ML110060694

Attachment 2, Structural Integrity Associates, Inc., Report No. 1000915.401, Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel

ML110060694
Person / Time
Site:	Palisades
Issue date:	11/12/2010
From:	Griesbach T, Marthandam V Entergy Nuclear Palisades, Structural Integrity Associates
To:	Office of Nuclear Reactor Regulation
References
1000915.401
Download: ML110060694 (145)

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{{#Wiki_filter:ATTACHMENT 2 STRUCTURAL INTEGRITY ASSOCIATES, INC. REPORT NO. 1000915.401 REVISED PRESSURIZED THERMAL SHOCK EVALUATION FOR THE PALISADES REACTOR PRESSURE VESSEL 144 pages follow

Report No.: 1000915.401 Revision No.: 1 Project No.: 1000915 November 2010 Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel Preparedfor: Entergy Nuclear Corp. Palisades Nuclear Power Plant Covert, Michigan Preparedby.- Structural Integrity Associates, Inc. San Jose, California Preparedby: Date: 11/12/10 Timothy J. Griesbach Preparedby: Date: 11/12/10 Vikram Marthandam Reviewed by: Date: 11/12/10 Danen Heath Approved by: ec4Li4 Date: 11/12/10 Timothy J. Griesbach StructuralIntegrityAssociates, Inc.

REVISION CONTROL SHEET Document Number: 1000915.401

Title:

Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel Client: Entergy Nuclear Corp. SI Project Number: 1000915 Quality Program: E] Nuclear RI Commercial Section Pages Revision Date Comments All 1- 29 0 10/30/2010 Initial Issue Appendix A Appendix B Appendix C Pages 3, 9, 1 11/12/2010 Fixed typo and added one capsule data 10,20 point for plate heat no. C-1279 and 28 V StructuralIntegrity Associates, Inc.

EXECUTIVE

SUMMARY

This updated analysis was performed to review the previous Pressurized Thermal Shock (PTS) evaluation for Palisades and incorporate new data and information that could affect the date to reach the PTS screening limit in 10CFR50.61. 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 additional surveillance capsules containing weld data matching the Palisades vessel beltline materials. This report examines the updated fluence calculations performed by Westinghouse and all known surveillance data relevant to the Palisades reactor pressure vessel weld heat numbers W5214 and 27204. The scope of this new evaluation includes all of the materials located in the Palisades reactor vessel beltline region. This report is an extension of the earlier Structural Integrity Associates Report that only evaluated weld heat No. W5214 [5]. Using the revised fluences and chemistry factors based on the refitted surveillance data for limiting weld heat No. W5214, 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. Revised chemistry factors based on surveillance capsule results were also calculated for weld heat No. 27204 and plate heat No. C-1279. This further evaluation of PTS confirms that the limiting vessel beltline material in the Palisades reactor vessel for evaluation of PTS remains the axial weld heat No. W5214. Report No. 1000915.401, Rev. 1 i Structural IntegrityAssociates, Inc.

Table of Contents 1.0 IN TR O DU C TION ...................................................................................................... 1 2.0 TECHN ICAL APPROA CH ...................................................................................... 2 3.0 RTPTS CALCULATION METHOD ................................... 3 4.0 FLUENCE PROJECTIONS AND FLUENCE METHODOLOGY ............. 4 5.0 REVISED VESSEL MATERIAL PROPERTIES ...................................................... 5 5.1 W eld H eat N o. W 5214 ............................................................................................... 5 5.1.1 Surveillance Datafor Weld Heat No. W5214 ............................................................. 6 5.2 W eld Heat No. 27204 ............................................................................. 7 5.2.1 Surveillance Datafor Weld Heat No. 27204............................................................. 7 5.3 W eld H eat N o. 34B 009 ............................................................................................... 8 5.3.1 Surveillance Datafor Weld Heat No. 34B009 ......................................................... 9 5.4 V essel Beltline Plate Materials ................................................................................... 9 6.0 D ISC U SSIO N ..................................................... ............................................ 10

7.0 CONCLUSION

S ............................................... 11..... 1 8.0 REFER EN C E S ........................................................................................................ 12 APPENDIX A DATA CREDIBILITY ASSESSMENT FOR WELD HEAT NO. 27204 ... A-i APPENDIX B SURVEILLANCE CAPSULE DATA FOR WELD HEAT NO. 27204 ......... B-1 APPENDIX C SURVEILLANCE CAPSULE DATA FOR PLATE HEAT NO. C-1279 ...... C-1 Report No. 1000915.401, Rev. 1 ii StructuralIntegrity Associates, Inc.

List of Tables Table 1: Palisades Vessel Beltline Material Properties on Operating License Expiration Date (3 /2 4 /1 1) ............................................................................................................................. 15 Table 2. Original Estimated Date for Weld Heat No. W5214 to Reach PTS Screening Criterion Lim it (RTpTs = 270'F) ................................................................................... 15 Table 3. Calculated Clad-to-Base Metal Interface Fluence in Palisades Vessel .......................... 16 Table 4. Calculated Fluence at End of License Renewal Date (March 24, 2031) ........................ 17 Table 5. Evaluation of all Surveillance Capsule Results Containing Weld Heat No. W5214 ........ 18 Table 6. Evaluation of Surveillance Capsule Results Containing Weld Heat No. 27204 ............ 19 Table 7. Weight Percent Nickel in Heat 34B009 Welds ............................................... 19 Table 8. Evaluation of Surveillance Capsule Results Containing Plate Heat No. C-1279 ....... 20 Table 9. Calculation of PTS Limit Date Based on Limiting Fluence for Axial W eld Heat No. W 5214 @ 60' Location ........................................................................ 21 Table 10. Palisades Vessel Beltline Material Properties on Extended Operating License Expiration D ate (3/24/31) ............................................................................................. 22 Table 11. Revised Estimated Date for Weld Heat No. W5214 to Reach PTS Screening Criterion Lim it (RTpTS = 270 0 F) ................................................................................... 23 Table 12. Revised Estimated Date for Weld Heat No. 27204 to Reach PTS Screening Criterion Lim it (RTPTS = 300°F) ................................................................................. 23 Table A-1. Evaluation of Palisades Surveillance Data Results for Weld Heat No. 27204 ............ A-4 Table A-2. Evaluation of all Surveillance Capsule Results Containing Weld Heat No. 27204 .... A-6 Table A-3. History of Time-Weighted Operating Temperature for Palisades ............................... A-7 Table A-4. Correlation Monitor Material HSST Plate 02 Calculation of Fitted CF ...................... A-8 Table A-5. Correlation Monitor Material HSST Plate 02 Calculation of Measured - Predicted Scatter ...................................... A-9 Report No. 1000915.401, Rev. 1 iii StructuralIntegrity Associates, Inc.

List of Figures Figure 1. Projected Fluence at Limiting Vessel Axial Weld (600) Using Previous Palisades V essel Fluence C alculation ......................................................................................... 24 Figure 2. Best Fit for all W5214 Surveillance Data with Revised Fluence and Refitted Shift ......... 25 Figure 3. Best Fit for Palisades Weld Heat No. 27204 Surveillance Data ................................... 26 Figure 4. Best Fit for all Weld Heat No. 27204 Surveillance Data ........................................... 27 Figure 5. Best Fit for all Base Metal Heat No. C-1279 Surveillance Data ................................. 28 Figure 6. 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 ....................................... 29 Report No. 1000915.401, Rev. 1 iv StructuralIntegrityAssociates, Inc.

1.0 INTRODUCTION

The PTS Rule in 10CFR50.61. [1] specifies that all PWRs must monitor the reactor vessel beltline materials for comparison to the PTS screening criteria limits of 270'F for axial weld and base metal, and 300'F for circumferential welds. 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 [2]. These inputs to the PTS Rule equations were used to calculate RTPTS, and the Palisades vessel was projected to reach the screening criterion limit of 270'F for the limiting axial weld (heat no. W5214) 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 beitline material. This evaluation is being performed as a part of Palisades' TLAA process under 10 CFR 54.21 (c)(1)(iii) for the NRC approved license renewal application. The PTS Rule establishes the following requirements for'all domestic, operating PWRs:

    " All plants must submit projected values of RTPTS for reactor vessel beltline materials. The PTS submittal must be updated whenever there are changes in core loadings, surveillance measurements or other information that indicates a significant change in.projected RTPTS values.
   "    The submittal must include the following:

1: The basis for the projection (including assumptions regarding core loading pattern)

2. Copper and nickel content and fluence values used in the calculations for each of the vessel beltline materials (if those values differ from those previously submitted to the NRC, justification must be provided).

• All values of RTPTS must be verified to be bounding values for the specific reactor vessel.

In doing so, each plant should consider plant-specific information that could affect the level of embrittlement. Report No. 1000915.401, Rev. 1 1 StructuralIntegrity Associates, Inc.

The PTS Rule provides two methods for calculating the adjusted reference temperature of the reactor vessel beltline materials. The first method is described in 10CFR50.61, paragraph (c)(1) and uses the copper and nickel chemistry to determine a chemistry factor. The second method is described in 10CFR50.61, paragraphs (c)(2) and (c)(3), for use of surveillance data. These procedures can only be applied when two or more credible data sets become available. Both methods have been used to update the PTPTS values for the Palisades vessel. 2.0 TECHNICAL APPROACH Pressurized Thermal Shock (PTS) is a condition that could challenge the integrity of the reactor pressure vessel (RPV). PTS may occur during a severe transient such as a Loss of Coolant Accident (LOCA) or a steam line break. Such transients can challenge the RPV integrity under the following conditions:

• Severe overcooling of the inner surface of the RPV followed by high repressurization Radiation embrittlement of RPV materials causing a shift in the nil-ductility reference temperature and a decrease in the fracture toughness as measured by the material parameter RTPTS.
• Presence of a flaw/defect of a critical size in the vessel wall The RTPTS values obtained from this evaluation are compared against the PTS screening limits for plates, forgings and axial welds, and circumferential welds to justify the continued operation until the End-of-Life-Extended (EOLE) fluence is achieved. The PTS screening criterion is 270'F for
• plates, forgings, and axial weld materials, and 300'F for circumferential weld materials.

The materials used to fabricate the Palisades vessel, the associated best-estimate copper (Cu) and nickel (Ni) chemistries, the corresponding chemistry factors as well as the method used to calculate the chemistry factor, and the corresponding RTpTs values from the previous PTS submittal [2] are documented in Table 1 for the current operating license expiration date (March 24, 2011). The estimated date to reach the PTS screening criteria limit was previously determined to be January 2014, as shown in Table 2. This date has been reevaluated using updated fluence and materials data to determine revised projections to reach the PTS screening Report No. 1000915.401, Rev. 1 2 I StructuralIntegrityAssociates, Inc.

criteria limit. The guidance provided by the NRC Staff for the use of surveillance capsule data for determining chemistry factors (as published in Reference 6) has been implemented in this evaluation. 3.0 RTPTS CALCULATION METHOD RTpTs must be calculated for each beltline material using a fluence value,f, which is the EOLE fluence for the material. RTPTs has been evaluated using the same procedures used to calculate RTNDT, as indicated in paragraph (c)(1) of Reference 1, except that the fluence values at the clad/base metal interface is used instead of the 1/4T fluence. The RTPTS is evaluated using the following equation: RTpTs = RTNDT(U) + M + ARTPTS (1) ARTpTS = CF x FF (2) where: RTNDT(U) = Reference temperature of nil ductility transition for the unirradiated material M = Margin term to cover for uncertainties in the value of initial RTNDT and the scatter in the shift Margin=2* U1 (3) a]= the standard deviation for the initial RTNDT (OF). For non-Linde 80 type welds, if a generic initial RTNDT value is used, o7 = 17'F, if a measured value is used for the initial RTNDT, cl = 00 F 0:4 = the standard deviation'for ARTNDT (OF). The values for GA are 28°F for welds and 17' for base metal (plates or forgings) ARTpTs = the mean value of the transition temperature shift due to irradiation, and 28 FF = fluence factor fo. -0.10 og (f) Report No. 1000915.401, Rev. 1 3 StructuralIntegrityAssociates, Inc.

where: 2# f = Neutron fluence, in units of 1019 n/cm 2 (E > 1 MeV), at the clad/base metal interface, and CF = Chemistry factor in 'F, which is a function of the copper and nickel content, obtained from either the tables or a fitted CF value from surveillance data. 10 CFR 50.61 [1] states that GA need not exceed 0.5 times the mean reference temperature shift (0.5* ARTNDT), or the standard value of (A of 28 'F for welds and 17 'F for base metal (plates or forgings), whichever is lower. Note: the margin term, M, may be reduced by half if credit is obtained for credible surveillance data. 4.0 FLUENCE PROJECTIONS AND FLUENCE METHODOLOGY Westinghouse performed a detailed fluence evaluation of the Palisades vessel in 2000 [3]. This previous evaluation determined that the peak fluence at the clad-to-base-metal interface at the 60' location of the limiting axial weld was 1.158x10' 9 n/cm 2 (E > 1 MeV) at the end of Cycle 14 (i.e., October 1999). That evaluation provided the basis for fluence projections in the vessel through the end of license (EOL) period of March 24, 2011. A linear projection of fluence beyond EOL showed that the Palisades vessel could operate within the PTS screening criteria limit through January 2014 (as shown in Figure 1). Since December 1999, the Palisades plant has been operating with an Ultra-Low Leakage core strategy and stainless steel shielding of the limiting vessel weld at 60' azimuthal angle. The reactor vessel fluence reduction associated with the Ultra-Low Leakage core design requires that the flux suppression assemblies be loaded in specific core design locations and oriented with the stainless steel rods facing the reactor vessel. This configuration has been maintained to minimize flux at the limiting vessel weld location. It was observed that the flux at the limiting weld location may vary slightly from cycle to cycle because of limitations in the core loading patterns for each fuel reload. Recognizing that the flux and operating history of the Palisades plant may have changed over the years from the earlier projections, Westinghouse performed an updated fluence assessment for the Palisades vessel beltline region in 2010 [4]. This revised fluence evaluation provided an updated fluence assessment for the vessel beltline region that included cycle specific analyses for known core configuration through operating Report No. 1000915.401, Rev. 1 4 StructuralIntegrity Associates, Inc.

Cycles 15 through 21, and projections for future operation based on the best available knowledge as a function of EFPY. The calculated and projected neutron fluence values for the limiting 60' weld location and the peak (750) fluence location are given in Table 3 [4]. The projected fluence values at the EOLE date of March 24, 2031 is shown in Table 4. Note: the cycle specific projections for the designs of Cycle 21 and beyond were provided by Entergy and include an assumed load factor of 95% for future plant operation. The calculated fluences in the vessel were interpolated to determine the limiting axial weld and peak (600 and 750) fluences for the end of license renewal date of March 24, 2031 as shown in Table 4. 5.0 REVISED VESSEL MATERIAL PROPERTIES The Palisades reactor vessel consists of the following beltline region materials [2, 20]: 0 Intermediate Shell, Axial Welds 2-112 A/B/C, material heat No. W5214, 0 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,
• 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.

5.1 Weld Heat No. W,5214 Weld heat no. W5214 was used in the intermediate shell axial welds 2/112A/B/C. The limiting vessel beltline material for PTS was determined to be the welds made from weld heat No. W5214 at the 60' azimuthal location [2]. Previously this weld was projected to reach the PTS screening criterion in January 2014, before any other beltline region material. This determination considered the fluence analysis and relevant surveillance data available at that time. In particular, seven surveillance capsules containing weld heat No. W5214 were evaluated, the data fitted to determine Report No. 1000915.401, Rev. 1 5 StructuralIntegrity Associates, Inc.

a revised CF value. However, the previous results were not used to adjust the RTPTS value because the data were deemed to be non-credible [12]. A more accurate determination of the vessel beltline materials was recently performed to consider additional surveillance data, revised fluences, and other available information that could improve the embrittlement predictions for the limiting weld material. A more complete evaluation of the surveillance data for weld heat no. W5214 is given in Reference 5. The results of that study are summarized here. 5.1.1 Surveillance Datafor Weld Heat No. W5214 Surveillance capsule data from eleven capsule reports were found to contain this weld heat. These data were obtained from ( the Palisades supplemental capsules, and additional data from H. B. Robinson 2, Indian Point Unit 2, and Indian Point Unit 3 was evaluated using the credibility requirements in 10CFR50.61. The NRC guidance for evaluation and use of other plant's surveillance data is contained in Reference 6. The data were adjusted to account for difference in .specimen chemistry and plant operating temperatures, and the irradiated Charpy shift results were fitted using the least squares fit relation given in Equation (4) [6].

                                       ~[A,~    (O-0"w o CFP =  M     ,                                                      (4)

I"' where "n" = the number of surveillance data points, "Ai" = the measured value of AT 30 from the Charpy specimens, and "fi" = the fluence for each surveillance capsule data point. The results of this evaluation are given in Table 5 and the results are plotted in Figure 2. It is noted that the fitted CF value = 227.74°F for weld heat no. W5214. Further analyses based on Palisades surveillance data only showed that the two plant-specific data points yield a lower CF value with a scatter from a mean fit less than 28°F (i.e., within the range for credible data); however, these results for weld heat No. W5214 have not been credited since all surveillance data were used to develop a revised CF value as given above. Report No. 1000915.401, Rev. 1 6 V StructuralIntegrity Associates, Inc.

5.2 Weld Heat No. 27204 In the September 1998 RAI response [12], the best estimate chemistry for weld heat No. 27204 was reevaluated. A study performed by the Combustion Engineering Owners Group (CEOG), CE NPSD-1039, Rev. 02 [7], determined the best estimate chemistry values of 0.203% Cu and 1.018% Ni for welds fabricated with weld wire heat number 27204. Given that the values reported in CE NPSD-1039, Rev. 02 are comparable to those that had been calculated previouisly, it was concluded the best estimate chemistry for the Palisades reactor vessel beltline welds fabricated with weld wire heat number 27204 is 0.203% Cu and 1.018% Ni as reported in CE NPSD-1039, Rev. 02. Using Table 1 in. OCFR50.61, a chemistry factor (CF) of 226.8°F was determined based on the best estimate chemistry for the surveillance data for Weld Heat No. 27204. 5.2.1 Surveillance Datafor. Weld HeatNo. 27204 The previous analysis of surveillance data for weld heat No. 27204 [12] included only two capsule data points from Diablo Canyon Unit 1, Capsule S [8] and Capsule Y [9]. That analysis performed a least-squares fit to the surveillance data results and determined the data to not be credible because the scatter exceeded the allowable scatter for credible surveillance data (i.e., lcy > 28°F). Since then, two new data surveillance data points were obtained from the Palisades supplemental capsules SA-60-1 [10] and SA-240-1 [11] and one from Diablo Canyon Unit 1, Capsule V [25]. The surveillance data results for the capsules containing weld heat No. 27204 are shown in Appendix B. It is noted that the Charpy V-notch test data had been fitted with the TANH function to determine the AT 30, or RTNDT shift values. The measured RTNDT shift values from the fitted surveillance capsules were considered for projection of embrittlement in the Palisades vessel weld. The two (2) surveillance capsules from Palisades were found to be credible. The Palisades supplemental surveillance data were combined with the Diablo Canyon 1 surveillance data and the results are shown in Table 6. The analysis of the surveillance data was performed using Case 4 of the NRC guidance, "Surveillance Data from Plant and Other Sources" [6]. Adjustments were made to the measured shift values to account for chemistry differences and temperature differences between the capsules and the vessel, as shown in Table 6. The irradiation temperatures for the Diablo Canyon Unit 1 capsules were Report No. 1000915.40 1, Rev. 1 7 StructuralIntegrityAssociates, Inc.

obtained from Reference 27, Using the least-squares fitting method in Eq. (4), a fitted CF value of 216.13'F was obtained for weld heat No. 27204 for application to the Palisades circumferential weld, 9-112. A discussion of data credibility for weld heat No. 27204 is given in Appendix A. A plot of all the capsule data for weld heat No. 27204 is shown in Figure 4 along with the 1-sigma (28°F) scatter bound for weld materials. These additional surveillance capsule data were included for completeness. As a result, the (measured - predicted) scatter for the surveillance data was found to fall within the 28°F band rendering the data to be credible and applicable to improve the projected RTPTS value for the circumferential weld by taking advantage for the reduced margin term, as discussed in Appendix B. 5.3 Weld Heat No. 34B009 The technical basis for the weld heat No. 34B009 material properties has been reviewed and no changes are proposed. This technical basis has been reviewed and approved by the NRC as a part of the Palisades Safety Evaluation Report [20]. In examining the basis, it was noted that CE NPSD-1039, Rev. 02 specifies best estimate values of 0.192% Cu and 1.038% Ni for weld fabricated with weld wire heat No. 34B009 [7]. In the submittal dated September 8, 1998, it was determined that a copper value of 0.192% is the best estimate value for the welds made from heat No. 34B009 in the Palisades vessel [12]. However, it was also determined at that time that the best estimate chemistry value for nickel recommended in CE NPSD-1039, Rev. 02 for nickel addition welds could not be endorsed for the Palisades vessel welds. The value of 1.038% Ni was determined by finding the mean of 144 nickel measurements. It was noted that 45 of those measurements were from the retired Palisades steam generators, and the calculated mean was dominated heavily by just two welds. A new evaluation of the nickel content using a coil-weighted average was performed by the CEOG in "Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best Estimate Copper and Nickel Content," CE NPSD-1 119, Revision 01, July 1998 [13]. The best estimate value of 1.007% nickel derived using a sample weighted mean was considered a technically superior approach to that used in CE NPSD-1039, Rev. 02. Further studies were performed after the CEOG work was completed in order to establish the best estimate nickel value to be used for this weld in the Palisades vessel. These were described in Reference 14. 10CFR50.61(c)(1)(iv)(A) states "For a weld, the best Report No. 1000915.401, Rev. 1 8 StructuralIntegrity Associates, Inc.

