ML22069A338

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Supporting Documents for Response to Request for Additional Information Related to Partial Site Release and Recent Site Survey Activities, 07-46D-RE-088, Activation Analysis and Component Characterization
ML22069A338
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Site: Zion  File:ZionSolutions icon.png
Issue date: 01/31/2008
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ZionSolutions
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Office of Nuclear Material Safety and Safeguards
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ZS-2022-005 07-46D-RE-088
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ZION UNITS 1 AND 2 ACTIVATION ANALYSIS AND COMPONENT CHARACTERIZATION Report 07-046D-RE-088 January 2008 WMG Project 07-046D Prepared for:

EnergySolutions Prepared by:

16 Bank Street Peekskill, NY 10566

FOREWORD This report summarizes the activation analysis work performed by WMG, Inc. to support EnergySolutions decommissioning of Zion Station Units 1 and 2. This work was performed by WMG, Inc. under EnergySolutions Purchase Order No. PO-001531.

Proprietary Notice This document contains proprietary information of WMG, Inc. and has been submitted in confidence. The information herein is not to be disclosed to parties other than the recipient of this copy.

Zion Units 1 & 2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 i

TABLE OF CONTENTS

1.0 INTRODUCTION

.................................................................................................. 1 2.0 NEUTRON TRANSPORT AND ACTIVATION METHODOLGY ........................... 2 2.1 ANISN DISCRETE ORDINATES NEUTRON TRANSPORT CALCULATIONS ............. 2 2.2 ORIGEN 2.1 NEUTRON ACTIVATION CALCULATIONS ...................................... 2 3.0 ESTIMATED COMPONENT RADIOACTIVITY AND CLASSIFICATION STATUS ............................................................................................................... 5 3.1 OVERVIEW ................................................................................................... 5 3.2 COMPONENT RADIOACTIVITY ......................................................................... 8 3.2.1 Upper Internals Assembly ............................................................... 8 3.2.1.1 Upper Core Plate ............................................................ 9 3.2.1.2 Balance of Upper Internals............................................ 10 3.2.2 Core Barrel Assembly ................................................................... 11 3.2.3 Thermal Shield .............................................................................. 12 3.2.4 Core Baffle Assembly.................................................................... 13 3.2.5 Lower Internals.............................................................................. 14 3.2.5.1 Lower Core Plate .......................................................... 15 3.2.5.2 Balance of Lower Internals............................................ 16 3.2.6 Reactor Vessel Assembly ............................................................. 17 3.2.6.1 Reactor Vessel Wall...................................................... 18 3.2.6.2 Stainless Steel Vessel Cladding ................................... 19 4.0 NORMALIZATION ............................................................................................. 20

5.0 REFERENCES

................................................................................................... 21 Zion Units 1 & 2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 ii

LIST OF TABLES Table Title Page 2-1 Zion Unit 1 Operating History..................................................................... 4 2-2 Zion Unit 2 Operating History..................................................................... 4 3-1 Zion Unit 1 Component Activation Activity and Part 61 Status Table......... 6 3-2 Zion Unit 2 Component Activation Activity and Part 61 Status Table......... 7 3-3 Zion Unit 1 and 2 Upper Core Plate Characterization Results ................... 9 3-4 Zion Unit 1 and 2 Upper Internals Characterization Results .................... 10 3-5 Zion Unit 1 and 2 Lower Core Barrel Characterization Results................ 11 3-6 Zion Unit 1 and 2 Thermal Shield Characterization Results..................... 12 3-7 Zion Unit 1 and 2 Baffle Plates Characterization Results......................... 13 3-8 Zion Unit 1 and 2 Baffle Formers Characterization Results ..................... 14 3-9 Zion Unit 1 and 2 Lower Core Plate Characterization Results ................. 15 3-10 Zion Unit 1 and 2 Balance of Lower Internals Characterization Results .. 16 3-11 Zion Unit 1 and 2 Reactor Vessel Wall Characterization Results ............ 18 3-12 Zion Unit 1 and 2 Reactor Vessel Cladding Characterization Results ..... 19 LIST OF FIGURES Figure Title Page 2-1 Zion Units 1 and 2 ANISN Radial Thermal Flux Distribution ...................... 3 2-2 Zion Units 1 and 2 ANISN Axial Thermal Flux Distribution ........................ 3 Zion Units 1 & 2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 iii

1.0 INTRODUCTION

In August 2007, EnergySolutions engaged WMG to support Project Greenfield at the former Zion Nuclear Power Station (Zion). Phase 1 of the contract awarded to WMG included the characterization and classification of the Zion Units 1 and 2 reactor vessel(s) and internals using demonstrated and approved methodologies. This report summarizes the results of WMG's analytical methodology used to complete this phase of work and presents the results in terms of activation product content within the reactor pressure vessel and internals. The results presented herein are based on analytical data as well as empirical data. The empirical data exists in the form of surveillance capsule analysis data (References 1-4).

The preliminary results presented in this report will require further normalization after representative surveys have been obtained from each unit in accordance with the survey plan provided in November 2007 (Reference 5). The reported results are considered preliminary because normalization to measured dose rates has yet to occur and because surface contamination, which covers the surfaces of the reactor vessel and internals, has yet to be evaluated.

Based on WMGs extensive experience, surface contaminants do not dictate the NRC waste classification of the activated components. However, the surface contaminant activity, which adds relatively small quantities of activation products, fission products and transuranics, has to be considered prior to packaging the Low Level Radioactive Waste (LLRW) for disposal.

The reactor vessels and internals components are dimensionally the same between Zion Units 1 and 2. However, each unit has a unique operating history, and unique reactor vessel material resulting in different activation results. With the exceptions of drawing-specific material specifications, material data from Reference 6 was used.

Low-cobalt stainless steel was specified for components closest to the active core including the baffle plates, formers, and upper and lower core plates.

The relevant activation product radionuclide concentrations determined from these results were used to classify the reactor pressure vessel and internals according to the requirements of 10 CFR Part 61. The activation product scaling factors are also presented in this report and will be used to quantify the hard to detect radionuclide concentrations important to final classification under 10 CFR Part 61. The reported scaling factors are Co-60 based and are final.

