 n/cm 2 (E> 1.0 MeV).

This results in an irradiated average upper shelf energy of 94 ft-lb for the longitudinally oriented specimens.

The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 33 ft-lb after irradiation to 4.49 x 1019 n/cm 2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 80 ft-lb for the weld metal specimens.

The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 24 ft-lb after irradiation to 4.49 x 10"9 n/cm2 (E > 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 105 ft-lb for the weld HAZ metal.

Analysis of H.B. Robinson Unit 2 Capsule X

4-4 Table 4-1 Chemical Composition (wt %) and Heat Treatment of Material for the H.B. Robinson Unit 2 Reactor Vessel Surveillance Materiad)

Chemical Composition Element Plate W10201-4 Plate W10201-5 Plate W10201-6 Weld Metal Correlation Monitor Material C 0.19 0.20 0.19 0.16 0.24 Mn 1.35 1.29 1.32 0.98 1.34 P 0007 0.010 0.010 0.021 0.011 S 0.019 0.021 0.015 0.014 0.023 Si 0.23 0.22 0.19 0.34 0.23 Mo 0.48 0.46 0.49 0.46 0.51 Cu 0.12 0.10 0.09 0.34 0.20 V --- ... --- 0.001 ---

Ni --- --- 0.66 0.18 Cr ..---

--- 0.024 0.11 Co ....... --- ..

Heat Treatment Plate W10201-4, 1550'F to 1600 0F, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Water Quench Plate W10201-5, & 1200 0F to 1250 0F, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Air Cooled Plate W10201-6 1125 0F to 1175 0F, 15 1/2 hours, Furnace cooled to 6007F Weld Metal 1125°F to ] 175-F, 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , Furnace cooled to 600°F Correlation Monitor 1650'F, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Water Quenched 1200°F - 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , Air Cooled Notes:

a) The data given in this column (originally) is from WCAP-7373 & WCAP-10304.

Analysis of -l.B.Robinson Unit 2 Capsule X

-* 5-3 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in capsule X, which received a fluence of 4.49 x 1019 rfcm2 (E> 1.0 MeV) in 20.39 EFPY of operation, are presented in Tables 5-i through 5-8, and are compared with unirradiated results as shown in Figures 5-1 through 5-12.

The transition temperature increases and upper shelf,energy decreases for the capsule X materials are summarized in Table 5-9. These results led to the following conclusions:

Irradiation of the reactor vessel intermediate shell plate W 10201-4 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction of the plate (longitudinal orientation), to 4.49 x 1P n/cem2 (F> 1.0MeV) resulted in a 30 ft-lb transition temperature increase of 104.73°F and a 50 ft-lb transition temperature increase of 98.68°F. This results in an irradiated 30 ft-lb transition temperature of 86.55°F and an irradiated 50 ft-lb transition temperature of 116.041F for the longitudinally oriented specimens Irradiation of the weld metal Charpy specimens to 4.49 x 10'9 n/cm2 (E> 1.0MeV) resulted in a 30 ft-lb transition temperature increase of 265.93OF and a 50 ft-lb transition temperature increase of 251.74 0 F. This results in an irradiated 30 ft-lb transition temperature of 179.64 0F and an irradiated 50 ft-lb transition temperature of 211.38*F.

Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens to 4.49 x 10"'n/cm2 (E > 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 210.13*F and a 50 ft-lb transition temperature increase of 216.59 0 F. This results in an irradiated 30 ft-lb transition temperature of 100.47°F and an irradiated 50ft-lb transition temperature of 150.54 0 F.

Irradiation of the correlation monitor material Charpy specimens to 4.49 x 10"'n/cm 2 (E > 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 125.21 OF which resulted in an irradiated 30 fl-lb transition temperature of 188.151F. The tested specimens did not reach the 50 ft-lb transition temperature.

The average upper shelf energy of the intermediate shell plate Wi10201-4 (longitudinal orientation) resulted in an average energy decrease of 1 ft-b after irradiation to 4.49 x 10" n/cm2 (E> 1.0 MeV). This results in an irradiated average upper shelf energy of 94 ft-lb for the longitudinally oriented specimens.

The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 33 ft-lb after iriadiation to 4.49 x 1019 n/cm 2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 80. ft-lb for the weld metal specimens.

-The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 24 ft-lb after irradiation to 4.49 x 10"'n/cm2 (E > 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 105 ft-lb for the weld HAZ metal.

The average upper shelf energy of the correlation monitor material Charpy specimens resulted in no energy decrease after irradiation to 4.49 x 10"' n/cm2 (E > 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 42 ft-lb for the correlation monitor material.

Analysis of l.B. Robinson Unit 2 Capsule X

5-4 A comparison of the H.B. Robinson Unit 2 reactor vessel beltline material test results with the Regulatory.

Guide 1.99, Revision 2'I}, predictions led to the following conclusions:

The measured 30 ft-lb shift in transition temperature values of the intermediate shell plate WI 0201-4 contained in capsule X (longitudinal) is greater than the Regulatory Guide 1.99, Revision 2, predictions. However, the shift value is less than two sigma allowance by Regulatory Guide 1.99, Revision 2.

- The measured 30 ft-lb shift in transition temperature values of the weld metal contained in capsule X (longitudinal) is less than the Regulatory Guide 1.99, Revision 2, predictions.

- The measured percent decrease in upper shelf energy of the Capsule X surveillance material is less than the Regulatory Guide 1.99, Revision 2, predictions.

The fracture appearance of each irradiated Charpy specimen from the various surveillance capsule X materials is shown in Figures 5-13 through 5-16 and show an increasingly ductile or tougher appearance with increasing test temperature.

The load-time records for individual instrumented Charpy specimen tests are shown in Appendix A.

The Charpy V-notch data presented in this report is based on a re-plot of all capsule data using CVGRAPH, Version 4.1, which is a hyperbolic tangent curve-fitting program. Hence, Appendix C contains a comparison of the Charpy V-notch shift results for each surveillance material (hand-fitting versus hyperbolic tangent curve-fitting). Additionally, Appendix B presents the CVGRAPH, Version 4.1, Charpy V-notch plots and the program input data.

