View source for JAFP-08-0067, Calculation No. FITZ-10Q-301, Revision 0, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts.

{{Adams
| number = ML082100455
| issue date = 02/15/2008
| title = Calculation No. FITZ-10Q-301, Revision 0, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts.
| author name = Jaeger M J, Lohse C S
| author affiliation = Structural Integrity Associates, Inc
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000333
| license number = 
| contact person = 
| case reference number = 10166220, JAFP-08-0067
| document report number = FITZ-10Q-301, Rev 0
| document type = Calculation
| page count = 24
}}

=Text=
{{#Wiki_filter:Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)
ATTACHMENT 3 to JAFP-08-0067 Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant Structural.Integrity Associates Calculation No .FITZ-10Q-301, Revision 0,"Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts," 2/15/2008 (Non-proprietary Version)Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary.
Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)
ATTACHMENT 3 to JAFP-08-0067 CONTENTS 1) SIA Calculation FITZ-10Q-301 (Non-proprietary Version)Calculation FITZ-IOQ-301 14 Pages Calculation Attachment A 8 Pages 22 Pages N Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary. 
/Structural Integrity Associates, Inc. File No.: FITZ-10Q-301 CALCULATION PACKAGE Project No.: FITZ-10Q PROJECT NAME: Analysis for Vessel Pressure-Temperature Curve Revision CONTRACT NO.: 10166220 CLIENT: PLANT: Entergy Nucle'ar Northeast James A. Fitzpatrick Nuclear Power Plant CALCULATION TITLE: Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts NON-PROPRIETARY VERSION Project Manager Preparer(s) 
&Document Affected  DocuentsAffted Revision Description Approval' Checker(s)
Revision Pages Signature Dae Signatures 
& Date 0 1-14, Initial Issue g Al -A8 /. w ....G. L. Stevens M. J. Jaeger 2/15/2008 2/15/2008 C. S. Lohse 2/15/2008 Page 1 of 14 F0306-O1RO Structural Integrity Associates, Inc.Table of Contents 1.0 IN TRODU CTION ...........................................................................................................................
4 2.0 TECHN ICAL APPROA CH .......................................................................................................
4 3.0 M ETH OD OLO GY ..........................................................................................................................
5 4.0 CA LCU LA TION S ...........................................................................................................................
7 5.0 CON CLU SION S .............................................................................................................................
8 6.0 REFEREN CES ................... 
............................................................................................................
9 APPENDIX A: NRC RVID2 DATABASE FOR JAFNPP ...............................................................
Al File No.: FITZ-1OQ-301 Revision:
0 Page 2 of 14/F0306-O01 RO 0 Structural Integrity Associates, Inc.List of Tables Table 1: JAFNPP ART Calculations for 32 EFPY ...............................................................................
10 Table 2: JAFNPP ART Calculations for 40 EFPY .................................................................................
11 Table 3: JAFNPP ART Calculations for 48 EFPY ...............................................................................
12 Table 4: JAFNPP ART Calculations for 54 EFPY ...............................................................................
13 List of Figures Figure 1: JAFNPP Fluence Determination in the Lower Shell #1 plate for 32, 40, 48 and 54 EFPY ...... 14 File No.: FITZ-IOQ-301 Revision:
0 Page 3 of 14 F0306-01 RO Structural Integrity Associates, Inc.

==1.0 INTRODUCTION==

The purpose of this calculation is to develop Adjusted Reference Temperature (ART) and Reference Temperature Shift (ARTNDT) values for the James A. Fitzpatrick Nuclear Power Plant (JAFNPP).
In accordance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2 (RG1.99), the ART and ARTNDT values will be developed for all Reactor Pressure Vessel (RPV) plates and welds exposed to fluence levels greater than 1.Ox 1017 n/cm 2 [1]'. Based on updated fluence calculations, ART and ARTNDT values are provided at four different state points: 32, 40, 48 and 54 effective full power years (EFPY). The values at 54 EFPY are applicable until the end of JAFNPP's extended operation period (60 years). Input is obtained as stated throughout.this calculation from References 
[1] through[10].2.0 TECHNICAL APPROACH, RKadiation embrittlementof RPV materials causes a decrease in the fracture toughness.
RG1.99.[1]
describes general procedures to calculate the effects of neutron irradiation embrittlement on the alloy steel used in RPVs. The ART values are used to determine the local fracture toughness of the RPV wall, according to ASME Code, Section XI, Nonmandatory Appendix A [2] and Nonmandatory Appendix G[3] evaluations.
(IThe fluence value of 1.Ox101 7 n/cm 2 is considered to be a lower bound value below which there are insignificant material effects due to irradiation, based on Section IIl.A of IOCFR50 Appendix H [8].File No.: FITZ-1OQ-301 Revision:
0 Page 4 of 14 F0306-O1RO VStructural Integrity Associates, Inc.3.0 METHODOLOGY When surveillance data is limited or not available, RG1.99 [1] specifies that ART is calculated with the following equation: ART = Initial RTND7 + ARTNJrT + Margin (1)The "Initial RTNDT" term refers to the reference temperature of nil ductility transition for the non-irradiated material.The reference temperature shift, ARTNDT, is defined in RG1.99 [1] as the shift in the reference temperature resulting from neutron irradiation.
ARTNDT is calculated from the product of the chemistry factor (CF) and fluence factor (FF) as follows: ARTNDT = CF *FF (2)The CF is a function of the weight percent copper (Cu) and weight percent nickel (Ni) of the weld and base metal (plate or forging) materials.
Tables 1 and 2 of RG1.99 [1] provide the standard CF values used in this calculation.