The neutron transport and activation analysis methods used for this project are discussed in Section 2. The component specific results in terms of estimated activation activity and 10 CFR Part 61 status as of March 1, 2008 are presented in Section 3.

Normalization and benchmarking of the results are discussed in Section 4. References are presented in Section 5.

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 1 of 21

2.0 NEUTRON TRANSPORT AND ACTIVATION METHODOLOGY The ANISN (Reference 7) computer program is used to estimate neutron fluxes at various radial and axial locations in the vessel using the BUGLE-96 (Reference 8) cross-section library. The resultant fluxes are normalized to surveillance capsule analysis results. These normalized fluxes are used as inputs to the ORIGEN2.1 (Reference 9) computer program to perform activation analysis on individual components. This section discusses the models developed for the project and summarizes program output.

The same ANISN/ORIGEN methodology has been used to support decommissioning activities at 15 reactors including San Onofre 1, Shoreham, Yankee Rowe, Trojan, Saxton, Maine Yankee, Connecticut Yankee, Millstone 1, and Rancho Seco. The methodology has been refined and benchmarked over the years and has been found to provide reasonable characterization results for the components of interest.

Although the operational history differs between the Zion Units, the neutron flux results are comparable between the units because of the virtually identical dimensions, materials and temperatures of the reactor vessel and internals assemblies. The different operating histories primarily affect the activation calculations due to relative changes in power and irradiation periods.

2.1 ANISN Discrete Ordinates Neutron Transport Calculations The ANISN code is used to develop one-dimensional radial and axial neutron transport models. The ANISN cylindrical source geometry is used for the radial model, and the slab geometry is used for the axial models. Figures 2-1 and 2-2 summarize the thermal flux distribution for the radial and axial transport calculations respectively normalized to surveillance capsule data.

2.2 ORIGEN 2.1 Neutron Activation Calculations ORIGEN is used to calculate the activation and depletion of radionuclides in components exposed to a neutron flux. Each component is irradiated based on the plant specific operating histories summarized in Tables 2-1 and 2-2 using the appropriate flux as determined from the ANISN transport models.

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 2 of 21

FIGURE 2-1 Zion Units 1 and 2 ANISN Radial Thermal Flux Distribution 1.00E+14 1.00E+13 1.00E+12 1.00E+11 1.00E+10 Thermal Flux (n/cm2-sec) 1.00E+09 1.00E+08 1.00E+07 1.00E+06 1.00E+05 Region #: 1 2 3 4 5 6 7 1.00E+04 1 - Reactor Core 2 - Core Baffle & Formers 1.00E+03 3 - Core Barrel 4 - Thermal Shield 1.00E+02 5 - Reactor Vessel 6 - Vessel Insulation 1.00E+01 7 - Bioshield 1.00E+00 0 50 100 150 200 250 300 350 400 Radius (cm)

FIGURE 2-2 Zion Units 1 and 2 ANISN Axial Thermal Flux Distribution 1.00E+14 1.00E+13 1.00E+12 1.00E+11 1.00E+10 Thermal Flux (n / cm2 - s) 1.00E+09 1.00E+08 Region #:

1.00E+07 1 2 3 4 5 6 7 1.00E+06 1.00E+05 1.00E+04 1 - Secondary Core Support 1.00E+03 2 - Lower Core Support 3 - Lower Support Columns 1.00E+02 4 - Lower Core Plate 5 - Reactor Core 1.00E+01 6 - Upper Core Plate 7 - Upper Support Columns 1.00E+00 0 100 200 300 400 500 600 700 800 900 1000 Height (cm)

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 3 of 21

Table 2-1 Zion Unit 1 Operating History Cycle Start Stop Length Total EFPDs Capacity Date Date Days Days Factors 1 06/19/73 03/05/76 990 1096 444.4 44.89 2 06/19/76 09/09/77 447 533 335.6 75.09 3 12/04/77 09/14/78 284 332 250.0 88.03 4 11/01/78 10/06/79 339 475 274.3 80.92 5 02/19/80 01/14/81 330 428 296.3 89.79 6 04/22/81 02/13/82 297 441 283.6 95.48 7 07/07/82 09/07/83 427 585 324.1 75.90 8 02/12/84 01/30/85 353 490 253.5 71.81 9 06/16/85 09/04/86 445 642 381.9 85.83 10 03/20/87 02/24/88 341 416 291.7 85.53 11 05/09/88 09/07/89 486 627 401.6 82.64 12 01/26/90 02/27/92 762 930 403.9 53.01 13 08/13/92 10/21/93 434 598 392.4 90.41 14 04/03/94 09/09/95 524 623 413.2 78.85 15 12/17/95 02/21/97 432 365.7 84.66 Table 2-2 Zion Unit 2 Operating History Cycle Start Stop Length Total EFPDs Capacity Date Date Days Days Factors 1 12/24/73 01/07/77 1110 1190 482.4 43.46 2 03/28/77 02/04/78 313 372 281.1 89.82 3 04/04/78 03/09/79 339 379 291.2 85.90 4 04/18/79 05/02/80 380 464 251.1 66.08 5 07/25/80 09/11/81 413 494 342.3 82.89 6 12/01/81 02/24/83 450 542 284.5 63.21 7 05/27/83 03/27/84 305 409 284.8 93.37 8 07/09/84 09/05/85 423 575 378.8 89.56 9 02/04/86 03/25/87 414 550 369.1 89.15 10 08/08/87 10/12/88 431 508 395.8 91.84 11 12/28/88 03/01/90 428 610 361.8 84.53 12 08/30/90 11/12/92 805 907 476.1 59.15 13 02/22/93 01/06/95 683 786 459.5 67.28 14 04/19/95 09/19/96 519 462.8 89.18 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 4 of 21

3.0 ESTIMATED COMPONENT RADIOACTIVITY AND CLASSIFICATION STATUS This section presents the estimated activity for each component of interest as of March 1, 2008. These preliminary estimates are based on activation analysis results and, as stated previously in this report, will require normalization to measured dose rates to be considered final. The activities presented in this section represent the activation products only.