Analysis of H.B. Robinson Unit 2 Capsule X

5-7 Table 5-2 Charpy V-notch Data for the H.B. Robinson Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 4.49 x I0' n/cm 2 (E> 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number F C ft-lbs Joules mils mm %

W3 0 -18 4 5 0 0.00 0 W2 100 38 14 19 4 0.10 15 W6 175 79 28 38 16 0.41 35 W4 200 93 38 52 22 0.56 40 W8 250 121 74 100 49 1.24 100 W7 350 177 78 106 51 1.30 100 W5 375 191 85 115 56 1.42 -100 W1 425 218 82 111 54 1.37 100 Analysis of H.B. Robinson Unit 2 Capsule X

5-15 Table 5-10 Comparison of the H.B. Robinson Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99 Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Temperature Shift Decrease Material Capsule Fluence Predicted Measured Predicted Measured 2 (OF) (a) (OF) 'b) (%) (a) (%)(C)

(X 1019 n/cm )

Inter, Shell Plate S 0.479 45.39 32.51 18 10 W10201-4 X 4.49 78.86 104.73 30 1 (Longitudinal)

Surveillance V 0.530 179.17 209.32 39 38 Program T 3.87 293.68 288.15 52 46 Weld Metal X 4.49 300.64 265.93 54 29 Heat Affected V 0.530 - 59.21 --- 26 Zone Material T 3.87 - - (d) -- - 24 X 4.49 .. 210.13 --- 19 Correlation S 0.479 - 72.79 --- 3 Monitor Material V 0,530 - - 69.39 - -, 5 T 3.87 - - 156.83 --- 5 X 4.49 - - 125.21 --- 0 Notes:

(a)' Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material, (b) Calculated using measured Charpy data plotted using CVGRAPH, Version 4.1 (See Appendix B)

(c) Values are based on the definition of upper shelf energy given in ASTM El 85-82.

(d) Only 2 specimens were tested from capsule T to confirm the upper shelf energy, thus, there is insufficient data to determine the measured 30 ft-lb shift.

Analysis of H.B. Robinson Unit 2 Capsule X

5-20 7--

1 SURVELLIANCE PROGRAM WELD MATERIAL CVGRAPH 4,1 Hyperbolic Tangent Curve Printed at 095457 on 10-24-2001 Results Curve Fluence LSE d-ISE USE d-USE T o 30 d-T o 30 T o 50 d-To 50 2 [1 2.19 0 113 0 -8629 0 -4025 0 0 2.19 0 70 -43 123.02 20932 214.59 25494 3 0 22 0 61 -52 201B6 28K.15 205.94 246.3 4 U 2.19 0 80 -33 179.64 265.93 211.38 251.74 b.V

-300 -200 -:100 0 100 200 300 400 500 600 Temperature in Degrees F Curve L.egend 1D- 20--- 3 49ý 4-Data SelLs) Plotted Curve Plant Capsule Material ' Ori. Heat#

I1 H112 UNIRR WELD N/A W5214 2 H2 V WELD N/A 1Y5214 3 HB2 T WELD NI/A WY5214 4 HB2 X WELD N/A W5214 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for H.B. Robinson Unit 2 Reactor Vessel Surveillance Weld Metal Analysis of H.B, Robinson Unit 2 Capsule X

7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the intent of ASTM E1 S-'2 and is recommended for future capsules to be removed from the H.B. Robinson Unit 2 reactor vessel. This recommended removal schedule is applicable to 29 EFPY of operation.

Notes:

(a) Updated in Capsule X dosimetry analysis. Lead Factor in Parentheses are for Future Cycles.

(b) Effective Full Power Years (EFPY) from plant startup.

(c) Plant specific evaluation.

(d) Capsule U will reach a fluence of approximately 6.00 x 10'9 (50 EFPY Peak Fluence) at approximately 29.8 EFPY.

Thus, it should be pulled at the closest outage to 29.8'EFPY.

(e) If further material data is desired, then it is recommended that these capsules be moved to a higher lead factor location and then removed once their accumulated neutron fluence equals the license renewal (50 EFPY) fluence on the vessel inner surface.

(f) Moved to Capsule "S" Location (2800) at Cycle 8.

(g) Capsule Zwas inadvertently removed from the H.B. Robinson 2 Reactor Vessel. At this time it is unconfirmed that Capsule Z was re-installed into the vessel or placed in the spent fuel pool.

Analysis of H.B. Robinson Unit 2 Capsule X

4-4 Table 4-1 Chemical Composition (wt %) and Heat Treatment of Material for the H.B. Robinson Unit 2 Reactor Vessel Surveillance Materialfa)

Chemical Composition Element Plate W1I0201-4 Plate W10201-5 Plate W10201-6 Weld Metal Correlation

/ Monitor Material C 0.19 0.20 0.19 0.16 0.24 Mn 1.35 1.29 1.32 0.98 1.34 P 0007 0.010 0010 0.021 0.011 S 0.019 0.021 0.015 0.014 0,023 Si 0.23 0.22 0.19 0.34 0.23 Mo 0.48 0.46 0,49 0.46 0.51 Cu 0.12 0.10 0.09 0.34 0.20 V ... --- ... 0.001 -- -

Ni -.. --- --- 0.66 0.18 Cr ---- -- 0.024 0.11 Co - ........-

Heat Treatment Plate W10201-4, 1550°F to 1600TF, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Water Quench Plate W10201-5, & 1200°F to 1250-F, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Air Cooled Plate W 10201-6 1125°F to 117 50F, 15 1/2 hours, Furnace cooled to 600°F Weld Metal 1125°F to I 175°F, 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , Furnace cooled to 600'F Correlation Monitor ) 650°F,4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Water Quenched 1200°F - 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , Air Cooled Notes:

a) The data given in this column (originally) is from WCAP-7373 & WCAP-10304.

Analysis of H.B. Robinson Unit 2 Capsule X

5-7 Table 5-2 Charpy V-notch Data for the H.B. Robinson Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 4.49 x 10"9 n/cm2 (E> 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number F C ft-lbs Joules mils mm %

W3 0 -18 4 5 0 0.00 0 W2 160 38 14 19 4 0.10 '15 W6 175 79 28 38 16 0.41 35 W4 200 93 38 52 22 0.56 40 W8 250 121 74 100 49 1.24 100 W7 350 177 78 106 51 1.30 100 W5 375 191 85 115 56 1.42 100 W1 425 218 82 111 54 1.37 100 Analysis of H.B. Robinson Unit 2 Capsule X

5-15 Table 5-10 IComparison of the H.B. Robinson Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Temperature Shift Decrease Material Capsule Fluence Predicted Measured Predicted Measured (X 1019 n/cm 2 ) (OF) (a) (OF) (,) (/) (a) (/)(c)

Inter. Shell Plate S 0.479 45.39 32.51 18 10 W10201-4 X 4.49 78.86 104.73 30 1 (Longitudinal)

Surveillance V 0.530 179,17 209.32 39 38 Program T 3.87 293.68 288.15 52 46 Weld Metal X 4.49 300.64 265.93 54 29 Heat Affected V 0.530 - - 59.21 --- 26 Zone Material T 3.87 - - (d) - -- 24 X 4.49 -- 210.13 -- - 19 Correlation S 0.479 -- 72.79 --- 3 Monitor Material V 0.530 - - 69.39 - -- 5 T 3.87 156.83 - -- 5 X 4.49 125.21 - -- 0 Notes, (a) Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveiflance material.

