ML17325B451

Rev 1 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies

ML17325B451
Person / Time
Site:	Cook
Issue date:	12/15/1998
From:	Savino A, Whittaker M CHEM-NUCLEAR SYSTEMS, INC.
To:
Shared Package
ML17325B450	List: ML17325B449 ML17325B451
References
ER-98-009, ER-98-009-R01, ER-98-9, ER-98-9-R1, NUDOCS 9903040296
Download: ML17325B451 (36)

Text

{{#Wiki_filter:CHEM-NUCLEARSYSTEMS PREPARED BY: INDEPENDENT REVIEWER: 'RINTED OR TYPED NAME Mark Whittaker Anthony Savino SIGNATURE DATE '<</iS/qg l~ii6"tS DOCUMENTTITLE: Preliminary Waste Characterization of D.C. Cook Steam Generator Lower Assemblies DOCUMENT NO. ER-98-009 REV. 1 PAGE 1 of19 99030402'Ph 9902i8 PDR ADQCK 050003iS P PDR

TABLEOF CONTENTS 1.

SUMMARY

2. PHYSICAL DESCRIPTION OF STEAM GENERATORS 3. RADIOACTIVESOURCE CHARACTERISTICS 4. CHARACTERIZATIONASSUMPTIONS 5. SOURCE CHARACTERIZATION. 5.1 Microshield Calculations 5.2 Source Distribution 6. WASTE CLASSIFICATIONAND DOT SUBTYPING. 7. REFERENCES APPENDIXA AEP SUPPLIED INFORMATION APPENDIX B SHIPPING PAPERS AND DISPOSAL MANIFESTS APPENDIX C MICROSHIELD MODELS AND OUTPUT. APPENDIX D SURFACE AREA CALCULATIONS Pacae No. .3 .3 .7 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~\\l .9 .9 10 13 15 16 17 18 LIST OF TABLES AND FIGURES Table 2-1 SGLA Characteristics Table 2-2 Internal Surface Area and Material Density Information. Table 3.1 - Radionuclide Distribution. Table 5-1 Curie Content in Straight Tube Section. Table 5-2 SGLA Total Contamination Content Results Table 6-1a DOT Subtyping of D.C. Cook SGLA 1. Table 6-1b DOT Subtyping of D.C. Cook SGLA 2 Table 6-1c DOT Subtyping of D.C. Cook SGLA 3. Table 6-1d DOT Subtyping of D.C. Cook SGLA 4. Table 6-2 Disposal Classification of D.C. Cook SGLA 3 4 5 ~ ~ ~ ~ ~ 6 9 .10 .11 11 12 12 13 Figure 2-1 D.C. Cook Steam Generator-Reference Dimensions 4 Figure 2-2 Steam Generator Channel Head Region Components .5 Figure 5-1 Microshield Model Representation of Steam Generator Source Region.......8 ER-98-009 Rev. 1 Page 2

1. Summary This report presents the preliminary analyses performed in support of the source characterization and classification of the four D.C. Cook Unit 2 Steam Generator Lower Assemblies (SGLAs) for American Electric Power, the owner and operator of the D.C. Cook plant.. The radionuclide content of the SGLAs was determined based on recently obtained isotopic and dose rate information to demonstrate compliance with applicable criteria for transportation and disposal. A final characterization willbe performed after removal of the SGLAs from the storage facilityand prior to shipment for disposal. 2. Physical Description of Steam Generators The steam generators at D.C. Cook Unit 2 are Westinghouse Model 51 and were placed in service in 1977. The generators were removed in 1988 and the steam domes removed. The remaining "lower assemblies" were placed in storage at the reactor site. Similar Westinghouse Model 51 generators were transported from Salem for disposal in 1996. The basic physical dimensions and design criteria of the SGLAs is included in Table 2-1 [from information provided in Appendix A]. A summary sketch of these basic characteristics is provided in Figure 2-1. This information is utilized to develop the surface areas and effective source region density information listed in Table 2-2. Additionally, a sketch of the channel head region is provided in Figure 2-2. ER-98-009 Rev. 1 Page 3

Table 2-1 SGLA Characteristics General.Information Weight Length Lower Shell Diameter Lower Shell Thickness 476,000 Ibs 533 in 135 in 2.82 in 2.16E+05 kg 1354 cm 343 cm 7.16 cm Tube Bundle Data Number ofTubes Tube Bundle Radius Straight Tube Length Tube OD , Tube Wall Thickness Wrapper Data Wrapper Thickness Wrapper OD 'hannel Head Data Channel Head Radius Channel Head Thickness 3388 59.8 in 357 in 0.875. in 0.05 in 0.38 in 124.9 in 62.81 in 5.16 in 152 cm 907 cm 2.22 cm 0.13 cm 0.97 cm 317.2 cm 159.5 cm .13.1 crn Figure 2-1 D.C. Cook Steam Generator Reference Dimensions DC COOK UNIT 2 SOLA REFERENCE DATA FOR 'ITASTE CHARACTERIZATION 3.00 76.75 356.75 2.82 21.00 1 4.00 175.75 Dlo 'I 2.19 R. Smohee't Tube 59.84 R, Lor9eel Tube I i 6750 135.CO O.DIo. 3.25 129.36 LOIo 1.31 ChOnnel Heed OIYI($er Pleio Trone16on Sreh Wropper/SoHle Lower Shell Tube Plole ER-98-009 Rev. 1 Page 4