3.1 Overview The activation results of all components presented in this section are based on ORIGEN output using ANISN generated flux levels normalized to surveillance capsule data. Normalization to measured dose rates will change the activation activity for each component but will not change the component-specific scaling factors. Based on WMGs past experience, normalization to measured dose rates is expected to reduce component total activity and possibly NRC waste classification for some of the components.

Tables 3-1 and 3-2 summarize the preliminary results in terms of total activation activity, Co-60 activity, and 10 CFR Part 61 classification status. The estimated activity for all components, which includes the reactor vessel and internals is approximately 930,000 curies per unit as of March 1, 2008. Curie contents discussed in the text are per unit approximations representative of both units.

The reactor vessel insulation was not included in the activation portion of the analysis due to lack of any pertinent physical information. The Greater Than Class C (GTCC) components contain approximately 850,000 curies, or about 90% of the total activity. The components are separated into two basic categories in Tables 3-1 and 3-2 below. These categories are GTCC components and LLRW components.

The GTCC components will have to be segmented and either stored on site or selectively concentration averaged with other components for classification as LLRW. The GTCC components are the core baffle plates, the baffle formers and the lower core plate. The remainder of the components meets all 10 CFR Part 61 requirements for disposal as LLRW. The LLRW components include Class A, B & C waste. The Class A LLRW components can be segmented and disposed at an existing commercial disposal site. The Class B & C LLRW must also be segmented, but will be stored on-site because Zion does not currently have access to a disposal facility accepting these wastes.

The GTCC waste consists of nearly 50,000 lbs. of activated metal and contains approximately 850,000 curies per unit. The LLRW internals consist of about 380,000 lbs. of activated metal and contain approximately 80,000 curies. When these LLRW internals are combined with the reactor vessel, there is a total of 548 tons of activated metal containing approximately 81,000 curies as March 1, 2008. The specific characteristics of each significant component in Tables 3-1 and 3-2 are discussed in detail below.

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 5 of 21

TABLE 3-1 Zion Unit 1 Component Activation Activity and Part 61 Status Table Component Name Total Activity Co-60 10 CFR Part Weight (Ci) Activity 61 (lbs.) (Ci) Classification Status Greater Than Class C Waste Baffle Plates and Angles 2.66E+04 5.90E+05 3.37E+05 GTCC Baffle Formers 1.10E+04 2.17E+05 9.98E+04 GTCC Lower Core Plate 6.82E+03 3.88E+04 2.20E+04 GTCC GTCC Subtotals 4.44E+04 8.46E+05 4.59E+05 Low Level Radioactive Waste Lower Internals Balance of Lower Internals 7.90E+04 8.78E+03 4.13E+03 A, B & C Core Region Internals Lower Core Barrel 6.17E+04 5.64E+04 3.43E+04 C Thermal Shield 7.54E+04 9.99E+03 6.11E+03 B Core Region Internals Subtotal 1.37E+05 6.64E+04 4.04E+04 Upper Internals Upper Core Plate 5.67E+03 3.47E+03 2.04E+03 C Balance of Upper Internals 1.05E+05 1.17E+03 6.21E+02 A&B Upper Core Barrel 4.57E+04 5.64E+02 3.43E+02 A Hold Down Spring 4.15E+03 < 1.0 < 1.0 A Upper Internals Subtotal 1.61E+05 5.21E+03 3.00E+03 LLRW Subtotals 3.77E+05 8.04E+04 4.75E+04 Reactor Pressure Vessel Vessel Cladding* 4.73E+03 1.48E+02 8.32E+01 B Reactor Vessel Wall** 7.14E+05 4.56E+02 1.27E+02 A RPV Subtotals 7.18E+05 6.03E+02 2.10E+02 LLRW Internals and RPV Totals 1.10E+06 8.10E+04 4.77E+04

  • vessel clad weight +/- 2 feet active core region only
    • total weight - vessel clad, does not include head, studs, nuts & washers Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 6 of 21

TABLE 3-2 Zion Unit 2 Component Activation Activity and Part 61 Status Table Component Name Total Activity Co-60 10 CFR Part Weight (Ci) Activity 61 (lbs.) (Ci) Classification Status Greater Than Class C Waste Baffle Plates and Angles 2.66E+04 5.74E+05 3.30E+05 GTCC Baffle Formers 1.10E+04 2.11E+05 9.74E+04 GTCC Lower Core Plate 6.82E+03 3.77E+04 2.15E+04 GTCC GTCC Subtotals 4.44E+04 8.22E+05 4.49E+05 Low Level Radioactive Waste Lower Internals Balance of Lower Internals 7.90E+04 8.53E+03 4.04E+03 A, B & C Core Region Internals Lower Core Barrel 6.17E+04 5.48E+04 3.34E+04 C Thermal Shield 7.54E+04 9.71E+03 5.95E+03 B Core Region Internals Subtotal 1.37E+05 6.45E+04 3.94E+04 Upper Internals Upper Core Plate 5.67E+03 3.38E+03 1.99E+03 C Balance of Upper Internals 1.05E+05 1.14E+03 6.06E+02 A&B Upper Core Barrel 4.57E+04 5.48E+02 3.34E+02 A Hold Down Spring 4.15E+03 < 1.0 < 1.0 A Upper Internals Subtotal 1.61E+05 5.06E+03 2.93E+03 LLRW Subtotals 3.77E+05 7.81E+04 4.42E+04 Reactor Pressure Vessel Vessel Cladding* 4.73E+03 1.43E+02 8.11E+01 B Reactor Vessel Wall** 7.14E+05 3.12E+02 7.82E+00 A RPV Subtotals 7.18E+05 4.55E+02 8.88E+01 LLRW Internals and RPV Totals 1.10E+06 7.86E+04 4.43E+04

  • vessel clad weight +/- 2 feet active core region only
    • total weight - vessel clad, does not include head, studs, nuts & washers Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 7 of 21

3.2 Component Radioactivity Individual component estimated activation activities are decay corrected to March 1, 2008. NRC Class A and B components include the upper core barrel, hold down spring, thermal shield, reactor pressure vessel, and the balances of the upper and lower internals. These components have relatively low specific activities and may be disposed of intact or segmented and selectively packaged for disposal. The NRC Class C and GTCC components are presented as individual components. These components have relatively high specific activities and must be segmented and packaged either for on-site storage or disposal.