(b) Calculated using measured Charpy data plotted using CVGRAPH, Version 4.1 (See Appendix B)

(c) Values are based on the definition of upper shelf energy given in ASTM El 85-82.

(d) Only 2 specimens were tested from capsule T to confirm the upper shelf energy, thus, there is insufficient i

data to determine the measured 30 fl-lb shift.

Analysis of H.B. Robinson Unit 2 Capsule X

5-20 SURVELLIANCE PROGRAM WELD MATERIAL CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 0954:57 on 10-24-2001 Results Curve Fluence [SE d-LSE USE d-USE T o 30 d-T o 30 T o 50 d-T o 50 1 0 219 0 113 0 -41629 0 -40.35 0 5-20 2 0 2.19 0 70 -43 123.02 209132 21409 254.94 3 0 22 0 61 -52 2016 28.15 205.94 246.3 4 0 2.19 0 BO -33 179.64 265.93 211.3 251.74

.4)

-30o -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend I C- 2 - . . . 30- 4 -

Data Set(s),Plotted Curve Plant Cansule MAaterial Ori. Heat#

1 112 UNIRR WELD N/A -W5214 2 HB2 Y WELD N/A W5214 3 H2 T WELD N/A W5214 4 B2 x WELD N/A W5214 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for H.B. Robinson Unit 2 Reactor Vessel Surveillance Weld Metal Analysis of H.B. Robinson Unit 2 Capsule X

5-21 SURVEILLANCE PROGRAM WELD MATERIAL CVGRAPII 4.1 Hyperbolic Tangent. Curve Printed at 099M on 10-24-2001 Results Curve Fluence USE d-USE- T o LE35 d-T v LE35 (1 91.91 0 -6064 0 2 0 65.7 -2627 19026 250.9 3 0 41.57 -50.4 2042 26485 4 0 542 -37.77 21924 279.89

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend to-Data Set~s) Plotted Curve Plant Capsule Material Ori. lHeati 1 H112 UNIFE WELD NI/A W15214 2 V WELD N/A W5214 3 HB2 T' WELD N/A W5214 4 HB2 x WELD N/A W5214 Figure S-5 Charpy V-Notch Lateral Expansion vs. Temperature for D.B. Robinson Unit 2 Reactor Vessel Surveillance Weld Metal Analysis of H.B. Robinson Unit 2 Capsule X

H B Robinson Weld Data PREP-4 Hyperbolic Tangent Curve Printed on 10/19/2009 10:38:40 PM Page 1 Coefficients of Curve 1 A = 59.8 B = 57.6 C = 118.8 TO = -18.8 Equation is A + B * [Tanh((T-To)/C)]

Upper Shelf Energy=117.4 Lower Shelf Energy=2.2 Temp.@30 ft-lbs=-86.8 Deg F Temp.@50 ft-lbs=-39.2 Deg F Plant: H B Robinson 2 Material: SAW Heat: W5214 (S)

Orientation: TL Capsule: Unirr. Fluence: 0.

250 200 0

o15 100 z

50

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy Ye-Notch Data Temperature Input CVN Computed CVN Differential

-150.00 30.00 13.60 16.40

-150.00 2.00 13.60 -11.60

-150.00 3.00 13.60 -10.60

-150. 00 10 00 13. 60 -3. 60

-150.00 19.00 13. 60 5.40

-150. 00 34.50 '13. 60 20. 90

-100. 00 29.00 25.60 3.40

H B Robinson Weld Data Page 2 Plant: H B Robinson 2 Material: SAW Heat: W5214 (S)

Orientation: TL Capsule: Unirr. Fluence: 0.

Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-100. 00 38.00 25; 60 12.40

-100. 00 25.00 25. 60 -. 60

-50. 00 5'4. 5o 45.01 9.49

-50. 00 21.00 45.01 -24.01

-50. 00 36.50 45.01 -8.51 10.00 73. 510 73.50 0.0 10.00 65.50 73.50 -8.00

60. 00 68.00 73.50 -5.50 97.00 93.24 3.76

60. 00 116.00 93.24 22.76

60. 00 99.00 93.24 5.76 100. 00 107. 50 103.67 3.83 110.00. 104 .00 105.58 -1.58 110. 00 97 00 105.58 -8. 58 210.00 112. 00 -115.00 -3. 00 210.00 111. 00 115.00 -4.00 210. 00 115. 00 11,5.00 .00 Correlation Coefficient = .000

H B Robinson Weld Data PREP-4 Hyperbolic Tangent Curve Printed on 10/19/2009 10:40:29 PM Page 1 Coefficients of Curve 2 A =31.6 B = 29.4 C = 63.57 TO = 225.94 Equation is A + B * [Tanh((T-To)/C)]

upper Shelf Energy=61.0 Lower Shelf Energy=2.2 Temp.@30 ft-lbs=222.5 Deg F Temp.@50 ft-lbs=272 6 Deg F Plant: H B Robinson 2 Material: SAW Heat: W5214 (S)

Orientation: TL Capsule: T Fluence: 4.42E+19 250 200

.0 o 15o U.

0 100 z

50 0 "'-%-"-- -- '---*- - '- -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 175.00 14 .00 12.06 1.94 200.00 23.50 20.23 3.27 200.00 17.00 20.23 -3.23 225.00 .64.00 31.17 32.83 250.00 38. 50, 42.22 -3.72 275.00 51. 50 50.65 .85 300.00 60. 50 55.79 4.71 Correlation Coefficient = .000

H B Robinson Weld Data PREP-4 Hyperbolic Tangent Curve Printed on 10/19/2009 10:41:23 PM Page 1 Coefficients of Curv~e 3 A = 34.35 B = 32.15 C = 142.03 TO =141.21 Equation is A + B * [Tanh((T-To)/C)]

Upper Shelf Energy=66.5 Lower Shelf Energy=2.2 Temp.@30 ft-lbs121.9 Deg F Temp.@50 ft-lbs=216.7 Deg F Plant: H B Robinson 2 Material: SAW Heat: W5214 (S)