The FF is'based o'n thle accumulated fast neutron exposure (E > 1 MeV), and is typically corrected by the.thickness at the location'0of interest.
The FF can be read directly from Figure 1 of-RG 1.99,or calculated.---
using the'foilowing equation []FF = fO.2 8-0.10 log (f) (3)Where: f = fast neutron fluence at the depth of interest (1019 n/cm 2 , E > 1 MeV)Due to attenuation effects, the fluence decreases with distance into the RPV wall. Per RG1.99 [1], the calculated or measured fluence from the inside surface 'of the RPV is attenuated using the following formula: f = f 0.2
* 4. (4)Where: f, = fast neutron fluence (1019 n/cm 2 , E > 1 MeV)furf = fast neutron fluence at the RPV inside surface (i.e., at base metal / cladding interface, same units as f)x = depth into the RPV wall from the inside surface (inches)For ASME Code, Section XI, Nonmandatory Appendix G [3] evaluations, "x" is taken at one-quarter of the base metal thickness (1/4t). The fast neutron fluence can be attenuated through the stainless steel cladding on the inside surface of the RPV. By design, however, the cladding is treated purely as a lining, and not as a load-bearing member. Thus, for the purposes of this evaluation, the inside surface neutron fluence is considered to be at the base metal / cladding interface.
File No.: FITZ-1OQ-301 Page 5 of 14 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.The end of life measured fluence at the inside surface of the JAFNPP RPV is obtained at 22.2 and 54 EFPY from the recently revised fluence evaluation performed by TransWare Enterprises Inc [7].Margin (M), a conservative term defined in RGl1.99 [1], accounts for uncertainty in the initial reference temperature and for variance in ARTNDT., The margin is calculated using the following formula: 2'2 Margin =2* r+ 2  (5)U' +A Where: c*= the standard deviation for the initial RTNDT ('F)GA = the standard deviation for ARTNDT (&deg;F)RG1.99 [1] states that the standard value of GA is 28&deg;F for welds and 17 'F for base metal (plates or forgings), and GA need not exceed 0.5 times the mean reference temperature shift (0.5* ARTNDT).The G, term, which is related to the uncertainty in the precision of the initial RTNDT, is applied for values that are determined by measurement and also when generic .or default values are used. Consistent with Reference 
[4], cl is set equal to 0 'F, for all JAFNPP materials.
This assumption is valid, since the estimation of RTNDT is considered to be conservative where the most limiting data point is always used.File No.: FITZ-1OQ-301 Revision:
0 Page 6 of 14 F0306-OIRO Structural Integrity Associates, Inc.4.0 CALCULATIONS Based on the most recent JAFNPP fluence evaluation contained in Tables 7-1 through 7-6 of Reference[7], ART and ARTNDT values are calculated for the JAFNPP plates and welds whose fluence exceeds the threshold value of 1.Oxl01 7 n/cm 2.The calculated ART and ARTNDT values, along with their required inputs, are provided in Table 1 through Table 4; values were computed at 32, 40, 48 and 54 EFPY.The Initial RTNDT values were obtained directly from Tables 3-2 and 3-3 of Reference 
[4]. The wall thickness at each evaluated location was obtained from Table 7-1 of Reference 
[4]. The fluence values at each EFPY were obtained by linearly interpolating between the values at 22.2 and 54 EFPY documented in Reference 
[7]. A graphical depiction of the interpolation process is provided in Figure 1.Appendix A provides the contents of the NRC RVID2 datalase [5] for JAFNPP. Comparing the information in Appendix A with that contained in Tables 3-1 through 3-3 of Reference 
[4], it was observed that the values are identical.
The chemical compositions of the JAFNPP welds were also compared to those in Table 5 of [9], and found to be identical for all welds except 13253/12008.
File No.: FITZ-l0Q-301 Revision:
0 Page 7 of 14 F0306-01 RO V Structural Integrity Associates, Inc.Thus, the input parameters specified in Reference 
[4] are used for all plates and welds in the analysis, with the exception of plate C3278-2 and weld CE-2(WM).
The chemical composition, chemistry factor and margin of these components are adjusted with the values discussed in the two preceding paragraphs.

==5.0 CONCLUSION==
S File No.: FITZ-IOQ-301 Revision:
0 Page 8 of 14 F0306-01 RO Structural Integrity Associates, Inc.

==6.0 REFERENCES==
: 1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99,,Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.2. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix A, "Analysis of Flaws," 2001 Edition including the 2003 Addenda.3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix G, "Fracture Toughness Criteria for Protection Against Failure," 2001 Edition including the 2003 Addenda.4. GE Report No. GE-NE-B 1100732-01, Revision 1, "Plant Fitzpatrick RPV Surveillance Materials Testing and Analysis of 1200 Capsule at 13.4 EFPY," February 1998, SI File No. FITZ-1OQ-202.5. U.S. Nuclear Regulatory Commission, "Reactor Vessel Integrity Database Version 2.0.1," September 7, 2000, http://www.nrc.gov/reading-rm/doc-collections/gen-comm/reg-issues/2000/riOOO6.html.
6.7. TransWare Enterprises Report No. ENT-FLU-002-R-005, Revision 0, "Non-Proprietary Version of James A. Fitzpatrick Reactor Pressure Vessel Fluence Evaluation at End of Cycle 17 and 54 EFPY," October 2007, SI File No. FITZ- OQ-201.8. U.S. Code of Federal Regulations, Title 10, Energy, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix H, "Reactor Vessel Material Surveillance Program Requirements," January 1, 2004 Revision.9. Combustion Engineering Owners Group Report No. CE NPSD-1 119, Revision 01, "Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best Estimate Copper and Nickel Content," July 1998, SI File No. COOP-27Q-203.