Based on the empirical data from previous decommissioning activities, the additional effect of surface contaminants could increase component dose rates marginally but is unlikely to change component classification. As discussed previously, surveys of the internals components are necessary to update the preliminary results presented herein to provide final characterization results.

Activities presented in this report for the components of interest are radionuclides with half-lives greater than 90 days. This is done because of the long cooling time between the end of irradiation and the time of this analysis. As a result, the short-lived activation products (i.e., Co-58, Cr-51, and Fe-59) were considered negligible.

3.2.1 Upper Internals Assembly - Drawing 685J903 The upper internals consist of the upper core plate with fuel assembly guide pins, support columns, Control Element Assembly (CEA) guide tubes, deep beam assembly, and top plate. This region extends upward from the top of the fuel assemblies. The upper internals assembly is removed as a unit during refueling. The upper core plate has a variety of holes for coolant flow and CEA penetration. The upper core plate also has a variety of fuel assembly guide pins attached that interface with the fuel assembly top nozzles for proper alignment. The support columns make the assembly rigid and maintain the distance between the upper core plate and the deep beam/top plate assembly. The CEA guide tubes ensure the CEAs, when withdrawn from the fuel maintain their alignment for insertion. With the exception of the deep beam being welded to the top plate, the other constituents are bolted together. The upper internals assemblies have a total weight of about 111,000 lbs. and contain approximately 4,600 curies.

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 8 of 21

3.2.1.1 Upper Core Plate - Drawing 685J836 The upper core plate weighs nearly 5,700 lbs. with the fuel assembly alignment pins and contains approximately 3,500 curies.

Because of its close proximity to the active fuel it is the most activated upper internals component. The radionuclide content and distribution, as well as the 10 CFR Part 61 status for the upper core plates is presented in Table 3-3. The upper core plate is NRC Class C waste and will likely require segmentation for packaging and disposal.

TABLE 3-3 Zion U1 Upper Core Plate Zion U2 Upper Core Plate Characterization Results Characterization Results Component: U1 Upper Core Plate Component: U2 Upper Core Plate Component Weight (lb.): 5.67E+03 Component Weight (lb.): 5.67E+03 Total Activity Curies 3.47E+03 Total Activity Curies 3.38E+03 Co-60 Activity Curies 2.04E+03 Co-60 Activity Curies 1.99E+03 Part 61 Table 1 C Fraction 0.42 Part 61 Table 1 C Fraction 0.42 Part 61 Table 2 C Fraction 0.37 Part 61 Table 2 C Fraction 0.37 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 1.29E-06 3.31E+00 1.63E-03 H-3 1.27E-06 3.27E+00 1.65E-03 C-14 4.33E-07 1.11E+00 5.47E-04 C-14 4.33E-07 1.11E+00 5.61E-04 Mn-54 3.36E-08 8.63E-02 4.24E-05 Mn-54 2.48E-08 6.38E-02 3.21E-05 Fe-55 2.35E-04 6.05E+02 2.97E-01 Fe-55 2.15E-04 5.54E+02 2.79E-01 Co-60 7.92E-04 2.04E+03 1.00E+00 Co-60 7.73E-04 1.99E+03 1.00E+00 Ni-59 2.50E-06 6.43E+00 3.16E-03 Ni-59 2.50E-06 6.44E+00 3.24E-03 Ni-63 3.20E-04 8.23E+02 4.04E-01 Ni-63 3.21E-04 8.24E+02 4.15E-01 Nb-94 6.98E-09 1.79E-02 8.81E-06 Nb-94 6.99E-09 1.80E-02 9.05E-06 Tc-99 1.61E-09 4.15E-03 2.04E-06 Tc-99 1.61E-09 4.15E-03 2.09E-06 Totals 1.35E-03 3.47E+03 Totals 1.31E-03 3.38E+03 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 9 of 21

3.2.1.2 Balance of Upper Internals The balance of the upper internals weighs about 105,500 lbs. and contains approximately 1,100 curies. The balance of the upper internals is NRC Class A and B waste, the majority of which can be segmented and packaged for disposal or disposed intact. The radionuclide content and distribution, as well as the 10 CFR Part 61 status, for the balances of the upper internals is presented below in Table 3-4.

TABLE 3-4 Zion Unit 1 Balance of Upper Zion Unit 2 Balance of Upper Internals Characterization Results Internals Characterization Results Component: U1 Balance of Uppers Component: U2 Balance of Uppers Component Weight (lb.): 1.05E+05 Component Weight (lb.): 1.05E+05 Total Activity Curies 1.17E+03 Total Activity Curies 1.14E+03 Co-60 Activity Curies 6.21E+02 Co-60 Activity Curies 6.06E+02 Part 61 Table 1 A Fraction 0.06 Part 61 Table 1 A Fraction 0.06 Part 61 Table 2 B Fraction 0.08 Part 61 Table 2 B Fraction 0.08 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 2.75E-08 1.31E+00 2.11E-03 H-3 2.72E-08 1.30E+00 2.14E-03 C-14 8.52E-09 4.07E-01 6.56E-04 C-14 8.53E-09 4.08E-01 6.73E-04 Mn-54 1.87E-10 8.94E-03 1.44E-05 Mn-54 1.38E-10 6.61E-03 1.09E-05 Fe-55 4.86E-06 2.32E+02 3.74E-01 Fe-55 4.45E-06 2.13E+02 3.51E-01 Co-60 1.30E-05 6.21E+02 1.00E+00 Co-60 1.27E-05 6.06E+02 1.00E+00 Ni-59 5.43E-08 2.59E+00 4.18E-03 Ni-59 5.43E-08 2.60E+00 4.28E-03 Ni-63 6.59E-06 3.15E+02 5.07E-01 Ni-63 6.61E-06 3.16E+02 5.21E-01 Nb-94 7.11E-11 3.40E-03 5.47E-06 Nb-94 7.12E-11 3.40E-03 5.62E-06 Tc-99 9.16E-12 4.38E-04 7.05E-07 Tc-99 9.18E-12 4.38E-04 7.23E-07 Totals 2.45E-05 1.17E+03 Totals 2.38E-05 1.14E+03 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 10 of 21

3.2.2 Core Barrel Assembly - Drawing 686J030 The core barrel assembly is a 365-inch long hollow cylinder with an inside diameter of 148 inches and a nominal thickness of nearly 2.3 inches. The core barrel assembly includes the upper and lower core barrels and the core support casting. The hollow cylinder portions of upper and lower core barrel closest to the active core (excluding the core support casting, and the uppermost portion of the upper core barrel) weigh about 61,700 lbs and contain the majority of the approximate 55,000 curies of activity.