Orientation: TL C apsule: V Fluence: 6.01E+18 250 200O 0

o 150 U-Uj100 z

> 0 L)~~ .. ~

~~~~~~~~~

0 -;' "" ":' ": ....... ..".'".

0.........

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 30.00 23. 50 13.31 10.19 75.00 23. 50 20.36 3.14 110. 00 30.00 27.40 2. 60 160.00 14 .00 38 58 -24.58 180.00 44.00 42.92 1.08 210.00 58.50 48.81 9.69 300. 00 72.50 60.29 12 .21

H B Robinson Weld Data Page 2 Plant: H B Robinson 2 Material: SAW Heat: W5214 (S)

Orientation: TL Capsule: V Fluence: 6.01E+18 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 400.00 68.50 64.86 3. 64 Correlation Coefficient = .000

APPENDIX G CVGRAPH TANH CURVE-FITS FOR W5214 SURVEILLANCE WELD DATA (from Reference 32)

Report No. 0901132.40 1, Rev. 0 G-1 RN0 2StructuralIntegrity Associates, Inc.

Table G-1. Fitted Results for CVGRAPH Hyperbolic Tangent Curve-Fits [321

ýPlant Capsule A B C TO T30 Palisades Unirradiated 53.14 50.94 100.7 -10.76 -60.1 Palisades SA-60-1 28.35 26.15 158.11 188.85 198.9 Palisades SA-240-1 27.35 25.15 111.62 208.13 220 H. B. Robinson 2 Unirradiated 56.05 53.85 107.57 -29.1 -85.8 H. B. Robinson 2 T 31.35 29.15 9.09 203.64 203.3 H. B. Robinson 2 V 36.35 34.15 150.19 151.23 123 H. B. Robinson 2 X 40.97 38:78 59.96 197.18 179.8 Indian Point 2 Unirradiated 59.32 57.12 86.23 -16.54 -65.4 Indian Point 2 V 39.1 36.9 123.56 163.14 132.1 Indian Point 2 Y 34.35 32.15 91.6 140.88 128.5 Indian Point 3 Unirradiated 60.38 58.19 45.25 -37.64 -63.8 Indian Point 3 T 46.35 44.15 98.27 124.16 86 Indian Point 3 Y 35.6 33.4 90.16 122.54 107.3 Indian Point 3 Z 39.1 36.9 97.52 188.96 164.5 Indian Point 3 X 38.6 36.4 121.83 157.96 128.7 Report No. 0901132.401, Rev. 0 G-2 R2StructuralIntegrity Associates, Inc.

Palisades Unirradiated Capsule Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/09/2010 06:36 PM Page 1 Coefficients of Curve I A = 53.14 B = 50.94 C = 100.7 TO = -10.76 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy= 104.1 Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-60.1 Deg F Temp@50 ft-lbs=-16.9 Deg F Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: Unirradiat n/cmA2 300 250 200 0

2 150 z

> 100 50 0 I T I 1, t i k i i I 1

-300 -200 -100 0 100 200 300 400 500 600

'Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-1 10. 00 11. 80 14. 66 -2. 86

- I10.o 00 11.80 14. 66 -2.86

-80. 00 33. 90 22. 76 11.14

-80. 00 20. 60 22. 76 -2. 16

-80. 00 29. 50 22. 76 6. 74

-40. 00 47. 90 38. 75 9. 15

-40. 00 43. 50 38. 75 4. 75

-40.00 29. 50 38.. 75 -9. 25

-40.00 41.29 38. 75 2. 54

Palisades Unirradiated Capsule Report Page 2 Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: Unirradiat n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 00 64. 19 58. 56 5.63

\.00 39.09 58. 56 -19.47 20.00 62.70 68.24 -5.54

20. 00 60.50 68. 24 -7. 74

30. 00 78. 19 72. 70 5. 49 40.00 61.20 76.85 -15.65 60.00 87.00 84.02 2.98

60. 00 75. 19 84. 02 -8. 83 60.00 111.40 84.02 27.38 110.00 110.59 95.60 14.99 110.00 98.80 95.60 3.20 210.00 110.59 102. 83 7. 76 210.00 95.90 102.83 -6.93 300.00 97.40 103. 87 -6. 47 300.00 94.40 103.8,7 -9.47 Correlation Coefficient = .947

Palisades SA-60-1 Capsule Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 10:39 AM Page 1 Coefficients of Curve I A = 28.35 B = 26.15 C = 158.11 TO = 188.85 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=54.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=198.9 Deg F Temp@50 ft-lbs=375.7 Deg F Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: SA Fluence: 1.5E] 9 n/cmA2 300 250 200 0

0 U-150 z

> 100 50 0n 0 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

74. 00 10. 00 12.11 -2. 11 129. 00 24. 00 18.90 5. 10 154. 00 23. 50 22. 68 82 204. 00 30. 00 30. 85 85 229.00 33. 50 34. 85 1 35 254. 00 28. 00 38. 55 -- 10. 55 279. 00 43. 50 41L83 1. 67 279. 00 48. 50 41,.83 6. 67 329. 00 47. 50 46. 91. 59

Palisades SA-60-1 Capsule Report Page 2 Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: SA Fluence: 1.5E19 n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 404. 00 51.50 51.27 .23 454. 00 55. 00 52. 73 2. 27 479. 00 57. 00 53. 20 3. 80 Correlation Coefficient = .957

Palisades SA-240-1 Capsule Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 10:34 AM Page 1 Coefficients of Curve I A = 27.35 B = 25.15 C = 111.62 TO = 208.13 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=52.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=220.0 Deg F Temp@50 ft-lbs=372.9 Deg F Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: SA-240 Fluence: 2.38E19 n/cmA2 300 250 200 0

U-im 150 z

100 50 0 0 00 0 r t ~-------- - - -t--------

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

70. 00 14. 00 6. 10 7. 90 125. 00 15. 50 11. 45 4. 05 175. 00 24. 50 20. 10 4. 40 200. 00 13. 00 25. 52 12. 52 200. 00 26. 50 25. 52 98 225. 00 25. 00 31. 12 -6. 12 250. 00 40. 00 36. 36 3. 64 300. 00 54. 50 44. 37 10. 13 350. 00 49. 00 '48. 83 17

,Palisades SA-240-1 Capsule Report Page 2 Plant: PALISADES Material: SAW Heat: W5214 Orientation: NA Capsule: SA-240 Fluence: 2.38E19 n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN. Differential 400. 00 50. 50 50. 93 . 43 450.00 52. 50 51.85 .65 500. 00 54. 50 52. 23 2. 27 Correlation Coefficient = .935