10.-General Electric Design Specification No. 25A5024, Revision 0, "Reactor Vessel -Power Uprate," 7/31/91, SI File No. NYPA-78Q-203.
: 11. Stone and Webster Drawing 729E762, "Reactor Thermal Cycles," 4/18/69, SI File No. NYPA-78Q-205.File No.: FITZ-IOQ-301 Page 9 of 14 Revision:
0 F0306-01RO Structural Integrity Associates, Inc.Table 1: JAFNPP ART Calculations for 32 EFPY (NOTE: This table covers all RPV materials with an exposed fluence, E> 1 Me V, of greater than 10x 10 17 n/cm 2.)....... _Lower Shell #3 ----- G-3415-2 Lower-Int.
Shell #1 G-3413-7 Lower-Int.
Shell #2 G-3414-2 C3368-1I -10.0 0.12 0.50 C3278-2 -10.0 0.11 0.61 81.00 40.2 17.0 0.0 64.2 89.56 44.4 17.0 0 68.4 L. int. bneil Long. vvei #1 1--ZJ-A 1ItZZ/1zUUu VlUX 1U09 Lot 394t -bU.U U.21 U.8j 32b.94 122.9 14.U U.U 1UU.9 L. Int. Shell Long. Weld #2 1-233-B 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 113.2 14.0 0.0 91.2 L.ntSeLong.
Weld #3 .. .1-233-C 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 .0.873 326.94 122.9 14.0 0.0 .100.9-L. Int/L. Shell Girth Weld 1-240 305414 Flux 1092 Lot 3947 -50.0 0.337 0.609 209.11 95.8 28.0 0.0 101.8 L roLwer Shell Long. We #2 2-233-BA -27204'412008 Flux 1092 Lot 3774 -48.0 0.219 -- 0.996 -231.06 84.1.t6 28 .0 -0.0 109.6 Lower Shell Long. Weld #2 2-233-B 27204/12008 Flux Io1092 Lot 3774 -48.0 0.2194 0.996 2,31.06 84.1 28.0 0.0 92.1 (0 0)0~Co 0)Lower Shell #2 .' 6.375 1.594 Lower Shell #3 6.375 1.594 Lower-Int.
Shell #1 5.375 1.344 Lower-Int.
Shell #2 5.375 1.344.Lower-Int.
Shell #3 5.375 1.344 L. Int. Shell Long. Weld #1 5.375 1.344 L. Int. Shell Long. Weld #2 5.375 1.344 L. Int. Shell Long. Weld #3 5.375 1.344 L. Int./L. Shell Girth Weld 5.375 1.344 Lower Shell Long. Weld #1 5.375 1.344 Lower Shell Long. Weld #2. 5.375 1.344 Lower Shell Long. Weld #3 5.375 1.344 1.686E+18 0.682 1.15E+18 0.445 1.686E+18 0.682 1.15E+18 0.445 2.01E+18 0.724 1.456E+18 0.496 2.01E+18 0.724 1.456E+18 0.496 2.01E+18 0.724 1.456E+18 0.496 1.118E+18 
-0.724 8.096E+17 0.376 9.49E+17 0.724 6;874E+17 0.346 1.118E+18 0.724 8.096E+17 0.376 1.686E+18 0.724 1.221 E+18 0.458 1.&#xfd;44E318 0.724 1. 119E+18 0.440 ,! 048E+18 0.724 7.592E+17 0.364 9.632E+17 0.724 6.977E+17 0.349 File No.: FITZ-1OQ-301 Revision:
0 Page 10 of 14 F0306-01 RO VStructural Integrity Associates, Inc.Table 2: JAFNPP ART Calculations for 40 EFPY (NOTE: This table covers all RPV materials with an exposed fluence, E> 1 MeV, of greater than I.x 1017 n/cm 2.)Lower , ri el1 7 1 (3-341b-1-N U.3,394-1 I -1 () I .11 0.56 Lq r &sect;v&#xfd;e~rthli#2 G-3415-3 C3376-2\ 24.0 > ~ 0.13 06 Lower Shell #3 G-3415-2 C3103-2 -2.0.1 Lower-nt.
Shell #1 G-3413-7 C3368-1 --10. 0.12 0.50 Lower-Int.
Shell #2 G-3414-2 C3278-2 -10.0 0.11 0.61 1 -t-im Q..Int *holl *q ('-_A1A~l 11l _11 1 q n r7 L. lilt. JIIt:Ul LUIll. VVViU It I l-400-/" lO UJ0114UUO FIUA I UUt LUL 3U't I -UU.U U.L I U.O1 a2 34U.O;+ I 34'+f I -+.U U.j I 11.f L. Int. Shell Long. Weld #2 1-233-B 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 124.4 14.0 0.0 102.4 L. Int. Shell Long. Weld.#3 1-233-C 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 134.7. 14.0. 0.0 112.7 L. Int./L. Shell Girth Weld 1-240 305414 Flux 1092 Lot 3947 -50.0 0.337 0.609 209.11 103.4 28.0 0.0 -109.4 Lower Shell Long. Weld #2 ----- 2-233--AB 27204'/12-008 
&deg;F-Iu-Fiux 109'2 Lot- -3 7-74 -- --- --48-."0 -------0.219 --- -0.996...
231.06 10. ..0 28O. 1O!0.. 1i8.00 Lower Shell Long. Weld #2 2-233-B 27204/1 2008 Flux 1092 Lot 3774 -48. 0.219 0.996 2316 91 2. 0. 101 1 --1 'hoI-1 I ,-.I' I ''',-I *'~ j ' C 97 nA)~n 1) qa' q (- ',77 -F, 1 1 El. " ooo' , nI Io "--I n OI 11 0I'l 1- -in 0.Lower bneii ;1i b.3jb Lower Shell #2 6.375 Lower Shell #3 6.375 Lower-Int.