The component activities, 10 CFR Part 61 status, and scaling factors are summarized in Table 3-5 below. This component is NRC Class C waste and must be segmented and packaged for disposal.

TABLE 3-5 Zion Unit 1 Lower Core Barrel Zion Unit 2 Lower Core Barrel Characterization Results Characterization Results Component: U1 Lower Core Barrel Component: U2 Lower Core Barrel Component Weight (lb.): 6.17E+04 Component Weight (lb.): 6.17E+04 Total Activity Curies 5.64E+04 Total Activity Curies 5.48E+04 Co-60 Activity Curies 3.43E+04 Co-60 Activity Curies 3.34E+04 Part 61 Table 1 C Fraction 0.68 Part 61 Table 1 C Fraction 0.68 Part 61 Table 2 C Fraction 0.52 Part 61 Table 2 C Fraction 0.52 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 1.88E-06 5.27E+01 1.54E-03 H-3 1.87E-06 5.23E+01 1.56E-03 C-14 6.23E-07 1.74E+01 5.09E-04 C-14 6.24E-07 1.75E+01 5.23E-04 Mn-54 6.21E-08 1.74E+00 5.07E-05 Mn-54 4.60E-08 1.29E+00 3.85E-05 Fe-55 3.33E-04 9.31E+03 2.72E-01 Fe-55 3.05E-04 8.53E+03 2.55E-01 Co-60 1.23E-03 3.43E+04 1.00E+00 Co-60 1.19E-03 3.34E+04 1.00E+00 Ni-59 3.48E-06 9.74E+01 2.84E-03 Ni-59 3.49E-06 9.76E+01 2.92E-03 Ni-63 4.54E-04 1.27E+04 3.70E-01 Ni-63 4.55E-04 1.27E+04 3.81E-01 Nb-94 1.20E-08 3.35E-01 9.77E-06 Nb-94 1.20E-08 3.35E-01 1.00E-05 Tc-99 2.97E-09 8.30E-02 2.42E-06 Tc-99 2.97E-09 8.31E-02 2.49E-06 Totals 2.02E-03 5.64E+04 Totals 1.96E-03 5.48E+04 The uppermost portion of the core barrel assembly (upper core barrel) weighs about 45,700 lbs and based on experience, has an activity of about 1% of the lower core barrel. The upper core barrel contains about 550 curies and is NRC Class A waste. The hold down spring is another low activity NRC Class A waste item.

Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 11 of 21

3.2.3 Thermal Shield - Drawing 684J709 The thermal shield is a 184-inch long hollow cylinder with an inside diameter of 158.5 inches and a nominal thickness of nearly 2.8 inches.

The thermal shield weighs about 75,400 lbs. and contains about 10,000 curies. The component activities, 10 CFR Part 61 status, and scaling factors are summarized in Table 3-6 below. This component is NRC Class B waste and must be segmented and packaged for storage and disposal.

TABLE 3-6 Zion Unit 1 Thermal Shield Zion Unit 2 Thermal Shield Characterization Results Characterization Results Component: U1 Thermal Shield Component: U2 Thermal Shield Component Weight (lb.): 7.54E+04 Component Weight (lb.): 7.54E+04 Total Activity Curies 9.99E+03 Total Activity Curies 9.71E+03 Co-60 Activity Curies 6.11E+03 Co-60 Activity Curies 5.95E+03 Part 61 Table 1 A Fraction 0.98 Part 61 Table 1 A Fraction 0.99 Part 61 Table 2 B Fraction 0.75 Part 61 Table 2 B Fraction 0.75 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 2.58E-07 8.80E+00 1.44E-03 H-3 2.57E-07 8.78E+00 1.47E-03 C-14 8.94E-08 3.05E+00 5.00E-04 C-14 8.95E-08 3.06E+00 5.14E-04 Mn-54 9.06E-09 3.10E-01 5.07E-05 Mn-54 6.70E-09 2.29E-01 3.85E-05 Fe-55 4.77E-05 1.63E+03 2.67E-01 Fe-55 4.37E-05 1.49E+03 2.51E-01 Co-60 1.79E-04 6.11E+03 1.00E+00 Co-60 1.74E-04 5.95E+03 1.00E+00 Ni-59 5.03E-07 1.72E+01 2.81E-03 Ni-59 5.04E-07 1.72E+01 2.89E-03 Ni-63 6.51E-05 2.23E+03 3.65E-01 Ni-63 6.53E-05 2.23E+03 3.75E-01 Nb-94 1.74E-09 5.96E-02 9.76E-06 Nb-94 1.75E-09 5.97E-02 1.00E-05 Tc-99 4.36E-10 1.49E-02 2.44E-06 Tc-99 4.37E-10 1.49E-02 2.51E-06 Totals 2.92E-04 9.99E+03 Totals 2.84E-04 9.71E+03 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 12 of 21

3.2.4 Core Baffle Assembly - Drawing 686J123 The core baffle assembly is divided into two regions in the radial transport model. These regions are the baffle plate and angles region and the baffle former region. This is done because of the large difference in the water to metal fractions in the two regions. The core baffle is constructed of plates about an inch thick screwed in place to the baffle formers and to each other. The core baffle assembly provides lateral support for the fuel assemblies, directs coolant through the reactor core region, and is the most activated component due to its proximity to the active fuel. The activation analysis results for these two regions are presented as individual components. The component activities, 10 CFR Part 61 status, and scaling factors for baffles are summarized in Table 3-7 and for the formers in Table 3-8 below. The baffle plates have a total activity in excess of 500,000 curies and weigh about 26,600 lbs. The baffle formers have a total activity more than 200,000 curies and weigh approximately 11,000 lbs. The core baffle assemblies greatly exceed NRC Class C limits and must be segmented and stored on site as GTCC waste.