Figure 2-2 Steam Generator Channel Head Region Components Tube Plots 62.8l R. Pzwnory Nozzle 5.16 Dlndet Piete onwoy Channel Read Region Components Table 2-2 Internal Surface Area and Material Density Information Contaminated Surface Areas Total Tube Bundle Inner Surface Straight Tube Surface Area Tubes in Tube Sheet U-Tube Section Surface Area Channel Head Components Channel Hea Tube Shee DividerPlate (in'.04E+06 5.89E+06 3.47E+05 8.04E+05 4.64E+04 2.48E+04 9.20E+03 1.24E+04 (cm') 4.54E+07 , 3.80E+07 2.24E+06 5.19E+06 2.99E+05 1.60E+05 5.93E+04 8.00E+04 Densities Tubes (Nickel Alloy) Shells 8 Wrapper (Ib/in') 0.298 0.284 (glcm') 8.25 7.86 Tube Bundle Data Straight Tube Mass Straight Tube Region Volume 9.33E+4 Ibs 4.0E+6 in'.24E+7 g 6.56E+7 cm'ffective Source Region Density 0.646 g/cm'. Radioactive Source Characteristics Two contamination samples (smears) were taken from the interior of one of the SGLAs on August 20, 1998. The samples were analyzed for radionuclide content. The analysis reports are included in Appendix A. The average radionuclide content was calculated and this result was used as the isotopic distribution of radioactivity within the ER-98-009 Rev. 1 Page 5

SGLAs. For two pair of radionuclides, Cm-243/244 and Pu-239/240, a single activity is reported. This reported grouped activity was distributed equally among the radionuclides to give a curie value for each radionuclide. The average activity was normalized to 1 curie to provide the source term used in determining the dose to curie conversion factor from the shielding model. The average sample activity and the normalized source term are provided in Table 3-1. Table 3.1 - Radionuclide Distribution Radionuclide Average Measured Activity(Ci) Normalized Source (Ci) Am-241 Cm-243 2.85E-05 3.35E-06 1.57E-05 1.85E-06 Cm-244 3.35E-06 1.85E-06 Co-60 Fe-55 Ni-63 PU-238 1.69E+00 7.50E-02 5.30E-02 1.80E-05 9.29E-01 4.14E-02 2.92E-02 9.93E-06 Pu-239 PU-240 Pu-241 7.00E-06 7.00E-06 3.30E-04 3.86E-06 3.86E-06 1.82E-04 External radiation surveys were taken on the SGLAs on 6 July 1998. This survey information is included in Appendix A. Measurements taken radially on the straight tube region of the SGLA are expected to be uniform due to expected uniform deposition of contaminants in the straight tubes. Due to the storage arrangement, measurements made on the surfaces of the SGLAs facing each other show higher readings due to the contribution from the adjacent SGLA. Calculation of the expected contribution from the adjacent SGLA assuming a uniform dose field equal to that measured on the opposite side, corrected for distance using a Microshield model, shows that the higher reading can be attributed to this contribution rather than to a non-uniform dose field on the ER-98-009 Rev. 1 Page 6

measured SGLA. The 30 cm readings corrected for contribution from the adjacent- . SGLA, averaged over the, straight tube region are 21, 21, 22, and 20 mR/hr respectively for'SGLA 1, 2, 3, and 4. These average values are used in calculating the surface area contamination on the straight tubes. The final characterization willbe performed based on dose rate profiles taken on the SGLAs on removal from the storage facility. However, these dose rates are not expected to change signiTicantly from those measured in July, 1998 except for eliminating the contribution from an adjacent SGLA. 4. Characterization Assumptions Several assumptions are made in the course of performing" the characterization analyses of the steam generators. These assumptions are utilized 'to simplifythe analysis, while maintaining accuracy in the overall result.

1. Secondary-side steam generator surfaces c'ontain no activity.

Since the secondary side of the stea'm generator is exposed only to secondary side water, it is assumed that the secondary side contains only negligible quantities of radioactive contamination. This assumption has been used for previous steam generator characterizations. 2. Residual water in plugged tubes contains no activity. The plugged tubes in the steam generator could contain relatively small amounts of water that seeps into the tubes during operation of the generators. It is assumed that this water contains negligible quantities of radioactive material, and is not considered in this characterization. 3. Uniformity in distribution of primary-side surface contaminates. Two EPRI reports [2, 3] address the issue of steam generator primary side surface contamination. These reports indicate that, while the straight tube sections with the SGLAs exhibit fairly uniform surface contamination, the U-tube and tube sheet sections of the heat exchanger tubes contain higher surface contamination values than that of the straight tube sections. Additional uncertainty exists concerning the relative surface contamination levels between the tubes and the channel head surfaces, including the tube sheet, divider plate, and bowl itself. The studies indicate that the differing materials used for the tubes versus the channel head components, combined with other factors, could result in higher surface contamination values in the channel head region. To address these issues, this analysis assumes that all surfaces other than the straight tube sections contain surface contamination levels twice that of the straight ER-98-009 Rev. 1 Page 7