H. B. Robinson 2 Unirradiated Capsule Report CVGRAPH 5.0.2 Hyperbolic TangentCurve Printed on 03/25/2010 11:43 AM Page 1 Coefficients of Curve I A = 56.05 B = 53.85 C = 107.57 TO = -29.1 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy= 109.9(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-85.8 Deg F Temp@50 ft-lbs=-41.2 Deg F Plant: H B Robinson 2 Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: n/cmA2 300 250

- 200

0 0

LL 150 4)

C z

> 100 0-50 0 7 _-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 150. 00 19. 00 12. 49 6. 51

- 150. 00 10. 00 12.49 -2. 49

- 150. 00 30. 00 12.49 17. 51

- 150. 00 34. 50 12.49 22. 01

- 150. 00 3. 00 12. 49 -9. 49

- 150. 00 2. 00 12. 49 -10. 49

-100. 00 25. 00 24. 94 06

- 100. 00 38. 00 24. 94 13. 06

- 100. 00 29. 00 24. 94 4. 06

H. B. Robinson 2 Unirradiated Capsule Report Page 2 Plant: H B Robinson 2 Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-50.00 36.50 45.72 -9.22

-50.00 21.00 45.72 -24.72

-50.00 54.50 45. 72 8.78

10. 00 65.50 74. 80 -9.30 10.00 73.50 74.80 -1.30 10.00 68.00 74. 80 -6.80 60.00 97.00 92. 64 4.36 60.00 99.00 92.64 6.36 60.00 116.00 92.64 23.36 100.00 107.50 100.94 6.56 110.00 97.00 102.36 -5.36 110.00 104.00 102.36 1.64 210.00 115.00 108.65 6.35 210.00 111.00 108. 65 2. 35 210.00 112.00 108. 65 3. 35 Correlation Coefficient = .962

H. B. Robinson 2 Capsule T Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 04/14/2010 09:40 PM Page 1 Coefficients of Curve I A = 31.35 B = 29.15 C = 9.09 TO = 203.64 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=60.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=203.3 Deg F Temp@50 ft-lbs=210.6 Deg F Plant: H B ROBINSON 2 Material: SAW Heat: W5214 Orientation: NA Capsule: T Fluence: 3.87E19 n/cmA2 300 250

- 200 0

U-2 150 w

z

> 100 0

50 ff 0-0-

0 A

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 175. 00 14. 00 2.31 11'. 69 200. 00, 17. 00 20. 27 -3. 27 200. 00 23. 50 20. 27 3. 23 225. 00 64. 00 59. 97 4. 03 250. 00 38. 50 60. 50 -. 22. 00 275. 00 51.50 60. 50 -9.00 300. 00 60.-50 60. 50 .00 Correlation Coefficient = .908

H. B. Robinson 2 Capsule X Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:45 AM Page 1 Coefficients of Curve I A = 40.97 B = 38.78 C = 59.96 TO = 197.18 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=79.8(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=179.8 Deg F Temp@50 ft-lbs=211.4 Deg F Plant: H B ROBINSON 2 Material: SAW Heat: W-5214 Orientation: NA Capsule: X Fluence: 4.49E19 n/cmA2 300 250 S200 0

U-2t 150 4) z

> 100 0

0 50 0

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 00 4. 00 2. 31 1. 69 100. 00 14. 00 5. 12 8. 88 175. 00 28. 00 27. 25 75 200. 00 38. 00 42. 80 -4. 80 250. 00 74. 00 68. 39 5. 61 350. 00 78. 00 79. 28 - 1. 28 375. 00 85. 00 79. 54 5. 46 425. 00 82. 00 79. 71 2. 29 Correlation Coefficient = .992

H. B. Robinson 2 Capsule V Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:47 AM Page 1 Coefficients of Curve I A = 36.35 B = 34.15 C = 150.19 TO = 151.23 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=70.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=123.0 Deg F Temp@50 ft-lbs=214.9 Deg F Plant: H B ROBINSON 2 Material: SAW Heat: W5214 Orientation: NA Capsule: V Fluence: 5.30E18 n/cmA2 300 250 200 0

0 U-Em 150 z

> 100 50 0 I F I

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

30. 00 2.3. 50 13. 54 9. 96

75. 00 23. 50 20. 37 3. 13 110. 00 30. 00 27. 20 2. 80 160. 00 14. 00 38. 34 -24. 34 180. 00 44. 00 42. 81 1. 19 210. 00 58. 50 49.07 9. 43 300. 00 72. 50 62. 22 10. 28 400. 00 68. 50 68. 10 40 Correlation Coefficient = .865

Indian Point 2 Unirradiated Capsule .Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 10:55 AM Page 1 Coefficients of Curve I A = 59.32 B = 57.12 C = 86.23 TO = -16.54 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=I 16.4(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-65.4 Deg F Temp@50 ft-lbs=-30.7 Deg F Plant: INDIAN POINT 2 Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: Unirradiat n/cmA2 300 250 200 0

U-2L~150 W

z

> 100 0

50 0 [ *l I I 1 I *

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 150. 00 12. 50 7. 15 5. 35

- 150.00 10. 50 7. 15 3. 35

- 100. 00 35. 00 16. 61 18. 39

- 100. 00 18. 00 16.61 1. 39

- 100. 00 9. 00 16. 61 -7. 61

- 80. 00 13. 00 23. 52 10. 52

-80. 00 26. 00 23. 52 2. 48

-80. 00 32. 50 23. 52 8. 98

-40. 00 35. 50 44. 15 -8. 65

Indian Point 2 Unirradiated Capsule Report Page 2 Plant: INDIAN POINT 2 Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: Unirradiat n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-40.00., 48.00 44. 15 3.85

-40.00 34.00 44. 15 -10. 15

10. 00 74.00 76. 37 -2. 37 10.00 81.00 76.37 4.63

10. 00 78.50 76. 37 2. 13 60.00 102.50 99..89 2.61

60. 00 102.00 99. 89 2. 11 60.00 100.00 99.89 .11 110.00 .112.50 110.68 1.82 110.00 108.50 110.68 -2.18 110.00 108.50 110.68 -2.18 160.00 120.00 114.57 5.43 160.00 115.50 114.57 .93 160. 00 113.00 114. 57 -1 .57 210. 00 123.50 115. 85 7. 65 210. 00 121.00 1 15.85 5. 15 210.00 117.50 115.85 1.65 Correlation Coefficient = .990

Indian Point 2 Capsule V Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 02:35 PM Page 1 Coefficients of Curve I A = 39.1 B = 36.9 C = 123.56 TO = 163.14 D = O.O0E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=76.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=132.1 Deg F Temp@50 ft-lbs=200.8 Deg F Plant: INDIAN POINT 2 Material: SAW Heat: W5214 Orientation: NA Capsule: V Fluence: 4.92E18 n/cmA2 300 250 200 0

U-150 1U0 z

>' 100 0.