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." The concept of determining the best estimate nickel from all nickel addition welds made from the same heat is a reasonable technical assumption. The multiple measurements of nickel from samples of weld heat No. 34B009 were averaged (i.e., average of the averages) to obtain the mean nickel value, as shown in Table 7 [14]. Therefore, the best estimate value of 0.98% Ni reported in the December 20, 1995 and November 17, 1995 submittals [14, 15] is considered more representative of the best estimate for nickel provided in CE NPSD- 1119, Rev. 01. It was concluded that the best estimate chemistry for the Palisades reactor vessel beltline welds fabricated with weld wire heat No. 34B009 (with nickel addition) is 0.192% Cu and 0.98% Ni. Using Table 1 in 10CFR50.61, a chemistry factor (CF) of 217.71F was determined based on the best estimate chemistry for this weld. Thus, there is no change from the previously reported values for this weld. 5.3.1 SurveillanceDatafor Weld Heat No. 34B009 The only surveillance program results known to contain weld wire heat No. 34B009 are from the Millstone 1 reactor vessel. These data were evaluated previously and found to not have relevance to Palisades because Millstone 1 is a Boiling Water Reactor [12]. No further analysis of the surveillance data for this weld heat was performed. 5.4 Vessel Beltline Plate Materials The reported copper and nickel chemistry values and calculated chemistry factors for the beltline plates are shown in Table 1. There is no additional capsule data for the Palisades vessel beltline plate materials. However, there is new fluence data for the Palisades surveillance capsules containing the surveillance plate heat No. C-1279. The Palisades surveillance capsules containing base metal include A-240 [21], W-290 [22], W-110 [23], and W-100 [26]. The Charpy test results and the evaluated AT30 shift values from these capsule test reports are given in Appendix C. Updated surveillance capsule fluence values were obtained from WCAP-15353, Supplement 1 [4], and the least-squares fit to the data using the revised fluence values is given in Table 8. The least-squares fit to these data is determined to be CF = 147.71OF,'and a plot of the Report No. 1000915.401, Rev. 1 9 V StructuralIntegrity Associates, Inc.

data and fitted results is given in Figure 5. However, it is observed that three data points fall outside the 1-sigma bound and one data point falls outside the 2-sigma bound for plate materials and, therefore, the data were determined to not be credible and a fitted CF value should not be used for projections of the vessel RTPTS for the beltline plates with the same heat number. The projection of RTprs for the vessel beltline plates made from plate heat No. C-1279 used a CF value of 157.5°F (from the Reg. Guide 1.99, Rev. 2 tables) and a full margin term of 34°F. 6.0 DISCUSSION Additional surveillance capsule data and fluence calculations were considered that could affect the projection of embrittlement in the Palisades vessel beltline materials. The results have been evaluated to determine the effect on the date to reach the PTS screening criteria limit for the materials with the highest RTPTs values. These are the axial weld heat No. W5214 at the 60'F azimuthal locations, and weld heat No. 27204 with a peak fluence at the 750 azimuthal location. The projected date for the limiting axial weld to reach the PTS screening criteron limit of 270'F is shown in Table 9 based on a maximum fluence for this locations of 1.685x10' 9 n/cm 2 . The date to reach this limit is April 2017, as has been confirmed by the evaluation of surveillance data for weld heat No. W5214 in Reference 5. The next closest material to the PTS screening criterion is axial weld heat No. 34B009. For the circumferential weld heat No. 27204, using a fitted CF value of 216.13'F based on surveillance data with a 1-sigma margin term (i.e., 44°F) and revised projections of fluence in the vessel [4], the maximum fluence for the circumferential weld to remain below the PTS screening criterion limit of 300'F is determined to be 6.24x10'9 n/cm 2 (see Table 12). Table 10 shows the updated RTPTS values for all the vessel beltline materials at the EOLE date of March 24, 2031, including use of best available data and revised fluence calculations for the Palisades reactor pressure vessel. Table 11 shows how the maximum fluence value for the axial weld at the 600 location was determined. Similarly, Table 12 gives the details for estimating the maximum (peak) fluence in the circumferential weld at the 75' location. New data has been included for the Palisades vessel beltline materials, and the results shown in Table 10 confirm that the limiting vessel beltline material for PTS is the axial weld made from heat No. W5214. This analysis provides the basis to assure that the Palisades vessel remains below the limits defined in 10CFR50.61 through April 2017 or beyond. Report No. 1000915.401, Rev. 1 10 StructuralIntegrity Associates, Inc.

7.0 CONCLUSION

S The results for all available surveillance capsules have been evaluated for applicability to the Palisades limiting vessel welds. A thorough examination of the use of surveillance data for weld heat No. W5214 was previously performed for the limiting axial welds [5]: The results of that study have been confirmed to be the applicable for the limiting beltline material since the other weld and base materials would not overtake this 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. Reference 5 showed that by using Position 1 of the PTS Rule (without the use of surveillance data), the projected date to reach the PTS screening criteria limit would be as late as July 2014. To summarize the results from Reference 5, use of the weld heat No. W5214 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 for RTPTS using the Palisades supplemental surveillance data show that the PTS screening criteria limit of 270'F would not be reached until after 2034 if the data were fully credible; however, other vessel beltline materials would become limiting and that would change that date. By comparison, considering an evaluation of the surveillance data available from the plant and other sources, the surveillance data results 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. Using all the available weld heat No. W5214 surveillance data, a CF value of 227.74°F was determined for limiting axial weld and a projected date to reach the screening criteria limit of approximately April 2017 (or later) was estimated. The other vessel beltline materials have been shown to be less sensitive to neutron irradiation effects, so the April 2017 date is the revised projected RTPTS limiting date for the Palisades vessel to stay below the screening criteria limits in 10CFR50.61. Palisades plans to inspect the reactor vessel beltline region in 2012, following which, the results of the NDE will be used to perform a new PTS evaluation to ensure that the reference toughness values per 10CFR50.61 a [24] are satisfied throughout the period of extended operation. Report No. 1000915.401, Rev. 1 11 StructuralIntegrity Associates, Inc.

8.0 REFERENCES

1. Code of Federal Regulations, Title 10, Part 503 Section 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," U. S.

Nuclear Regulatory Commission. (SI File No. 0901025.201).

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

Reactor 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).

3. "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation," WCAP-15353, Rev.

0, January, 2000 (SI File No. 0901025.203).

4. "Palisades Reactor, Pressure Vessel Neutron Fluence Evaluation," WCAP-15353-Supplement 1-NP, May, 2010 (SI File No. 1000915.211).

5. "Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis," SI Report No. 0901132.402, Rev. 0, April 2010.

6. "Generic Letter 92-0 Vand RPV Integrity Assessment," NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. (SI File No. 0901132.213).

7. "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds,"

CE NPSD-1039, Rev. 02, Combustion Engineering Owners Group, June 1997. (SI File No. 1000915.202)

8. Westinghouse Report, WCAP-1 1567, "Analysis of Capsule S from the Pacific Gas and Electric Company Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program," December 1987. (SI File No. 1000915.209)

9. Westinghouse Report, WCAP-13750, "Analysis of Capsule Y from the Pacific Gas and Electric Company Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program," July 1993. (SI File No. 1000915.210)

10. Framatome ANP Report, "Test Results of Capsule SA-60-1 Consumers Energy Palisades Nuclear Plant - Reactor Vessel Material Surveillance Program," BAW-2341, Revision 2, May 2001. (SI File No. 0901132.210).

Report No. 1000915.401, Rev. 1 12 j StructuralIntegrity Associates, Inc.

11. 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).

12. 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)

13. "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)

14. Smedley (Consumers Energy) to NRC, "Docket 50-255-License DPR-20 -Palisades Plant Response to NRC Generic Letter 92-01, Revision 1, Supplement 1: Reactor Vessel Structural Integrity," November 17, 1995. (SI File No. 1000915.212)

15. Smedley (Consumers Energy) to NRC, "Docket 50-255-License DPR-20 -Palisades Plant Response to NRC Generic Letter 92-01, Revision 1, Supplement 1: Reactor

     '-Vessel Structural Integrity - Correction of Typographical Errors," December 20, 1995.

(SI File No. 1000915.213)

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

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

18. 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, April 15, 2010. (SI File No. 0901132.224)

19. 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. (SI File No. 1000915.215)

20. "Evaluation of Palisades Nuclear Plant Reactor Pressure Vessel Through the Period of Extended Operation,"-Constellation Nuclear Services Report, CNS-04-02-01, Rev. 1, June 2004. (SI File No. 0901132.219) r Report No. 1000915.401, Rev. 1 13 StructuralIntegrity Associates, Inc.

21. Perrin, J. S., et al., "Palisades Nuclear Plant Reactor Pressure Vessel Surveillance Program Capsule A-240," BCL-585-12, March 13, 1979. (SI File No. 1000915.216)

22. Kunka, M. K., Cheney, C. A., "Analysis of Capsules T-330 and W-290 from the Consumers Power Company Palisades Reactor Vessel Radiation Surveillance Program," WCAP-10637, September 1984. (SI File No. 1000915.217)

23. Peter, P. A., et al., "Analysis of Capsule W-1 10 from the Consumers Power Company Palisades Reactor Vessel Radiation Surveillance Program," WCAP-14014. (SI File No.

1000915.218)

24. Federal Register/ Vol. 75, No. 1/ Monday, January 4, 20 10/ Rules and Regulations, 10 CFR Part 50, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."

25. Westinghouse Report WCAP-15958, Revision 0, "Analysis of Capsule V from Pacific Gas and Electric Company Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program," January 2003. (SI File No. 1000915.219).

26. BWXT Services Report No. 1295-001-03-08:00, "Analysis of Capsule W-100 from the Nuclear Management Company Palisades Reactor Vessel Material Surveillance Program," February 2004. (SI File No. 1000915.220).

27. Westinghouse Letter Report No. CPAL-10-34 Dated October 15, 2010, "Westinghouse Review of Structural Integrity Associates Reports on Pressurized Thermal Shock for Palisades." (SI File No. 1000915.221).

Report No. 1000915.401, Rev. 1 14 StructuralIntegrity Associates, Inc.

Table 1: Palisades Vessel Beltline Material Properties on Operating License Expiration Date (3/24/11) (from Ref. 2) Surface CF Fluence RTNDT(U) RTNDT Shift Margin RTPTS Cu% Ni% (OF) (E19) FF (OF) (OF) (OF) (OF) RPV Material Heat No. Axial Weld 2-112A/B/C W5214 0.213 1.01 231.08 1.492 1.111 -56 256.7 65.5 266 W5214 0.213 1.01 231.08 1.492 1.111 -56 256.7 65.5 266 Axial Weld 3-112A/B/C 34B009 0.192 0.98 217.7 1.492 1.111 -56 241.8 65.5 251 Circ Weld 9-112 27204 0.203 1.018 226.8 2.061 1.197 -56 271.5 65.5 2_81 Plate D-3803-1 C-1279 0.24 0.50 153.3 2.061 1.197 -5 183.5 17 195 Plate D-3803-2 A-0313 0.24 0.52 160.4 2.061 1.197 -30 192.0 34 196 Plate D-3803-3 C-1279 0.24 0.50 153.3 2.061 1.197 -5 183.5 17 i95 Plate D-3804-1 C-1308A 0.19 0.48 128.8 2.061 1.197 0 154.2 34 188 Plate D-3804-2 C-1308B 0.19 0.50 131 2.061 1.197 -30 156.8 34 161 Plate D-3804-3 B-5294 0.12 0.55 82 2.061 1.197 -25 98.2 34 107 Table 2. Original Estimated Date for Weld Heat No. W5214 to Reach PTS*Screening Criterion Limit (RTPTS = 2700 F)* CF Surface RTNDT(U) RTNDT Shift Margin RTPTs RPV Material Heat No. Cu% Ni% (F (E19) FF Axial Weld 3-112A/B/C W5214 0.213 1.007 231.08 1.584 1.127 -56 260.5 65.5 270

  *Limiting weld heat no. W5214 w/original projected fluence and CF (Estimated date to reach PTS screening criterion limit = January 2014) [2]

Report No. 1000915.401, Rev. 1 15 StructuralIntegrity Associates, Inc.

Table 3. Calculated Clad-to-Base Metal Interface Fluence in Palisades Vessel [4] End of Estimated Cumulative Fluence (n/cmA2, E > 1 MeV)* Fuel Calendar Time Cycle Date (EFPY) 600 750 21 10/2010 23.4 1.472E+19 2.157E+19 22 4/2012 24.7 1.520E+19 2.252E+19 23 10/2013 26.1 1.571E+19 2.345E+19 24 4/5/2015 27.4 1.619E+19 2.433E+19 25 10/2016 28.8 1.670E+19 2.527E+19 26 4/2018 30.2 1.721E+19 2.621E+19 27 10/2019 31.5 1.772E+19 2.714E+19 28 4/2021 32.9 1.823E+19 2.808E+19 29 10/2022 34.3 1.874E+19 2.902E+19 30 4/2024 35.7 1.925E+19 2.995E+19 31 10/2025 37.1 1.976E+19 3.089E+19 32 4/2027 38.4 2.027E+19 3.182E+19 33 10/2028 39.8 2.078E+19 3.276E+19 34 4/2030 41.2 2.129E+19 3.370E+19 35 10/2031 42.6 2.180E+19 3.463E+19 36 4/2033 44.0 2.231E+19 3.557E+19

                      *Source WCAP-15353-Supplement 1-NP, Rev. 0 [4]

Report No. 1000915.401, Rev. 1 16 StructuralIntegrityAssociates, Inc.

Table 4. Calculated Fluence at End of License Renewal Date (March 24, 2031) Estimated Fluence Axial at Weld* Peak Fluence*

                                                                         @5 Calendar Date                  ,          @75'
                                                     @60' End of Cycle 34         4/1/2030       2.129E+19           3.370E+19 Start of Cycle 35       5/1/2030       2.129E+19           3.370E+i9 6/1/2030       2.132E+19           3.375E+19 7/1/2030       2.135E+19           3.381E+19 8/1/2030       2.138E+19           3.386E+19 9/1/2030       2.141E+19           3.392E+19 10/1/2030       2.144E+19           3.397E+19 11/1/2030       2.147E+19           3.403E+19 12/1/2030       2.150E+19           3.408E+19 1/1/2031       2.153E+19           3.414E+19 2/1/2031       2.156E+19           3.419E+19 3/1/2031       2.159E+19           3.425E+19 EOLE Date          3/24/2031        2.161E+19           3.429E+19 4/1/2031        2.162E+19           3.430E+19 5/1/2031       2.165E+19           3.436E+19 6/1/2031       2.168E+19           3.441E+19 7/1/2031       2.171E+19           3.447E+19 8/1/2031       2.174E+19           3.452E+19 9/1/2031       2.177E+19           3.458E+19 End of Cycle 35        10/1/2031       2.180E+19           3.463E+19
                          *Source WCAP-15353-Supplement 1-NP, Rev. 0 [4]

Report No. 1000915.401, Rev. 1 17 StructuralIntegrityAssociates, Ind.

Table 5. Evaluation of all Surveillance Capsule Results Containing Weld Heat No. W5214 [51 Measured Ratio Chem. & Table Revised Fluence Irrad. (Refitted) Adjusted Temp. Adj. Predicted Adjusted-Capsule %Cu %Ni CF (F) Fluence Factor Temp. ARTndt ARTndt ARTndt ARTndt Predicted (n/cmA2) FF Ti (F) (F) (F) (F) (F) (F) SA-60-1 0.307 1.045 -266.5 1.50E+19 1.11 535 259 224.2 224.0 253.3 -29.27 SA-240-1 0.307 1.045 266.5 2.38E+19 1.23 535.7 280.1 242.5 243.0 281.0 -38.00 HB2T 0.34 0.66 217.7 3.87E+19 1.35 547 289.1 306.4 318.2 307.2 10.97 HB2V 0.34 0.66 217.7 5.30E+18 0.82 547 208.8 221.3 233.1 187.3 45.75 HB2X 0.34 0.66 217.7 4.49E+19 1.38 547 265.6 281.5 293.3 314.4 -21.14 IP2V 0.20 1.03 226.3 4.92E+18 0.80 524 197.5. 201.4 190.2 182.7 7.48 IP2Y 0.20 1.03 226.3 4.55E+18 0.78 529.1 193.9 197.7 191.6 177.8 13.77 IP3T 0.16 1.12 206.2 2.63E+18 0.64 539.4 149.8 167.6 171.8 145.0 26.81 IP3Y 0.16 1.12 206.2 6.92E+18 0.90 539.5 171.1 191.5 195.8 204.2 -8.48 IP3Z 0.16 1.12 206.2 1.04E+19 1.01 538.9 228.3 255.5 259.2 230.2 28.92 IP3X 0.16 1.12 206.2 8.74E+18 0.96 539.7- 192.5 215.4 219.9 219.1 0.76 Vessel Best Estimate CF = 230.73 Mean T= 535.2 I I I_____ Least Squares Fitted CF= 227.74 Report No. 1000915.401, Rev. 1 18 V StructuralIntegrity Associates, Inc.

Table 6. Evaluation of Surveillance Capsule Results Containing Weld Heat No. 27204 Ratio Chem. & Table Revised Fluence Irrad. Measured Adjusted Temp. Adj. Predicted Adjusted - Capsule %Cu %Ni CF (F) Fluence Factor Temp. ARTndt ARTndt ARTndt ARTndt Predicted (n/cmA2) FF Ti (F) (F) (F) (F) (F) (F) CAP Y(DCPP) 0.198 0.999 222.26 1.05E+19 1.01 542 232.59 237.3 244.1 219.1 25.06 CAPS (DCPP) 0.198 0.999 222.26 2.84E+18 0.66 544 110.79 113.1 121.9 141.8 -19.97 SA-240-1 (PNP) 0.194 1.067 227.8 2.38E+19 1.23 535.7 267.8 266.7 267.2 266.7 0.49 SA-60-1 (PNP) 0.194 1.067 227.8 1.50E+19 1.11 535 253.1 252.0 251.8 240.4 11.43 CAP V (DCPP) 0.198 0.999 222.26 1.37E+19 1.09 541.5 201.07 205.2 211.5 235.0 -23.56 Vessel Best Estimate CF = 226.8 Mean T = 535.2 _ Least Squares Fitted CF = 216.13 Table 7. Weight Percent Nickel in Heat 34B009 Welds [141 Sample Description Average Ni% Millstone 1 Surveillance Weld 1.05 H.B. Robinson 2 Torus-Dome Weld 0.80 Palisades Steam Generator Weld 1.09 Mean Value 0.98 Report No. 1000915.401, Rev. 1 19 V StructurIalIntegrityAssociates, Inc.

Table 8. Evaluation of Surveillance Capsule Results Containing Plate Heat No. C-1279 Capsule Measured Predicted Measured - Material I.D. Capsule fluence* FF ARTndt ARTndt Predicted (n/cm 2 ) (0 F) (OF) ARTndt (OF) D3803-1 (Longitudinal) A-240 [21] 4.09E+19 1.361 205.0 201.0 4.0 D3803-1 (Transverse) A-240 [21] 4.09E+19 1.361 205.0 201.0 4.0 D3803-1 (Longitudinal) ,W-290 [22] 9.38E+18 0.982 155.0 145.1 9.9 D3803-1 (Transverse) W-290 [221 9.38E+18 0.982 175.0 145.1 29.9 D3803-1 (Longitudinal) W-110 [23] 1.64E+19 1.136 180.0 167.9 12.1 D3803-1 (Transverse) W-100 [26] 2.09E+19 1.201 142.5 177.3 -34.8 D3803-1 (Longitudinal) W-100 [26] 2.09E+19 1.201 159.1 177.3 -18.2 Fitted CF = 147.71

      *Revised fluence values from WCAP-15353, Supplement 1-NP [4]

Report No. 1000915.401, Rev. 1 20 V StructuralIntegrityAssociates, Inc.

Table 9. Calculation of PTS Limit Date Based on Limiting Fluence for Axial Weld Heat No. W5214 @ 600 Location Neutron Date Fluence @ 60° 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 = 1.685x10' 9 n/cm 2 using revised fluence and W5214 surveillance data with fitted CF = 227.74°F and full (2-sigma) margin term Note: Further analyses based on Palisades surveillance data only showed that the date to reach the PTS screening limit could be beyond April 2017 [5]. However, these capsule results for weld heat No. W5214 have not been fully credited since all surveillance data were used to develop a revised CF but without a reduced margin term.

Report No. 1000915.401, Rev. 1 21 StructuralIntegrityAssociates, Inc.

Table 10: Palisades Vessel Beltline Material Properties on Extended Operating License Expiration Date (3/24/31) CF Surface RPV Material Heat No. Cu% Ni%F Fluence FF RTNDT(U) RTNDT Shift Margin RTpTs (OF) (E19) (OF) (OF) (OF) (OF) Axial Weld 2-112A/B/C W5214 0.213 1.007 227.74* 2.161 1.209 -56 275.4 65.5 284.9 W5214 0.213 1.007 227.74* 2.161 1.209 -56 275.4 65.5 284.9 Axial Weld 3-112A/B/C 34B009 0.192 0.98 217.7 2.161 1.209 -56 263.2 65.5 272.7 Circ Weld 9-112 27204 0.203 1.018 216.13* 3.429 1.322 -56 285.7 44 273.7 Plate D-3803-1 C-1279 0.24 0.50 157.5 3.429 1.322 -5 209.5 34 238.5 Plate D-3803-2 A-0313 0.24 0.52 160.4 3.429 1.322 -30 212.0 34 216.0 Plate D-3803-3 C-1279 0.24 0.50 157.5 3.429 1.322 -5 209.5 34 238.5 Plate D-3804-1 C-1308A 0.19 0.48 128.8 3.429 1.322 0 170.3 34 204.3 Plate D-3804-2 C-1308B 0.19 0.50 131 3.429 1.322 -30 173.2 34 177.2 Plate D-3804-3 B-5294 0.12 0.55 82 3.429 1.322 -25 108.4 34 117.4

• Fitted CF values based on use of plant-specific surveillance data from all available sources Report No. 1000915.4 01, Rev. 1 22 X *ruc Iural Integrity Assocites, Inc.

Table 11. Revised Estimated Date for Weld Heat No. W5214 to Reach PTS Screening Criterion Limit (RTPTS = 2701F) CF Surface RTNDT(U) RTNDT Shift Margin RTPTs RPV Material Heat No. Cu% Ni% (OF) (E19) FF (OF) (OF) (OF) (*F) Axial Weld 3-112A/C W5214 0.213 1.007 227.74 1.685 1.144 -56 260.5' 65.5 270

• Limiting weld heat no. W5214 w/revised fluence and CF value (Estimated date to reach PTS screening criterion limit = April 2017) [5]

Table 12. Revised Estimated Date for Weld Heat No. 27204 to Reach PTS Screening Criterion Limit (RTPTS = 3000 F)* CF Surface RTNDT(U) RTNDT Margin RTPTs (OF) Fluence*. (OF) Shift (OF) (OF) (OF) RPV Material Heat No. Cu% Ni% (OF) (E19) FF (OF) Shift (OF) _(OF) (OF) Circ Weld 9-112 27204 0.203 1.018 216.13 6.24 1.444 -56 312.2 44 300 dn

       *Weld heat no. 27204 projected fluence to reach PTS screening criteria limit =300°F (Estimated date > March 2031)

Report No. 1000915.401, Rev. 1 23 StructuralIntegrityAssociates, Inc.

Fluence Jan 2014 1 -8OE+ 19 l..60E+19 1.40E+ 19 A 1.20E+19 UJ 1JODE+19 E 8.OOE+18 Fluence 6.OOE+18 4.AODE+18 2JJIJE+1.8 OGOIE+00

                                      *1i  4
                                                     ,.,'bF Figure 1. Projected Fluence at Limiting Vessel Axial Weld (60°) Using Previous Palisades Vessel Fluence Calculation (from Reference 3)

Report No. 1000915.401, Rev. 1 24 StructuralIntegrity Asscite, nc Associates, Inc.

400.00

                                                                                                   + 2-Sigma 350.00 300.00 250.00 C.