tube sections. This factor of two is addressed specifically in the reference [2] study for the various tube sections. It is reasonable to apply this assumption to the channel head sections as well, as they are of a similar geometry and represent only a minimal fraction ofthe total surface area, and thus only a small portion of the total activity in the SGLAs. 5. Source Characterization Employing the information from the previous sections, the radionuclide content of the SGLAs can be determined from the measured external SGLA dose rates and the SGLA design parameters. The straight tube section of the lower barrel of the SGLA is modeled with the Microshield [4] point kernel shielding code, using the normalized source term provided in Table 3-1. The shortest straight tube length is approximately 357 inches, not including the 21 inch length of tube in the tube sheet. The diameter and thickness of the radial source and shielding regions of the model are taken from the data provided by AEP included in Appendix A. A schematic of the Microshield model is provided in Figure 5-1. Figure 5-1 Microshield Model Representation of Steam Generator Source Region 356.75" Effective Straight Tube Length Source / Tube Region - 59.84" Centerline Void 2.23" Wrapper -.38" Void 2.23" Lower Barrel 2.82" The source region is modeled as nickel alloy, Alloy600, at a density of 0.658 g/cc to represent the fraction of the source region cross-section occupied by the tubes. The ER-98-009 Rev. 1 Page 8

void regions are modeled as air, and the wrapper and lower barrel are modeled as A 533 steel. The densities are provided in Table 2-2. 5.1 Microshield Calculations Analyses are performed with Microshield using the model previously described with the normalized source term provided in Table 3-1. The calculation produces an exposure rate 30 cm from the surface resulting from a 1 curie normalized source of 1.101 mR/hr/Ci ~ The measured exposure rates of 21, 21, 22, and 20 mR/hr, respectively, are then divided by this dose-per-curie factor to determine the number of curies in the straight tube section of the SGLA. The resulting activities are 19.1, 19.1, 20.0, and 18.2 Ci. This activity is then divided by the surface area of the straight tubes (3.80E+07 cm') to give the activity per unit area. The results of these calculations are presented in Table 5-1. Table 5-1 Curie Confenfin Sfjaighf Tube Secfjon SGLA 1 SGLA 2 SGLA 3 SGLA 4 Average 30 cm Exposure Rate (mR/hr) 21 21 22 20 Activityin Straight Tube Section (Ci) Areal Activity(pCi/cm') 19.1 .19.1 0.50 0.50 , 20.0 0.53 18.2 0.48 5.2 Source Distribution The straight tube source contamination calculated in Section 5.1 is utilized to determine the contamination on the U-tube and tube sheet sections of the heat exchanger tubes, as well as the channel head components. As shown in Table 5-1, the straight tube sections of the steam generator heat exchanger tubes contain 0.50, 0.50, 0.53, and 0.48 NCi/cm', respectively, of radioactive material of the distribution shown in Table 3-1. Using the factor of two discussed in Section 4, the surface contamination level on the remaining primary side surfaces of the steam generator is 1.0, 1.0, 1.05, and 0.96 pCi/cm', respectively. 'hese surface contamination levels are used to calculate the total number of curies in each steam generator as shown in Table 5-2. ER-98-009 Rev. 1 Page 9

Table 5-2 SGLA Total Contamination Content Results. Contaminated Surface Areas Surface Area (cm SGLA 1 Activity (Ci) SGLA 2 Activity (Ci) SGLA 3 Activity (Ci) SGLA 4 Activity (Ci) Straight Tube Surface Area Tubes in Tube Sheet U-Tube Section Surface Area Channel Head Tube Sheet Divider Plate Total 3.80E+07 19.1 2.25E+06 2.26 5.1 9E+06 5.21 1.60E+05 0.16 5.93E+04 0.06 8.00E+04 0.08 26.8 19.1 2.26 5.21 0.16 0.06 0.08 26.8 20.0 2.37 5.46 0.17 0.06 0.08 28.1 18.2 2.15 4.96 0.15 0.06 0.08 26.6 6. Waste Classification and DOT Subtyping The shipping and disposal classifications can be performed for the SGLAs based on the calculated radionuclide content in accordance with regulatory requirements [5, 6, 7, and 8]. This information is important to demonstrate that the SGLAs meet applicable requirements for transportation and disposal. The DOT subtyping for the SGLAs are shown in Table 6-1a 1d. As shown, the SGLAs contain a greater-than-Type-A quantity of radioactive material, with a cumulative A, values of 2.5, 2.5, 2.6, and 2.4, respectively. While the average surface I contamination levels were shown in Table 5-2 to be less than the SCO-II limitof 20 pCi/cm', uncertainty in the distribution of activity over all surfaces in the SGLA results in an uncertainty that all areas are less than the SCO-II limit. As such, an exemption from SCO-II limits and packaging requirements willbe requested from the DOT as suggested in Reference 9. The total amount of fissile material is 0.0069g which is less than 15g; therefore, the shipment qualifies as fissile excepted. . ER-98-009 Rev. 1 Page 10