Shell #1 5.375 Lower-Int.
Shell #2 5.375 Lower-Int.
Shell #3 5.375 L. Int. Shell Long. Weld #1 5.375 L. Int. Shell Long. Weld #2 5.375 L. Int. Shell Long. Weld #3 5.375 L. Int./L. Shell Girth Weld 5.375 Lower Shell Long. Weld #1 5.375 Lower Shell Long. Weld #2 5.375 Lower Shell Long. Weld #3 5.375 1.594 1.594 1.344 1.344 1.344 1.344 1.344 1.344 1.344 1.344 1.344 1.344 1.993hL+1 U.btz 1.jb9L+1b U.461"1:993E+18 0.682 1.359E+18 0.481 1.993E+18 0.682 1.359E+18 0.481 2.41E+18 0.724 1.746E+18 0.537 2.41E+08 0.724 1.746E+18 0.537 2.41E+18 0.724 1.746E+18 0.537 1.348E+18 0.724 9.761 E+17 0.412 1. 1,46E+18 0.724 8.299E+17 0.381 1.348E+18 0.724 9.761E+17 0.412-.1..993E+18 0.724 1.444E+18 0.494 0.724 1.328E+18 0.476 1.26E+18 0.724 9.125E+17 0.399 1.151E+18 0.724 8.338E+17 0.381 File No.: FITZ-IOQ-301 Revision:
0 Page I 1 of 14 F0306-01 RO Structural Integrity Associates, Inc.Table 3: JAFNPP ART Calculations for 48 EFPY (NOTE: This table covers all RPV materials with an exposed fluence, E > I MeV, of greater than I.OxlO 17 n/cm 2.)Lower Shell #3 G-34115-2 Lower Shell #3 G-3413-7 Lower-Int.
Shell #2 G-3414-2IO/ -.U u. I J uJ.,.r 3U.U- j u.. u I U ~ .u~ LJAJu IL.u C3368-1[ I -10.0 0.12 0.50 81.00 46.5 17.0 0.0 70.5 C3278-2 -10.0 0.11 0.61 89.56 51.4 17.0 0.0 75.4 L. Int. Shell Long. Weld #1 1-233-A 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 145.2 14.0 0.0 123.2 L. Int. Shell Long. Weld #2 1-233-B 13253/12008 Flux 1092 Lot 3947 .-50.0 0.21 0.873 326.94 134.5 14.0 0.0 112.5 L.-In.tShellLong Weld #3 1-233-C 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 145.2 14.0 0.0 123.2 z L. Int./L. Shell Girth Weld 1-240 305414 Flux 1092 Lot 3947 : --50.0 -0.337 0.609 209.11 110.1 28.0 0.0 116.1 Lower Shell Long. Weld #2 2-233-B 27204/12008 Flux 1092 Lot'3774 -48.0 0.219 0.996 231.06 99.3 28.0 0.0 107.3 Lower Shell Lonor Weld #3 2-233-C 27204/12008 Flux 1092 Lot 3774 -48.0 0.219 0,996 231.06 94 9 28.0 0.0 10279 Co 0~go V 0)LUvW UI 0 1i e"I1 I I O. iji i. 0JU ' .JU E ' 10 Lower Shell #2 .6.375 1.594 2.30E+18 Lower Shell #3 6.375 1.594 2.30E+18 Lower-Int.
Shell #1 5.375 1.344 2.81E+18 Lower-Int.
Shell #2 5.375 1.344 2.81E+18 Lower-lnt.
Shell #3 5.375 1.344 2.81.E+ 18 L. lIt. Shell Long. Weld #1 5.375 1.344 1.578E+18 L. Int. Shell Long. Weld #2 .5.375 1.344 1.342E+18 L. Int. Shell Long. Weld #3 5.375 1.344 1.578E+18 L. Int./L. Shell Girth Weld 5.375 1.344 2.30E+18 Lower Shell Long. Weld #1 5.375 1.344 2:123E+18 Lower Shell Long. Weld #2 5.375 1.344 1.471 E+1 8 Lower Shell Long. Weld #3 5.375 1.344 1.339E+18 u.U o4 i.Ju07 IQ Yi0 U.UIJ 0.682 1.569E+18 0.513 0.682 1.569E+18 0.513 0.724 2.035E+18 0.574 0.724 2.035E+18 0.574 0.724 2.035E+18 0.574 0.724 1.143E+18 0.444 0.724 9.724E+17 0.411 0.724 1.143E+18 0.444 0.724 1.666E+18 
.0.527 0.724 1.538E+18 0.508 0.724 1.066E+18 0.430 0.724 9.699E+17 0.411 File No.: FITZ-IOQ-301 Revision:
0 Page 12 of 14 F0306-OI RO Structural Integrity Associates, Inc.Table 4: JAFNPP ART Calculations for 54 EFPY -(NOTE: This table covers all RPV materials with an exposed fluence, E> 1 MeV, of greater than 1.0x10.1 7 n/Cm 2.)Loe hel# G-34~15-3 C3376-2. 2 4.f ~0 &#xfd;13 0.6 Lower Shell #3 G-3415-2 03103-2 ..-2.0 J 0.14 0.57 Lower-mnt.
Shell #1 G-3413-7 C3368-1 --10.0 0.12 0.50 Lower-Int.