TABLE 3-7 Zion Unit 1 Baffle Plates Zion Unit 2 Baffle Plates Characterization Results Characterization Results Component: U1 Baffle Plates Component: U2 Baffle Plates Component Weight (lb.): 2.66E+04 Component Weight (lb.): 2.66E+04 Total Activity Curies 5.90E+05 Total Activity Curies 5.74E+05 Co-60 Activity Curies 3.37E+05 Co-60 Activity Curies 3.30E+05 Part 61 Table 1 C Fraction 17.3 Part 61 Table 1 C Fraction 17.3 Part 61 Table 2 C Fraction 13.4 Part 61 Table 2 C Fraction 13.4 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 1.88E-05 2.27E+02 6.73E-04 H-3 1.85E-05 2.23E+02 6.77E-04 C-14 1.73E-05 2.09E+02 6.19E-04 C-14 1.73E-05 2.09E+02 6.34E-04 Mn-54 1.86E-06 2.24E+01 6.66E-05 Mn-54 1.38E-06 1.66E+01 5.03E-05 Fe-55 9.17E-03 1.11E+05 3.28E-01 Fe-55 8.40E-03 1.01E+05 3.07E-01 Co-60 2.80E-02 3.37E+05 1.00E+00 Co-60 2.74E-02 3.30E+05 1.00E+00 Ni-59 7.31E-05 8.82E+02 2.61E-03 Ni-59 7.32E-05 8.83E+02 2.68E-03 Ni-63 1.17E-02 1.41E+05 4.17E-01 Ni-63 1.17E-02 1.41E+05 4.27E-01 Nb-94 3.16E-07 3.81E+00 1.13E-05 Nb-94 3.17E-07 3.82E+00 1.16E-05 Tc-99 7.02E-08 8.47E-01 2.51E-06 Tc-99 7.03E-08 8.48E-01 2.57E-06 Totals 4.89E-02 5.90E+05 Totals 4.75E-02 5.74E+05 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 13 of 21

TABLE 3-8 Zion Unit 1 Baffle Formers Zion Unit 2 Baffle Formers Characterization Results Characterization Results Component: U1 Baffle Formers Component: U2 Baffle Formers Component Weight (lb.): 1.10E+04 Component Weight (lb.): 1.10E+04 Total Activity Curies 2.17E+05 Total Activity Curies 2.11E+05 Co-60 Activity Curies 9.98E+04 Co-60 Activity Curies 9.74E+04 Part 61 Table 1 C Fraction 11.5 Part 61 Table 1 C Fraction 11.5 Part 61 Table 2 C Fraction 15.2 Part 61 Table 2 C Fraction 15.2 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 2.43E-05 1.21E+02 1.21E-03 H-3 2.38E-05 1.18E+02 1.21E-03 C-14 1.87E-05 9.28E+01 9.30E-04 C-14 1.87E-05 9.29E+01 9.54E-04 Mn-54 4.37E-07 2.17E+00 2.18E-05 Mn-54 3.24E-07 1.61E+00 1.65E-05 Fe-55 1.03E-02 5.14E+04 5.15E-01 Fe-55 9.48E-03 4.71E+04 4.83E-01 Co-60 2.01E-02 9.98E+04 1.00E+00 Co-60 1.96E-02 9.74E+04 1.00E+00 Ni-59 9.08E-05 4.51E+02 4.53E-03 Ni-59 9.10E-05 4.52E+02 4.64E-03 Ni-63 1.32E-02 6.56E+04 6.58E-01 Ni-63 1.32E-02 6.58E+04 6.75E-01 Nb-94 1.55E-07 7.73E-01 7.75E-06 Nb-94 1.56E-07 7.74E-01 7.94E-06 Tc-99 2.06E-08 1.02E-01 1.02E-06 Tc-99 2.06E-08 1.02E-01 1.05E-06 Totals 4.38E-02 2.17E+05 Totals 4.24E-02 2.11E+05 3.2.5 Lower Internals The lower internals include:

Component Drawings Core support casting, 685J224 Lower core plate 618F155 Lower support columns 617F593 Support column extensions 649D88, and 5649D86 Flow distributor plate 541F102 Instrument guide tubes 617F596 and 5649D88 Secondary core support 542F115 This region extends from the bottom of the fuel assemblies to the reactor vessel bottom head. The lower internals, including the core support casting, has a total weight of about 86,000 lbs. and contains approximately 47,000 curies. The lower core plate contains approximately 38,000 curies, or about 80% of the total lower internals activity.

Understandably this is because the lower core plate is the closest component to the active fuel.

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3.2.5.1 Lower Core Plate - Drawing 618F155 The lower core plate, like the upper core plate, is about 2 inches thick, has a variety of through holes and includes bolted-on fuel assembly alignment pins. The lower core plate weighs about 6,800 lbs including the alignment pins, and manway cover, and contains about 38,000 curies. The radionuclide content and distribution, as well as the 10 CFR Part 61 status for the lower core plates is presented in Table 3-9. Because the lower core plates are much closer to the active fuel than the upper core plates, the lower core plates, by themselves, exceed NRC Class C limits and must be segmented and stored on site as GTCC waste.