Table 6-1a DOT Subtyping ofD.C. Cook SGLA 1 Isotope AM-241 CM-243 CM-244 CO-60 FE-55 Nl-63 PU-238 PU-239 PU-240 PU-241 TOTALS Curies A2 Value A2 0.000422 0.00541 4.96E-05 0.00811 4.96E-05 0.0108 24.94224 '0.8 1.110189 1080 0.784533 811 0.000266 0.00541 0.000104 0.00541 0.000104 0.00541 0.004885 0.27 26.84284 Fraction 0.07798 0.006114 0.004592 2.309466 0.001028 0.000967-0.049251 0.019153 0.019153 0.018092 2.505796 Table 6-1b DOT Subfyping ofD.C. Cook SGLA 2 Isotope AM-241 CM-243 CM-244 CO-60 FE-55 Nl-63 PU-238 PU-239 PU-240 PU-241 TOTALS Curies A2 0.000422 4.96E-05 4.96E-05 24.94224 1.110189 0.784533 0.000266 0.000104 0.000104 0.004885 26.84284 Value A2 0.00541 0.00811 0.0108 10.8 1080 811 0.00541 0.00541 0.00541 0.27 Fraction 0.07798 0.006114 0.004592 2.309466 0.001028 0.000967 0.049251 0.019153 0.019153 0.018092 2.505796 ER-98-009 Rev. 1 Page 11

Table 6-1c DOT Subtyping ofD.C. Cook SGLA 3 Isotope AM-241 CM-243 CM-244 CO-60 FE-55 Nl-63 PU-238 PU-239 PU-240 PU-241 TOTALS Curies 0.000442 5.19E-05 5.19E-05 26.12996 1.163055 0.82'I 892 0.000279 0.000109 0.000109 0.005117 28.12107 A2 Value 0.00541 0.00811 0.0108 10.8 1080 811 0.00541 0.00541 0.00541 0.27 A2 Fraction 0.081693 0.006406 0.00481 2.419441 0.001077 0.001013 0.051596 0.020065 0.020065 0.018953 2.62612 Table 6-1d DOT Sublyping ofD.C. Cook SGLA 4 Isotope AM-241 CM-243 CM-244 CO-60 FE-55 Nl-63 PU-238 PU-239 PU-240 PU-241 TOTALS Curies 0.000402 4.72E-05 4.72E-05 23.75451 1.057322 0.747174 0.000254 9.87E-05 9.87E-05 0.004652 26.56461 A2 Value 0.00541 0.00811 0.0108 10.8 1080 811 0.00541 0.00541 0.00541 0.27 A2 Fraction 0.074267 0.005823 0.004373 2.199492 0.000979 0.000921 0.046905 0.018241 0.018241 0.01723 2.386472 The disposal classification of SGLA ¹3, which has the largest total activity, is shown in Table 6-2. The disposal volume is 104.52 m'nd the mass is 1.266E+08g. This classiTication lists the required nuclides from 10 CFR 61, and demonstrates that the Table 1 and Table 2 isotopes meet the requirements for classification of the SGLAs as Class A waste. ER-98-009 Rev. 1 Page 12

Table 6-2 Disposal Classification ofD.C. Cook SGLA 3 . Table 1 Isotopes Total Activity(Ci) Specific Activity Class A Limit Fraction of Table 1 Limits C14 TC 99 I129 CM242 PU241 TRU >5 yr Half Life Table 1 Total 0.00E+00 0.000E+00 Ci/m'.00E+00 0.000E+00 Ci/m'.00E+00 0.000E+00 Ci/m'.00E+00 0.000E+00 Ci/g 5.12E-03 4.042E-11 Ci/g 1.04E-03 8.232E-12 Ci/g 0.8 Ci/m'.3 Ci/m'.008 Ci/m'.00E-06 Ci/g 3.50E-07 Ci/g I.OOE-08 Ci/g O.DOE+00 0.00E+00 0.00E+00 0.00E+00 1.15E-04 8.23E-04 0.00094 Table 2 Isotopes CO 60 CS137 H 3 Nl 63 SR 90 Total Activity(ci) 2.61E+01 0.00E+00 0.00E+00 8.22E-01 0.00E+00 Specific Activity (Ci/m') 2.499 E-01 O.OOOE+00 O.OOOE+00 7.86E-03 0.000E+00 Class A Limit (Ci/m') Fraction of Class A Limits 700 3.57E-04 1 0.00E+00 40 0.00E+00 2.25E-03 3.5 0.04 0.00E+00 Isotopes < 5yr Half Life 1.16E+00 Table 2 Total 1.11E-02 700 1.59E-05 0.0026 7. References [1] CNS Procedure EN-AD-010, "Procedure for Waste Characterization of Non-Irradiated Components or Items." [2] EPRI-NP-2968, "Primary-Side Deposits on PWR Steam Generator Tubes," Electric Power Research Institute, Palo Alto, CA, March 1983. [3] EPRI-NP-3107, "Gamma-Ray Exposure Rate Distribution in a Steam Generator," Electric Power Research Institute, Palo Alto, CA, May 1983. [4] Grove Engineering, Inc. "Microshield Computer Code," Version 5.01. [5] NRC, "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification," (May 1983). [6] Code of Federal Regulations, 10CFR Part 61 and 10CFR Part 71. ER-98-009 Rev. 1 Page 13