C" 200.00 150.00 100.00 50.00 0.00 - 0.G0E+00 2.O0E+19 4.OOE+19 2 Fence (n/cm ) Figure 2. Best Fit for all W5214 Surveillance Data with Revised Fluence and Refitted Shift Report No. 1000915.401, Rev. 1 25 V StructuralIntegrity Associates, Inc

350 300 250 200 P 150 100 50 0 O.OOE+00 1.00E+19 2.OOE+19 3.OOE+19 2 Fluence (n/cm ) Figure 3. Best Fit for Palisades Weld Heat No. 27204 Surveillance Data Report No. 1000915.40 1, Rev. I 26 V StructuralIntegrityAssociates, Inc.

350.00 300.00 __... _ 250.00 ___4001__ -1 Si ma _-

                                                                  --4+...                                                                             ....

200.00

                          .                    -,                                            -       -      -i       Best Fit CF =216.13-F 150.00 100.00                                                                               ----    -t                     __i
                             --d  I~-                                                               -L 50.00                                  ...............
                                            ,4
                                                                                                                         -                      I            --------

0.00 ~_ 0.OOE+00 1.00E+19 2.OOE+19 3.00E+19 4.OOE+19 Fluence (n/cm 2) Figure 4. Best Fit for all Weld Heat No. 27204 Surveillance Data Report No. 1000915.401, Rev. 1 27 !V StructuralIntegrity Associates, Inc

250.00 200.00 150.00 P aL 100.00 50.00 0.00 O.OOE+00 1.00E+19 2.OOE+19 3.OOE+19 4.OOE+19 5.OOE+19 2 Fluence (n/cm ) Figure 5. Best Fit for all Base Metal Heat No. C-1279 Surveillance Data Report No. 1000915.401, Rev. 1 28 V StructuralIntegrity Associates, Inc.

100 --I

               ---    Two SigVa 50-F K

x J

• A533&-1 HSST01/02 CMM 80-
• Plate Mateials x WeW Matedars e0 a Forging Materials U) 40 40+f - x x AX x

01 20 ~~B 1,0 003 x

                                                                                                   'C S1) 0                                                                                   04 T

0 U) 0 0 0 Woa- J A& 0 0 A A x

        -404-                                                                00 x                         ,
       -G0
       -80/4 0
     - I Ul 1

1.00E+17 11.00E+18 1.00E+19 1.OE÷20 Fluence, E > I MeV [nlcmt Figure 6. 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 [191. Report No. 1000915.401, Rev. 1 29 - StructuralIntegrityAssociates, Inc.

Appendix A DATA CREDIBILITY ASSESSMENT FOR WELD HEAT NO. 27204 Report No. 1000915.401, Rev. 1 A- 1 Structural Integrity Associates, Inc.

DATA CREDIBILITY ASSESSMENT FOR WELD HEAT NO. 27204 The purpose of this evaluation is to apply the credibility requirements in 10CFR50.61 to the Palisades, and Diablo Canyon 1 surveillance capsule data and to determine if the surveillance capsule data is credible and can be used to improve the RTNDT predictions for the vessel circumferential weld heat No. 27204. 1 OCFR50.61 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. NRC provided additional guidance for evaluation and use of surveillance data in Reference 6. 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. 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:

• 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, Report No. 1000915.40 1, Rev. 1                  A- 2         ~         StructuralIntegrityAssociates,Inc.

    "   Intermediate Shell, Plate D-3803-3, material heat No. C-1279,
    " 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 [ 16]. 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" [ 17]. At the time that the Palisades surveillance capsules were built, 10 CFR50 Appendices G and H did not exist. Palisades supplemental capsules SA-240-1 and SA-60-1 were reinserted into the Palisades vessel at the end of Cycle 11 and removed for testing at the end of Cycle 13. The capsules contain reconstituted Charpy specimens made from weld heat No. 27204 obtained from Fort Calhoun, another C-E designed plant with the same weld heat. The weld material was carefully chosen, including the post weld heat treatment condition, in order to match the Palisades vessel beltline weld. Because weld heat No. 27204 in the capsules matches the limiting circumferential weld, the beltline material with the highest adjusted reference temperature and the limiting material for P-T curves, 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 determination 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. 27204 can be fitted to determine the 30 ft-lb temperature (T 30 ) and upper shelf energy (USE) unambiguously. The data and Charpy energy curve fits for weld heat No. 27204 are shown in Appendix B. It was determined that the Charpy curve-fits have produced accurate 30 ft-lb temperatures and USE values. Hence, Criterion 2 is met for all the surveillance capsules evaluated here which contain weld metal heat No. 27204. 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. Report No. 1000915.401, Rev. 1 A- 3 V StructuralIntegrity Associates, Inc.

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. 27204. The Palisades limiting weld metal will be evaluated for credibility using the NRC recommended guidelines [6]. Of the recommended methods, Case 4 most closely represents the situation for the Palisades surveillance weld metal where data is available from the plant of interest and from other plants. Case 4a CredibilityAssessment - Palisades2 7204 Data Only The data most representative for the Palisades limiting vessel weld are the supplemental surveillance capsules containing weld heat No. 27204 since the irradiation environment of the surveillance capsules and the reactor vessel are the same. The data requires the least adjustment since the radiation conditions are the same as the vessel. The Palisades weld heat No. 27204 capsule data are shown in Table A- 1 and in Figure 3, along with the fitted solution (i.e., mean shift prediction) result, and the comparison of the measured - predicted scatter from the fitted CF of 221.8°F. A plot of the measured AT30 vs. fluence results for the Palisades supplemental capsule weld (27204) is shown in Figure 3 along with the +/- 1(Ybounds 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. Table A-1. Evaluation of Palisades Surveillance Data Results for Weld Heat No. 27204 Material I Caosule I Heat ICaosule fluence I AFF RTndt- IFF=6RTndt IFF^2 27204 SA-240-1 (PNP) 27204 2.38E+19 1.234 267.8 330 1.52 27204 SA-60-1 (PNP) 27204 1.50E+19 1.112 253.1 282 1.24 CF (SumSqrs) Measured ARTndt Predicted &RTndt Scatter ARTndt 27204 SA-240-1 (PNP) 27204 221.8 267.8 273.6 -5.8 27204 SA-60-1 (PNP) 27204 221.3 253.1 246.7 6.4 FF ARTndt FF^2 Sum 611.9 2.8 Fitted CF 221.8 Report No. 1000915.401, Rev. 1 A- 4 StructuralIntegrity Associates, Inc.

Case 4b CredibilityAssessment - All 2 7204 Surveillance Capsule Data Following the guidance in Case 4 [6], the data from all sources should also be considered. For weld heat No. 27204 there are a total of five surveillance capsules, two from Palisades and three from Diablo Canyon Unit 1. 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. The five capsule results and the fitted CF value, as shown in Table A-2, is determined to be 216.13'F for this case. The results for (measured - predicted) scatter for all the 27204 surveillance data results are also shown in Table A-2. The results for all the surveillance capsule data are plotted in Figure 4 along with the +/- Icy scatter bands. The scatter in the measured - predicted values does not exceed 28°F (1-sigma). 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. In this case the fitted CF value is lower. The chemistry factor from the tables in paragraph (c)(1) is 226.8°F, and the adjusted chemistry factor using the Palisades surveillance capsule data is 216.13'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 reduced margin term if the data is also credible in all other ways. 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 216.13'F in combination with a reduced (1-sigma) margin term of 44°F. Report No. 1000915.401, Rev. 1 A- 5 StructuralIntegrity Associates, Inc.

Table A-2. Evaluation of all Surveillance Capsule Results Containing Weld Heat No. 27204 Ratio Chem. & Table Revised Fluence Irrad. Measured Adjusted Temp. Adj. Predicted Adjusted - Capsule %Cu %Ni CF (F) Fluence Factor Temp. ARTndt ARTndt ARTndt ARTndt Predicted (n/cmA2) FF Ti (F) (F) (F) (F) (F) (F) CAP Y (DCPP) 0.198 0.999 222.26 1.05E+19 1.01 542 232.59 237.3 244.1 219.1 25.06 CAP S (DCPP) 0.198 0.999 222.26 2.84E+18 0.66 544 110.79 113.1 121.9 141.8 -19.97 SA-240-1 (PNP) 0.194 1.067 227.8 2.38E+19 1.23 535.7 267.8 266.7 267.2 266.7 0.49 SA-60-1 (PNP) 0.194 1.067 227.8 1.50E+19 1.11 535 253.1 252.0 251.8 240.4 11.43 CAP V (DCPP) 0.198 0.999 222.26 1.37E+19 1.09 541.5 201.07 205.2 211.5 235.0 -23.56 Vessel Best Estimate CF = 226.8 Mean T = 535.2 [ Least Squares Fitted CF = 216.13 Note: None of the five (measured - predicted) data points exceed the 1 standard deviation of 28°F for credible data for welds. Report No. 1000915.401, Rev. 1 A- 6 StructuralIntegrity Associates, Inc.

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 wall opposite the center of the core. These supplemental surveillance capsules were installed in the capsule holders located on the core support barrel. Table A-3 provides a history of the time-weighted temperature for the Palisades supplemental surveillance capsules and reactor vessel wall. Table A-3. 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 A-240 526 3 342.5 534 4 321.0 536 5 386.7 536 W-290 531 6 326.7 536 7 362.5 536 8 366.1 537 9 292.5 534 10 349.7 534 W-110 533 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 18 (b) Cycle average vessel temperatures obtained from Reference 20 (c) Cycles 1-12 EFPDs are reduced by 2% to account for power reduction factor per the guidance in [18] Report No. 1000915.40 1, Rev. I A'7 Rt 0 5StructuralIntegrity Associates, Inc.

The location of the specimens with respect to the reactor vesselbeltline 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 Diablo Canyon 1 capsule irradiation temperatures are shown in Table A-2 [12]. These temperatures are also within 25°F of the Palisades average vessel irradiation temperature of 535.2 0 F. 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 Al 195-

1) from SA-60-1 and SA-240-1 are documented in BAW-2341 Rev 2 [10] and BAW-2398

[ 11], respectively. Charpy energy versus temperature for the unirradiated correlation monitoring material (HSST Plate 02, Heat A 1195-1) is taken from NUREG/CR-6413, ORNL/TM- 13133 [19]. Tables A-4 and A-5 provide the updated calculation of (measured - predicted) scatter versus fast fluence in the correlation monitor material (HSST 02) data. Figure 6 (from Reference 19) shows that the measured scatter band for the correlation monitor materials is 50 0 F. Table A-4. 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 I Sum 300.305 2.7588 CF Surveillance weld = Y (FF x RTNDT) IX (FF2)= 300.305/2.7588 = 108.853 Slope of best fit line is 108.853 Notes: (a) Calculated fluence (x 1019 n/cm 2, E>1.0 MeV) (b) FF = fluence factor = f o.28-o.1*ogf) (c) Irradiated values of 30 ft-lb Transition Temperature From BAW-2341 Rev 2 and BAW-2398 [10, 11] Report No. 1000? 15.40 1, Rev. I A-8 R0StructuralIntegrity Associates, Inc.

Table A-5. 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 SA-240-1 2.38 1.234 140.9 134.324 6.575 Where predicted ARTNDT = (slope bestfit)*(Fluence Factor) Slope of best fit line is 108.853 Notes: (a) Calculated fluence (x 101'ý n/cm 2, E>1.0 MeV) (b) FF = fluence factor = f(O.28-o.l*ogf) (c) Irradiated values of 30 ft-lb Transition Temperature From BAW-2341 Rev 2 and BAW-2398 [10, 11] Table A-5 shows that the scatter in these data is less than 50'F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM-13133 [19]. Thus, criterion 5 is satisfied for the correlation monitor materials. Report No. 1000915.401, Rev. 1 A-9 StructuralIntegrityAssociates, Inc.

Appendix B SURVEILLANCE CAPSULE DATA FOR WELD HEAT NO. 27204 Report No. 1000915.401, Rev. 1 ,,B-1 StructuralIntegrity Associates, Inc.

BAWM2341, Revision 2 May 2001 Test Results of Capsule SA-60-1

                 .ConsumersEnerg PalisadesNuclear Plant.

-, Reactor Vessei ]Material Surveillince Program,'-- byM MA .J.eVan. FTI Doucument No. 77-.2.34102 (See Section 7 for document siglatures.)' Prepared for Consumers Energy Prepared by Framatome:ANP, Inch 3315 Old Forest 'Road P. 0. Box 10935. LyncIhburg, Virginia 24506-0935 IfRAMATOME ANP

ExecutiveSum'mary This report describes the results of the test specimensifrom the first Supplemental capsule (Capsule SA-60-) of the Consumers'Energy Palisades NuclearPlant as part oftheir reactor vessel surveillance program. The Objective of the program is to monitorthe effects of neutron irradiation on the mechanical properties of the reactor vessel materials by testing and evaluation of Charpy impactý specimens. Supplemental -Capsule SA-601I was removed from the Palisades reactor vessel atthe end-of-cycle 13 (EOC-13) for testing and evaluation. Theo capsule cofitents Were removed from Capsule SA ifo testifng and examination.,: The test specim'ensincluded modified.18'mm.Charpy -V-: notch iiniserts ýfor three weld metals fabricated with weld wire heats W52,14. 34B009, .and 27.204 and standard Charpy V-notch specimens fabricated from the correlation monitorplate material, HSST Plate 02. The weld metal Charpy inserts were reconstituted to full size Charpy V-notch ispecimens. mf pact t tes tedTherecoinstituited

                    ..      ..        weld metals along withHSST Plate'02 material were Charpy Fo0lowing the initial Charpy V -notch impact testing, the-laboratory performeda calibration of the temperature indicator Used in the Palisades Capsule SA-60l testing. The resu s of the laboratory calibration indicated the instrument Was out-ýf-tolerance. Eased on the results of this

ýcalibrationhtest, the laboratory revised.the Charpy impact test temperatuires accordingly. Revision 1 corrects the testltempetatulres for the Suppiementai Capsule -SA-60-1 reconstituted weid metal Ch.apy V-notch impact specimes and the IHSST Plate 02 Charpy V-notch impact specimens. Revision 2 provides an update to the hyperboic tangentcurve fits ofthe-Charpy impact curves by restraining the upper-§shelf energy. For these curve fits, the l6ower-shelf energy was fixed at 2.2 ft-lbs for all cases, and for each materials the upper-shelfenergy was fixed at theaverage o .all test efiergies,exhibitiig 100% shear, consistent witiihASTMStafnd'd E 185-82. ii (RAMATOME AMP

of full size Type A Charpy, V-nýotch'specimends in accordance with ASTM Standard E 23-9. The reconstituted Charpy specimeni dimensions for each :specimen are shown in Table 4-2. Upon completion of the machining of the reconstituted Charpy'specimens, twelve (12) specimeins-were selected from each weld metal for Charpyimpact testing 4.5. Charpy V-Notch Impact Test *Results The Charpy V-notch impact testing was performed in-accordance with the applicable requirements of ASTM Standard E 23-91. Impact energy, lateral expansion, ad percent shear fracture were measured':at numerous test temperatures and recorded for each specimen., The impact energy was measured using a certified Satec S 1-1K

• pkict tester (traceable io NIST Standard) with i2.40 ft-lb of available energy. Thelateral expansion was measuredusing a certified dial indicator. The specimen percent-shear was estimated by video examinationi and comparison with the visual standards presented in ASTM Standard E 23-9.1. In :addition, all Charpy V-notch :impact testing was performed using instrumentation torecord 2a lad-versus-time trace and energy-versus-time trace for each impact event. The load-versus-time traces were:analyzed to determine time, load,

,and impactenergy for general yielding, maximum load, fastfracture, and crack, arrestprqperties during the test. The dynamic yield stress is calculated from the three-point bend formula:

                                  -=3333 * (general yielding load)

Theqdynamic flow stress is calculated from the average-of the yield and maximum loads, alsovusing the three-point bend formula:

                         =33,   3;(k(genera yiiding ioa       + minximum loadd) '

The results of the Chapy 'V-notch impact testing areshown in Tables 4-3 through 4-0 and Figures'4-2 through4-5, and the individual load-versus-time traces for the instrumenited Charpy V-notch impact tests are presentedjin Appendix B. The curves were generated using a hyperbolic, tangent curve-fittingprogram to prodUce the best-fit'curve through the data. The hyperbolic tangent (TANI) function (test response, i.e., absorbed :energylateral expansion, and percent shear fracture, "R," as a function of test temperature, "T") used to evaluate the surveillance data is as follows:

                                                ,4.3                              f    RAMATOME ANP

A +B"*tn[(T ý-To)] For the absorbedr(impact) energy cupresthe lower-shelf energy was fixed at.2 ft-lbs for al materials, and theupper-shelf energy wasjfixedsatthe average of 'all test energies exhibiting: 100 percent shear for each material, consistent with the ASTM Standard EI185-82. The lateral eXpansion curves were generated with the lower-shelf mils lateral expansion fixed at 1 mlland J2 the upper-shelf mils lateral expansion not constrained (i.e., not fixed). The percent shear fracture curves for each material were generated with the lower-shelvhesand upper-shelves fixed at 0 and 100 iespectively. The Charpy V-notch-data was entered, and the coefficients A, B, To, and C are determinedby the program minimizing the surn of the errors squared (least-squares fit) of the data points: about the fittedcurve. Using these coefficients and -the above TANH function, .a smooth'icurve is

  .generated through the datatforinterpretation ofthe material tansition region behaior, The coefficienits determiried for irradiated materials in Capsule SA-60-1 are shown in Table 411..

The transition temperatureshifts' aid upper-shelfenergy-decreases, for-theQCapsule SA-60-1 materfals :with' respect to the unirriadiated material properties are sumn arized in Table 4-12. Photographs of the Chaarpy: V-notch specimer fractutre suffaces are presented in Figures4-;6 through 4-9. ii 4-4 IFRAM.AýTME ANP,

Table 4-5. Charpy Impact-Results for Palisades Capsule SA-60-i Irradiated Weld Metal 27204 Testf Impacti Lateral 'Shear Specimen Temperature,, Energy, Expansion, Fracoture, ID OF ft-lbs m.il PB68 74 '12.5 T' Q PB56 1295 16.5, 13, 40 PB81 '154 17 10 30 PB78 204 251 19 45 PB093' 229 28 27 70 PB91 .254 39.5 35. 85 PB28 279 44.5 39 J5 PB96 329 52.5*: 48 100 PB94 329 52*ý 50 100 PB15: 404, 57*- 53 100 PB42 454 55* 49, 100 PB95 479ý 485 43 100

• Value used todetermine upper-shelfenergy (USE) in accordance

 'with ASTM Standard E 185-82 .B 4-9                              42RAMATOME-ANP

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

     ,Material                 Hyperbolic Tangent Curve.Fit Coefficients Description       AbsorbedEnerfgy    Lateral Expansion    Percent Shear Fracture Weld Metal               A:    28.4         A:     25.0             A:       50.0 W5214                   B:     26.2         B:     24-.             B:       50.0 C:    158.1         C: 160.0                C:       80K5 TO:   188.8.        T0: 239.6               TO:   214.9 Weld Metal              A:     287'         A:    %25.3             A:      50:0 34B009                  B:     26.5         B:     24.3             B:       50.0 C:    123.iS        C:     97.6                      89;6.:

TO:: 61.8 TO: '196.4 TOý: 179.6 12 Weld Metal A:; 27.6, A: 25.,9 A:. 50.0 27204 B: 25.4 B: 24.9 B ý50.0 C: 11.4 C: 101.8 C: :92.1 TO: 201.4 TO': 214.4 TO: 187.1 Correlation A: 44.53 A: 413 A: '50.0 Monitor Plate, B: 42.1 B: 40.3 B: 50.0 HSST'Plate 02 C: 95.1 C: 104.9 C: .85.12-(Heat No. A1195-1) TO: 1i930 TO:, 208.6 TO: 183.7 45RAMATOME ANP

Table'4-12. Sumiiiary-.of Charpy ImpactTest Results forlthe Palisades Capsule SA-60.1 Surveillance Materials Material

30 ft-lb TransitionTemperature, "Tran_

50 ft lb TransitioaTemperature, ____"_ °F 35miiLateral Expasion Transition Temperature, °F - 1 Upper-Self Energy, ftlbf Unirradiated. AT Ufirradikited Irradiated AT Unirradiated irradiated T Uniradiated Irradiated cas Weld Metal -60.2i8 7198W8 2590. 4(2)1 375i6 393.0 -29 310.1 3397 102 ' 54 5 48.2

W5214, Weld&Metal '-2.0(a) 167.8 249.8 -45.0(R)l 298.6 343.6 -51.6a): 2375 -289:A 113-90() -55.25 58.65 34B009 2

Weld Metal 41J2#1' 211 .9 2'53.1 -(br 355.6 361.7. N6t: 249.4 --  : i084  : 53.0. 554. 27204 available. HSST Plate 02 ,457*(ýc 159.4. 113.7 78.3(c) 206.0 127.7 Not: 187.9 -- 120.3*0 *86.3 34.0 Heat..No Al 195-1 availabfe-w (a) Data reported in AEA Techno6logyReport AEA-TSD-0774. 8: (b) Data rported in CE Reportt No. TR-MCC-1* 89.' 1. (c) Data reported in NUREG/CR-6413A.