500 0-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

74. 00 24. 00 16. 30 7. 70 130. 00 26. 50 29. 44 -2. 94 180. 00 40. 50 44. 11 -3. 61 220. 00 53. 00 54. 98 -1. 98 260. 00 62. 50 63. 27 .77 300. 00 76. 00 68. 74 7. 26 325. 00 72. 50 70. 99 I .51 350. 00. 76. 00 72. 58 3. 42 Correlation Coefficient = .978

Indian Point 2 Capsule Y Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 10:59 AM Page 1 Coefficients of Curve I A = 34.35 B = 32.15 C = 91.6 TO = 140.88 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=66.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=128.5 Deg F Temp@50 ft-lbs=189.6 Deg F Plant: INDIAN POINT 2 Material: SAW Heat: W5214 Orientation: NA Capsule: Y Fluence: 4.55E18 n/cmA2 300 250 200 0

0 U-2m 150 z

> 100 50 0 -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

74. 00 17. 50 14. 32 3. 18 110. 00 23. 00 23. 90 90 160. 00 40. 00 40. 96 96 190. 00 47. 00 50. 11 3. 11 210. 00 55. 00 54. 86 14 260. 00 71. 50 62. 06 9. 44 300. 00 61. 00 64. 57 3. 57 350. 00 67. 00 65. 84 1. 16 Correlation Coefficient = .978

Indian Point 3 Unirradiated Capsule Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:16 AM Page 1 Coefficients of Curve 1 A = 60.38 B = 58.19 C = 45.25 TO = -37.64 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=l 18.6(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-63.8 Deg F Temp@50 ft-lbs=-45.8 Deg F Plant: INDIAN POINT 3 Material: SAW Heat: W5214 Orientation: NA , Capsule: Unirra Fluence: Unirradiat n/cmA2 300 250 200 0

0 U-p~150 z

> 100 50 O0 -,

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 150. 00 5. 00 3.01 1 99

- 150. 00 2. 00 3.01 -1 01

- 150. 00 4. 50 3.01 1 49

- 100. 00 29. 00 9. 15 19. 85

- 100. 00 18. 00 9. 15 8. 85

- 100. 00 25. 50 9. 15 16. 35

- 50. 00 35. 00 44. 88 -9. 88

-50. 00 33. 00 44. 88 - 11. 88

-50. 00 32. 50 44. 88 -12. 38

Indian Point 3 Unirradiated Capsule Report Page 2 Plant: INDIAN POINT 3 Material: SAW Heat: W5214 Orientation: NA Capsule: Unirra Fluence: Unirradiat n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-35.00 78.00 63.78 14.22

-35.00 69.50 63.78 5.72

-35.00 54.50 63.78 -9.28

-20.00 87.00 81.98 5.02

(--20.00 82.00 81.98 .02

-20.00 89.00 81.98 7.02 10.00 100.00 105.94 -5.94

10. 00 105.00 105. 94 -. 94 10.00 113.50 105.94 7.56 60.00 115.00 117.04 -2.04 60.00 119.00 117.04 1.96 60.00 121.50 117.04 4.46 160.00 124.00 118.55 5.45 160. 00 125.00 118.55 6. 45 160.00 112.00 118.55 -6.55 Correlation Coefficient = .981

Indian Point 3 Capsule T Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:19 AM Page 1 Coefficients of Curve I A = 46.35 B = 44.15 C = 98.27 TO = 124.16 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=90.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=86.0 Deg F Temp@50 ft-lbs=132.4 Deg F Plant: INDIAN POINT 3 Material: SAW Heat: W5214 Orientation: NA Capsule: T Fluence: 2.63E18 n/cmA2 300 250 200 0

0 U-150 z

> 100 50 I J I I [ *I 10 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 00 13. 00 8.73 4. 27

70. 00 17. 50 24. 21 -6.71 110. 00 48. 00 40. 03 7. 97 150. 00 55. 50 57. 70 -2. 20 150. 00 53.. 00 57. 70 -4. 70 165. 00 66. 00 63. 71 2. 29 210. 00 78. 00 77. 39 ,.61 300. 00 90. 50 88. 10 2. 40 Correlation Coefficient = .984

Indian Point 3 Capsule Y Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:18 AM Page 1 Coefficients of Curve I A = 35.6 B = 33.4 C = 90.16 TO = 122.54 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=69.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=107.3 Deg F Temp@50 ft-lbs=164.2 Deg F Plant: INDIAN POINT 3 Material: SAW Heat: W5214 Orientation: NA Capsule: Y Fluence: 6.92E18 n/cmA2 300 250

- 200 0

0 U-150 4)

C UJ z

>100 50 I ; I I -

nl 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

25. 00 20. 00 9. 08 10. 92

72. 00 19. 50 18.62 88 1125. 00 31. 00 36. 51 -5. 51 125. 00 29. 50 36.51 -7. 01 150. 00 49. 00 45. 47 3. 53 200. 00 67. 50 58. 84 8. 66 300. 00 69. 50 67. 72 1 .78 400. 00 68. 50 68. 86 - . 36 Correlation Coefficient = .960

Indian Point 3 Capsule Z Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 11:21 AM Page 1 Coefficients of Curve I A = 39.1 B = 36.9 C = 97.52 TO = 188.96 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=76.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=164.5 Deg F Temp@50 ft-lbs=218.7 Deg F Plant: Indian Point 3 Material: SAW Heat: W5214 Orientation: NA Capsule: Z Fluence: 1.04E19 n/cm^2 300 250

- 200 0

0 U-150 z

> 100 Q.

50 0 I I - i I I

-300 -200 -100 0 100 200 300. 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 10 00 12. 45 -2. 45 150. 00 21. 00 25. 10 -4. 10 150. 00 44. 00 25. 10 18. 90 175. 00 26. 00 33. 85 -7. 85 200. 00 33. 00 43. 26 - 10. 26 225. 00 57. 00 52. 15 4. 85 300. 00 75. 00 69. 14 5. 86 400. 00 77. 00 75. 04 1. 96 Correlation Coefficient = .929

Indian Point 3 Capsule X Report CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/25/2010 02:34 PM Page 1 Coefficients of Curve 1 A = 38.6 B = 36.4 C = 121.83 TO = 157.96 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=75.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=128.7 Deg F Temp@50 ft-lbs=197.5 Deg F Plant: INDIAN POINT 3 Material: SAW Heat: W5214 Orientation: NA Capsule: X Fluence: 8.74E18 n/cmA2 300 250 200 0

0 LL z

> 100 0

50 0 1 _ i I "

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