[7] Code of Federal Regulations, 49CFR Parts 100 to 177. [8] DHEC License CNSI-SC-097, (Barnwell Site Criteria). [9] NRC Generic Letter 96-07, "Interim Guidance on Transportation of Steam Generators," U.S. NRC Office of Nuclear Material Safety and Safeguards, December 5, 1996. [10] NUREG-1608, "Categorizing and Transporting Low Specific ActivityMaterials and Surface Contaminated Objects," U.S. Nuclear Regulatory Commission, July 1998 ER-98-009 Rev. 1 Page 14-

APPENDIX A AEP SUPPLIED INFORMATION (14 PAGES) ER-98-009 Rev. 1 Page 15

Nuclear Generation Gr~ 500 Circle Orive Buchanan, Ml491071373 Mr. John Bender Chem-Nuclear Systems, Inc. 140 Stoneridge Drive Columbia, SC 29210 Z ANERlCAN ELEClRlC POWER August 27, 1998

Dear John:

This letter serves to document two issues related to the dimensions and center of gravity of the steam generators. We have reviewed the dimensions of the steam generator as shown in CNS Sketch 46628-01, Rev. 0. The dimensions'in this drawing accurately reflect the dimensions of the steam generators at the Cook Plant. This was reviewed by comparing the CNS sketch to the drawings and other data from Westinghouse. The primary purpose of our review was to understand the shell thickness and steam generator wrapper thickness for use in Chem-Nuclear's shielding calculations. Attached are Figure 1-1 "Outline" and Figure 1-2 "General Arrangement" and the cover page from the Vertical Steam Generators Instructions. These figures show the dimensions that compare with the CNS Sketch. Also attached is a letter from Westinghouse that confirmed the wrapper thickness. The issue related to the center of gravity has been reviewed by both Westinghouse and AEP. The center of gravity is 16.5 feet above the support pad faces. This is a calculated value for the Westinghouse drawing and does not include any water, sludge,

closures, or other material.

Ifyou have any questions, please contact me. Sincerely C Walter T. MacRae Attachments ER-9IWI9, REV. 1 APPENDIXA PAGE 1

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Service Corpifratt6n DonaldC:CooR Moclear Power Plant UnitNo.2",

'ridgrhan,Michigan ~ ~ C (C IrmtesttnghouseGeneraforder NY-87398-ARB-AR5 I )Use,1971 TechnicalManual 1440-C226 APPPOVED SPIN AMP RC PC SGl AMP RC PC SG2 AMP RC PC SG3 AMP RC PC SG4 SO 1341 '1342 lrI glFI<fl'I'j'l I ~ ~ '..', Abi="lllC:"JI ELEC)'"'iC fQVl' E?lVi'"i CGilp. QATE g~ /7 7 Westinghouse Electric Corporation Tampa Division, P.O. Box 19218, Tagnpa, Florida 33616 ER-98409, REV. 1 APPENDIXA, PAGE 2

iWeatinghouse pmprietaD'lass SC ~ WesbnghOIIse Electric Company, a6oAsion ot C8S Corporation Huotear Services DiVtYgon 8ox 355 Pittsborah, Pennsytvarva ~SnMSSS Mr.John Jensen American Electri Power Replacement Steam Generator Project Office One Cook Place Btidgman, M49106 ABP-98-121 NSD-CPM-98-126 August 4, 1998 Reference; ABP RSG Data B/0 Checklist gtem 41 &) American Electri Power Service Corporation D.C. Cook Units 1 and 2 S/6 Non LOCAData

Dear John,

Attached is thc D. C. Cook, Unit 1, steam generator Non-LOCAgeometric data requested by D. C. Cook. This information was originally faxcd to Phil Monk (AEP) on Friday, July 31, 1998, in rough format. This data reflects input used in current non-LOCA licensing basis analyses for Unit 1. This data is for the current Unit 1, Model 51 steam generator design. Similar data used in LOCA licensing basis analyses is being gathered and will be forwarded when it becomes available. Should you have any questions, Please contact Mr. BillHicks on 412-374A734 or me on 4 12-374M&1. Sincerely, +get.eeI, 4&lk, ~~~ u Md k>> UCOR)n b~ lA. QW CIg 'k4s Gylel un~he J,m pp ~. M4r ,J Coe(L tIt h 3 t It usher, sue>>>>>ar ossa 44\\ 9I ~4 lo ~4 44 W 4 Oaa Vora l 4 44444 vo ovo>> tsar 0 ao 4 4 gQT'oo 44>>swsr44>>1 a~ 4444>>rvvo aa ~ 44>>oo>>r fsae 4>>sl Cpa O 0 VV ~ 0 . r ~8 ~ 44444>>4444 AO 44 r>>v 444 + u4>> I 4 ~~sr>>44~ >> 4>>OOVO wilo4 posaA '~ o>>>>vasss lO 4~ >>>>aa \\) 4 ooa>>444araaaos>>>>sasv, ~444>>ovaroau a>>osrI assur Ossa>> 4>>v>>4 C..son>>>rsaar~ f~~a~ ~ass I 44 loo II ~M\\ I a a>>44 4 4a 'ls v sos>> ~ v>>w>>a 44 IO>>>>4>> vora 4 ~ f n>> ~ 44 444>> 4 Co %~ 444% ar ssoo D wad ~ 1 I I I 4 sr I I II 1 OJOO au>>a>> pss g ~ I44a AoKgaolJ>> araa>>up>>ras>>~ Oil%VS 4>>w>>4>>saladr~ ~>m >>z (, X le bo$ H QpRQCO Addi% P,IIJivy boH ua>hevg RFC lg-49 <+C+ HCb CoilS Iot'IaVIoo5 I '4'B hole Qc,aj(oil~, I FIIIIIII' I - Ou(lug m