Fiue4-4.1 ýCharpy Im;pact Datat for IrradiatedWeld.Meta 27204 too S

• SU 2, 75

   -= *50 0~

S25

             -0
             -1.00          o0         100       ý20         3000          400         500 o60o To r l"mperafure,:  F
      =100 e     80 60 x     40

9. "

           "0
       -Jj U         OF         100'        o200      300           ,400        500,          6006 TemperatureF

] S2. 120 S+253A.F ] 1od Tv6: OIvUSE: ~H

                              +21 1,2 I  'c     80 B  LuI
  -C w

I . 40' U '20

                                *   :o        0

io i¸S Materia:- Weld Metal H;e At Nuimber: 27204 B ). I

            .100 I%

0 100

                                            . I 200         300 400         500
                                                                                               " ,,.I 600 Temperature, F Li 4*F/RAMATOME ANP
                                                       '4.-20

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 IfRAMATOME ANP

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 w'eld 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. 1 'A tRAMATOME ANP

the center position of the temperature verification mockup insert ranged from 347°F to 51 I 0 F, which is less than the Palisades reactor vessel cold-leg temperature and meets the temperature requirement of ASTM Standard E 1253-88. Twelve (12) stud-welded inserts were then selected from each of the weld metals W5214, 34B009, and 27204 for machining of full size Type A Charpy V-notch specimens in accordance with ASTM Standard E 23-91. The reconstituted Charpy specimen dimensions for each specimen are shown in Table 4-2. 4.5. Charpy V-Notch Impact Test Results The Charpy V-notch impact testing was performed in accordance with the applicable requirements of ASTM Standard E 23-91. Prior to testing, the specimens were temperature-controlled in liquid immersion baths, capable of covering the temperature range -100 0 F to +550 0 F. Specimens remain immersed in the liquid medium at the test temperature +/-2°F for at least 10 minutes before testing to assure achievement of thermal equilibrium. A certified Omega Model 462 device was used to measure the temperature. Impact energy, lateral expansion, and percent shear fracture were measured at numerous test temperatures and recorded for each specimen. The impact energy was measured using a certified Satec S 1-1K Impact tester (traceable to NIST Standarda) with a striker velocity of 16.90 ft/sec and 240 ft-lb of available energy. The lateral expansion was measured using a certified dial indicator. The specimen percent shear was estimated by video examination and comparison with the visual standards presented in ASTM Standard E 23-91. In addition, all Charpy V-notch impact testing was performed using instrumentation to record a load-versus-time trace and energy-versus-time trace for each impact event. The load-versus-time traces were analyzed to determine time, load, and impact energy for general yielding, maximum load, fast fracture, and crack arrest properties during the test. The dynamic yield stress is calculated from the three-point bend formula: UrY = 33.33 * (generalyielding load) The dynamic flow stress is calculated from the average of the yield and maximum loads, also using the three-point bend formula: Each year, two sets of Charpy specimens are purchased from NIST and tested on the Charpy test machine. The results are then sent to NIST for evaluation. A letter is then issued by NIST certifying the calibration of the Charpy test machine. The accuracy of the Charpy tester is +/-1 ft-lb or 5% of the dial reading whichever is greater. 4-3 fRAMATOME ANP

aflow = 3333 (generalyielding load + maximum load)) The results of the Charpy V-notch impact testing are shown in Tables 4-3 through 4-10 and Figures 4-2 through 4-5, and the individual load-versus-time traces for the instrumented Charpy V-notch impact tests are presented in Appendix B. The curves were generated using a hyperbolic tangent curve-fitting program to produce the best-fit curve through the data. The hyperbolic tangent (TANH) function (test response, i.e., absorbed energy, lateral expansion, and percent shear fracture, "R," as a function of test temperature, "T") used to evaluate the surveillance data is as follows: R = A + B

• tanh[ (T -To) 1 For the absorbed (impact) energy curves, the lower-shelf energy was fixed at 2.2 ft-lbs for all materials; and the upper-shelf energy was fixed at the average of all test energies exhibiting 100 percent shear for each material, consistent with the ASTM Standard E 185-82. The lateral expansion curves were generated with the lower-shelf mils lateral expansion fixed at 1 mil and the upper-shelf mils lateral expansion not constrained (i.e., not fixed). The percent shear fracture curves for each material were generated with the lower-shelves and upper-shelves fixed at 0 and 100 respectively.

The Charpy V-notch data was entered, and the coefficients A, B, To, and C are determined by the program minimizing the sum of the errors squared (least-squares fit) of the data points about the fitted curve. Using these coefficients and the above TANH function, a smooth curve is generated through the data for interpretation of the material transition region behavior. The coefficients determined for irradiated materials in Capsule SA-240-1 are shown in Table 4-11. The transition temperature shifts and upper-shelf energy decreases for the Capsule SA-240-1 materials with respect to the unirradiated material properties are summarized in Table 4-12. Photographs of the Charpy V-notch specimen fracture surfaces are presented in Figures 4-6 through 4-9. 4-4 FRAMATOME ANP

Table 4-5. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal 27204 Test Impact Lateral Shear Specimen Temperature, Energy, Expansion, Fracture, ID OF ft-lbs mil  % PB45 70 5.5 3 0 PB62 125 16.5 12 10 PB71 175 16 18 30 PB54 200 26.5 29 55 PB07 200 33.5 27 60 PB73 225 29 24 65 PB52 250 34.5 26 55 PB35 300 36 32 65 PB06 350 44.5 43 95 PB58 400 49.5* 42 100 PB57 450 59* 52 100 PB61 500 53* 47 100 Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.[171 4-9 fRAMATOME ANP

Table 4-11. Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-240-1 Surveillance Materials Hyperbolic Tangent Curve Fit Coefficients Material Description J Absorbed Energy Lateral Expansion 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 41F5RAMATOME 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 mil Lateral Expansion Material OF OF Transition Temperature, OF Upper-Shelf Energy, ft-lb Description Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated Decrease Weld Metal -60.2(a) 219.9 280.1 -17.4(a) 372.7 390.1 -29.6(a) 284.3 313.9 102.7(a) 52.5 50.2 W5214 Weld Metal -82.0(a) 177.4 259.4 -45.0(a) 280.8 325.8 -51.6(a) 238.6 290.2 113.93a) 57.4 56.5 34B009 Weld Metal -41.2') 226.6 267.8 -6.10' 399.7 405.8 Not 293.7 --- 108.41b) 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(c) 84.4 35.9 Heat No Al 195-1 available. (a) Data reported in AEA Technology Report AEA-TSD-0774.t 91 (b) Data reported in CE Report No. TR-MCC-189." 181 (c) Data reported in NUREG/CR-6413.E"' 3:nl~ XI 0

Figure 4-4. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal 27204 100 0;~ 75 I.

'U  50 U-
'U 0

25 Ci) 0 0 100 200 300 400, 500 600 Temperature, F = 100 E C 80 60 x 40 -------------------------- 20 9* 0 0 100 200 300 400 500 600 Temperature, F' 120 T3SMLE - +293.7F T50: +399.7F 100 T30: +226.6 F OvUSE: 53.8 ft-lb 80 U, 60 0 CL .E 40 0 0 20 Material: Weld Metal Heat Number: 27204 1 b0 0 100 200 300 400 500 600 Temperature, F

                                              '4-ý20'.                             fFRAMATOME ANP

                              .WESTINGHOUSE CLASS 2 cusToMERDESIGNATED D0,TRkIUTION WCAP-11567 ANALYSIS OF CAPSULE SJFROM THE
                              .PACIFIC: GAS AND ELECTRIC COMPANY DIABLO CANYON UNIT I REACTOR VESSEL
                                .RADIATIONSURVEILLANCE PROGRAM S. Li Yanichko, IS. L. Anderson 3.lC., Schmertz
                                           ,L.Albertin DECEMBER. 1987.
            'Approved by:

TI.-A.. Meye'JýManager Structural Materials *and Reliability Technology Work Performed Under Shop Order PFUJ-_106 tPrepared, by WestinghouseE:lectrit Corporation for the PacificwGas an.d.Ele*tri:cComan-Although information:contained .nsthosreport Is nonproprietarly, no,,distr'ibution tshall be:made oqutsideWestnghouse or its licensees Without the customer's approval..

                    .WESTINGHOUSE' ELECTRIC CORPORAMION,,

Generation, Technology Systems DiVision PAO. Box 2728 Pittsburgh, Pennsylvania 15230-2728 99.02030038D 8e8o0129 PR ADOCK 05000275 .ýDR z~h-zcaloP_

SECTION 1 SUMKARY OF RESULTS The. inalysiS'of the reactor ves'se- material contained in surveillance Capsule S, the first capsule tdo beý removedr fromý the Pacifi c Gas. and Electric Company Diablo Canyon. Unit 1 reactor pressure- vesselr, led to the following conclusions: o "The capsule recei*ved an average fast neutron fluence. (E,,> 1.0 MeV) of 2.ý98, x 10IB n/ o I'rradiatio of specimens madeý from the reactor Vesrsel intermedi ate. shell plate B41063 to 2.M98 x 1018 n/cm2 resulted in 30, and 50 ft-lb transiti~on temperature ýshifts of -oF and '4*F .,respectively,. fr spec.imens oriented, parall!el to the majorworking k direction (longitud ina 1 orientation)ý. pecie made from Weld metal irr:adiated too 2.98 x 1018* ( resulted in, 300 and.50 ft-lb transition temperature6 increases .of-110°F and 1448 F respec-ively.

18. 2

0 Irradiation to 2.98 X 10 n/cm resulted in a,.r11 ft-'lbdecrease in the upper shelf enhergy 'of-the weld metal specimens and no decrease in the upperý shelf of. the shell plate B4106-3 specimens.

Both materi/als .exhibi,t. a more than aldequatequppr shelf level for continued safe plant operat:ion. o C of the: 30 ft-lb transition temýrature* increases for the

                            'mparison Di ablo Canyon Unit 1 surveillance :material witth predicted increases Using the methods of NRC" Regul atory' Gde 1.99 proposed RevisOn 2 shows that -the plate material and-weld metal transition temperatur'e.

increase are, less .than predicted. o Capsule, S contained specimens. from the same, heat of -weld wire (Heat 27204) as the limi.ting, reactor vessel weld seam. The surveillance

program is therefore representative of the imi'ting reacitor vessel ma~terial.

2 SS,-12Uio08:)o 171

SECTION 5, TESTING OF SPECIMENS FROM CAPSULE S 5.1 OverView The postirra-diation mec haniical testing of the Charpy V-notch and tensile-specimens was performed at the, Westinghouse Research and ,Development Laboratory with consul tation by Westinghous'e Poer Systems Divion personnel. Testing was performed. in accordance- with 1CFR50, Appendices G and H,2] .ASTM Specification E-185-82, and Westinghouse PrOcedure RtF-8402, Revi sion O 'as, modi fied by RMF Prdcedures 8102 and 8103. Upon receipt of the capsule at the- laboratory, the, specimens and sPacer 1bocks were carefully .removed, inspected: fortidentification number, and' checked' against the master list in WCAP-8465.[1[ No discrepancies werel foukd

 'Examination of the two low-melting poinht 304,PC (5797F)andk 3100C        1(590 F) eutectic allos i ndicate'd no melting of either type bf thermal mon ittor.:%, Based"
 'on this examination, the'maximum temperature to. which the test -:specimens. were exposed, was less than 304C (579 F),

The Charpy impact testS- were, performed per ASTM SpecificatOn E23-82 andoRMF Procedure 8103 on a Tni Us-Olsen Model 74,i358J machihe. The tup (striker) of the Charpy machine is instrumented with an Effects :Technology Model 500 instrumenptation system. Wi:th this system; load-!ime and.energy-time s ;ignals can be recorded In addition to the standar.d measurement of Charpyenergy (ED). From the ýload-time curve, the load of general yielding (PGy), the time to g6en"eral yieldingi 'the maximum lbad (P), .and -the time *t

                                   )(tY4
 *maximum load (itM) can' be determined. The load at which fast fracture was ini~tiated is-identified -as the fast fracture load (PF) ,and the, load at which fast fracture terminated is identified:as the arrestt load (P The energy at maximum load (EM) was, determined.by. omparing the energy-time record and the load-time record. The energy-.*a: maximum load isAroughl;y equivailent `to the energy required to initiate a crack in the specimen.

- 2569t-121v08: 1O S5-1

                                                                                      ý. I

.Therefore, the propagation energy for the crack. ý(E ) is the difference between the total endergy to fracture :,(ED) and the energy at maximum load. The yield stress (ay) is tcalculated frm .the three-point bend formula. The flow; stresS is calculated from th. average of the yield and Maximum loads, also using the three-point bend 'formula., Percent shear was ,determined from postfractfure photographs using the rat io-of-areas -methods. in compliance With 'ASTM Specificatifon 'A370"77. The lateral expansion was measured using a dia gage rig simila'r to that shown in the same speciftication. Tension tests 'were. performed on a 20",00'0pound Instron, split-console 'test machinea(Mde] 1115) per ASTM Specifications and 1EB83 E21-79, Wnd RMF Procedure 8102. Ali pull rods, grips, and pins' were made, of Inconel 718; hardened, to Rc .45. The upper pull rod was. connected :through a universal, joint, tof loading. The tests were conducted ,atý a constant. to im"prove axi10ality crosshead speed of 0.05 inches per minute throughout the test. ( Deflec'Itibn measurements were made with a 'linear variable displacement transducer (LVDT) eextensometer., The extensometer knife edges were spri ng-ipoaded to the speicimen and operated through specimen failure. The extensometer gage length is '1.00 inch. The'extensometer is: rated as. ClasS I -2 per ASTM E83-67. Elevated, test temperatures ýwere obtained, with a three'zone'."electri c resistance split-tube fur nace ith a 9-inch.hot, zone. All tests, were conducted Iýn air.*o Because of the difficulty'ýin remotely attachi ng a :thercouple direc_tly tthe specimen, the fol owi ng procedure was ,used tO moniitores*pecimn temperature.,

"Chromel-alumeil thermocouples were inserted in shallow"holes in the 'center and each -end of the gage secton of -a dummy specimen and in each-grip.         I, the test configuration, with a slight :load on the speckimen, a plot of specimen' temperature v4ersus Upper and 1ower-grip,and controller" temperatur es was developed over- the range room temperature to. 550OF (2881C )Q. The upper geip, 2II9s-~2tOg7:1O 2r

was used to control the'furnace, temperature. During the actual testing the grip temperatures- were Used to ,obtan desired peimen temperatures . Experiments inditcated, that this method is accurate to + 20 F, The yield, load, ultimate load, fracture load, total elongation, and unifort'n elongation were determined directly Ifrom the load-extension curve. The Iyeld 7 Strength, ultimate strength, and f racture strength were, ca.lcul.ated using- 'the original .cross-sectional area., The fi~nail diameter and final gage length were, Sdetermined fr'om poslt-fractureý photographs. The fac-ture. area used to .calculate the fracture stress: (true stress at fraceture) and pe0rcent -e duction in area was computed using the final diameter measuremenrt. 5.2ý Charpy. V-Notch !mpact Test Results The .results of cCharpy V-notch impact:, teststperformed on, the various materialts, contained in CapSile rS irradated at 2.98 x 1018 n.cm 2 aare.. presented ;in tables' 5--: through 5-6 and figures 5-1 through 5-4. Initial and Irradiated transition. temperature and :upper shel f energy level s were determined us.Ing :a h.yper bolIi c tangent (TANH) curve fittiqng model aS used by'Oldfield [3] to fit the data. Tables contain-ing the'results of the curve fitting were suppied. to Westinghouse by the Pacific. Gas a d E-lectric Cofpany for- use in determining 'the impact ýpropert!y changes. The transition temperature increases and upper .shelf energy decreases for: the :Capsule. S material are summarized. in table. 5-7. Iirradi atibn of6vessel intermediate- sheljl pljate 84106-3 material (ldongitudinal orientation), specimens to 2.98 x i018 n/cm2 (figure 5-1) resulted in a 30 and 5.0 ft-l1b transition! temperatIre shift of -2 and A4OF,, respectivey, and an average upper shelf energy increase of 4 ft-lb. The small increase inupper shelf nergy. is not unusual and is considered to be the result of data scatter. Weld metal irradiated to 2.98 x 1018 'n/Cm2 (figure 5-2) resulted in 30 and 50 ft-"lb transiti on temperature increases"of 110 and 148F respectively and an average upper shelf energy decrease of 11 ft-lb. zsao.-12148? tO 5-3

Weld HAZ metal irradiated to 2..98 x 1018 n/cm? figure 5-3.) resulted in 30 and 50 ft-lb transitions temprature increases of 77 and -56qFrespedtlvely and an average upper shelf' energy decrease of 22 ft-lb. gy. eces ft, ,f2 '. HSST plate 02 correlation monitor material irradiated toI2.98x 1018 n/cm2 (figure 5-4) ,resu ted in a 3.0 and 50 ft-lb trans'iton temperature increase of 66and '68F respectively, and a' average upier shelf energy decrease of 1 ft-lb, which fal f wi thin, the data base. for thi7s material. The: fracture appearance of each irradiated Charpy, specimen .from the .various materials iIs shown in figure 5-5 through 5-8 and show an increasing, ductile or touher -appearance with ilncr'easing test, temperature.*i ' Table, 5-8 shows a comparison of the 30. fft-lb transition temperature increases for the various Dbiablo, Canyon 'Unit -1 surveillance materials with predicted increases, using the methods of proposed NRC Regulatory Guide 1.99 Revision 24 (4] This comparison shows that the transition tem ature increase resulting from irradiation to 2.98 x 1018 n/cm2 is less than predicted by thi, Guide for plarte B4106-3 weld metal and correlation monitor material. Four weld metal Charpy. V-notch :impact specimens from Capsule S were reconsstituted by' Westinghouse tO obt-an: additional im-act toughn~ess daita to better definer the transition region and the upper shelf of the6- weld metal.1 A separate report [5) describes the reconstit;ution Pourer and discusse ,the analysi-s of t-Khe t.e st. dat. t Two of the four reconstituted speci-men.s were noicheýd6 too deep and.. theref ore were considered- inappr..opr'iate for obtain'ing reliable test. data. Tarbe 5-9 shows"the results of the imact tests performed at 125 :.and 4000 F` on the -other two :reconstituted specimens, The ,toughness resul..ts for these two6tests ýwhen comp6'ared to. the orginal' irradiated, wed shown in figure 5-24appear to be* questionable6 Iurssaince metal test results .they do not fit the irradited energy and.lateral expansion transition Ncurves. A review of the rec'onstitibon and testing techniques* Ued in this ,pogkkam was conducted which did not identify any obv ious, abnormalities that could have produced th lower th an expected toughness values- Thee recon'stituted Charpy data points have not been included innthe develOpment of the Charpy transition curves. On:y two of theIfour 'reconstituted' specimens were succesSfUl in 256,,-,,17 o 5"4

a TABLE ,5-7 EFFECT":OFI 550".F IRRADIATION AT 2.98 x o18 "n/Cm2 (E 1.0. MeV) ON NOTCH TOUGHNESS PROPERTIES OF- DIABLOCANYON UNIT I REACTOR VESSEL MATERIALS Averrate ; 35-mlI' AverageB 0 ft-lb La teral Expansion ýAverage 30 f t- lb Average"Upper,, TemperatUre (,*F,) Temperature (.) Temperature (",F) Shel fEnergy (tt-lb) Material Unirradlatedc-rradiated AT Unirradiated Irradiated AT Unirradated Ir.radlated AT Uniirradiatedl rradiated A(ft-lb) Plate B4:W673 41" 45 -4 ' 29 629 0 5 .3 -2 122 126 .4 (Longitudi nal)

                          -23                                             96       142 WedA MetalI                              125     148          -46                              -67            43   110       Be          87 77      147         125       -22
                                       -55       56'      -107           -64        43       -168           -91 Correlation                  78         -146:     68           59         124        65,        46           112    66      124         123        -'1 Ilonitor Mt'?Il 2589s- 1'210817"-.IO.

110 iao

                                                                              /I 100 so S

S. 70 0. a I0 a a 50 R N '40 a Ii S

              .1 100             500 Tea.watuz     (7) 100 TO eo a
              &      70.

09 b.

                     ,I0 U

I. 50 S N, h am I. U A U 40

                                               -100       1U          00  5O0 TOMps   tun   7 Figure 5-2. Irradiated Charpy V-Notch I mpact Properties for Diablo Canyon Unit I Reactor Vessel weld Metal 25&5s-Cg22~ ~O                          S' 1,6; 5-16

WESTINGHOuSE CLASS 3

  'WCAP-13,750 ANAIYSIS O'OF CAPSULEY FROM THE PACIFICý CAS'AND ELECTRIC COMPAN4Y DIABLO CANYON UNIT 1 REAcrOR VESSEL RADIATION SURVE LNCE.PROGRAM E.: Terek S. L. Anderson A. Madeyski

July,1993,,

Work Performed Undeir:ShopOrderLUKP0406' Prepared by We ghouseElectr.,icCrporation for the Pacific Gas and Electric Company Approved by:. 1 ,~~ 1~ T. -A:.Meye....... M, agef StructuralReliability and Plant U fe Optimization

               'WESTIGHOUSE ,ELECTRIC CORPORATION Nuclear and A*dvan             edTe oogy Divsion-P.* ,Box.355          -

Pittsburgh, Pennsylv6ia 15230-0355

                  ©  -1993,WestinghouSe             Electric Cgororation Q.

SEC,TION.1.0 SUMMAR OF RESUL~t The"analysis of the reactr vesseI materialsc6ntained in surveiilance Capsule .Y, the second capsule to be removed from the Pacific Gas and ElecfticdCmny Diablo. CanynUnit 1 rieactor pressu.revessel, 'ledto thefo11owing c6nclusions: o 7Th capsUle received'an average fast neutron fluenie. (> 1.0 MeV) of 1.02 x 1019 2 after dcm 5.8.6 E.FPY of plant operatio n. o Iadi*ation of the reactor vessel intemfediate shll p*late B4106-3 :arpy s:pecens, orie with he ongidiinal ais of the specim...en p el to the mjor rolling *diein(longidal orientation), to 1.02 x 10j19n/* 2 -(E> 1.0.

                                                     ,MeV)esulte           i a.3 ft-lb&tansition temperature increase of 470F and a, 50 ft-lb transiion tem pete ]inrease of 5310f 'Tis results in a 3 f-lb transition. temperature of       and a -50 ft-lb transition tp        ture of94F. for the longitudinalyoriented speciens.

o Irradiation of the weld metal ai.arpy specimens tob.O2 x 109:n/cm2 (E> ý1.0 Me)-,resulted-in a 30 ft-lb transition temperature incres of 2 F and a 50ft-lb 0 transition temperature increaseof 2706F. This rlts in a'30 ft-ib aition tempera of167F and a 50 ft-lb ttiasition temjerature f 253TF. o Irradition of the'weld Heat-Affected-Zone (HAZ) metal Charpypecim to 1.02x 10" n/cm 2 i(E`>4'1.0 MeV) resulted in a 30 ft-lb transition- temperature increase 'of '"?Fand .a 50 ft-lbtransition tem ratureincreise of 750 F. 7Thi results in a 30ft-lbWtrnsition tmperatu of -840 F and a 50 ft-lbtranition temPature of, R36. o Irradiation of the ýCorrelation Monitr Material Plate HSST 02 Carpy pens to 102.x "n/cm21_(F,.0 MeV) ,resulted in3 and 50ft-ltrans*tio6ntimperatu iIncre o 01F' *f This results in a 30 ft-lb transitiottemperture of- 158TFand a 50 ft-lb ransition temperature of 190 0F., 1-1

o The surveillance Capsule Y st *r*uhsidicate that the Correlation Monitor PlatHSST 02 maierial 30 ft-lb trinsition temp ture Shift is 10F greater than ihe Regulatory Guide 1.99, R*vision 2 prodiction. This increase is bounde-d by the 2 sigma allowance for shift preion of 34 0 F. Theaverage upp-e'rhelf energy dec of the Correlation- Monitor Material is less than ihie Reglatory Guide1.l99, Re-ision 2 prediion. "o ~Thesureillance capsule mteriaL :exhibit a more' adequateuppershelf ene.rey 1tha.Ifor, con nued* safe plant oprtion and are ex tomaintain-an uppershelfenergy of no less than 50 ft;lb through outthe life (32 EFPY) of the vessel as required by 1O O, Appendix ;G.. o The calculated end-of-life (32,EFPPY maximum neutron .fluence (.E> 1.0MeV) for the Diablo,

   .anyon Uiiii reactor: vessel is as follows:

Vessel nnetr radius', ='1I54 :x 10", rj/6t 2 Vessel 1/4-thickneýss 8.110 it 108 n/ýM2 2 Vessel 3/4 thickness-= 1.62 xý 1018-n/n*

                       .aad/bse metal interface o   Bised on thecritriagiven in R          latory Guide 1.99, Revision 2,'the Dib!O Canyo. Unit 1 Su*eiManceýProgram is judg edto b cedble.