75. 00 9. 00 17. 05 -8. 05 125. 00 49. 00 28. 99 20. 01 125. 00 24. 00 .28. 99 -4. 99 150. 00 35. 00 36. 22 - 1. 22 200. 00 37. 00 50. 68 -13. 68 25,0. 00 67.'00 61.84 5. 16 300. 00 72. 00 68. 56 3.44 350. 00 75. 00 72. 02 2.98 Correlation Coefficient = .907

APPENDIX H CALCULATION OF TIME-WEIGHTED AVERAGE TEMPERATURES FOR SURVEILLANCE CAPSULES CONTAINING WELD HEAT NO. W5214 (from Reference 33)

Report No. 0901 132.401, Rev. 0 H-i StructuralIntegrity Associates, Inc.

Calculation of Time-weighted Average Temperatures for Surveillance Capsules Containing Weld Heat No. W5214 The irradiation temperatures for the various surveillance capsules have been reviewed and verified in support of the credibility analysis for all sources of W5214 weld metal [33].

The Palisades time-weighted average capsule and vessel temperatures were determined from plant operating history data [23]. The weighted average temperatures considered that the capsules were inserted for only two and three cycles. The resulting time weighted temperature for capsule SA-60-1 and SA-240-1 is 535.0'F and 535.70, respectively, as determined from the values shown in Table 8. The vessel time-weighted average temperature is determined to be 535.2'F, as shown in Table H-7.

Discussions with staff at H. B. Robinson 2 indicate that the values for irradiation temperature of HB2 T, HB2 V, and HB2 X are 547'F, which is consistent with the temperature values, listed in Table D-5 of WCAP-15085 [12].

Cycle by cycle Tcold temperatures were reviewed for Indian Point Unit 2 and Indian Point Unit 3 in order to generate time weighted temperatures corresponding to each of the surveillance capsules which contain W5214 weld metal. For Indian Point Unit 2 the data was reviewed from Calculation Number FCX-00538 [29]. For Indian Point Unit 3 the data was reviewed from Calculation Number IP3-CALC-RV-03720 [30].

The radiation exposure and temperature history of Indian Point Unit 2 relative to Capsule Y and Capsules V is shown below.

1P2 History Cycle EFPY T cold Capsule la 1.041 540.6 lb 1.419 528.6 2a 1.666, 529.2 2b 2.337 524.2 Capsule Y Removed 3 3.266 522.9 4 4.112 524.0

.5 5.173 522.7 6 6.323 523.2 7 7.414 522.7 8 8.622 523.1 Capsule V Removed Report No. 0901132.40 1, Rev. 0 H-2 R2StructuralIntegrity Associates, Inc.

Time weighted temperature values for these (2) surveillance capsules is derived in Table H-I and Table H-2.

TABLE H-1.

IP2 CAPSULE Y Cycle EFPY , Cold Leg Temp EFPY x Cold Leg Temp la 1.041 540.6 562.7646 lb 1.419 528.6 750.0834 2a 1.666 529.2 881.6472 2b 2.337 524.2 1225.0554 SUm 6.463 3419.5506 Time Weighted Average Temperature = 3419.5506/6.463=529.0965 TABLE 11-2.

IP2 CAPSULE V Cycle EFPY Cold Leg Temp EFPY x Cold Leg Temp la 1.041 540.6 562.7646 lb 1.419 528.6 750.0834 2a 1.666 529.2 881.6472 2b 2.337 524.2 1225.0554 3 3.266 522.9 1707.7914 4 4.112 524 2154.688 5 5.173 522.7 2703.9271 6 6.323 523.2 3308.1936 7 , 7.414 522.7 3875.2978 8 8.622 523.1 4510.1682 SUM 41.373 21679.6167 Time Weighted Average Temperature = 21679.6167/41.373=524.0039 Report No. 0901132.401, Rev. 0 H-3 e2StructuralIntegrityAssociates, Inc.

The radiation exposure and temperature history of Indian Point Unit 3 relative to Capsule T, Y, Z, and X is shown below.

IP3 HISTORY Cycle EFPY T cold Capsule 1A 1.342 539.4 Capsule T Removed 1B" 1.382 540 2 2.280 539.4 3 3.30 539.4 Capsule Y Removed 4 4.424 539.4 5 5.566 537.5 Capsule Z Removed 6 6.579 537.5 7 7.839 539.8 8 8.972 539.8 9 10.518 540.1 10 12.310 540 11 13.791 540.4 12A 15.361 . 540.1 12B 15.601 540 Capsule X Removed 13 17.433 539.5 14 19.297 538.7 Time weighted temperature values for each of the four- (4) surveillance capsules with W5214 weld metal from Indian Point Unit 3 is derived in TablesH-3, H-4, H-5, and H-6.

TABLE H-3.

IP3 CAPSULE T Cycle EFPY Cold Leg Temp EFPY x Cold Leg Temp 1A 1.342 539.4 723.8748 Average Temperature = 723.9/1.342 = 539.4 Report No. 0901132.401, Rev. 0 H-4 V StructuralIntegrity Associates, Inc.

TABLE H-4.

IP3 CAPSULE Y Cycle EFPY Cold Leg Temp EFPY x Cold Leg Temp 1A 1.342 539.4 723.8748 1B 1.382 540 746.28 2 2.28 539.4 1229.832 3 3.3 539.4 1780.02 SUM 8.304 4480.0068 Time Weighted Average Temperature = 4480.0068/8.304=539.507 TABLE H-5.

1P3 CAPSULE Z Cycle EFPY Cold Leg Temp EFPY x Cold Leg Temp 1A 1.342 539.4 723.8748 lB 1.382 540 746.28 2 2.28 539.4 1229.832 3 3.3 539.4 1780.02 4 4.424 539.4 2386.3056 5 5.566 537.5 2991.725 SUM 18.294 9858.0374 Time Weighted Average Temperature =9858.0374/18294=538.867 TABLE H-6.

IP3 CAPSULE X Cycle EFPY Cold Leg Temp EFPY x Cold Leg Temp 1A 1.342 539.4 723.8748 1B 1.382 540 746.28 2 2.28 539.4. 1229.832 3 3.3 539.4 1780.02 4 4.424 539.4 2386.3056 5 5.566 537.5 2991.725 6 6.579 537.5 3536.2125 7 7.839 539.8 4231.4922 8 8.972 539.8 4843.0856 9 10.518 540.1 5680.7718 10 12.31 540 6647.4 ,

11 13.791 540.4 7452.6564 12A 15.361 540.1 8296.4761 12B 15.601 540 8424.54 SUM 109.265 58970.672 Time Weighted Average Temperature =58970.672/109.265=539.703 Report No. 0901132.40 1, Rev. 0 H-5 R2StructuralIntegrity Associates, Inc.

Table H-7.