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RADlOLOG AL AREA STA Q Q pgggg~E.u ~ - Qg h)C QpholL OE&.L EET ~ ulGH T ~ CX H aetame Ml AT x4cM4./ i ~~~ti i+ OBOTH CQPlCt/I CM. /Ag. Qcp 4~~) co 5/9 Qos,gw~ ANQS W Nt IN W LEVEL C CDNI'hMIMATIDN IM ~ ~~2 SURVEYED B g TNE.(0>o DA awt ufo:aS/~ I %Vie@ BY-DATE I 7 3o 25 9u'~kcc, 70o 00 > 3I I o II 11 Eg-98409 APPENDIXA PAGE 7

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~ l RADIOLOGi,L AREA STATU&SWEET 5 & I IAvsd46< w GQMc QA4LDFR.E MAP No HGH TUN ~ KX HGH RAQATGN Ml S/9 Qasgq,aha ae use: a5/~ I REVIEW@ B GATE 7. g ,g,~ S.~vga.l.) r ro.n,&c/s,oiiu~ I( i + DBMS CNISCT /30 CL tutKS IK Nt HII i LMX. ( CNTAMIKATlDK IK ~ IDD~t 5URvEYED 8 TtME./osa DATE 9o'ame, 7bo Dl 2o ~ 0 ~ ER-98409, REV. 1 APPENDIXA PAGE 10

500(Rh Drive ~MI491071373 X AMERICAN'lECTRIC POWER December 10, 1998 Mr. Mark S. Whittaker Chem-Nuclear

Systems, Inc.

140 Stoneridge Drive

Columbia, SC 29210

Dear Mark:

On August 20,

1998, we took two smears of the internals of one of the old Donald C. Cook Nuclear plant's unit 2 steam generators.

These were sent to Teledyne Brown Engineering Environmental Services for a complete isotopic analysis. The results of that analysis are attached and should be used to determine the if the shipment of the generators needs an exemption from the conveyance limits. If you have any questions, please call me at 616-697-5067. Sincerely, Walter T. MacRae Attachment ER-98409, REV. 1 APPENDIXA PAGE 11

TELEDYNE BRO'AN ENGINEERING EnvironeLental Services REPORT OF ANALYSIS Nov 03 1998, 09:44 ara LOGIN 8 L2890 G J MASRAK L2890 INDIANA MICHIGAN PONER COMPANY D C COOK NUCLEAR PLANT ONE COOK PLACE BRIDGEMAN MI 49106 09/15/98 10/15/98 Pro5ect Manager: C.MENDOLA Continued NP-237 H-3 AM-241 CM-242 CM-243/244 PU-238 PU-239/240 PU 241 U-233/234 U-235 U-238 L.T. 4. L.T. 5. 3.1 +-0.6 L.T. 1 ~ 6.3 +-2.7 2.3 +-0 5 1.3 +-0 4 3.4 +-0.9 L.T. 2. L.T. 8. L.T. 1. E-03 E-04 E-05 E 06 E-06 E 05 E-05 E-04 E-06 E-07 E-06 Total uCi 09/28/98 10/21/98 10/29/98 10/29/98 10/29/98 10/29/98 10/29/98 10/31/98 10/29/98 10/29/98 10/29/98 52 62 62 62 62 62 62 62 62 62 "" q@,.~, y ~,;, ~,.;~aygzgP@~g08/20)98 09 00g,, Soea,).>P@~ IAm<.;gC,SVIP(~% +.."" P:e~<PNP~,W'~g~~vgs.Y,P,?,+a<<r" "~y,,""".>(k" FE-55 6.1 +-0.2 E 02 10/18/98 I-129 L.T. 1. E 05 10/14/98 NI-63 4.3 +-0.1 E-02 10/17/98 SR-89 L T. 1 E 04 10/17/98 SR-90 L.T. 3. E-05 10/17/98 TC-99 L.T. 3. E-05 10/14/98 BE-7 L.T. 3. E-02 09/28/98 K-40 L.T. 6. E-03 09/28/98 CR-51 L.T. 3. E-02 09/28/98 MN-54 L.T. 4. E-03 09/28/98 CO-58 LeT. 5. E-03 09/28/98 PE-59 L.T. 2. E-02 09/28/98 CO-60

1. 64+-0. 16E 00 09/28/98 CO-60 L.T. 2.