1-3

SECTION 5.0 TESTING OF SPECIMENS FROM CAPSULE Y 5.1 Overview The post-iriadiation 'me6hanical testing of theQiarpy V-notch and tensile specunens, was per-formed at, the WestinghouseScience and TOchnolbo-gyCeter hot-cell with consultation by Westinouse.Powe, Systems personnel. Tig was performed* in accordance, with: 10CFR50, -Apendices Gand'WH", ASTM Specification E185-82m7, and Westinghoe moteMetall aic Faclity (MF) Prfo6cure 8402Rision 2 as mo ed by F Procedu*re 8102,Reviion 1and 8103, Reision 1. Upo~nreceiptof thetcapsule at the lot 6ell laboratory, the specmn and spacer blocks were caredfuly ov inspected for idntifiation number,, ad :checked against the masie list inW- 8SW 1 1 . Nodi.screpancies were found. IExamation of the two low-melting point 797 (4C and 50 0 F (1C euti alloysindicated no 'melting of either type ofthermal monitor. Based on this exammation,-the m mum temperature to which the test specimens were exbosed w w laslessthan 579°F (*04C). The.harpy impact ests were performed per ASTM Specification Et3-92M and RMF Procedure 8103, Revision I on a Tinius-Olsen Model 74, 358J. mahine. The tup (striker) of the Charpy machine is; instruented with.a GRC6830I instrumentaiion system, fe g into an iBM XT Computer. With this tsystemoadime and enery-time signals can be recorded in addition todte standard measurement of Qharpy energy (ED). From the, load-time curve (Appedix A), :the load'of genera yielding (P), ted time togenera yielding:(t*), the maximum, load',(Pi),. andthetime to maxim 16ad,'(t) can be determined. lUndersome test conditions, a sharp op in loadidicative ofIdfast fracrewas observed. 7The load at which fast fracture was initiated is' identified as the fast fracture load (PF), 'ad the load'at: which fast fracture terminated isidentified as thearrdst load (PA)* Th- energy at maximum0_ad(E,)* determinedby mwas comparng, the energy-tierecord ýan the load-time record. 7T1he ergy at maximum load is roghly equivalentf to the energy'reuir*ed toinitiate a cack *n the s*peki. Therefore, the pro-aga on energy for the cack (Es is the difference between the total e.ergy to fractUre (E0 ).and the energy at maximum oad ,(E). 541

The yield stress (ay)was calculated fromthe threepoinit bendlformula having the following expression,

                *= P**-{ L / [B     B.-(W -.a )2, C ])                                                          .(1) where L =..distance between- the spe,cimen supports in the impact testing             ma     e; B    te    dh of te specimen measured parallel to the notch; W = heightof the specimen, measured perpendicularly to the notch; a;= notch depth. The constant C is dependent on the notch flankangie:(0),; notchroot radius (p)1, and the type 0of, loading (iLe., pure bending or'three-point bending).

In ýthree-point bending a aiarpy spem*en in.whichh =450 and p 0 Equation 1isvalid wth C. =21. Therefore (for L = 4W), cr Proy I[,B. * 'W' a)2:,e-r;121 ] P4=;3 PGY`W ]/[B ('W*:-2].) For the rarpy specimens, rB = 0394 in. W = 0394in, and-a4= 0.079 in. Equation 2 then reduces, ýto:: Cry =133r.3* Pj (3) where Oyis in units of a6iad Pi is in units of Ibs. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula. Percent shear was determined from post-fracture photographs using the ratio-'of-areas methods in compliance with A'STM Specification A370-92--, ThelaterIl expansion was measured using a dial gage rig simil t that ýshownin the same sp fication. Tension tests wehr performed on a 20,00-pound ron

                                                              -Model        1115, split-console t     mauine, per A      STM Specfication E8-910° and E21-79 (1988),                  -andRMF  IProcedure 8102' Revisid:n    . All pull ros grips,: and:pin6siwere made of'inconel 718 hardeneddtoHRC45. Theup6per pull rod was connected through a universal joint to improveaiaty of loading. The tests were conducted atia constant crosshead Speed of 0.05 inches per minute throughut ithe tes 5-2

Deflection measurements were made with a linearvariable displacement transducer,(LVDT) extensometer. The extensometer knife edges were spring-loaded to the specimen and operated through specimen failure. The ex*nsometer gageiength is 1.00" inch. The extensometer is rated as Claw B-2 per ASTM`tE3-921*2P EleVated test temperatures. were obtained with a three-zone electric: resistance split-tube furnace with a 9-inch hotvzone. All tests weeconducted in air. Because of the difficulty in remotely auachIing a thermocouple d4rectly to the spedmen, the following procedure was used'-tomonitor specimen temperature., Clhromel'alumel thermocoupies were inserted in shallow holesAin the center and each end of the gage secon of adummy specimen and inweach grip. In the. test configurationwith a Siight load on the spcien, aplot of sp en temprature versus upperand lowergrip and controller temperatures was-developedoV er the range of room temperature to 550 0 F ('2880*). he6 upper grpwasused to control the furnace temperature. During the actual testing the.grip temperatures were used to obtain desired specimen temperatures. Expeimeits indicated that this method is accurate to :+20 F. The yield loadultimate6load,. fracture load, total elongation, and iiform elongtion Were determined directly from the load nion curve. 'The yield strength, ultimat sength, and f re strent were calculated ing the orig~ial cross-sectional a The finfdiaimeter and final gage-leng were determined from post fracture photograp#s.. TheM fratu areausred to calcuilatelthe frcWie stress stress at'frate) and percent reduction in, areaýwasc6mptedusig the final diameter measurement. 52 ClarpovV-Nitch ImpadtTest Results The results of the Charpy V-notch impacttesis perfrmed on the variusmaerialscntained in Capsule Y, whichwas irradiated to 1.02x i n/cm2 (>, 1.0 MeýV) are presenied in Tables 5-i

througho5-8 and are compr with n ditresultsdr as shown in Figures5-1 tug 5-12. The Iransition temperature increases and upper shelf'energy decreases for the. Capsule Y materials are_

summarized in TAbleW59., K5-3

Irradiation of the reactor vessel intermediate shell piate B4106-3 Charpy specimens oriented with the longitudinal axis of the specimenparaliel to the major rolling, direion of the ,plate(longitudinal orientation) to 1.02 x 10(9 n/cm 2 (E> 1.0 MV.) at 5500 F (Figure-5-4) resulted in a 30ft-l.b transition temperature increase of.47 F-and a. 50,,ft-lb transition temperature increase of 53f. This resulted in a 30ft-lb transition temperatureI of'520 F-anda 50 ft-lb transition temperature of 94OF (longitudinal, orientation). The average, upper shelf energy (USE) of the intermediate shell plate B410603 Charpy specimens 2 (0ongitudinal.Orientation) resulted. in a energy decrease of 3 ft-lb af*teriradiationito 1.02x 1019M nk/cm (E :1.0 MeV) at 5561F. This results in an average'USE of_119 ftrlb (Figure-5), Irradiation of the surveillance weld metal Charpy specimes' to 1.02 x119 k.0MeV)atn/cm 2 (E > 550°F (Figure5-4.) resulted 4in a 30 ft-lb transition temperature shift' of:2347F and a 50 ft-lb transition tempeature incfrase of 2766F.This resuts in a 30 ft-lb transitio-on*t*emeture of l6rF and a 50 ft-lb transition, tmperature of 253T. The average upper jhelf energy (USE) of the sivfice weld mt resulted in an en rgy decrease of 32 ft-lb after irradiation to 1.02 x10, n/cm2 (E>-10.MeV) at 550F.T This resulted in:an average ( USE of 66 ft-lb&(Figure 54-4)ý. rradiation of tMe ýracor, vessel weld HAZ metal .Ciarpy specimens to 1.,02 x 101 n/cm 2 (>- 1.,0 MeV) at 5$ 0 F igur 5-7) resulted in a 30, ft-b transition temperature inIcreas of 84OF and a 50 ft-lb transition, temperatre icrease of 750 F 'This resulted,,in a 30 ft-lb transition temperature of -84 0 Fand a 50 iftib :transition temperaturetof v-36 F Te average upper shelf energy (USE) ofgthe weld HA metalrulted in an energy: d of 37 ft-lb afterirdiation to1.02kx,109 q/cm (E, 1,,i.0 MeV) at 550*,F:-This r'esuited i:n'an average USE of 110oft-lb.(Figure '5-ý7).- Irradiation of theHSST 02 correation monitor materia arpspeimensn to 1.02x 10 1 9 n/cin2 (E> 1.0 MeV) at 550 0F (Figure 5-10) resulted in.30 and 50 ;ft-lbtransition temnerte t inca of F.12F. This results ,in a30 ft-lbo transition ,a50 tmprat of 15ssF i:and fIb transition temprature of 9 F.'. 54:

lhe average upper shelf energy of the HSST 02 correlation monitor material xperienced an energy decrease of 2 ftilb after irradiation to 1.029x 1019 c/ 2 (E> 1.0 Mev) at 550-F. This resuited in C'* average USE of 122 ft-lb (Figure 5-10). Plots of the Capsule Y Clarpy test results are presentedjin Figures 5-13 through 5T24. Thie fracture appearance of ech:irradiatedi iarpy specimen from the various;materials is showAnin Figures 5j-25 through 5-28 and .showan increasingly .ducle or tou ".appearance with ,increasing Ste temperature. A ,comparison, of-the 30 ft-lb transition temperature increases:and upper ishelf energy decreases for, the various Diablo Canyon Unit' I surveillance materials with predi*t Values using the methods of NRC Regulatory Guide 1.99, Revision , ispresented, inTabler5-l0and led to thefollowing conclusions: o This comparison indicateis that the trasiontemperature increases and theoUSE decreases for intermediate shell Plate B4106-3 resulting fomi irrad iation to 1.02 x. 10" n/cm (E > I.0:MeV) are less thanwthedRegulatory Guide preditions. So This comparison indicates' that the surveillanc weld metal 30 ft.lb shiftintrnition temperaituieis 10*F greatei than the6Regul*t*oy Guide41.99, RevisiU- 2 prediction. However, this increase the 2"sigma alloiwance for shifti

                                                                  'isbounddby                          dtin of 56"F. The average uxppe shelf energy decrýeaof the surveillance weld m etalis less than        Regulatory Guide 1.99, Reion 2 prediction.

the o This; cmparison inýicates thteHsST 02crrelationmontor mate6 30ft-lb

                        ýshift in transitiontemperture isl00 greater han ,the Regulatry Guide 1.99, Revision 2 prediction. However, this inicrease is bounded by ite 2'sigma allowance for shif prediction of 340 F. The average, upper shelfenergy decrease of the HSST 02 corraeltion monitor-material is ,less than the Regulatory Guide 1.99, Revision 2 prediction.

The load-time records for the individ'ualinstrumented Ciarpy: secimen tests are- presented in Appendix A. 5-5.

                 £i Effect of 550*F Irradiation to,1.02`X i0V    n/cm2 (E > 1.0 MeV) on the Notdh ToughnessProperties of the Diablo CanyonUit 1 Reactor Vesse ISurveillance Matrialsd Average 30(f-lb),                  ,Average,35mil Lateral            "              Average 50 ft-lb0 )                  Average Energy Absorption 0),

Transition Temperature (V' Expansion Temperature ('F)% TransitioinTemperature (°F) jatFullShear (f-lb) M a ter ia l - "..

                      .uirradiated     Irradiated   AT     Unirradiated      Irradi                             diaed     Irradiated     AT         .Unirradiated Irrdiated        A 52        47          29                 75       46               41                94        53           122           119           -3 Plate.B4106-3                5 4,6.......,.                       4        5(-12)3_,.                (1  10)1,

.(o1ngitudihal) WeldMetal -67 .. " . 167 _ 234

                                                      .... ,     -46* ~-___  ___76_195                       -32241

• 253

                                                                                                                             ....        276    __.  . 98            (60) 66    ,   (--32 38 HA"Metal                 -168
                              . . ..       -84
                                            '*       84*:       -10'7
                                                                  .     .     .   .36.      :71              -111I -          -36         75147110.-3
                                                                                                                              .71          7           147           ý1!0.-3 47-                                                               6(-38)         -                   09)

Correlation

M onitor M t'l 46 158 12 .59- 178 ... ,19 78 .-_ . 190_ 112 . , , 124

                                                                                                                                                         ..          122 (11.2).        -2

_____.____ _ _ _ " .(-12)" (a) ' AVegs isdefined as the.value read' from the curve fit thrugh Lthe data points of the Chapy tests-(see-Figures 5-1hugh 5-4) (b) The data were:fitbyTPG&E usifngthe EPRI HyWprboli& Tangent CurveFittingRoutine, Revisionr20(-3) (c) Values:in parenthesis'were calculated'per the definition 'of Upper Shelf Energy givenwinf. . -TE18S-82* (d) Unirradiated* vales presented here are, .frm the Capsule"5" Analysis.2 . 5-14

TABLE.5-10 Comparison of the Diab*ioCanyon Unit 1-Surveillance Materiiil 30 ft-lb.,TransitionTemperatureShifts andUpper

                                .Shelf, Energy iDecreases:with RegulatoryGiide: .99 Revision 2Predictions 30 ft-lb Transition        UpperShelf Energy TemPerature Shift:                Deciease:

Material Capsule: (X10" n/cm 2 )-Predicted W Measured Predicted (8') Measured,') lPate B4106&3 S 0.305 35 +2 14 0 (Longitudinl) -Y 1.02 52-  ! 47 19 3(10) SurveillanceWeld Metal ' . ** S* '.. ,0.305

                                                      '-               150

• 1012 4 26 3 .1 .

                                                                                                                  '3 ",3
                                      .Y'            1.02.         .224                   234        343 Heat.AffectedAZone              r         0S?305            .   -                77        - -              15 Metal Y            1.02               .                 :84          -          26:(26)

Correlation Monitor. .S, '0.305: 68 66 . -8 2' PlateH SST002 Y 0212112 23210 (a) Based on ,RRegulatory Guide1.99,' Revision 2 methodology -using Mean w. % values of Cu and Ni. (b) -Valuesin parenthesis were calculatedper the definition of Upper Shelf Energy given in T E185-82( 5-1.5

C V r K r.< g, yJ, 0 o100 00 300 600 Tmpe:atu~e iz ,Degrees Im* Pn Unirradiate Test Data Capsule S Test Dfba C A Capsule Y Test Data Figure 5-16 Qarpy V-Notch Impact Energy vs. Temperature for Diablo Canyon Unit 1 Surveillance Weld,Metal 5-32

Westinghouse Non-Proprietary Class 3 WCAP-15958 January 2003 Revision 0 Analysis of Capsule V from. Pacific Gas and Electric Company Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-15958, Revision 0 Analysis of Capsule V from Pacific Gas and Electric Company Diablo Canyon Unit I Reactor Vessel Radiation Surveillance Program A. R. Rawluszki J. Conermann R. J. Hagler January 2003 Approved:- 4L'i)/~ J.A. Gresham, Mat~ger V Engineering & Materials Technology Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02003 Westinghouse Electric Company LLC All Rights Reserved

ix EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance Capsule V from Diablo Canyon Unit 1. Capsule V was removed at 14.27 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 database. Capsule V received a fluence of 1.37 x 1019 n/cm 2 after irradiation to 14.27 EFPY. This is equivalent to a vessel fluence at the end of the current license (32 EFPY). The peak clad/base metal interface vessel fluence after 14.27 EFPY of plant operation was 6.07 x 1018 n/cm 2. This evaluation lead to the following conclusions: Specimen results are behaving in accordance with predictions. The surveillance program, however, does not meet the regulatory criteria for credibility. Regulatory Guide 1.99 requires that all five criteria for credibilitybe met. For the Diablo Canyon Unit I surveillance program, four out of five of the criteria for credibility were met. 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 V, the fifth capsule removed (third capsule tested) from the Diablo Canyon Unit I reactor pressure vessel, led to the following conclusions: The Charpy V-notch data presented in WCAP-846513 ', WCAP-1 1567141 and WCAP-1375015 3were based on Charpy curves using a hyperbolic tangent curve-fitting routine. The results presented in this report are based on a re-plot of all capsule data using CVGRAPH, Version 4.1. which is a symmetric hyperbolic tangent curve-fitting program. Appendix B presents a comparison of the Charpy V-Notch test results for each capsule based on previous fit vs. symmetric hyperbolic tangent fit. Appendix C presents the CVGRAPH, Version 4. ], Charpy V-notch plots and the program input data. Capsule V received an average fast neutron fluence (E> 1.0 MeV) of 1.37 x 1019 n/cm 2 after 14.27 effective full power years (EFPY) of plant operation. Irradiation of the reactor vessel intermediate shell plate B4106-3 (heat number C2793-1) 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 39.46°F and an irradiated 50 ft-lb transition temperature of 77.5 1IF. This results in a 30 ft-lb transition temperature increase of 34.32'F and a 50 ft-lb transition tempeiature increase of 38.19'F for the longitudinal oriented specimens. See Table 5-9. Irradiation of the weld metal (heat number 27204) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 135.45°F and an irradiated 50 ft-lb transition temperature of 219.26'F. This results in a 30 ft-lb transition temperature increase of 201.07'F and a 50 ft-lb transition temperature increase of 243.430 F. See Table 5-9. Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of-52.65'F and an irradiated 50 ft-lb transition temperature of -1.98°F. This results in a 30 ft-lb transition temperature increase of 110.9°F and a 50 ft-lb transition temperature increase of 109.77'F. See Table 5-9. Irradiation of the Correlation Monitor Material Plate HSST02 Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 163.05*F and an irradiated 50 ft-lb transition temperature of 197.42'F. This results in a 30 ft-lb transition temperature increase of 116.61IF and a 50 ft-lb transition temperature increase of 119.12'F. See Table 5-9. The average upper shelf energy of the intermediate shell plate B4106-3 (longitudinal orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf

                                                 /

energy of I 18 ft-lb for the longitudinal oriented specimens. See Table 5-9. Summary of Results

2 The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 25 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 66 ft-lb for the weld metal specimens. See Table 5-9. The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 116 ft-lb for the weld HAZ metal. See Table 5-9. The average upper shelf energy of the Correlation Monitor Material Plat6HSST02 Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 117 ft-lb for the weld correlation monitor metal. See Table 5-9. A comparison, as presented in Table 5-10, of the Diablo Canyon Unit I reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 21" predictions led to the following conclusions: The measured 30 ft-lb shift in transition temperature for all the surveillance materials of Capsule V contained in the Diablo Canyon Unit I surveillance program are in good agreement or less than the Regulatory Guide 1.99, Revision 2, predictions. The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules V contained in the Diablo Canyon Unit I surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions. The credibility evaluation of the Diablo Canyon Unit I surveillance program presented in Appendix D of this report indicates that the surveillance results are not credible. This is based on not satisfying the third criterion for credibility.

• 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 (32 EFPY) as required by IOCFR50, Appendix G [2J The calculated and best estimate end-of-license (32 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Diablo Canyon Unit I reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows:

2 Calculated: Vessel inner radius* = 1.26 x 1019 n/cm 2 Vessel 1/4 thickness = 7.51 x 1018 n/cm Vessel 3/4 thickness = 2.67 x 10's n/cm2 Summary of Results

4-4 Table 4-3 Chemical Composition (wt%) of the Diablo Canyon Unit I Reactor Vessel Surveillance Materials (Unirradiated)(c) HSST 02 Element Intermediate Shell Plate Weld Metal 1b) B4106-3 Ladle Check N 0.010 0.009 - - C 0.200 0.140 0.22 0.22 Si 0.250 0.450 0.22 0.25 Mo 0.460 0.480 0.53 0.52 Cu 0.077 0.210 - 0.14 Ni 0.460 0.980 0.62 0.68 Mn 1.330 1.360 1.45 1.48 Cr 0.035 0.060 - - V 0.001 0.001 - Co 0.001(a 0.001(a) - Sn 0.007 0.010 - Zn 0.001 a) 0.056 - Ti 0.001111 0.010l Zr 0.00l°( 0.030 - As 0.009 0.016 - Sb 0.001 0.003 - S 0.012 0.025 0.019 0.018 P 0.011 0.016 0.011 0.012 Al 0.036 0.018 - - B 0.003'a' 0.03(a) - Notes: (a) Not detected, the number represents the minimum of detection. (b) Surveillance weld was made of the same weld wire Heat 27204 and Linde 1092 Flux as the betline region reactor vessel intermediate and lower shell longitudinal weld seams. Linde 1092 flux lot 3714 was used to fabricate the surveillance weld whereas flux lot 3724 and 3774 was used to fabricate the intermediate and lower shell longitudinal weld seams respectively. (c) This table was taken from WCAP-137501' 1 . Description of Program

4-5 The best estimate copper and nickel weight percent remains as presented in the Diablo Canyon Unit 1 FSAR. The values used for the intermediate shell plate B4106-3 (Heat Number C2793-1) in all calculations documented in this report are as follows: Cu wt. % = 0.086, and Ni wt. %= 0.476 The values used for the surveillance weld (Heat Number 27204)* in all calculations documented in this report are as follows: Cu wt. % = 0.198, and Ni wt. % = 0.999

• The overall best estimate Cu and Ni for heat 27204 is 0.203 Cu and 1.018 Ni. These values are documented in the Diablo Canyon Unit I FSAR.

