DOC.20050826.0001

3. Document Identifier. 4 Rev.. 5. Title 2AL-D SU-NU-0000 1 2 OOA PWR Axial Bumup Profile Analysis

Engineering Change Notice

Complete only applicable items.

6. ECN:

2

1. QA: QA 2. Page 1 o f 4

8. Supersedes Change Document: Yes If, Yes, Change Doc.: El No

Inputs Changed. rives @No

Assumptions Changed Yes N o

1. p. 24 - Source should state as follows: Source: ASME 2001 (Section 11, Part A, SA-5 1mA-5 16M, Table 1); Density from ASME 2001 (Section TI, Pzrt A, SA-20, Sectiun 14.1).

Results trnpacted O ~ e s NO Design Impacted: Yes No

2. pp. 39-40 modified to incorporate additional refcrence and removal of data tracking number refcrcncc.

k summary list of attachments is as fallows: p. 24 and pp. 39-40.

< / & h a & ? . Phqh5- 2ty+!Ld &S/X

1 7 , Originator (PrintlSignlDats) John M. Scagliune

Cheng T. Hsu Checker. (PrintlSignlDate)

Approved. (PrintlSignlDate) William E. Hutchins E"-*% -.

LP-3.12Q-BSC FORM NO. L312-1 (Rev. Q512012005)

Licensing & Nuclear Safe@ Calculation Title: PWR Axial Burnup Profile Analysis Document Identifier: CAL-DSU-NU-000012 REV OOA ECN 2

d o w Page 24 of 41 I

I

Table 13. Grade 70 A516 Carbon Steel Composition

Si-nat ] 14000.50~ I 0.2900 Density = 7.850 glcrn3

ElernentRsotope 2AID" Gnat 6D00.50~ Si-nat 14000.50~

The cladding composition was ZircaIoy-4 as presented in Table 14 and the spacer grids were Incone1 7 1 8 as presented in Table 15. Table 16 presents the component material voIwne fractions for the upper and lower end-fitting regions and Table 18 presents the upper and lower fuel rod plenum material volume fractions for the B&W 15x1 5 assembly design. TabIe 17 presents the upper and lower end-fitting homogenized material compositions and Table 19 presents the upper and lower h e 1 rod plenum homogenized material compositions for the B&W 15x15 assembly design.

wt% Elernentlsotope ZAlD W h 0.0400 Fe-58 26058.60c a 0537 0.1800 Ni-58 28058.60~ 35.2846

Table 14. Zircaloy-4 Material Composition

Source:

NOTES:

ASTM 3 81 1-90 1991. p. 2, Table 2 a ZAlD = MCNP material identifier.

From ASM International 1990, p. 666, Table 6.

1 S-3 2 I 16032.50~ I 0.0080 I Ni-60 I 28060.60~ I 14.0574

I 0-50 I 24050.60~ I 0 7940 I Ni-61 I 2806350~ I 0.6214 I Cr-52 Ni-62 1 28062.60~ I 2.0110

I CT-53 1.8380 I Ni-64 I 28064.60~ I 0.5319 I Cr-54 1 24054.60~ ' I 0.4652 I Ti-nat I 22000.5oc I 0.9001 I Mn-55 I 25055.50~ I 0.1800 I AI-2J I 13027.50~ I 0.5001

Licensing, & Nuclear Safetv Calculation Title: PWR Axial Burnup Profilc Analysis Document Identifier: CAL-DSU-NU-0000 12 REV OOA ECN 2 Page39of41 1

7. REFERENCES

10 CFR 961. Energy: Standard Contract for Disposal o f Spent Nuclear Fuel andor High-Lcvcl Radioactive Waste. Rcadily available.

ASM International. 1987. Cmroskm. Volume 13 of Mt?luls Handhook. 8th Edition. Metals Park, Oho: ASM International. TIC: 209807.

ASM International 1990. Properties and Selection: Nmfwrous Alloys and Special-Purpose Materriuls. Volume 2 of ASM Hund’hook. Formerly 10th Edition, Metals Handbook. 5th Printing 19%. [Materials Park, Ohio]: ASM International. TIC: 241 059.

ASME (American Socicty of Mechanical Engineers) 1998. 1998 ASME Boiler and Pressure Vessel Code. 1998 Edition with 1999 and 2000 Addenda. New York, New York: American Society of Mechanical Engineers. TIC: 247429.

ASME {American Society of Mechanical Engineers) 200 1. 2001 ASME Boiler nnd Pressure Vessel Code (includes 2002 addenda). New York, New York: American Society of Mechanical Engineers. TIC: 251425.