E-02 09/28/98 ZN-65 I.T. l. E-02 09/28/98 NB 94 L.T. 4. E-03 09/28/98 NB-95 L.T. 5. E-03 09/28/98 ZR-95 L.T. 9. E-03 09/28/98 N)-99 L.T. 2. E 01 09/28/98 RU-103 L.T. 4 ~ E-03 09/28/98 32 32 32 32 32 32'2 42 42 42 42 42 42 42 42 42 42 42 42 Copy: 1 of 1 ER-98409, REV. 'I APPENDIXA PAGE 13

TELEDYNE BROWN ENGINEERING cmental Services REPORT OF ANALYSIS Nov 03 1998, 09:44 an LOGIN II L2890 G J HASHAK L2890 INDIANA MICHIGAN POWER COMPANY D C COOK NUCLEAR PLANT ONE COOK PLACE BRIDGEMAN HI 49106 B 1060 C81 Release Ã: 09/15/98 10/15/98 Pro)ect Managers C.MENDOLA Continued RU-106 AG-110M SB-124 SB-125 I-131 CS-134 CS-137 BA-140 LA-140 CE-141 CE-144 RA-226 TH-228 NP-237 H-3 AM 241 CH-242 CH-243/244 PU-238 PU-239/240 PU-241 U-233/234 U-235 U-238 L.T. 3. I.T. 6. L.T. 2. L.T. 6. L.T. 5. L.T. 4. L.T. 3. L.T. 5. L.T. 5. L.T. 5. L.T. 1. L.T. 3. L.T. 3. L.T. 4. L.T. 5. 2.6 +-0.5 L.T. 9. 7.1 +-2.6 1.3 +-0.4 1.5 +-0.4 3.2 +-1.0 L.T. 3. L.T. 1. L.T. 1. E-02 Total uCi E-03 E-03 E-03 E-02 E-03 E-03 E-02 E-03 E-03 E-02 E 02 E-03 E-03 E-04 E-05 E-07 E-06 E-05 E-05 E-04 E-06 E-06 E-06 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 09/28/98 10/21/98 10/29/98 10/29/98 10/29/98 10/29/98 10/29/98 10/31/98 10/29/98 10/29/98 10/29/98 42 42 42 42 42 42 42 42 42 42 42 42 42 52 62 62 62 62 62 62 62 62 ~ Approved By: Last Page of Report ER-98409, REV. 1 APPENDIXA PAGE 14

APPENDIX B SHIPPING PAPERS AND DISPOSAL MANIFESTS (0 PAGES) P 0 BE INCLUDEDIN FINAL WASTE CHARACTERIZATIONREPORTJ ER-98-009 Rev. 1 Page 16

APPENDIX C MICROSHIELD MODELS AND OUTPUT (2 PAGES) ER-98-009 Rev. 1 Page 17

Page

1 DOS File: DCCOKCH1.MS5 Run Date: December 7, 1998 Run Time: 2:57:09 PM Duration: 00:00:21

~IcroShield v5.01 (5.01-01072) ~ Chem-Nuclear Systems, Inc. File Ref: Date: By: Checked: Case

Title:

DC Cook

== Description:== DC Cook, characterization model @30cm, normalized smears Geometry: 7 - Cylinder Volume - Side Shields Height Radius Source Dimensions 906.145 cm 29 ft 8.7 in 151.994 cm 4 ft 11.8 in IrI'ega >-: t" ~ Dose Points X Y 0 1 201.45 cm 453.07 cm 6 ft 7.3 in 14 ft 10.4 in z 0cm 0.0 in er !s."- 'u ' dhI,' Z Shield Name Source Shield 1 Shield 2 Shield 3 Shield 4 Transition AirGap Shields Dimension 6.58e+07 cm'.664cm .965 cm 5.664 cm 7.163 cm Material Alloy600 Air A 533 Air A 533 Air Air Densitel 0.646 0.00122 7.86 0.00122 7.86 0.00122 0.00122 Nuclide Am-241 Cm-243 Cm-244 Co-60 Fe-55 Ni-63 Pu-238 Pu-239 Pu-240 Pu-241 Grouping curies 1.5700 e-005 1.8500e-006 1.8500e-006 9.2920e-001 4.1359e-002 2.9227e-002 9.9300e-006 3.8600e-006 3.8600e-006 1.8200e-004 Source Input Method: Actual Photon Energies becceuerels ttCi/cm'.8090e+005 2.3873e-007 6.8450e+004 2.8130e-008 6.8450e+004 2.8130e-008 3.4380 e+010 1.4129 e-002 1.5303e+009 6.2889e-004 1.0814e+009 4.4441e-004 3.6741e+005 1.5099e-007 1.4282e+005 5.8693e-008 1.4282e+005 5.8693e-008 6.7340 e+ 006 2.7674 e-006 ~B/cm'.8329e-003 1.0408 e-003 1.0408e-003 5.2277e+002 2.3269e+001 1.6443e+$ 01 5.5867e-003 2.1717e-003 2.1717e-003 1.0239e-001 Buildup The material reference is: Shield 4 Integration Parameters Radial Circumferential Y Direction (axial) 10 10 20 EnercnEr MeV 0.0263 A~ctivit hotons/sec 1.394e+04 Fluence Rate Results Fluence Rate ~No Buildu 0.000e+00 W~th B itd 4.044e-30 MeV/cm'/sec Me V/cm'/sec ~E ~ t ~ER t mR/hr mR/hr ~No Buildu W~th B itd 0.000e+00 5.936e-32 ER-98409, REV. 1 APPENDIX C PAGE 1