Description of Program

5-3 calculated using the original cross-sectional area. The final diameter and final gage length were determined from post-fracture photographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percent reduction in area was computed using the final diameter measurement. 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 V, which received a fluence of 1.37 x 109 n/cm 2(E> 1.0 MeV) in 14,27 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with unirradiated resultst 31 as shown in Figures 5-1 through 5-12. The transition temperature increases and upper shelf energy decreases for the Capsule V materials are summarized in Table 5-9 and led to the following results: Irradiation of the reactor vessel Intermediate Shell Plate B4106-3 (heat number C2793-1) 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 39.46'F and an irradiated 50 ft-lb transition temperature of 77.51°FE This results in a 30 ft-lb transition temperature increase of 34.32°F and a 50 ft-lb, transition temperature increase of 38.19'F for the longitudinal oriented specimens. See Table 5-9. Irradiation of the weld metal (heat number 27204) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 135.45'F and an irradiated 50 ft-lb transition temperature of 219.26°F. This results in a 30 ft-lb transition temperature increase of 201.07 0 F and a 50 ft-lb transition temperature increase of 243.43F. See Table 5-9. Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -52.65°F and an irradiated 50 ft-lb transition temperature of -1.98 0 F. This results in a 30 ft-lb transition temperature increase of I10.90 F and a 50 ft-lb transition temperature increase of 109.77°F. See Table 5-9. Irradiation of the Correlation Monitor Material Plate HSST02 Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 163.05°F and.an irradiated 50 ft-lb transition temperature of 197.42°F. This results in a 30 ft-lb transition temperature increase of 116.61"F and a 50 ft-lb transition temperature increase of 1I9.12'F. See Table 5-9. The average upper shelf energy of the Intermediate Shell Plate B4106-3 (longitudinal orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 118 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 25 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 66 ft-lb for the weld metal specimens. See Table 5-9. Testing of Specimens from Capsule V I"

5-4 The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 116 ft-lb for the weld HAZ metal. See Table 5-9. The average upper shelf energy of the weld correlation monitor metal Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 117 ft-lb for the weld correlation monitor metal. See Table 5-9. A comparison, as presented in Table 5-10, of the Diablo Canyon Unit I reactor vessel beltline material test results with the Regulatory Guide 1.99, Revision 2I1 predictions led to the following conclusions: The measured 30 ft-lb shift in transition temperature for all the surveillance materials of Capsule V contained in the Diablo Canyon Unit I surveillance program are in good agreement or less than the Regulatory Guide 1.99, Revision 2, predictions. The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules V contained in the Diablo Canyon Unit I surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions. The' fracture appearance of each irradiated Charpy specimen from the various surveillance Capsule V materials is shown in Figures 5-13 through 5-16 and shows an increasingly ductile or tougher appearance with increasing test temperature. All beltline materials exhibit a more than adequate upper shelfenergy 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 (32 EFPY) as required by IOCFR50, Appendix G t2J The load-time records for individual instrumented Charpy specimen tests are shown in Appendix A. The Charpy V-notch data presented in WCAP-8465t33 , WCAP-1 1567 14 and WCAP-13750I5 J were based on hyperbolic tangent curve fitting. The results presented in this report are based on a re-plot of all capsule data using CVGRAPH, Version 4 .1 t14), which is a symmetric hyperbolic tangent curve-fitting program. Appendix B presents a comparison of the Charpy V-Notch test results for each capsule based on previous fit vs. symmetric hyperbolic tangent fit. Appendix C presents the CVGRAPH, Version 4.1, Charpy V-notch plots and the program input data. Testing of Specimens from Capsule V

5-7 Table 5-2 Charpy V-notch Data for the Diablo Canyon Unit I Surveillance Weld Metal Irradiated to a Fluence of 1.37 x 1019 n/cm2 (E> 1.0 MeV) Sample Temperature Impact Energy Lateral Expansion Shear Number OF 0C ft-lbs Joules mils mm  % Wi1 .25 -4 11 15 1 0.03 5 W13 100 .38 23 31 13 0.33 15 W12 150 66 36 49 25 0.64 25 W9 200 93 37 50 24 0.61 30 W10 225 107 52 71 37 0.94 80 W15 300 149 71 96 51 1.30 100 W14 325 163 60 81 50 1.27 100 W16 350 177 66 89 48 1.22 100 Testing of Specimens from Capsule V

5-15 Table 5-10 Comparison of the Diablo Canyon Unit 1 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 Fluenceed' Predicted Measured Predicted Measured (X 1019 n/cm 2 , (OF) (a) (OF) (b) (%) (a) (%)() E > 1.0 MeV) Inter. Shell Plate S 0.284 36.2 -1.78 14 0 B4106-3 Y 1.05 56.0 48.66 19 6.8 (Longitudinal) V 1.37 60.0 34.32 20 0 Weld Metal S 0.284 145.8 110.79 25.5 11.0 (heat 27204) Y 1.05 225.4 232.59 34.5 34.1 V 1.37 241.6 201.07 36.5 27.5 HAZ Metal S 0.284 - - 72.31 - - 8.1 Y, 1.05 -79.77 - - 19.9 V 1.37 -- 110.9 -- 14.7 Correlation Monitor S 0.284 73.01 65.62 - - 2.4 Material Y 1.05 112.9 115.79 -- 8.9 V 1.37 121.0 116.61 -- 4.9 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 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 fluence values, not the~best estimate. For best estimate values see Section 6 of this report. Testing of Specimens from Capsule V

IT 5-20 SURVEILLANCE WELD METAL CVGRAPII 41 Hyperbolic Tangent Curve Printed at 12:M.17 on 08-19-2002 Results Curve Fluence ISE d-ISE USE d-USE T o 30 d-T o 30 T o 50 d-T o 50 1 0 2I9 0 91 0 --65.62 0 -24.16 0 2 2BIE+18 219 0 a1 -10 45.17 110.79 12D.38 144.54 3 1.05E+19 22 0 60 -31 166.9? 232.59 255.73 2799 4 1.37E+19 219 0 66 -25 135.45 251.07 21926 24143 C-)

             -300         -200       -100             0         100           200         300        400       00       600 Temperature in Degrees F Curve Legend ID-                       20 ..........                30    _                    4_

Data Set(s) Plotted Curve Plant CaDsule Material Off. 11eat/ Heat# 1 DCI UNIRR WELD LINDE 1092 Ori. 27204 FLUX LOT 3714 2 DIO S WELD LINDE 1092I7M4 FLUX LOT 3714 3 DCI Y IRELD LINDE )92 27204 FLUX LOT T714 4 DCI Y WiELD LINDE 1092 27204 FLUX LOT 3714 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Diablo Canyon Unit I Reactor Vessel Weld Metal Testing of Specimens from Capsule V

5-23 SURVEILLANCE PROGRAM. WELD METAL CYGRAPH 4IJ Hyperbolic Tangent Curve Printed at 1J3W39 on 00-19-20M 5-2 Results Curve Fluence USE .d-USE ToLM3 d-T oLE35 1 0 88J7 0 -4652 0 2 ME4E18 73.91 -1425 9528 141.81 3 1.05E+19 6124 -26.93 19425 240.77 4 L37E+19 54.47 -33.7 220DJ 267J9 0)

            -300        -200      -100             0          G00          200          300           400  500 600 Temperature in Degrees F Curve Legend I     D-                  2G.........--                30                            4 ,-

Data Set(s) Plotted-Curve Plant Cap~sule Material Od. eati 2 DC1 UNIRR WELD LINDE 102 2720 FLUX LOT 3714 DC1 S WELl) UINDE I1M2 27204 FLUX LOT 37)4 3 DC1 Y W LINDE 1092 27204 FLUX U)? 3714 4 DOI Y WELD UNDE 1092 2r204 FLUX LOT 3714 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Diablo Canyon Unit 1 Reactor Vessel Weld Metal Testing of Specimens from Capsule V

5-22 SURVEILLANCE PROGRAM WELD METAL CYGRAPI 4.1 Hlyperholic Tangent Curve Printed at 2-4450 on 0W-19-2002 Rmilts Cmrve Fluence T o S0z. Shear d-To 50"/. Shear rve Fluence T o 50r/ Shear 1 0 0 2 2M8E+16 110.74 126.67 3 1.05E+19 168.75 I17.6 4 127E+19 201.56 217.5 a) Ch a) 0 a)

           -300       -200        -100             0        100          200       300        400          500    600 Temperature in Degrees F Curve Legend ID-                         20----------              3l                      4     -

Data Set(s) Plotted Curve Plant Causule i Material OrL Heat# II I DCI UNIRR WELD LINDE 1092 27204 FLUX LOT 3714 2 DOl S WELD LINDE 109 27204 FLUX LOT 3714 3 DII Y WELD LINDE 1092 27204 FLUX LOT 3714 4 DJO V WELD LINDE 1092 27204 FLUX LOT 3714 Figure 5-6 Charpy V-Notch Percent Shear-vs Temperature for Diablo Canyon Unit I Reactor Vessel Weld Metal Testing of Specimens from Capsule V

Appendix C SURVEILLANCE CAPSULE DATA FOR PLATE HEAT NO. C-1279 Report No. 1000915.401, Rev. 1 C-1 StructuralIntegrity Associates, Inc.

BCLU-585142, FINAL REPORT PALISADES NUCLEAR PLANT REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM: to CONSUMERS POWER-COMPANY March l13, j1979! by J. S. Perrtin, E.. OFromtb, D. R. Faýtmel,. R. S. Denning, and R. G. Juig BATTELLE Columbus Laboratories 505 King Avenue ColumbUs, Ohio 43201

                                                                              ~L FINAL REPORT on PALISADES, NUCLEAR PLANT. REACT"OR PRESSURE ,VESSELM SURVEILLANCE PROGRAM:.

CAP.SULE A-240 to6;

                             -CONSUMERS    POWER COMPANY
                                          -from
                                       -BATTELLE:

ColumbusO L.Ab6ratries. Marc-h 13 979ý

SUMMARY

CapsUle A-240 was- removed, from the Palis'ades Nuciear :"P6wer TPlant after 2.26 equivalent ful .power years of eactrt Toperation. The. capsu,:e was sent :to the' Battelie 'Ckdlumbuls Hot Lbratory I Thr examInationý and evaluadtion.. The' irfadiationf tempera*ure, did not exceed 536. F as inadicated by thei ixaminationrof thee 12 thermal monitors. The neutron fluence At the locaat-ion of' the specimens, was, ,determined to ;be 4.4 x 10-19 ( M6V), using neutron dosimeters fro'm wi:'th~in the capsule. -At the vessel. wall the maximum exposure' was determiried to be 3.2 -x- 10 1 9 'n/cm2-at 32 f-ull powerý years. The radiation-i-nduced changes, in- the mechanica-l. propties of pressur e: vessel' materilai specimens were determined. Charpy impact specimens were, used to determine 4 changes in the ýimpac tbehavior, includingthe: shifts in e, tran-sition temperature re gion dand the drops 'in t per shelf energy level*. :Evaluation of the, tensile property specimens included the yield and ulitimate strengths as ,well as elongation and reduction in area.,"

34 Char.py Impactz Prop~rties This, section contains results and' d.distciss19n, pertai~ning 'to. 'the Charpy impact testhing. Appendix A contains further re suIts and dipscussionh relating to the instrumented pr.cedure.s used:during: the impact- testing. The impact- propertie4 de.term"mined 4a -a funct:.6ion of, temperature are listed in Tables -9 through :112. In.,addition t6:the impact energy, values, the tables also list -the ýmeasured values, of lateral exansion :and. the estimated fralcturte ,ap~pearance: :f*,* each spe.c-imen. The lateral expansion' is a measure off thOte def-brmat-:in pt duc-ed bWy. the. `trikitig h` g of fthe impo ac-t hine; hammer when it%. impacts the specimeh' it is the chan-ge in spedimen thiickhiess directly .adjacent&'to the notch "I'cation. The ,fracture appearance 'is a visual estimate of the amount pof Shear or, ductile type-, of fractureý appearing. on6h 'the'specqimEnh fracture surfade., The impact data -are graphically shownin- .Figure -.11 th gh 14 These, figures show the changen'in imp'act tropeite as a fuction ,o ,tempera-tiure, incldding-'ý both the impact energy and the lateral, ,epansion;=. Figures 15 t-hrough 18 show the- fracture 'sur-faces of -theCharpy specimens. Table 13 summarizes the -Palisades a 30- and -50. -ft-lb transition, tempera-turre., the -35 mil1S lateral expansion temper.ture., adj ,for the uPP: he.f energy the present program and Ifor the,[ earlier ufi'tradiahted p.--------As *indica.d previously in the neutron dosimetry section, tae- Gharpyi specimens received ,fairly unifor .exposure. The neutron esureures based- on :the iron dosimeters ranged fromA.39 to .4..6'.x10 n/c. . (>1; M.V. P4tidul#.eo.s..e values can, be ass'igned to each To0f-,the fobur: Cha-rpy, ma~terials, sinc specimens of .'aa -i-lar materia Iwer e all l:ocated lh a, given -Charpy Aanonserva- Using tive approach,ý, 'the four Ceharpy -,materials from 14Caps6i1e

                                                                                    -240    recelied exposures estimated as, follows'.

4Base 065gitudini, n/cm

                                              -4,5*10                              ,MeV)
                                                                                     *-l Baseý transverse,              49 A      -  -- - i 2'C--Me HAZ,                           4.-3 x I09 n/dm2                 1 keV).

The impact properties of -the -Pal-isades bacse metal, .weld metal, and HAZ metal ar-e all significantly affected by -irradiation, as can-be seen in the figures of impact energy and lateral ekpa-sIoin versus' temperature (Figures 11 through 14).

317 10

                                                                   'A w
        -200                0     1;OO d100    200   300   400:  500' Tempperature, F FIGURE'. 11. CHARPY IMPACT PROPERTIES FORBASE METALj, PLATE.

NO.' D3~8di-1,~ LONGITUDINAL, 0RIE TATION

                                           .38ý irradiated Baselin~e      "                              "         100 O 0Q Uni
 ]irra O            0diate,-qap~yu   A-240 8O C

60 0 C x w 4O~

                                                                                  ~.1 20*

a0 120-100"

       '-I C,

w 4-80-! 0 C. E 60 4,04 20* "0 ' 2,0-

               -200        -10         . l0b        200   300    .400    !500,
                                         *Temperatlure, F; FIGURE 12.        :CHARPY IMPACT PROPERTIES ýýFOR ,BASE METAL,'

PLATE NO4.1D3803-i, TRANSV.ERSE OlIEN'TATION

                                                 ,4M5 T-ABLE    13-.      

SUMMARY

'OF CHARPY *IMPACT P~ROPERTIESý. FOR PALlSADESý PFluence,                                Upper         35tM~il E>i1~e*,       30 ft -1b      50     lb   Shelf        Lateral 1   rTransition --                    gaso Efpansio Material
 .Program                          x. 109 n/.cm2      Temp, F     Tfm:,        Energy-       emp.,aso

-*Base: L'a -Ref 10 0 0 .+20 165 ,+5 (a-) Base L(a) 'Present 4.5 +205, +250 95 +220 Base T; Ref 10 0 :25 4-55 105' +40 BaseT Pre-ients. -4 4.4 +230 +270 68 +235 WeldIRef 10' 0 -85 -50 120i -85 Weld Pre sent )4ý6 .+26-5 -305 54.. +285 HAZ Ref 10 0, -90 65 :125. 55 HAZ Present '4 +200 +2140 60. 205 (a) Base metai, longitudinal: orientationý. (b)Base etal, :transverse orientation.-

              .For the four materials inrCapsulie `A-20,,: the 50t ft-l-b and 30. ft-lb

-tranfsition tqem`peratures :ra.nge qfrom 240 F 'to 3'05 F and 200,! F. -to-265 F, respectively. The 35-'mie lateral expansion, temperature ranges, from 205 F to ,285, F', and the upper shelf energy levels range: from 54 tO'. 95 ft4b. The uP,per shelf energy l.evels: were ,taken as being' the highest poift off the curve drawn through the points...

46 Table 14 is a comparison of the 50 ft-lb and 30 ft-lb transition temperature shif-ts and the 35-mi lateral expansion temperature shift.,due to .irradiation for the" present program.,. The. 50, ft-l4b transition temperature,- shif~t is defined as the increase in the irradiated ,50 ft `lb. ,temperature with. respect .to unirradiated' ethe 0 ft-lb tempeaiture. Tie. 30 ft-lb transition temperature shift"arid the. 35--mil late'ral e'xpansion temrpet .re .shift are simiialy defined:. As ýclan. be- seeni, the grea'test shif t -occurs for the- weld material in all ,three, cases'. TABLE -14. 50 FT-LB, 30 .FT-LB, AND. 35"MIL. LATERAL EXPANSION TEMPERATURE SHIFTS DUE TO TRRADIATION FOR PALISADES ;APSULE A-240-

                                                                                                .35-.Mili
                                               *30unce-30                 'SQ. ft-lb            Lateral Flu         '            Transition                 Trahisition           EXpanSi6n Maeil1          2e     :iTemperature,              Tem~iperature         Temperature
                         -1 n/cm
                            '                  Shift, 'F   'Shift,                  F           Shift, Base L(a)             4.5                         +205                       ;230                   215 Base T                4. 4                        +205                         215                  195 Weld                  4,. 6                       +350                         355                  3.7-0 HAZ                   4.3                         +290                        -305                  260 (a)     Base longitudinal orientation./

(b) .Base transverse -:orientation. Int comp'akiig the 50 ft-7lb, .shiff to the 351m1l lateral expansion shift f or-*. .'Of 1 the 'four materialso,* note that 4the twEld metal mi1 later4A1 expan sion shi!.ft 'is greater than th&. weld metal1 50 ft-lb shift, 'but the 'reverse Ais true for, the other -three .materials. In considerPng the Charpy results, it should be 'realized that this surveillance capsule is an accelerated oh6e, and bas- a ver~y high lead fa'cfor of .19.4. This mians the flux the specim'ens in' the- cap-sule receive 'is much. hi'gh'er than any! point in; the vessel wall. Further PaIisadesý, dapsules to be examined inc-lude ,ones with sign.ificantly lower lead factors, more, closely approximatelY' tbe vessel wall,' The ac6u'al Iocation...of 'the v'arious surveillanie capsules inside thee pressure'vessel are given in Figure C-I of Appendix C.

47 The reference temperature, RTNT3 was -determined previously for the unirradiated base transverse materiail to be 0 F( 2 3 ). The ,procqdure fo thoe determihation.of the .RTDT is defined by ASME Boiler dhi And Pressure 'Vessel (2.4 Appendixý H,,, VReactr ess61 Material Survei.llancel Program. Requirements'.t, CFR 5O 'specifies how an adj usted rqeýfernce te~mperature for irradi*ted Sp'ý&ihmens can be dete6mnii',d .. (25)Thi*s 'temperature can. be Used in* revisng the plant presstfre-temp-erature operating- Cidrves -iln. th.ose cases where the Iluence of ýthe irra.iated spe'cimens isi the range to 'be "extpe.i-r ,enced *5ythe prsure ,,esl.*.The adjusted reference .temperature defined 'b "Appendix H is detdermine'd by adding to 'the te f e re ee temp' tatur.e the ýamount -,of' ,the temperature shift7 in, theý Charpy curves between- the .Uni'tadiated materia: ,an. the irradiated material, measured' a the. 5.0 f t-1db le've', o6r that Imeahsured a*t. 'the 35-mu lateral expan'sion levei, whhichever, temperature shifý-t is 'greater;. Tensile -pr~bpdr~tios The tensile: properties d*termined for the "ten!§Ae .s'e-imen cbntained iný. the. Palisades, A,20 -are iisted in Table I5.". the -table list~s test Acapsule tempe*aU're, fluen~e, 0.2i Percent offset 'yieId.strength, ultimate tensile strength, unifML elodgAtlin,; to0tal eldnga4tion, and reduction in area for he, presentn gr

            .      n.as .well -as for the Unirradiated baslirie p1rogra1.                     Posdt-tes t photographs of the tenssile specimens- are shown in Figure 19.                       "These photographs show 'the -necked doWn regibon of the gage length and ithe 'fracture,.                      A ltypi'caal tensiled test curve is slhownh in'Figure 20;_ the part'ic-ular test sh6n                         is  for base m~etal specimen lD4. tested at- 72 P.

Tensil'e, itest-s :were- run at .room temperatur.e (69 to FL), 535 and 565,F., The higher temperature t'ests '..hibited a de6rease in '0.2 percent offset yield ýstreegtBh and., aý decrease 'in ultimate tensile g'trengtfifr'each merial w th x'Lespec,t 'to e room- rtempeature' ?.tests. 'In generadl, ductility`'values.(;as tePi....d bt elongati

                           .tal                 nd reduýct.ion in area) decr..eased,. At higher

'temperatures as compaed' 'to room temtperature for each' material.. Palis'ades tensile spe 6cifis were locaffted in- thJ- vicini-ty' Iof, iron

                                                                                        ,9, dosimet ers which received fluen-ces ranging from '4.3 to. .4.6 x:                          n/m"   '2,-

(E MeV). "When "the tefasile data, fo* C.apsufle: ,A-2.*.0 is coqmpardd'. to-the unirradiate, baseline data (Table ..5it 5)' can b5e' s.een that as fluence increases., the yield strength and tensile' s-trength incrdase while ductility .decreasesl.

,WCAP-10637 WESTINGHOUSE'CL ASS 3

CUSTOMER. DESIGNArED D"I'STRIBUTION ANALYSIS OF CAPSUILES T1-330 AND W-290 FROM T*E CONSUMERS 'POWER ICOMP"ANY.

PALISADES REACTOR vESSEL ADiATION. SURVE!LLANICE PROGRA, M. K, Kunka

                                           'C.A.. Cheney September 1984,
              ;Work performed under       h-op Order Nos. ENVJ-106 and ENVJ-45o APPROVED:

T. A., Meyer, Managedr Structural Matier ial's and RIeli:a IbiliyTcnlg PIrepared ,by Wes'tinghouse for the Consumers P'ower'Company Although information containedn this repiortis nonproprie tary, no di~stribution shall be made outsid. eWgstinghoun e or its liicensees without.*hhe customer's .approv.0]

                             .WESTINGHOUSE ELECTRIC1CORPORATION
                                     .Nucle-arEeIrgy Syste P.O. Box 355.

Pittsburgh, Pennsyl-vania 1.5230

w~? SECTION 1

SUMMARY

.OF RESULTS The'analysis of the' ma'terial contained in, Capsu-le- T313, the first the mal surveillance capsuleremoved frm 'the Cbn'sumers Power' CbMpanys P61-isade'S reactor pressure. vessel, led to the following conclus-ions,: o the ýweld and heat-affected zone metal has bxperienced.a,60-.70 0 F shift in the duc-tilTe to br it tle terasi tion temperatures due to exposure. tQý elevated :temperature. he .anaaysi.s of the m'aterial contained in Capsule w290., tbe. econd irradiated-surveillance capsule to be removed from the Consumers Power Company Palisades reacto rpressure 4vessel, led to the folIlowing conpl:qisons: o p The .,O capsue. _ýS 019* received nc an av.erage fast neutron fluenc (E>104Mev) of o Irradiation of the reactor vessel initermed.iate shell course plate D-3803-1, to 1.09 x1019 n/cm, resulted in 30: and 50 ftl*b trans*ition temperature tincreases of 155 and i160`:F' res'etive1 Y, for specimens odiR0ted pWp*ndicu]a.r 'to the pri ncipal _ g direct.ipon 1roli (transverse oriehtation,: and 1'15-.F and 180.9F, respct'i Vely,A :fO specimens oriented parallel to the' princitpal rolling direction (lohg uud'i n b'.r ient e ,t i- 9jOn) i19 2 Weld metal irradl.ated to 1.i9 .x 10 n/cm,- .resulted in .30 and 50 ft-lb teansi-tion temperat-Ure increasp a e of 29.0 and 300e, respecAtively. o The average upper shelf energy of all 'the surveil lance mater-ial .s remained above 50 ftrlbs., thereby providing adequate toughrfess. for contin.ued safe plant operati6n.