PALISADES VESSEL TIME-WEIGHTED AVERAGE TEMPERATURE Cycle Cycle Average Factored Days x Length Cycle Cycle Operating Legh Factored Tmeaue ieWigtd (EFPD) Length Cycle Length F d Temperature Time Weighted from CNS- Adjusted by (EFPD) Days (Ti) Cycle Avg. Ti 04-02-01, 0.98xEFPD Revision I 1 371.7() 0.041 523 21.5 379.3 371.7 2 440.1(') 0.049 529 25.8 449.1 440.1 3 342.5() 0.038 534 20.2 349.5 342.5 4 321.0(') 0.036 536 19.0 327.6 321.0 5 386.7() 0.043 536 22.9 394.6 386`7 6 326.7() 0.036 . 536 19.4 333.4 326.7 7 362.5(') 0.040 536 21.5 369.9 362.5 8 366.1(') 0.041 537 21.8 373.6 366.1 9 292.5(1) 0.032 534 17.3 298.5 292.5 10 349.7(I) 0.039 534 20.7 356.8 349.7 11 421.9(1) 0.047 533 24.9 430.5 421.9 12 399.3(') 0.044 534 23.6. 407.4 399.3 13 419.6 0.046 536 24.9 14 449.3 0.050 537 26.7 15 401.3 0.044 537 23.8 16 444.3 0.049 537 26.4 17 493.1 0.055 537 29.3 18 472 0.052 537 28.0 19 459.2 0.051 537 27.3 20 499.8 0.055 537 29.7 21 519.2(2) 0.057 537 30.9 22 498.8(2) 0.055 537 29.6 SUM 1 SUM 9037.4 (1) EFPD for Cycles 1 - 12 have been reduced by 2% per Ref. 23.

(2) EFPD for Cycles 21 and 22 are projected values.

SUM 535.2 0 F Time Weighted 535.2 0 F Average Temperature Report No. 0901132.40 1, Rev. 0 H-6 R2StructuralIntegrity Associates, Inc.

APPENDIX I LISTING OF DESIGN INPUTS FOR WELD HEAT NO. W5214 SURVEILLANCE DATA RE-EVALUATION Report No. 0901132.40 1, Rev. 0 1-1 StructuralIntegrity Associates, Inc.

Listing of Design Inputs for Weld Heat No. W5214 Surveillance Data Re-evaluation A roadmap to the references used in this report is provided in this Appendix. This roadmap provides a snapshot of the various references used to obtain the design inputs for chemistry factor, un'irradiated and irradiated Charpy V-notch (CVN) data, the TANH methodology used to fit the CVN data, capsule fluences, the regulatory guidance documents and codes used, and the inputs used for the estimation of the time weighted average temperatures for the various surveillance capsules. It is to be noted that several of the inputs used in this report have been superseded by more recent reports based on the availability of new data (such as re-evaluation of capsule reports and updated fluence calculations).

The measured chemistries for the surveillance capsule materials were obtained from the respective surveillance capsule reports that contain the weld heat No. W5214. Fluence data that were historically used in previous reports and submittals were also obtained from the respective capsule reports. More recent fluence values for the surveillance capsules were obtained from an updated fluence calculation by Westinghouse [ 18]. It is to be noted that

.even though the design inputs used in this capsule re-evaluation may be available in more than one source, the roadmap points to specific references in order to use the most current and valid inputs in the analysis.

C-'

Report No. 0901132.40 1, Rev. 0 1-2 R StructuralIntegrity Associates, Inc.

Table I-1. Listing of Design Inputs and References Used Flunce Regulatory Time Weighted SI Calculation Report Chemistry CVN Data Reference Reference No. Description Factor Methodology Fluence Documents!Codes Average Package Temperature BAW-2398 14 Palisades capsule SA- X 240-1 BAW-234! Palisades capsule SA-60-1 x J.Kneeland Letter Dated 16 Palisades Unirradiated x Feb 2.1999 WCAP-7373 27 H.B.Robinson Unirtadiated WCAP-15905 12 HBR2 Capsule X X X X SwRIl Project No. 17-2108 6 IP 2 Capsule V X X X WCAP-7323 9 1P 2 Uniiradiated X SwRd Project No 02-5212 7 IP 2 Capsule Y X

-WCAP-16251-NP 13 IP 3 Capsule X X X X WCAP-8475 9 IP 3 Unirradiated X WC.AP-9491 10 IP 3 Capsule T X WCAP-10300 II IP 3 Capsule Y X N. Haskel (Palisades) 26 Palisades RAI X Letter to NRC WCAP-15353, Rev 0 3:34 Palisades FluenceX Evaluation Email from S. Anderson Revised luence Values (Westinghous e) to Tim is for Design Inputs to X Griesbach (SLU_): PTS Evaluation 04/1512010 Fluence evaluation and N. Hood S. (NRC) Letter to I schedule for reaching X N. Haskall (P*alisades) PTS Screening Criteria Report No. 0901132.401, Rev. 0 1-3 R StructuralIntegrity Associates, Inc.

Table I-1. Listing of Design Inputs and References Used (cont.)

Report Chemisry T.-AN11 Regulatory Time Weighted SI Calculation RReference eference No. Description CAN Data Package Factor Methodology Documents/Codes Average Temperature Neutron Fluence CAPL-01-009 n7alysis for Palisades Surveillance Capsule SA-240-1 CENPSD-1119 20 CEOG C* Ni Chemitstries ASTM E-185-66 22 Sumreidlance Testing X x M_ A- .icksonKixrk etaL CVN Data Fitting Journal of Pressure Vessel 25 Methodoltog X Technology, v. 131. 2009 CVGRPH-XPI 5 4 Software program to fit x CVN Data ICFR50.61 2 PTS Rule X Reg Guide1.1190 5 Fluence Calculation Methodology Generic Letter 912-01 19 R.PV Integrity eAssessment 'VWorkshop AS.E Section I11 21 Boiler and Pressure Vessel Code Irradiation Data for NUREG/CR-64 IS. 2 -A302B and A533B ORNIJTM.. - 1313, Correlation Monitor Materials NRC R~D2 31 NRC Reactor Vessel Integrity Database FCX-OOS 29 IP2 Vessel Head Temperature 1P3-CALC-RV-03720 30 IP3 VesseHeadx Temperature Evaluations of C'NS-04-02-0I, Rev'.1 28 Palisades RPV Throxigh Period of Extended x Operation Cycle I - 12 EFPD for LAR of 2-21-2000 23 Time Weighted EA-DOR-09-01 Rev, 0 Average Temperature

.-Calculation Detennination of AT_0 0901132.301, Rev. 0 32 Values for the Heat No. X VW5214 Verification of the Time-090!1!32.3302. Re v. 0 3 Weighted Average x Temperatures for L-2 and IP3 Capsules Report No. 0901132.401, Rev. 0 1-4 V StructuralIntegrityAssociates, Inc.

ML110060693

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1.0 INTRODUCTION

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8.0 REFERENCES

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