Shell #2 G-3414-2 C3278-2 .. -10. 0.11 0.61 I ..... .I-i -'~ l," ,- --4A .- -- " 1 1 l -" -' ' -d ----" .7 0 .UU 89.56 4 04 4 C L. inT. bneil Long. vvei 3i 1-IJ,'5-A 1JZDJ/1ZUUO -lUX 1U&#xfd;M LOT 5J14 -tU.U U U. U./ j zb.&#xfd;4 I oLz.J 14.U U.U 1jU..j L. Int. Shell Long. Weld #2 1-233-B 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 326.94 141.3 14.0 0.0 119.3..L..Int. S-hell Long. Weld. #.3.." 1-233-C 13253/12008 Flux 1092 Lot 3947 -..-50.0 0.21 0.873 326.94 152.3 14.0 0.0 130.3 L. Int./L. Shell Girth Weld 1-240 305414 Flux 1092 Lot 3947 .-50.0 0.337 0.609 209.11 114.7 28.0 0.0 120.7-Loer Shell Lng.Weld # 22233-BK 27204/12008i Flux1092 Lot 37-74 -- 48.0 -0.219- -0.996 -_9231.06-104.2 28.0 0.0 --112.2 Lower Shell Long. Weld #2 2-233-B 27204/12008 Flux- 1092 Lot 3774 -- -48.0 0.219 096 231.06 104.2 28.0 0.0 112 .2 U)0 a-In V 0 Lower Shell #2 ..6.375 1.594 2.53E+18 Lower Shell #3 6.375 1.594 2.53E+18 Lower-Int.
Shell #1 5.375 1.344 3.11 E+18 Lower-Int.
Shell #2 .5:375 1.344 3.11 E+18 Lower-Int.
Shell #3 5.375 1.344 3.11E+18.L. Int. Shell Long. Weld #1 5.375 1.344 1.75E+18 L. Int. Shell Long. Weld #2 5.375 1.344 1.49E+18 L. Int. Shell Long. Weld #3 5.375 1.344 1.75E+18 L. Int./L. Shell Girth Weld 5.375 1.344 2.53E+18 Lower Shell Long. Weld #1 5.375 1.344 2.34E+18 Lower Shell Long. Weld #2 5.375 1.344 1.63E+18 Lower Shell Lona. Weld #3 5.375 1.344 1.48E+18 0.682 0.682 0.724 0.724---------.-
0.723 4 ..........-..
0.724 0.724 0.724 0.724 0.724 0.724 0.724 1.726E+18 0.535 1.726E+18 0.535 2.253E+18 0.598 2.253E+18 0.598 2.253E+18 
----...........
0.598 ----1.268E+18 0.466 1.079E+18 0.432 1.268E+18 0.466 1.833E+18 0.549 1.695E+18 0.531 1.181E+18 0.451 1.072E+18 0.431 File No.: -FITZ-10Q-301 Revision:
0 Page 13 of 14 F0306-OI RO Structural Integrity Associates, Inc.Interpolated Fluence Values 3.OOE+18 2:50E+18 2.OOE+18 E 0-1.50E+18 LL 0)1.OOE+18 5.OOE+17 0.00E+00 0 10 20 30 40 50 Effective Full Power Years 60 Figure 1: JAFNPP Fluence Determination in the Lower Shell #1 plate for 32, 40, 48 and 54 EFPY File No.: FITZ-1OQ-301 Revision:
0 Page 14 of 14 F0306-01 RO Structural Integrity Associates, Inc.APPENDIX A: NRC RVID2 DATABASE FOR JAFNPP File No.: FITZ-10Q-301 Revision:
0 Page Al of A8 F0306-OIRO V Structural integrity Associates, Inc.EMEe Edit t 4 p Plant.Docket No.I FITZPATRICK I i 50-333 Loci -ate ~rlyrie ]27i 999 3 i Reactor Type Thickess: 
[j5]Plate 0 (generated by system), MlI INPUT DATA H-eat ID: 1 Yrscatc: I 32 1 BeflneID!
O R SHELL Base Metal: I A 533B cu J : Fo14-1N oJ---Value Method RTncdktu -2.01 PLANT SPECIFIC Fluence(E))
EOL [161 Chem Foctor: J ENTER OVERRIDE a(U): LlVALUES, cy(A) OiJTHERVSE Margin: LEAViE BLANK Linmting Material: Unrr USE: 82.6 1 65% l CALCULATED DATA Value Method RTrdn(u FLience Fodor @ EOL: Chemisitry Facto A RTr4f @ EOL: 0(u)c(A)-2.0 PLANT SPECIFIC RTnd(u)0.519 *iueno.C07(2&-.I Iog(tluenoe(1D))
987 TABLE 5-1.2 FFxCF 00 PLANT SPECIFIC IT.d(u)170 NO SURVEILLANCE DATA 340 POSITION 1.1 (NO S DATA)I J R1rW*z)+ 0 Rflis + ktr~i%Drop @EOL(1 14T) 3.6 I POSITION 1 2(NO S DATA)Reco Vese Inegiy aabs -[PaeDeal Edrle Edit lie-Plant FITZPATRICK Reactor Type: [E&#xfd;W1Vessel Thek~nemss 6.]Docket No:I 50-M33 Pl ateI I n dJ INPUT DATA Heat ID'. a l r Ct:E-Bet1n ID:JO&#xfd;PNTERMAEDIATE SHELL I ewse Metat A 533B C h0mitr6 CALCULATED DATA Cu:. 0 w [ 6 Value Method 21aLue RT4(uy -10.0 PLNTSPCIFIC IRTr(u)j Vale ethod Fluence Factr @ EOL: 0.546 flmW -A Wkewe D%)., RTn(ul 10&#xfd;O PLANT SPECIFIC itrfatr9 SURVEILLANCE NON-RATIO t Fuence() EOL: [0.81 A RTrK@EOL:
60 =FF"CF SURVEY CALC DETAIL Chemn Factor: ENTE OVERRIDE c~u) _ __RTndt(u)
CYLu): AUS __) Z Z W (A) J0THERVA' E, I .0 OVERRIDE MargiR n16 LEAVE BLANK RT QL j RTIN 2 D TndT + NAin Unrr US~E 1 4.3 65% +/- %Drop @ OL (1 4T)&#xfd;.M j [ POIT10tON2 2~SA File No.: FITZ-1OQ-301 Revision:
0 Page A2 of A8 F0306-O1 RO Structural Integrity Associates, Inc.PIN% Dom 114 14 1-0 1 pDaent: Docket No: I FITZPATRICK 50-333U~o Dm t~m:IP7I9365P Reactor Type: [w_] Vessel Tth ckes: r65 PlateID (generatedby systeny. _r11J INPUT DATA HieatV fj JyxJ Bentltke ID, LOOER INTERMEDIATE SHELL Base Metal A 533Bsty CA[Cu: r-6-85 Ni [o-570 Value Metho Fluenc Rtl't(u): 
-18.0 PLANT SPECIFEIC C Fluence(I)D)
EOL: .8 Cheam Factor: ENTER OVERRIDE', COTHERWISE Mar i i LE~jE BLANK Umtn ZaeliLI us Lnirr USE: 82.3 6% ! %Drc I-CULATED DATA Value Method RTndt(uX eFadeor @ EOL:&#xfd;ha~~ry Fedtor;A RTnck @ EOL.a~u)o(A)-18.0 PLANT SPECIFIC I RTnt(u)0.546 ftno(Y.28-.I bqMfwkeQ)00 131.1 TABLE It 71.6 FFxCF , 1 R )0.0 PLANT SPECIFIC RTndt(u)17.0 NO SURVEILLANCE DATA 111 34.0 POSITION 1.1 (NO S DATA) I RTrK1 @ EOL RThibQO. + RTnck +,bbw 0@EOL (IMTY.[ 8 F,- 7~1 Fueceq x) oL 43@ EOL (114T):T 16 -1DIOPI 1.2(NO S ATA&#xfd;Ji i mini m m i 1 i~ -, M Ell Edt WIIP Flardt FITZPATRICK Reactor Type: j5&#xfd;JVieasef TImess:6 Dok N 0-333 P e .
by .. ...INPUT DATA Halin V. =
INTERMEDIATE SHELL Base A 5338ete Chemtity CALCULATED DATA Cu: F1M20-.F0500
: p. S: 0.01 Value Method RT.- m ): 1o0 PLANT SPECIFIC RTndt(u)Value Metio IFlence Factor C OL- 0.546 fluesioeQD)'(8,1 k(ftlrK"ecO)
RTr (u) -10.0 -PLANT SPECIFIC +/- Chaqsy Factor 61 D0 TABLE Fklence(D)
EOL: 0.181 A RTnk~ Q FOL: 44.2 FFxCF Chemn Fader.- L.J PV9IRIDE C()00 PLANT SPECIFIC Rlndt(u)a ii): (A) 17. NO SURVEILLANCE DATA I Liii: Oj}E4LASE rgh 340 POSITION 1.1 (NO S DATA)Limitng M 1teriat USEo @ EO (i 4T 0O123 FkIence (1OT) 0 EOT I UnIrrUSE:
67.0 65%- -- 0! %Drop@CEOL (I 4T): 12 POIIN. N AA File No.: FITZ-IOQ-301 Page A3 of A8 Revision:
0 F0306-01 RO Structural Integgtv Associates, Inc.9 Ede E& Help Phh o'iJ.a__4 4 !l H P]jrin Ose t-Plart: FITZPATRICK Reactor Type: [-5F]Vessei Thckness: 
[.5 Docket No1 50-333 PIM Plate ID (gemeted by system). E INPUT DATA Hee I IVI Ctc 32 BeW .ItI ER SHELL Base Me/at A 5330 c: IhWFO0 CALCULATED DATA P [ s: S [ -1 Value Method RTnrd(u 24.0 PLANT SPECIFIC RTndt(u)Value Methond F-uence Factor @ EO 0519 fluuiwe0(IDT&-.1I mno.(10et))
RTnct(u) 24.0 PLANT SPECIFIC I Chemistry Facor; 910 TABLE Fke-(K)) EOL 0161 A RTnt@EOL 47 2 FFxCF Chem Factor. ENTER OVERRIDE a(u) 00 PLANT SPECIFIC RTndt(u)a(u): G jU1ES7 .10 NO SURVEILLANCE DATA I a(A): OTHMEWSE Mr 34.0 PO3 TION1.1 (NO S DATA) L Margh: LEDWE BLANK RtTn 0 @ L&#xfd; RTWO u4 DRThA + hrin Lhimitig Materiat LSEE0fl]Y 67 F-O 0-- kr I1T Lk*rUSE 77.4 5i% %DropQ@ EOL (14T POSITION 1.2 (NOS DATA)0 Ede Edit :e PlrL FITZPATRICK Ieacto Typ B5R&#xfd;JVessel Til*ness: 
[65 Docket No: 033 Plate ID(mtdby systam) j INPUT DATA Bebw ID &#xfd;a)A.R SHELLI"I ;. .Base M u t al: A 5338__ __ __CALCULATED DATA Cu FO1,0- ~t [ 0.5 P Value Method R~rI4Uj) -10.0 PLANT SPECIFIC RTndt(u)Value Methodj Fluanoe Fct~r C E)L- 0,519 fkame(OA28..?