      *qt~    ~    A

o Comparison :of the 3G. ft-lb transit-ion temperafture increases for the Palisades surveillance material with predi-c ted increaseý usi*gthe met'hds of NRC Regulatory Guide '1.99, Revi:"sion 1, shows that the weld meital transit ion temperature increase.was greater *than predicted. It is sutpected ,tKat therel'atively high nickel cohtent of the weld metal contr-ib.uted to -the greater than predicted transition temperature increase experienced by thw6eld: 6tal. 8092B:lb.092684 Y1'2

It1~e'se test results it appears that a mi-xup in moni;tors occurred during the in~iti-al loading of the capsules and therefore a reliable estimate of' the

 .capsule teperature cannot be determined from the ýthermal monitors.i 5-3. CHEMICAL ANALYSIS

,Cemicai analyses were performed on fractured Charpy V-notch specimens in 0rder to .c'onfi m,'the chlemicall compos-ittibn of thte survei I l"ance plate and we0ld materials. The chemical analyslis results are summar-ized in Table 5,-i. The mo.st notable feature .,of the'se ana'ly'sqs i s the -- td e ,a ianhce measlur-ed in the

'6ickel contke-it!,                   fiom A95 to 1.60 wt, . From he -high niickel ypecificait.'
"content, it is evident that: a:NAickel-.2'00 addlition was made.to the, survei.llance,
 .weldment, nd from the nitcke'l var'a4nces observed iltan be' concluded 'that, thb ra~te- of; Nicktel.-200. additibn was varied during welding.

5-4. CHARPY. VNOTH..MPACT TEST RESULTS

,Capsule T-330:

The,, resOltts, of the Charpy V-notch impact tes-.tXs performed on the vrario,65s maete 1. :icqn-tai~nied in C.appsble' *T-330, the. theemal cap.suliek ae pesented in Tables 5-2 through 5-9 and Figures 5-ý1 through 5-ý4 From t*he Charpy V-notch plots ba.sed on best- engineering judg-meht it appears that the. we'l!d an'd hde-atý-.affec ted zone rmetal s ha've exper-Hienced a 60 to 70°F shift-in the duc'tile io brittle transiiotn temperatures due to, exposure to elevaited temperature, but no decs`e in. upper sbhe-l f .energy:. The fracture appearance -of each Charpy specdmen from the Va`ious -mterials i's sown, in Figu-r es; 5-5 th-rough 5-8, ad sho`wan' nresg dute or 'tugher' appearance with.increasing test temperature. A typicail 1instrUofieited 'Charpy curve, representing the curves of Iboh: Capsul.e TI-330 and Cap~sule W/-290., 'ispresented In. Figure 5-9.ý 80928: l:b102984 5:-4

Cap sle. W-290: The results of the Charpy v-notch impact tests per.ormed on -'the' var'.US manteiah con tained in irradiated 9Capsul*0* i; i a1.09 x i109 n/cm2 , are 'preserAied "in T6ables e 5-0 through.. 5-17 and Figures .10 5-7 th eorough 5-13.: A, summary, of. t-he transi t ion temperat*urre increases and upper Shelf energy decregases. for the Capsule W290 materal is ,shown in Table 5-18. Ir"di aiti f the vessel in-h'ter di ate shel course:p'late D,38031 (tran sverse of oNiethati,6f) to 1.09. x .1019 n6cm2 (:Fiigure 5-40G) resuflted iri30 and 50 ft-lb transitibon temperature inceases of 155 :and 16.0F,. ,respectively, an an upperk ThelIf' -V, decrease of 18 ft*-lb. rradiatiýon of th vessel interedjate shell, plate 'material (longitudinal orientation) to .9o x109 n/cm2 (Figuqe 5-2i1) resulted in 30 :and 50 -- ft-lb transiti-ion,--.temperature jin.cqreases, of 175,. and 180FF respecttively,- and an upper sheif energyidecrease. of 43 ft-lb:, Welld me~tal i;rrad.i~a'tid'.to 1.*!09 *X 1O!9 n/'cm2 *(F~igore *5*.*2?),. r*S]ted in*.- 30 and .50 f~t-lb" tran~siti*on tempera~ture increeases of; 290 *arid -. 3000F; t*e~sp'eCtivei!y, and an upper shelf iergy decreaseof 54-nu -l enrbg.. Weld tx to 1.09 10",hl"

            -AZmetralirradiated                            F         4n....

r :- s' Isd"l3'd b30 transition temperature increases of 235 and' 50 ft!b 0

                                                                      ý A and 2"45ý   F, respectively, and; an uPper shelf- energy decrease             of    44  fft-l b..
*The~fr'actuire appear ance .of eac h i rrad i a~tedCh a-rpy'i spec imen *:from ,the v ar*ious.

mater ads is shown in.Figures 5-14 xnc through 5-17 ad show -an reasin5,f duct'i le

,or ,toughe~r. *apPea~rance; wifth i ncreasi ng test%t~iemperalturel.

3Figured 5-18 shows- a comparison of- tuhe 30 ft-h b trans'ition

                                                               -temperfa                 tude24F mintCrease s for theni.a F1rs PI 5i.t*d      Survei*lsahce ,iaeria s w               predi ai'h     ted increases usi ng the-rmethods of NRC, Regurl atoyo        Gui dei ii.99, Revi sion.

The regulatory curves used for comparison were developed from the average copper and phosphorus contents (averages of the analyses presented in Tables 4-1 and 5-1) of plate D-3803-1 and the weld metal. This comparison shows that the plate transition temperature increases resulting from irradiation to 1.09 X 10 1 9 n/cm2 are less than predicted by the Guide for plate D-3803-1. The weld metal transition temperature increase resulting from 1.09 x 10i19 n/cm2 is greater than predicted by the Guide. This can be explained by the high nickel content of the weld metal. It is widely recognized today that nickel has a profound effect upon the irradiation damage of reactor vessel materials, whereas the current revision of Regulatory Guide 1.99 does not incorporate this important variable. 5-5. TENSION TEST RESULTS Capsule T-330: The results of the thermil capsule tension tests performed on plate D-3803-1 (longitudinal orientation) and weld metal are shown in Table 5-19 and Figures 5-19 and 5-20, respectively. These results show that the thermal environment produced little change in the 0.2 percent yield strength of the plate and weld material. Fractured tension specimens for each of the materials are shown in Figures 5-22 through 5-24. A typical stress-strain curve for the tension specimens, representing the curves of both Capsule T-330 and Capsule W-290, is shown in Figure 5-25. Capsule W-290: The results of the irradiated capsule tension tests performed on plate D-3803-1 (longitudinal orientation) and weld metal irradiated to 1.09 x 1019 n/cm2 are show in Table 5-20 and Figures 5-26 and 5-27, respectively. These results show that irradiation produced an increase in the 0.2 percent yield strength of approximately 20 ksi for plate D-3803-1 and of approximately 30 ksi for the weld metal. Fractured tension specimens for each of the materials are shown in Figures 5-29 through 5-31. 8092B: lb-1029845- 5-6

TABLE 5-18 EFFECT OF IRRADIATION AT 1.09 x 1019 (E >1 MV) ON THE NOTCH- TOUGHNESS PROPERTIES,- OF THE PALISADES SURVEILLANCE VESSEL-MATERIALS. Average* Average. 35 mil Average Average Energy .Absorption 30 ft-lb Temp r(.F) Lateral ExipanSiion 1Temp :(T) 50 ilt.-lb Tempq(TF) at Full1 Shear (f.t-lb) Material Unirradiated ti-adiated' 0T' 'Unitrradiated irradiated 'AT Un'irradiated Irradiated AT Unirradiated Irradiated S(f.t-lb) Pla'te 25 180 155 *25 1§5 170 55 215 1660 102 84 .18 D0-380371: P.la te '0 175 175' .5 190' 185 20 '.200 180. 155 112. 43 0-3803-1 (Lo-ngitudihnal) Weld Mea 85 205l 290 -75 .240- 315. -50 ,250* ,3006 118 64. 54 HAZ Metail -90 145' 235; -ý55 160: .215 ý45 l8ff 245 4 16 72, 44:

f3/8 1:00.

                                  ,o2,
       -                                     0-I/

50 1000

       -3,
                                                                         ~~0, S OUNiBRRADiATED             ..-.... 0
                                                             /O .!

100 " I0IRRAD"IATED ' 30 0'6 U/liIl'llJ(r Fiue54.,'raitdCpU'~.hr*VNthIpat' rpete 5eOPae 3haiiae

• nereit 400 (Tr.nUre.r~n~~~n). i55°'~tj)6 (Tases Or 2BUbO19453 91984

..Zoo

                ,                 -bo0              5-8,6ao 80§9

   '2 ma 0

OW mpa 0 ma 00 map

r. 50.

t1,00 Y31PAt3 2906 Z(7 Figure 5-11. Irradiat6ed Capsule Charpy ,V-Notch Impact Properties. forPalisades Intermediate; Shell P;lateD,-3803-1 (Longi tudinal Orientation)

I wCX.,-P- 140 14 WESTINGHOUSE CLASS 3 (Non-Proprietary) ANALYSIS OF CAPSULE W- 110 FROM THE CONSUMERS POWER COMPANY P-AISA.DES REACTOR VESSEL. RADIATION SU-RVEILL,.ANCE PROGRAM I CONTROLLED COPy ERC

SECTION 1.0o

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance CapsuleW-1 10,the ,second Vessel wall capsUle !assembly"to be removed f:rom the Consumers Power Company Palisades rteactor, pressure vesseL led to the:f611owing conclusions: o Te capsUle received an average fast neutron fluednceof 1.779 x YWi0 n/cm 2 (E > 1,0 MeV: after 9.95 EFPY of:plant operaton., O I~radiation of the reoto vessel intermediate shell plaie D-3803-I Charpy specimens,,oriented with te longitdin axis ofthe specmen parAllel to :th major rolling dif on (longitudinal orientation), to 1.7791. 10' :n/cm- ,(E.> 10. Me resulted in a 30 ft-lb transition temperature increase of 180"F and a0 ft-lb transifion temperature-increase of190oF. This 'tesultsin han irradiated 30 ft-lb transition temperature of 1t80F and an irradiated 50 rft~lbtansition" temperaure of 2100 F' for longitudinally oriented spcimens. o irradiation of thesurveillance- weld met ChIrpy spIem to 1.,779 x l0' n/cm 2 (E 1.0 MeV) resuled~in*a 30 ft.-lb tition tempa 'increase of-314 0 F and a.50 ft-lb transition temperature increase of 355 PF. This results in An irradiated,304ft-b transition temperature of 2290 F and ;an irradiated 50ft-b, trtasi tion temperature of. 3059,.F for the weld metal. Irradiation ofthe reactoryessel weld Heat-Affectqd-Zone HAZ) metal Charpy specimens -to 1)779 :x ~i0 n/cm 2 (E> i.0 MeV.) resuitedi a 30 f-lb' transiition temperature;inqease of 2,0 0 F and la 50ýft-lbtransitiontemp~tarture increase of '275*F.R Th*isresufltsin an irradiated 301 ft-lb transition.'temperature of 150F and anirritadiAted 50 ft-lb trahsitiontemiperatureof 2,10iF

for thae weld rAZ metal.

o Irradiation of the-reactor vessel Correlation Monitor StandardReference Material.(SRM) metal Charpy specimens to 1.779 x i9 ni/cm2 .(E>: 1.0 MeV)resulte in a.30 ft-lb,,trnsition

                 ;tempeature increase 0f 148 0 F and1a 50 ft-lb t    ns      perae increas'eof 158 0F., This results in an irradiated 30 ft-lb transition temperature of 163F and an'irradiated 50 ft-lbý transition temperature of I03IF for the weld HAZ metal.

I4

o Irradiation of intermediate shell plate D-3803-1 (longitudinal orientation),to 1L779 x 10'9 n/cm2 (E > 1.0 MeV) resulted in an irradiated average upper shelf energy decrease of 52 ft-lbs, resulting in an irradiated upper shelf energy of 103 ft-lbs. o The average upper shelf energy of the weld metal decreased 56 ft-lb after irradiation to 1,779 x 10' n/cm2 (E > 1.0 MeV). This results in an irradiated upper shelf energy of 62 ft-lb for the weld metal specimens. o The average upper shelf energy of the weld HAZ metal decreased 35 ft-lb after irradiation to 1.779 x i0'9 n/cm2 (E > 10 MeV). This results in an irradiated upper shelf energy of 81 ftlb for the weld HAZ metal. o Irradiation of SRM metal to 1.779 x 101" n/cm2 (E > 1.0 MeV) resulted in an irradiated average upper shelf energy decrease of 34 ft-lbs, resulting in an irradiated upper shelf. energy of 99 ft-lbs. o The surveillance Capsule W- 110 test results indicate that the 30 ft-lb transition temperature shift of the surveillance materials is in good agreement with Regulatory Guide 1.99, Revision 2 predictions and that the upper shelf energy decrease of the surveillance materials, except for the weld metal, is less than the Regulatory Guide 1.99, Revision 2 predictions (Table 5-8). o Per Reference 6, the Surveillance Capsule Removal Schedule will not be generated as part of this analysis. 1-2

The extensometer gage length is 1.00 inch., The extensometer is rated as Class B-2 per ASTM 1 E83-93t 71 Elevated test temperatures were obtained with a three-zone electric resistance split-tube furnace with a 9-inch hot zone. AIU tests were conducted in air. Because of the difficulty in remotely attaching a thermocouple directly to the specimen, the following procedure was used to monitor specimen temperature. Chromel-alumel thermocouples were inserted in shallow holes in the center and each end of the gage section of a dummy specimen and in each grip. In the test configuration, with a slight load on the specimen, a plot of specimen temperature versus upper arid lower grip and controller temperatures was developed over the range of room temperature to 550'F (288°C). The upper grip was used to control the furnace temperature. During the actual testing the grip temperatures were used to obtain desired specimen temperatures. Experiments indicated that this method is accurate to + 2ot/4tJ. The yield load, ultimate load, fracture load, total elongation, and uniform elongation were determined directly from the load-extension curve. The yield strength, ultimate strength, and fracture strength were calculated using the original cross-sectional area. The final diameter and final gage length were determined from post-fracture photographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percent reduction in area was computed using the final diameter measurement. 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 W- 110, which was irradiated to 1.779'x 10'" n/cm2' (E > 1.0 MeV), are presented in Tables 5-1 through 5-6 and are compared with unirradiated results &t2 as shown in Figures 5-2 through 5-5. The transition temperature increases and upper shelf energy decreases for the Capsule W- 110 materials are summarized in Table 5-7. Irradiation of the reactor vessel intermediate shell plate D-3803-1 Charpy specimens oriented with the longitudinal axis of the specimen parallel to the major rolling direction of the plate (longitudinal orientation) to 1.779 x 10'9 n/cm2- (E > 1.0MeV) (Figure 5-1) resulted in a 30 ft-lb transition temperature increase of 180IF and in a 50 ft-lb transition temperature increase of 190 0 F. This results in an irradiated 30 ft-lb transition temperature of 180°F and an irradiated 50 ft-lb transition temperature of 210°F (longitudinal orientation). 5-3

The average Upper Shelf Energy (USE) of the intermediate shell plate D-3803-1 Charpy specimens (longitudinal orientation ) resulted in an energy decrease of 52 ft-lb after irradiation to 1.779 x 10"9 n/cm- (E > 1.0 MeV), This results in an irradiated average USE of 103 ft-lb (Figure 5-2) Irradiation of the surveillance weld metal Charpy specimens to 1.779 x 10'9 n/cm2 (E > 1.0 MeV) (Figure 5-3) resulted in a 314OF increase in 30 ft-lb transition temperature and a 50 ft-lb transition temperature increase of 355°F. This results in an irradiated 30 ft-lb transition temperature of 229 0F and an irradiated 50 ft-lb transition temperature of 305°F. The average USE of the reactor vessel core region weld metal resulted in an energy decrease of 56 ft-lb after irradiation to 1.779 x 10'9 n/cm' (E > 1.0 MeV), This results in an irradiated average USE of 62 ft-lb (Figure 5-3), Irradiation of the reactor vessel weld Heat-Affected-Zone (HAZ) metal specimens to 1.779 x 1019 n/cm2 (E > 1. MeV) (Figure 5-4) resulted in a.30 ft-lb transition temperature increase of 240°F and a 50 ft-lb transition temperature increase of 275 0F. This results in an irradiated 30 ft-lb transition temperature of 150*F and an irradiated 50 ft-lb transition temperature of 210 0 F. The average USE of the reactor vessel weld HAZ metal experienced an energy decrease of 35 ft-lb after irradiation to 1.779 x 10'9 n/cm2- (E > 1.0 MeV). This results in an irradiated average USE of 81 ft-lb (Figure 5-4). Irradiation of the reactor vessel Correlation Monitor Standard Reference Material (SRM) specimens to 1.779 x 10'9 n/cm'- (E > 1.0 MeV) (Figure 5-5) resulted in a 30 ft-lb transition temperature increase of 148°F and a 50 ft-lb transition temperature increase of 158 0 F. This results in an irradiated 30 ft-lb transition temperature of 163°F and an irradiated 50 ft-lb transition temperature of 2030 F. The average USE of the reactor vessel Correlation Monitor Standard Reference Material (SRM) experienced an energy decrease of 34 ft-lb after irradiation to 1.779 x 1019 n/cmr2 (E > 1.0 MeV). This results in an irradiated average USE of 99 ft-lb (Figure 5-5). The fracture appearance of each irradiated Charpy specimen from the various materials is shown in Figures 5-6 through 5-9 and show an increasingly ductile or tougher appearance with increasing test temperature. 5-4

A comparison of the 30 ft-lb triaisition temperawre.ini6eases and upper. shelf energy decreases for the various Palisades surveillance materials With predicted values-using *ie met'hods of NRC Regulatory Guide [.99,.Revision. 219M is. presentedi in Table 5-8. This comparison indicates, that the-30 ft-lb transition temperature shiift o0fthe s'uveillance materials is in good agreementiwith the. Regulatory Guide 1.99, Revision 2 peictli ons and "the USE decrease of the surweillance materials, except the weld

• metal,.is less than the Regulatory Quide 199. Revision 2 predictons.

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

'5.3 Tension-Test Results The results of. the te6sion tests 2p&rforied on.the.various materials contained in' Capsule-W- .10 irradiated to 1.779. x 10- n/cm (E>-[0 MeV) ~aepresented in Table 5-9 ad arecompared with:

urirradiated resultst 3 as shown in Figures,5 110 through 5-12. The results iof the tension tests performedon theintermediate shell plate D`3803-1 (longitudinal orientation) indicated that irradiation tol1.779 x 10',n/cm2 (E> 1.0 MeV).caused an 18 to 23 ksi increasein the 0.2 Percent offset-yield strengthahd ad12 to 15 ksi increase in the ultimate tensile

,strength, when compared to nirradiated datat2 r (Figure 'I0).

The results of 'the tension tests performed on the suirveillance Weld"imetal indicated tht; irradiation 1to 1.779 kx 109 n/(cm2 (Et> 1.0 MeV) caused a 17 to 35,ksi increase in the 02 pecent offset yield streqngthý aqnda 17 to 27 ksi increase in the ultimatetensile strength when compared to'unirradiated data1 12 *(ig"re 5-11),. The resuli- of the, tension tests performed on the heat-affected zone (HAZ)nmeal- indicated that irradiati6nto 1I.779 x 10'9 ncm2 'E,> 1.0 MeV) caiutsed a 12 to 20 ksi increase in the 0.2, percent offset;yild ,strength a a 15 to 17 ksi increase in the ultimate. tensile strengt when compared to unirradiated data!' 1 (Figre-1) The fractured tension specimens for-the surveillance materias are show0nindFigures 5-13'through 5-45;. The engine g stess-stain curves for the tensile tests are shown in Figures-5=16;through 5-21. 55,

TABLE 5-7 Effect of Irradiation to 1.779 X 10'9 n/ccm 2 (E > 1.0 MeV) on the Notch Toughness Properties of the Palisades Reactor Vessel Surveillance Materials Average 30 fR-lb (a) Average 35 mil (a) Average 50 ft-lbt0 - Average Energy Absorption Transition Temperature (*F) Lateral Expansion Temperature (*F) Tranitilon Temperature (OF) at Full Shear (ft-tb) M aterial-.......... Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradlated Irradiated AT Unirradiated Irradiated AE Plate D-3803-1 0 180 180 5 200 195 20 210 190 155 103 -52 Weld Metal -85 229 314 -75 280 355 -50 305 355 118 62 -56 HAZ Metal -90 150 240 -55 187 242 -65 210 275 116 81 -35 SRM 01MY 15 163 148 25 192 167 45 203 158 133 99 -34 (a) "Average" is defixed as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-1 through 5-4).

TABLE 5-28 Coniparison of the Palisades Surveiliance Material 30, ft-lb Transition TemperatUtre Shifts and upper Shlf Energy Decreases withRegulatory Guide- 1.99, Revision 2 PredictiOns. 304fl-lb.Transition Upper Shelf-Energy Tempherature Shift Decrease Fl"eice Prgedctedi-(a) Measured Predicted:(a), Measured Mafterial Caps-ule (O~nci 2 O)(F  %  % E:, 1.0MeV) _______ PIate-D-380341 A,240 6.0 2231 205 48 35 (rsvre W+-....90 1.09 4`59 155 33 18 1- 10 17790 -0 37 -- Plate. 0!"3803-:1' A-240 6.w 223 205.48 42 Li, '(Longitudinal) W-290 1.09 159 175 33 28 -iJ W,

                            ..                 779 1.-                 180                   180    .        37                      34 Weld
        .      Metal                      "        .     .,     423          ..        35....          56                      5 V.-24 009.30                                               290             40                      46 W-" 10           1.779.341                    -            314                       44            47 A,240,:.                            . -             .... 290                                     52-HAZ MetAl                                         *.

W-290. 1.09L: - 23 0 "38 V416 1.7 . 240

42 -- 30 SRM 1i0 1.779

                                               .8                                       148            31                      261 (a) Based on Regulatory Guide L99, Revision 2 methodology...                                    Reference .42.