TABLE 3-9 Zion Unit 1 Lower Core Plate Zion Unit 2 Lower Core Plate Characterization Results Characterization Results Component: U1 Lower Core Plate Component: U2 Lower Core Plate Component Weight (lb.): 6.82E+03 Component Weight (lb.): 6.82E+03 Total Activity Curies 3.88E+04 Total Activity Curies 3.77E+04 Co-60 Activity Curies 2.20E+04 Co-60 Activity Curies 2.15E+04 Part 61 Table 1 C Fraction 3.91 Part 61 Table 1 C Fraction 3.92 Part 61 Table 2 C Fraction 3.54 Part 61 Table 2 C Fraction 3.55 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 1.23E-05 3.81E+01 1.73E-03 H-3 1.22E-05 3.76E+01 1.75E-03 C-14 4.20E-06 1.30E+01 5.91E-04 C-14 4.21E-06 1.30E+01 6.06E-04 Mn-54 3.10E-07 9.59E-01 4.35E-05 Mn-54 2.29E-07 7.09E-01 3.30E-05 Fe-55 2.28E-03 7.06E+03 3.21E-01 Fe-55 2.09E-03 6.47E+03 3.01E-01 Co-60 7.12E-03 2.20E+04 1.00E+00 Co-60 6.95E-03 2.15E+04 1.00E+00 Ni-59 2.36E-05 7.30E+01 3.31E-03 Ni-59 2.36E-05 7.31E+01 3.40E-03 Ni-63 3.09E-03 9.55E+03 4.34E-01 Ni-63 3.09E-03 9.57E+03 4.45E-01 Nb-94 6.45E-08 2.00E-01 9.06E-06 Nb-94 6.46E-08 2.00E-01 9.30E-06 Tc-99 1.43E-08 4.43E-02 2.01E-06 Tc-99 1.43E-08 4.43E-02 2.06E-06 Totals 1.25E-02 3.88E+04 Totals 1.22E-02 3.77E+04 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 15 of 21

3.2.5.2 Balance of Lower Internals The balance of the lower internals weighs about 79,000 lbs. and contains approximately 8,600 curies. The component activities, 10 CFR Part 61 status, and scaling factors for the remaining components are summarized in Table 3-10 below. The balance of the lower internals are NRC Class B waste and must be segmented and packaged for disposal.

TABLE 3-10 Zion Unit 1 Balance of Lower Zion Unit 2 Balance of Lower Internals Characterization Results Internals Characterization Results Component: U1 Balance of Lowers Component: U2 Balance of Lowers Component Weight (lb.): 7.90E+04 Component Weight (lb.): 7.90E+04 Total Activity Curies 8.78E+03 Total Activity Curies 8.53E+03 Co-60 Activity Curies 4.13E+03 Co-60 Activity Curies 4.04E+03 Part 61 Table 1 A Fraction 0.63 Part 61 Table 1 A Fraction 0.63 Part 61 Table 2 B Fraction 0.85 Part 61 Table 2 B Fraction 0.85 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 2.93E-07 1.05E+01 2.54E-03 H-3 2.89E-07 1.04E+01 2.57E-03 C-14 9.72E-08 3.49E+00 8.43E-04 C-14 9.74E-08 3.49E+00 8.65E-04 Mn-54 1.89E-09 6.78E-02 1.64E-05 Mn-54 1.40E-09 5.02E-02 1.24E-05 Fe-55 5.43E-05 1.95E+03 4.71E-01 Fe-55 4.98E-05 1.78E+03 4.42E-01 Co-60 1.15E-04 4.13E+03 1.00E+00 Co-60 1.13E-04 4.04E+03 1.00E+00 Ni-59 5.94E-07 2.13E+01 5.15E-03 Ni-59 5.95E-07 2.13E+01 5.29E-03 Ni-63 7.43E-05 2.66E+03 6.44E-01 Ni-63 7.44E-05 2.67E+03 6.61E-01 Nb-94 7.79E-10 2.79E-02 6.76E-06 Nb-94 7.81E-10 2.80E-02 6.93E-06 Tc-99 9.41E-11 3.37E-03 8.16E-07 Tc-99 9.43E-11 3.38E-03 8.37E-07 Totals 2.45E-04 8.78E+03 Totals 2.38E-04 8.53E+03 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 16 of 21

3.2.6 Reactor Vessel Assembly The reactor vessel assembly consists of the reactor vessel, the reactor closure head, the stainless steel vessel cladding closure studs, nuts, and miscellaneous hardware.. The cladding region was separated from the vessel wall region because they are fabricated from two different materials, which are stainless steel and carbon steel, respectively. This causes the activation of these two regions to differ significantly. The curie content for the reactor vessel and cladding regions adjacent to the active fuel is determined using ORIGEN2. Based on previous analytical models and empirical data it is assumed 90 percent of the total activity of the vessel components is located adjacent to the active fuel region. The remaining activity is located + 2 feet of the active fuel. The results for the reactor vessel assembly are summarized below.

3.2.6.1 Reactor Vessel Wall The reactor vessel wall has a total height of approximately 508 inches. The reactor vessel wall has an inner diameter of 173 inches and a wall thickness as thick as 9.5 inches. The reactor vessel wall, including the cladding has a total weight of about 720,000 lbs. and a total activity of approximately 400 curies. Based on experience approximately 99% of the total activity of the reactor vessel wall and clad is contained +/- 2 feet of the active core. The results of the characterization and 10 CFR Part 61 status of the reactor vessel walls +/- 2 feet of the active core are presented below in Table 3-11. The reactor vessel wall is NRC Class A waste.

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TABLE 3-11 Zion Unit 1 Reactor Vessel Wall Zion Unit 2 Reactor Vessel Wall Characterization Results Characterization Results Component: U1 Vessel Wall Component: U2 Vessel Wall Component Weight (lb.): 2.63E+05 Component Weight (lb.): 2.63E+05 Total Activity Curies 4.56E+02 Total Activity Curies 3.12E+02 Co-60 Activity Curies 1.27E+02 Co-60 Activity Curies 7.82E+00 Part 61 Table 1 A Fraction 0.01 Part 61 Table 1 A Fraction 0.01 Part 61 Table 2 A Fraction 0.08 Part 61 Table 2 A Fraction 0.06 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 2.30E-08 2.75E+00 2.16E-02 H-3 2.30E-08 2.74E+00 3.51E-01 C-14 4.70E-10 5.61E-02 4.42E-04 C-14 4.71E-10 5.62E-02 7.19E-03 Mn-54 5.36E-10 6.39E-02 5.03E-04 Mn-54 3.97E-10 4.73E-02 6.05E-03 Fe-55 2.60E-06 3.10E+02 2.44E+00 Fe-55 2.39E-06 2.85E+02 3.64E+01 Co-60 1.07E-06 1.27E+02 1.00E+00 Co-60 6.55E-08 7.82E+00 1.00E+00 Ni-59 9.64E-10 1.15E-01 9.05E-04 Ni-59 1.04E-09 1.25E-01 1.60E-02 Ni-63 1.26E-07 1.51E+01 1.19E-01 Ni-63 1.37E-07 1.63E+01 2.09E+00 Nb-94 1.54E-11 1.84E-03 1.45E-05 Nb-94 1.55E-11 1.85E-03 2.36E-04 Tc-99 3.40E-11 4.06E-03 3.19E-05 Tc-99 3.91E-11 4.66E-03 5.96E-04 Totals 3.82E-06 4.56E+02 Totals 2.61E-06 3.12E+02 The significant difference between the two reactor vessel walls scaling factors and Cobalt-60 activities is due to the different material data derived from surveillance capsule reports.