logIinoe(Ift RTTndt(u) 
-10.01 PLANT SPECIFIC Chmisty For: 73.6 TABLE Fkience(ID)
EQL- 0161 A RTnck i E0L- 38.2 FFxCF Chem Fedor. [T O a u) 00 PLANT SPECIFIC RTIdt(u)U): VAUES, c(A) 170 NO SURVEILLANCE DATA t a(A,: OTEVS i arg 1I4. POSITION 1.1 (NO S DATA)USE:ir LA BL.6 I % IOTr [ -" --OL RO) ITIO+ 1. (NO Shl +AT Limiting MederiatLII]
USE @ EL (I 41T&#xfd; Flec I9)AE Unirr USE: 165.6 1 65% t %Drop Q OL( 14T): POS~j]~ITION 12 1NO SDATA)I File No.: FITZ-IOQ-301 Revision:
0 Page A4 of A8 F0306-0 l RO V Structural Inteqrity Associates, Inc.laReactor Vessel Integrity Database -[Weld Detal FEI0jle Edit U~elp WO DOW' 14 4 P H LIIT7ios~7l Docket No:. 50-333 FITZPATRICK
]Reactor Type:F[&#xfd;FJVessel Thickness:
I~VWel 1) (generated bw systemi):
r[0-8 INPUT DATA'ed ID: Yrs Caic: 32 Location:
ortertation: 
[ J Berlne CD: LOVER INT. SHELL AXIAL VWELDS 1-233A/C Capsuies Flux Type LINDE 1092 1 HeatWe 13253 & 12008 1Flux Lt 3774 1 w*M Code 092j ch-msb Value Method RTno(uY -500 PLANT SPECIFIC !Fluence(E))
5OL- .8 Cheum Factor: V- EN4TER OVERRIDE G(U) [ VALUES, a(A)" IOTHERWISE
=u I LEAVE BLANK-iiln Material: Lr*r USE. EMA t CALCULATED DATA Value Method RTnd.(u) -500 PLANT SPECIFIC h(u)F Fen d Fcor @ EOL, 0.546 fnOweTp).28-.t lcWfkiencepI))
ChelmitryFactor 208.7 TABLE I A RTnI@EOL:
113.9 FFxCF (u) 0.0 PLANT SPECIFIC RTndt(u, c(Al 28.0 NO SURVELLANCE DATA 1-.Mrgt 56.0 P 1.1 (NO S DATA) 12I@EO. RTk(p/ E)+RTh+ Wrgi t%Drop @ OL ( 1J ITMA FRatrVs se *Inert Daaae-[.l eal M le UE&W41 D"~ unj Ij;1F I E-rlt I r.,.. I Piart: Docket Np: FITZPATRICK I Reactor Typie: [71T]Vsel Thickneass 1 65]Wel 9)( aed by systern) EK INPUT DATA -Heat 1) Yrs Cab. 32Loao: BOOM C LOVER SHELL AXIAL WELDS 2-233AIC Fljx Type LINDE 1092 1 Heladrte" 27204 & 12008 1 F Lt 13774 orirtatZipZ
-ptle J Wel Code-P- 000 S: .099J Value Method RTnr2(u): 
-48.0 PLANT SPECIFIC 11 Fluence~o)
EOL: 0[161 Chem FedZor: ENTER 0YRRIDE c(u): ____ iMiS o(A): (OTHERWISE Marh L lEAVE SiALNK Limiting MatelaI YES 11 U*r USE-I I E I CALCULATED DATA Value L Show otes Method RTndt(uX -48.0 PLANT SPEC&#xfd;IFIC Rn&u Fluence Factor 0 EOL.. 0.519 tkwsio(IDA~20-.1 Iogwfruno.Q3D Chemistry Factor: 231.1 TABLE A RTrl~t (MEOL 119.9 rFxCF o(A) 28.0 NO UREILANCEDATA 11 M~h 56.0 1 OSIIO .1(NOS DATA)+/-RTrh 0 EOL RTndt~u) + DIRTdt +kb6w*USE @ EL (1 14T FIlueXI5 0 14T) QECIL%Drop @EOLC(I fTy. Z EiiA 1]I File No.: FITZ-OQ-301 Revision:
0 Page A5 of A8 F0306-01 RO Structural Itetgrity Associates, Inc.Z~Ede Ect UeIp Plt FITZPATRICK Reator Type: [--]Ves&#xfd;ei Thicimess: 
[6 Docket No: 50-333 Weld ID (generated by systeM). El-9 INPUT DATA HYrs CaI c32 Location:
I= le aion Beffm [Y CIRC 1-240 1Capste: [ 1 Flu LINDE 1092 Hieaed 305414 Flux Lo: 3947 Wed Code: LINDF 092J Oiemistiy CALCULATED DATA Pc o : Value Method sRTndl(uy 
-50.0 PLANT SPECIFIC Rlndt(u)Value Method Fluence Factor a EOL 0.519 *wvpOWA.28-.J k(fenOD)))
RTnrl(u): 
-50.0 PLANT SPECIFIC !&#xfd; Cherra- y FOC. 209,1 TABLE Fkluec ) EOL: 01.16 ARr@E L 1085. FFxCF Chain Factor: -8ITER OVERRIDE a(u) 0.0 PLANT SPECIFIC RTndt(u)J SU): -ALUES O(A) 28.0 NO SURVEILLANCE DATA I+/-J[]I I OTHIERVSE Mwgl 1 56.0 1POSITION 1.1 (NO S DATA) ItI Lz 1 LELANK RTnt@ EOL+Lku t e U EOL (I 0-- j Ruee (Ie'r) @ EOL Utrr USE. EMA L %Drop EOL (I14T)Y. I EMA File No.: FITZ-1OQ-301 Revision:
0 Page A6 of A8 F0306-01 RO V Structural Integrity Associates, Inc.19 EMe Fdit U*NRC -Reactor Vessel liegrity Database Printed 11/15r20071.46:08 P-T Limits Summary Report DocktNo 50-333 page 1 FITZPATRICK ECL Date 1o17f2014 Bekline I~entifanie RTndt Fklene .RTrk(u) PFa-r Chem Chwmstrf Fmaor T 2 8 e Heto IEOL *EOL RTIpu) RTret(u)METHOD 