ASTM B 81 1-90. 199 1. Standard Specfmtion fur Wrought Zirconium Alloy Seamle.w Tubes for Ntsclem Reactor Fuel Cladding. Philadelphia, PennsyIvania: American Society far Tcsting and Materials. TIC: 239780.

Audi, G. and Wapstra, A.H. 1995. Atomic Mms Adjustment, Mass List fo. AnaEysis. [Upton, New York: Brookhaven National Laboratory, National Nuclear Data Center]. TIC: 24271 8.

B&W Fuel Company 1991. Find Design Package Babcock & Wilcox BR-100 100 Ton R.d/Bargc Spend Fuel Shipping Cask. Volume 2. 5 1 - 1203400-01. DBABE0000-00272-1 OOQ- 000 14 REV 00. Lynchburg, Virginia: B&W Fuel Company. ACC: MOV. 1996O8O2.0083.

Bowman, S.M.; H e m a m , O.W.; and Brady, M.C. 1995. Sequoyuh U ~ i f 2 Cycle 3. Volume 2 of Scale-4 Analysis of Pressurized Water Reactor Criticd Configurations. URNLRM- I22941V2. Oak Ridge, Tennessee: Oak Ridge National Laboratory. TIC: 244397.

Bricsrncistcr, J.F., ed. 1997. MCIVP-A General Monte C d o N-Purfide Tramporb Code. LA- 12425-M, Vcrsion 4B. Los Alamos, New Mcxico: Los Alamos National Laboratory. ACC: MOL1 9980624.0328.

BSC (Bechtel SNC Company) 200 I a. 5ofmm-e Cude: Ft7lvOl. 0 1. HP. 10493-01 -00.

BSC (Bechtel SAIC Company) 200 1 b. Repository Design, Wmte Package, Project 21-P WR Wahyte Package with Absorber Plates, Sheel I of 3, Sheet 2 of 3, and Sheet 3 of 3. DWG-UDC- ME-00000 1 REV A. Las Vegas, Nevada: Bechtel SAIC Company. ACC: MOL.20020102.0 I 74.

,-

Y sc 4 I , Licensing & Nuclear Safetv Calculation

Title: PWR Axial B m u p Profile Analysis Document Identifier: CAL-DSU-NU-000012 REV OOA ECN 2 Page 40 of41 I BSC (Bechtel SAIC Company) 2003. Design and Engineerig, D&K/PRC IED Typical Waste Package Components Assembly I of 9. 800-IED-WISO-0020 E -000-OW. Las Vegas, Nevada: Bechtel SAIC Company, ACC: ENG.200309 17.0002.

Cacciapouti, R.J. and Van Volkinburg, S. 1497. Axial Bumup Pro$le Database fop. Pressurized ?-Voter Reactors. YAEC- 1937. Bolton, Massachusetts: Yankee Atomic Electric Company. ACC: MOL. 1998O2O9.Q 184.

CRWMS M&O J998a. Soffware Qualipcation Repor! for MCNF Version 4B2, A General Monte Carlo N-Particle Transport Code. CSCI: 30033 V4B2LV. DI: 30033-2003, Rev. 01. Las Vegas, Nevada: CRWMS M&O. ACC: MOL. 19980622.0637.

CRWMS M&O 1998b. Software Code: MCNP. V4B2LV. HP, HPUX 9.07 and 10.20; PC, Windows 95; Sun, Solaris 2.6.30033 V432LV.

CRWMS M&O 2000a. Software Code: SCALE. V4.4A. HP. 10129-4.4A-00,

CRWMS M&O 2OOOb. Users Manuul for SCALE-4.4A. 101 29-UM-4.4A-OO. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.2000 1 130.0 136,

CRWMS M&O 2000~. Validation Test Report (VTR) for SCALE-4.4A. 101 29-VTR-4.4A-00. Las Vegas, Nevada: C R W S M&O. ACC: MOZ.Z0001130.0139.

DeHart, M.D. 1996. SensitiviQ and Parametric Evaluafions of Sign8cant Aspects of Burnup Credit for PWR Spent Fuel Packages. OWTM-12973. Oak Ridge, Tennessee: Oak Ridge National Laboratory. ACC: MOL.14961205.0112.

Hogg, R.V. and Craig, A.T. .I 966. Introduction fo Mathemaiical Statistics. 2nd Edition. Pages 182-1 85. New YO&, New York: The Macmillan Company. TIC: 23.8588.

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Natrella, M.G. 1963. Experimentd Statistics. National Bureau of Standards Handbook 91. Washington, D.C.: US. Department of Commerce, National Bureau of Standards. TIC: 245911 1.

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