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3.2.6.2 Stainless Steel Vessel Cladding The vessel cladding is a stainless steel weld deposited along the entire inside surface of the reactor vessel and closure head. It has a nominal thickness of 5/32 inch. The total weight of the cladding +/-

2 feet of the active core is about 4,750 lbs. with a total activity of approximately 145 curies. Estimated activities, 10 CFR Part 61 status and scaling factors are summarized below in Table 3-12 for the vessel cladding. The cladding material, an integral part of the reactor vessel, is NRC Class A waste.

TABLE 3-12 Zion Unit 1 Reactor Vessel Cladding Zion Unit 2 Reactor Vessel Cladding Characterization Results Characterization Results Component: U1 Vessel Clad Component: U2 Vessel Clad Component Weight (lb.): 4.73E+03 Component Weight (lb.): 4.73E+03 Total Activity Curies 1.48E+02 Total Activity Curies 1.43E+02 Co-60 Activity Curies 8.32E+01 Co-60 Activity Curies 8.11E+01 Part 61 Table 1 A Fraction 0.17 Part 61 Table 1 A Fraction 0.17 Part 61 Table 2 A Fraction 0.20 Part 61 Table 2 A Fraction 0.20 Estimated Scaling Estimated Scaling Radionuclide Curies/g Curies Factors Radionuclide Curies/g Curies Factors H-3 6.92E-08 1.49E-01 1.79E-03 H-3 6.91E-08 1.48E-01 1.83E-03 C-14 2.24E-08 4.81E-02 5.78E-04 C-14 2.24E-08 4.82E-02 5.94E-04 Mn-54 8.50E-10 1.83E-03 2.19E-05 Mn-54 6.29E-10 1.35E-03 1.66E-05 Fe-55 1.27E-05 2.72E+01 3.27E-01 Fe-55 1.16E-05 2.49E+01 3.07E-01 Co-60 3.87E-05 8.32E+01 1.00E+00 Co-60 3.78E-05 8.11E+01 1.00E+00 Ni-59 1.40E-07 3.00E-01 3.61E-03 Ni-59 1.40E-07 3.01E-01 3.71E-03 Ni-63 1.71E-05 3.68E+01 4.42E-01 Ni-63 1.72E-05 3.69E+01 4.55E-01 Nb-94 2.36E-10 5.06E-04 6.09E-06 Nb-94 2.36E-10 5.07E-04 6.26E-06 Tc-99 4.10E-11 8.80E-05 1.06E-06 Tc-99 4.10E-11 8.81E-05 1.09E-06 Totals 6.88E-05 1.48E+02 Totals 6.68E-05 1.43E+02 Zion Units 1&2 Activation Analysis and Report 07-046D-RE-088 Component Characterization 01/08 Page 19 of 21

4.0 NORMALIZATION The ANISN transport calculations used to develop the one-dimensional radial and axial neutron transport models are normalized to the greater than 1 MeV flux at the surveillance capsule. This normalization data is provided in References 1-4.

Detailed radiation profiles of the internals have yet to be obtained. Radiation profiles will be used to normalize the ORIGEN2 calculated radionuclide concentrations previously presented in this report. WMG intends to use the forthcoming radiation level measurements in conjunction with QAD-CGGP-A (Reference 10) and MegaShieldTM models to normalize the activation results. The normalization to empirical data provides a more realistic determination of the neutron flux levels and energy spectra at the locations of interest. WMG uses similar methodology to characterize routine irradiated hardware from operating nuclear power plants. In addition, this methodology has been used for all irradiated reactor vessel and internals disposed to date.

Although radiation profiles are not yet available, normalization to surveillance capsule flux data is reflected in the previously presented results. WMG benchmarked the Zion activation analysis results presented in this report (i.e., normalized to surveillance capsule data only) to those from Trojan and found consistency within 5%. Therefore, the preliminary results presented herein are adequate for planning purposes.

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5.0 REFERENCES

1. Yanichko, S.E., et al., Commonwealth Edison Co., Zion Unit No. 1 Reactor Vessel Radiation Surveillance Program,, WCAP-8064, Westinghouse Electric Corporation, March 1973.
2. Yanichko, S.E., et al., Commonwealth Edison Co., Zion Unit No. 2 Reactor Vessel Radiation Surveillance Program,, WCAP-8132, Westinghouse Electric Corporation, May 1973.
3. Chicots, J.M. , et al., Zion Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations,, WCAP-10962 Rev. 3, Westinghouse Electric Corporation, September 1991.
4. Anderson, S.L., et al., ENDFB/VI Fluence Evaluation for Zion Units 1 and 2, REAC-CWE-048, Westinghouse Electric Corporation, June 1996.
5. Posivak to Bentley letter, Zion Units 1 and 2 Reactor Internals Surveys, November, 2007
6. Evans, J.C., et al., NUREG 3474, Long-Lived Activation Products in Reactor Materials, Pacific Northwest Laboratories, August 1984
7. ORNL CCC-254, ANISN-ORNL One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering, Oak Ridge National Laboratory, April 1991.
8. DLC-185, BUGLE-96, Coupled, 47-Neutron, 20 Gamma-Ray Cross Section Library derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications, Oak Ridge National Laboratory Radiation Shielding Information Center, July 1999.
9. ORNL/CCC-371, ORIGEN 2.1, Isotope Generation and Depletion Code, Matrix Exponential Method, Oak Ridge National laboratory, May 1999.
10. ORNL CCC-645, QAD-CGGP-A, A Point Kernel Code System for Neutron and Gamma-Ray Shielding Calculations using the GP Buildup Factor, December 1995.

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