@EOL OEOL Factor Method MgI Margin HMMMod Cu % Ni % P% S 5 LOWER SHELL 83.2 0.1e1 -2.0 PLANT SPECIFIC 51.2 4519 98.65 TABLE 348 POSITION 1.1 .140 0.570 8D012 0.015 PLATE C3103-2 (NO S DATA)LOWER INTERMEDIATESHELL 22.0 0.181 .108 PLAINT SPECIFIC 18.0 0584 29.34 SURAMLA84CE I18 OVERRIDE lAi 0.8400 0DI1 0016 PLATE 1 C3278-2 NONMRATIO LOWER INTERMEDIATE SHELL 8746 0.181 -18D PLANT SPECIFIC 71.6 0546 131.18 TABLE 348 POSITION 1.1 DAe 8.8670 O8DS 0,01e PLATE -C330I.I (NO S DATA)LOWER INTERMEDIATE SHELL 68.2 8.181 -188 PLANT SPECIFIC 44.2 8448 81.11) TABLE 348 POSITION 1.1 D.12 0.610 0818 80.17 PLATE 1 C 8- 1 (NO S DATA)LOWER SHELL 1852 8 161 24.0 PLANT SPECIFIC 472 08518 91M TABLE 348 POSITION 1.1 8.34 D.A00 015 8 .817 PLATE I C3376-2 (NO S DATA)LOWER SHELL 62.2 0.161 .108 PLANT SPECIFIC 3-2. 84518 73.60 TABLE 348 POSITION 1. 0.111) 0.560 8016 0.017 PLATE I C3394-1 (NO S DATA) I LOWER INT. SHELL. AIALWELDSI-233AFC 1199 0.181 -688 PLANT SPECIFIC 112.8 8846 20868 TABLE 588 POSITION 1.1 0.21H 0.873 0888 8.888 WELD 13253112088 (NO S DATA)LOWER SHELLAX IbLWELDS2.2333AC 1279 0.181 -48D PLANTSPECIFIC 119A. 0518 23188 TABLE 888 POSITION 1.1 0.219 0.908 8888 80.0 WELD 27284120088 (NOS DATA)CtRC WELD 1-240 1148 0.181 -60.0 PLANT SPECIFIC 108.6 0814 2D9.1 TABLE 868 POSITION 1.1 0.337 0.88 088D8 8.000 WELD 2 88414 (NO S DATA)Plant References and B eltline MNterial Nlotes Weld Chemistry data are Iran CE 41PSD- 039, Rev. 2. as stated bythe ticensee in its response (83t 11 998)to the RA on OL 92-01, Rev. 1, Supp. 1.Plate chenistrydcat a-md USE value are from the Odober 15,1999 response to the GL 92101 closeout letter deted July 6,1999. The plate chemisy data are consistert Wt those in GE-NE-B1100732-01, Reison 1, daed Feb'mury 1998.The actiusted CFs and reduced maqgins for all plates in Table 7.1 of 100732-01, Rev. I have not been imple ent ed because the licensee did not request the Co-nge i Its latest correzpondenoo dated Aug.st 31, 198. Frther, the staff po.ticri regding the use of seatveane-plate deta is (1) rato procedure does not apply to pltes, and (2)eeiatlion based on s-*veillanes plate d0te cma be applied to the surveilance plate only, rno to atl plates.RTrd(u I for the befline material (tAh the ewception of Matd 2-233A.'C 4eat 272041120(08) are from the July 9,1992, letter from R.E. Beede (NYP A)to the USNRC Document Control Desk, aibect ResporinetoNRCG G92-01,Rev.1.
The icensee's equivelern marJns analysis (E MA),
ofNE DO -32205-A to the FitzPatrick unit, ves submited cn August 10,1994. The staff approved it by an SER dated March 30,1995.Maern method for the lover Intermediate shell plate (heat number C3278-2) is "override" Since siem& delte need rn be greater than 12 delta RTrd per RG 1.99, Rev 2.R Tndt(u) for v*d 2-233A# (heat nn br 27204M1200) and vessel luerice data are fom GE-NE -81100732-O1, Rev. 1 (Feb. 1998) as stated by the licensee in its response (8.3t1998)tothe RAI on OL 92-01, Rev. 1, Supp. 1 File No.: FITZ-1OQ-301 Revision:
0 Page A7 of A8 F0306-01RO V Structural Integrity Associates, Inc.11311eactur Vessel inteqrity Database [Surveillance Data Summary ReportlEh dt l NRC -Reactor Vessel InegFity Dtabase Pirinted 1 Il U15)2D07 1:46:25 Surveillance Data Summary Docketft 50-333 Page 1 FITZPATRICK EOLDete 1iO7R2014 Uaed Pm&sect;ed -~i C,*d1A gol t4*a.M FP.r- Gee. up CF pr.~dk Nba- R61.90 Pred4Aea tks, Flaeno Fwdo CF CIA- A RTe.5 A RTnd A mReT tratr A RTndt USE File No.: FITZ-1OQ-301 Page A8 of A8 Revision:
0 F0306-OIRO}}