Page ~: 2 DOS File: DCCOKCH1.MS5 Run Date: December 7, 1998 Run Time: 2:57:09 PM Duration: 00:00:21 0.0332 0.0447 0.0543 0.0553 0.0569 0.0573 '.0595 0.0678 0.0692 0.0995 0.1038 0.1061 0.1129 0.117 0.167 0.2098 0.2282 0.2544 0.2776 0.2854 0.6938 1.1732 325 TOTALS: ActivitCr ddt I 6.158e+02 8.194e+01 7.493e+01 1.738e+02 1.945e+01 9.560e+01 2.085e+05 9.560e+01 1.042e+03 9.779e+03 1.572e+04 1.775e+02 6.796e+01 7.395e+03 2.287e+02 2.253e+03 7.239e+03 7.512e+01 9.560e+03 4.985e+02 5.608e+06 3.438e+10 3.438e+10 6.877e+10 Fluence Rate MeV/cm'/sec ~No Buildu 8.149e-1 88 6.010e-86 1.915e-53 5.952e-51 8.691 e-49 2.430 e-47 3.737e-40 2.593e-33 5.156 e-31 1.872e-16 2.075e-1 5 6.151e-1 7 2.509e-1 6 9.029e-14 5.615e-12 6.794e-10 4.394e-09 9.997e-11 2.217e-08 1.364e-09 8.859e-04 3.912e+01 6.131 e+01 1.004e+02 MeV/cm'/sec I~BIB B tld 2.282e-31 4.832e-32 6.244e-32 1.503e-31 1.784e-32 8.903e-32 2.112e-28 1.340e-31 2.524e-30 6.578e-1 6 7.730e-1 5 2.364e-1 6 1.050e-15 3.969e-1 3 4.111 e-11 6.602e-09 4.575e-08 1.112e-09 2.564e-07 1.594e-08 8.606 e-03 2.586e+02 3.680e+02 6.266e+02 mR/hr ~No Buildu 5.996e-190 2.033e-88 4.397e-56 1.328e-53 1.858e-51 5.141e-50 7.498 e-43 4.527e-36 8.856e-34 2.863e-19 3.181e-1 8 9A43e-20 3.880e-19 1.405 e-16 9.498e-15 1.211e-12 7.972e-12 1.850e-13 4.160e-11 2.570e-12 1.710e-06 6.991e-02 1.064e-01 1.763e-01 Fl I! t ~B* ~ Ex osure Rate mR/hr d~dtd B tld 1.679e-33 1.635e-34 1.434e-34 3.353e-34 3.813e-35 1.884e-34 4.237e-31 2.340e-34 4.334e-33 1.006e-1 8 1.185e-17 3.629e-1 9 1.624e-1 8 6.173e-16 6.954e-14 1.177e-11 8.299e-11 2.058e-12 4.811e-10 3.003e-11 1.662e-05 4.620e-01 6.385e-01 1.101 e+00 ER-98409, REV. 1 APPENOIX C PAGE 2

APPENDIX D SURFACE AREA CALCULATIONS (2 PAGES) ER-98-009 Rev. 1 Page 18

~ ~ D.C. Cook SGLA Tube and Channel Head Calculations - 8/28/98 Channel Head Parameters tu gm p b = 8.25 crn "tube openings'"tubes Channel Head 8 Tube Dimensions rhcad =62.81 in ru max '9 84 >n ru min =2.19 in I0.875 rt bc =( -0.05 ~in u .875 rtube od Ltube sheet =21. in L straight tube Channel Head Area Equations 2 Atube sheet "'rhead "tube openings'"'r tube Ahead 2.4 x rhead 2 Adiv~late 2'"'ead J'tubesheet tubes "tube openings'2'"'rtube L tube sheet Straight Tube Area Calculations straight tubes "tube openings '"'ube straight tube Astraight tub s 5 886'10 'in2 Astmlght tubes =3797 10'cm'-Bend Tube Area Calculation ru max+ ru min "ave u bend Lave'" tube n tubes A u bend = 8.037'10 'in Au bend =5.185'10 'cm L ave "'rave avc = ER-98409, REV. 1 APPENDIX D PAGE 1

"~ Area Totals 4 Atube sheet 9.197'10 'in Ahead 2.479 10.'in tub sheet 5 4 10 A head 1.599'10 cm Adiv~latc = 1 239'10 in 4 ~. 2 Ad;v~lat'e. 7.996'10 'cm ~ 4 ~ tubcsheet tubes 3 465 10'in tubeshcct tubes = A channel head tube sheet + head 'div~late Achannci head 4.638'10 'in 'channel head=2.992'10 'cm ~ 4 ~. 2 ~ 5 ~ tubes Astraight tubes+ Au bend+ Atubeshcct tubes Atub 7 036 10 'in2 A tubes 4 539'10 'cm2 Straight Tube Bundle Density Calculation tube i tube od tube )'" -I 2 2K tube metal straight tube " tube openings tube metal M tube tube metal'P tube M tube 4.235'10 'gm bundle =6.56 10 cm M tube bundle bundle p bundle ~ 0.646'gm cm ER-98409, REV. 1 APPENDIX D PAGE 2}}