(0 C)

                     -150     -100      -50        0       50     100   150   200    250 100 "80 S60 U-r 1" 40 20 0

100 25 U, o 2.0 a: 60 1.5 Uj 40 1.0 cr20 0J 0.5

              , 0                                                                         0 200 180                                                                        240 160 200 140 I-  120                                                                        160
          +1
                                                                                              .- )

(4~ v 100 w 120 La 80 La 60 80 40 40 20 0 - 0

                         -200      -100         0        100     200    300    400    500 TEMPERATURE (OF) o NADIA1E

• RDT TO A,M E IF L9 t0in/cmZ x (E)

U NeV) Figure 5-2 Charpy V-Notch Impact Properties for Palisades Reactor Vessel Intermediate Shell Plate D-3803-1 (longitudinal orientation) 5416

17 BWXT Services, Inc. ANALYSIS OF CAPSULE W-100 FROM THE NUCLEAR MANAGEMENT COMPANY PALISADES REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FEBRUARY 2004 1295-001-03-08:00 FEBRUARY 2004 125010-80 II2004I FEBRUARYI

BVIXT Services, Inc. Analysis of Palisades Capsule W-100 4

4.0 DESCRIPTION

OF THE PALISADES REACTOR VESSEL SURVEILLANCE PROGRAM Prior to initial plant start-up, ten surveillance capsules were inserted into the Palisades reactor vessel near the reactor vessel wall as shown in Figure 4-1. The capsules contain specimens made from intermediate shell plate D-3803-1, heat-affected-zone (HAAZ) metal fabricated by welding intermediate shell plates D-3803-2 and D-3803-3 with submerged arc process using Linde 1092 flux, and weld metal fabricated by welding intermediate shell plates D-3803-1 and D-3803-2 with submerged arc process-using Linde 1092 flux and a MIL-B4 electrode and a 1/16-inch diameter Nickel-200 wire feed. Capsule W-100 was removed after 16.93 effective full power years (EFPY) of plant operation. This capsule contained Charpy impact and tensile specimens made of intermediate shell plate D-3803-1, submerged arc weld metal, and HAZ metal as describe above. All test specimens were machined from material taken at least one plate thickness from any water quenched edge. The surveillance plate material was cut directly from the intermediate shell course plate after being subjected to 1.75 hours of interstage and 30 hours of final heat treatment at 1150 . 250 F. Charpy impact specimens from surveillance plate D-3803-1 were machined in the longitudinal orientation (longitudinal axis of the specimen longitudinal to the major working direction). The weld Charpy impact specimens were machined from the weldment such that the long dimension of each Charpy specimen was perpendicular to the weld direction. The notch of the weld metal Charpy specimens was machined such that the direction of crack propagation in the specimen was in the welding direction. Tensile specimens from surveillance plate D-3803-1 were machined with the major axis both in the tangential and longitudinal orientations. Tensile specimens from the weld metal were oriented with the long dimension of the specimen perpendicular to the weld direction. The chemical compositions of the surveillance materials are presented in Table 4-1. The chemical analysis reported in Table 4-1 was obtained from unirradiated material used in the surveillance program [3]. Capsule W-100 contained dosimeter wires of uranium, sulfur, iron, nickel, titanium, and copper. Cadmium covers were used for materials that have competing thermal activities (i.e., uranium, nickel, and copper). Dosimeters are used to determine flux spectrum and flux attenuation through the thickness of the Charpy specimens.

• - The temperature monitor assemblies consist of four separate coil-shaped monitors, each of different composition and thus having different melting points. They are identified by varying capsule lengths, with melting temperatures increasing with increasing capsule length. The alloys compositions and

-- melting points are listed as follows. Composition Melting Point 92.5% Pb, 5.0% Sn, 2.5% Ag 536 0F 90.0% Pb, 5.0% Sn, 5.0% Ag 558 0F 97.5% Pb, 2.5% Ag 580OF 97.5% Pb, 0.75% Sn, 1.75% Ag 590OF The arrangement of the various mechanical specimens, dosimeters, and thermal monitors contained in Capsule W-100 is shown in Figure 4-2.

BWXT Services, Inc. Analysis of Palisades Capsule W-100 5 TABLE 4-1 31 Chemical Composition (wt%) of the Palisades Reactor Vessel Surveillance Materials[ Weld Weld Weld Weld Element D-3803-1 D-3803-2 E-3803-3 D-3803-3/ D-3803-3/ D-3803-2/ D-3803-2/ D-3803-2 D-3803-2 D-3803-2 D-3803-1 Root Face Root Face Si 0.23 0.32 0.24 0.24 0.25 0.25 0.22 S 0.019 0.021 0.020 0.009 0.010 0.010 0.010 P 0.011 0.12 0.010 0.011 0.012 0.011 0.011 Mn 1.55 1.43 1.56 1.08 1.03 1.01 1.02 C 0.22 0.23 0.21 0.098 0.080 0.088 0.086 Cr 0.13 0.42 0.13 0.05 0.04 0.05 0.03 Ni 0.53 0.55 0.53 0.43 1.28 0.63 1.27 Mo 0.58 0.58 0.59 0.54 0.53 0.55 0.52 AI(T) 0.037 0.022 0.037 Nil Nil Nil Nil V 0.003 0.003 0.003 Nil Nil Nil Nil Cu 0.25 0.25 0.25 0.25 0.20 0.26 0.22

BWXT Services, Inc. Analysis of Palisades Capsule W-100 12 Table 6-1. Charpy Impact Data for the Palisades W-100 Capsule Plate D-3803-1 Specimen Number Temperature, 0F Impact Energy, Lateral Shear Fracture, % ft-lb . Expansion, mUls Transverse 213 70 9.5 2 0 255 110 14.0 7 5 25E 150 27.5 19 20 25B 200 44.0 32 40 25D 225 52.5 39 50 211 240 50.0 36 50 257 250 71.5 54 70 256 260 69.0 47 90 214 270 71.0 54 95 25A 285 77.0 56 100 25C 300 76.5 63 100 212' 325 67.5 56 100

          ..............                _     Longitudinal 152                      70                   5.5                 1                0 151                     110                  14.0                 7                5 153                      130                  29.5                 18              25 157                     175                  44.0                27               40 15A                      200                  45.0                34               45 154                     225                  74.4                51               70 15Y                      250                  86.5                50               85 156                     260                  73.0    -           50               80 15C                      270                  102.0               57               95 15B                      280                  100.5               58               100 15U                      300                  104.5               72               100 155                      325                 101.0                68               100

I C I~~. f* I I f I I I BWXT Services, Inc. Analysis of Palisades Capsule W-100 14 Table 6-3. Comparison of Palisades Surveillance Material (Capsule W-100) 30 ft-lb Transition Temperature Shifts (Position 2.1) and Upper Shelf Energy Decreases with Regulatory Guide 1.99 Revision 2 Predictions Material Unirradiated Capsule Measured Predicted Unirradiated Capsule Predicted USE 30 ft-lb W-100 30 ft-lb 30 ft-lb Temp. USE W-100 (ft-lb) Temp. 30 ft-lb Temp. Shift Shift (ft-lb) USE (OF) Temp. (OF) (OF) (ft-lb) D-3803-1 Tran03-s 18.3 160.8 142.5 189.1 101.6 73.0 61.7 Transverse D-3803-1 Di30- -0.5 158.6 159.1 189.1 .. 154.8 102.0 93.8 Longitudinal Weld Metal -86.6 218.8 305.4

• 117.7 51.8 63.7 HAZ Metal -89.6 101.4 191.0 ** 115.5 59.7 **

           *Could not be calculated because RG 1.99 Rev 2 Table 2 does not provide chemistry factors for base metals with Ni content greater than 1.2 wt%.
           ** The RG 1.99 Rev 2 CF tables do not cover HAZ metal Table 6-4.

Tensile Properties of the Palisades Capsule W-100 Materials Material Specimen Test 0.2% Ultimate Fracture Fracture Fracture Uniform Total Reduction Number Temp Yield Strength Load Stress Strength Elongation Elongation In Area Strength (Ksi) (MIp) (Ksl) (Ksl) (%) (%) (%) HAZ 4OK 70 92.0 106.3 3.60 175.9 73.4 6.0 N/A 58.3 4JJ 200 88.6 101.3 3.47 171.4 70.7 4.9 N/A 58.8 4JE 550 83.1 98.9 3.84 146.8 78.2 4.3 NIA 46.7 D-3803. 11 70 89.8 108.2 3.51 190.6 71.4 10.8 23.8 62.5 1 IEY 250 83.0 101.7 3.35 169.9 68.3 9.9 21.6 59.8 (Long.) 1E7 550 76.7 98.3 3.53 150.1 71.9 8.8 19.2 52.1 Weld 3DT 70 101.7 115.0 4.52 192.1 92.0 11.7 23.5 52.1 Metal 3DP 300 96.4 109.7 4.59 167.1 93.5 9.4 16.6 44.0 3DM 550 92.9 109.8 4.78 178.6 97.3 7.9 13.6 45.5 NA: Specimen failed outside the gage length.

BWXT Services, Inc. Analysis of Palisades Capsule W-100 15 Palisades Nuclear Plant - Base (Transverse) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 10:22 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat # 1 PALISADES UNIRR SA302BM TL C-1279-3 2 PALISADES W-290 SA302BM TL C-1279-3 3 PALISADES W-100 SA302BM TL C-1279-3 4 PALISADES A-240 SA302BM TL C- 1279-3 120 100 80 0 LL 60 w z 40 20 0 i::

                -200       -100          0           100          200         300        400           500 Temperature in Deg F o Set1                      Set2                  0 Set3                  6 Set4 Results Curve        Fluence     LSE     USE         d-USE       T @30        d-T @30       T @50       d-T @50 0            2.2     101.6           .0         18.3          .0        49.1            .0 2         9. 26E18     2.2      83. 8      -17. 8       176.3        158.0      202.5         153.4 3         2. 09E19     2.2      73.0       -28.6        160.8        142.5      206.3         157.2 4         4. 01E19     2.2      68.4       -33.2'       212.6        194.3      265.1        216.0 Figure 6-1. Charpy Impact Energy vs. Temperature for Palisades Surveillance Plate D-3803-111 (Transverse Orientation)
                                                                                                          *0 I

BWXT Services, Inc. Analysis of Palisades Capsule W-100 16 Palisades Nuclear Plant - Base (Transverse) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 10:25 AM Data Set(s) Plotted Curve Plant Capsule Material Or!. Heat # 1 PALISADES 2 IUNIRR SA302BM TL C-1279-3 PALISADES W-290 SA302BM TL C-1279-3 3 PALISADES W-100 SA302BM TL C-1279-3 4 PALISADES A-240 SA302BM TL C-1279-3 100 80 60 0 40 20 " 0

                  -200        -100          0            100          200         300    400      500 Temperature in Deg F o Set1                  o Set2                      c Set3              a Set4 Results Curve       Fluence     LSE      USE         d-USE        T @35         d-T @35

-1 0 .0 78.6 .0 23.5 .0 2 9. 26E18 .0 69.3 -9.3 181.7 158.2 3 2. 09E19 .0 57.3 -21.3 205.9 182.4 4 4. 01E19 .0 66.3 -12.3 219.2 195.7 Figure 6-2. Lateral Expansion vs. Temperature for Palisades Surveillance Plate D-3803-1 (Transverse Orientation) tc~fJ~

BWXT Services, Inc. Analysis of Palisades Capsule W-100 17 Palisades Nuclear Plant - Base (Transverse) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 10:23 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat # 1 PALISADES UNIRR SA302BM TL C-1279-3 2 PALISADES W-290 SA302BM TL C-1279-3 3 PALISADES W-100 SA302BM TL C-1279-3 4 PALISADES A-240 SA302BM TL C-1279-3 120 100 80 I-. cc 60 0 C. 40 2011 00

                  -200         -100          0           100          200           300    400       500 Temperature in Dog F o Set1                    a Set2                   0 Set3                a   Set 4 Results Curve         Fluence       LSE      USE        d-USE        T @50        d-T @50 0                 .0     100.0           .0         85.5            .0 2         9. 26E18          .0     100.0           .0        193.6        108.1 3           2. 09E19        .0     100.0           .0        218.7        133.2 4           4. 01E19        .0     100.0           .0        243.5        158.0 Figure 6-3. Percent Shear vs. Temperature for Palisades Surveillance Plate D-3803-1 (Transverse Orientation)

BWXT Services, Inc. Analysis of Palisades Capsule W-100 18 Palisades Nuclear Plant - Base (Long.) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 09:49 AM Data Set(s) Plotted Curve Phlt Capsule Material On. Heat # 1 PALISADES UNIRR SA302BM LT C-1279-3 2 PALISADES W-290 SA302BM LT C-1279-3 3 PALISADES W-110 SA302BM ,LT C-1279-3 4 PALISADES W-100 SA302BM LT C-1279-3 5- PALISADES A-240 SA302BM LT C-1279-3 200 175 150 125 S100 - w z 75 50 25 0 r

                   -200        -100           0          100           200          300        400           500 Temperature In Deg F o Set11                 Set2             0 Set3                   Set4             v Set5 Results Curve         Fluence    LSE       USE          d-USE       T @30         d-T @30       T @50       d-T @50 0            2.2      154.8            .0          -. 5          .0        25.3            .0 2         9. 26E18I    2.2      112.3        -42.5        176.3        176.8        198.0        172.7 3         1L 66E19     2.1      102.7        -52.1        179.0        179. 5       203.5        178.2
 -4

2. 09E19 2.2 102.0 -52.8 158.6 159. 1 190.4 165. 1 5 4. 01E19 2. 1 92.3 -62.5 204.6 205. 1 243.0 217.7 Figure 6-4. Charpy Impact Energy vs. Temperature for Palisades Surveillance Plate D-3803-1 (Longitudinal Orientation)

BWXT Services, Inc. Analysis of Palisades Capsule W-100 19 Palisades Nuclear Plant - Base (Long.) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 09:51 AM Data Set(s) Plotted Curve Plant Capsule Material Or. Heat # 1 PALISADES UNIRR SA302BM LT C-1279-3 2 PALISADES W-290 SA302BM LT C-1279-3 3 PALISADES W-110 SA302BM LT C-1279-3 4 PALISADES W-100 SA302BM LT C-1279-3 5 PALISADES A-240 SA302BM LT C-1279-3 100 80

        .2      60 0

a C 40 0 20 0

                  -200        -100           0           100           200          300     400       500 Temperature in Deg F 0 SetI              a Set2                0 Set3

• Set 4 v Set5 Results Curve Fluence LSE USE d-USE T @35 d-T @35 1 0 .0 87.8 .0 10.0 .0 2 9. 26E18 .0 81.0 -6.8 186.9 176.9 3 1. 66E19 .0 75.3 -12.5 190.0 180.0 4 2. 09E19 .0 63.8 -24.0 195.7 185.7 5 4. 01E19 .0 80.0 -7.8 214.4 204.4 Figure 6-5. Lateral Expansion vs. Temperature for Palisades Surveillance Plate D-3803-1 (Longitudinal Orientation)

BWXT Services, Inc. Analysis of Palisades Capsule W-100 20 Palisades Nuclear Plant - Base (Long.) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 02/03/2004 09:50 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat # 1 PALISADES UNIRR SA302BM LT C-1279-3 2 PALISADES W-290 SA302BM LT C-1279-3 3 PALISADES W-110 SA302BM LT C-1279-3 4 PALISADES W-100 SA302BM LT C-1279-3 5 PALISADES A-240 SA302BM LT C-1279-3 120 100 80

• A.,... ,

        'U S

a, 60 C 2S Phil II 0~ 40 20 0 0,74--*- T r iD V 0

                 -200         -100          0           100             200               300      400       500 o SetI               a   Set 2           0 Set 3                          Set 4         v Set5 Results Curve         Fluence      LSE      USE         d-USE       T @50             d-T @50 0               .0     100.0           .0            75.0                 .0 2          9. 26E18        .0     100.0           .0         203.5            128.5 3          1. 66E19        .0     100.0           .0         220.5            145.5 4          2. 09E19        .0     100.0           .0          195.7           120.7 5          4. 01E19        .0     100.0           .0         231.0            156.0 Figure 6-6. Percent Shear vs. Temperature for Palisades Surveillance Plate D-3803-1 (Longitudinal Orientation)

C00(

W-100 PLATE (LONGITUDINAL) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01/08/2004 10:29 AM Page 1 Coefficients of Curve 1 A = 52.1 B = 49.9 C = 73.2 TO = 193.41 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=102.0(Fixed) Lower Shelf Energy=2.2(Fixed) Temp@30 ft-lbs=158.6 Deg F Temp@50 ft-lbs=190.4 Deg F Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 n/cma^2 120 100 80 0 0 P 60 z 0 40 ./ 20

                                              /0 0

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

70. 00 5. 5 50 5.51 - .01 110. 00 14.( 30 11.47 2. 53 150.00 29. ! 50 25.55 3. 95 175.00 44. 30 39. 81 4. 19 200. 00 45. 30 56.58 -I1 .58 225. 00 74.5 50 72. 39 2. 11 250. 00 86. 5 0 84.47 2. 03 260. 00 73. 00 88.08 -15. 08 270. 00 102. 00 91.04 10. 96

W-100 PLATE (LONGITUDINAL) Page 2 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 nrcmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 280. 00 100. 50 93. 44 7. 06 300. 00 104.50 96. 86 7. 64 325.00 101.00 99. 33 1. 67 Correlation Coefficient = .978 I-

W-100 PLATE (LONGITUDINAL) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01/0812004 10:30 AM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 66.65 TO = 195.62 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Temperature at 50% Shear = 195.7 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 n/cm^2 120 100 L. 80 S60 U t.. 40 20 0 0 100 200 300 400 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

70. 00 .00 2. 25 -2.25 110. 00 5.00 7. 11 -2. 11

 ,150. 00                     25.00                              20.28             4.72 175. 00                     40. 00                             35.01             4.99 200. 00                     45. 00                             53.28           - 8 28 225. 00                     70.00                              70.71             -. 71 250.00                      85. 00                             83. 64             1. 36 260.00                      80. 00                             87. 34          -7.34 270.00                      95. 00                             90. 31            4.69

W-100 PLATE (LONGITUDINAL) Page 2 117 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 280. 00 100. 00 92.. 63 7. 37 300. 00 100. 00 95. 82 4. 18 325. 00 100. 00 97.98 2.02 Correlation Coefficient =.992

W-100 PLATE (LONGITUDINAL) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01/08/2004 10:35 AM Page 1 Coefficients of Curve 1 A = 31.9 B = 31.9 C = 73.39 TO = 188.47 D = 0.OOE+00 Equation is A + B * [Tanh((r-To)/(C+DT))] Upper Shelf L.E.=63.8(Fixed) Lower Shelf L.E.=.O(Fixed) Temp.@L.E. 35 mils=195.7 Deg F Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 n/cmA2 80 70 60

       =E.

S50 (0 40 230

           -20 10 0

0 100 200 300 400 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 70.00 1.00 2.43 -1.43 110.00 7. 0,0 6. 73 .27 150.00 18.00 16.56 1.44 175. 00 27. 00 26.11 .89 200. 00 34. 00 36.87 -2. 87 225.00 51.00 46.59 4. 41 250. 00 50.00 53.75 -3.75 260.00 50.00 55. 85 -5.85 270.00 57.00 57.56 -. 56 I --

W-100 PLATE (LONGITUDINAL) Page 2 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: LT Capsule: W-100 Fluence: 2.09E19 n/cMA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 280.00 58. 00 58. 94

• 94 300.00 72. 00 60. 89 7i.11 325.00 68. 00 62. 29 5.71 Correlation Coefficient = .981

W-100 PLATE (TRANSVERSE) S CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01/08/2004 10:37 AM Page 1 Coefficients of Curve 1 A = 37.6 B = 35.4 C = 77.92 TO = 177.79 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper.Shelf Energy=73.0(Fixed) Lower Shelf Energy=2.2(Fixed) Temp@30 ft-lbs=160.8 Deg F Temp@50 ft-lbs=206.3 Deg F Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: TL Capsule: W-100 Fluence: 2.09E19 n/cm^A2 80 0

                                                                - 0 70                                                               0            0 60 U)
                                                          /0 050 40 z 30 20 10 0                      I                   I    I                   I         I '

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

70. 00 9.50 6. 39 3. 11 110.00 14.50 12. 77 1.73 150.00 27.50 25.48 2.02 200. 00 44.00 47. 42 -3.42 225. 00 52.50 56. 76 -4.26 240. 00 50.00 61. 07 - II. 07 250. 00 71.50 63. 41 8.09 260. 00 69.'00 65. 34 3. 66 270. 00 71.00 66. 93 4.07

W-100 PLATE (TRANSVERSE) Page 2

  .                Plant: PALISADES          Material: D-3803-1     Heat: C-1279 Orientation: TL      Capsule: W-100      Fluence: 2.09E19    n/cm^2 Charpy V-Notch Data Temperature                Input CVN                     Computed CVN           Differential 285.00                   77.00                             68.75                 8.25 300. 00                  76. 50                            70. 05                6.45 325.00                   67.50                             71.42               -3.92 Correlation Coefficient = .970

,1

W-100 PLATE (TRANSVERSE) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01/08/2004 10:38 AM Page 1 Coefficients of Curve 1 A =50. B = 50. C = 58.39 TO = 218.6 D =0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Temperature at 50% Shear = 218.7 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: TL Capsule: W-100 Fluence: 2.09E19 n/cmA2 120 100 80 U) 60 w,, IL a,. 40 20 0 0 100 200 300 400 Temperature in Deg F Charpy V-Notch Data V Temperature Input Percent Shear Computed Percent Shear Differential

70. 00 ' 00 .61 - .61 110.00 5.00 2. 37 2. 63 150. 00 20. 00 8.71 11. 29 200. 00 40. 00 34. 59 5.41 225. 00 50. 00 55. 46 -5. 46 240. 00 50. 00 67. 55 -17. 55 250. 00 70. 00 74. 56 -4.56 260. 00 90. 00 80.50 9.50 270. 00 95.00 85. 33 9. 67

W-100 PLATE (TRANSVERSE) Page 2 Plant: PALISADES Material: D-3803-1 . Heat: C-1279 Orientation: TL Capsule: W-100 Fluence: 2.09E19 n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 285.00 100.00 90. 67 9.33 300.00 100. 00 94.20 5.80 325. 00 100. 00 97. 45 2. 55 Correlation Coefficient = .975

W-100/ PLATE (TRANSVERSE) CVGRAPH 5.0.1 Hyperbolic Tangent Curve Printed on 01108/2004 10:39 AM Page 1 Coefficients of Curve 1 A = 28.65 B = 28.65 C = 77.19 TO = 188.4 D = O.OOE+00 Equation is A + B * [Tanh((T-To)l(C+DT))] Upper Shelf L.E.=57.3(Fixed) Lower Shelf L.E.=.0(Fixed) Temp.@L.E. 35 mils=205.9 Deg F Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: TL Capsule: W-100 Fluence: 2.09E19 n/crA2 80 70 60 In1 r-0 50 2.40 1! 30 20 10 0 0 100 200 300 400 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 70.0,0 2. 00 2.55 - 55 110.00 7.00 6. 64 36 150.00 19.00 15.47 3. 53 200. 00 32.00 32. 92 -. 92 225.00 39. 00 41.30 -2. 30 240. 00 36.00 45. 38 -9. 38 250. 00 54. 00 47.64 6. 36 260. 00 47.00 49.55 -2.55 270.00 54.00 51. 13 2. 87

W-100 PLATE (TRANSVERSE) Page 2 Plant: PALISADES Material: D-3803-1 Heat: C-1279 Orientation: TL Capsule: W-100 Fluence: 2.09E19 n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 285. 00 56. 00 52. 96 3. 04 300. 00 63. 00 54. 29 8. 71 325. 00 56. 00 55. 68 .32 Correlation Coefficient = .973}}