ML13323B191

Attachment 2: CHLE-006, Rev. 1, STP Material Calculations.

ML13323B191
Person / Time
Site:	South Texas
Issue date:	08/14/2012
From:	Hammond K, Leavitt J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML13323A673	List: ML13323B187 ML13323B191 ML13323B194 ML13323B196 ML13323B198 ML13323B199 ML13323B200 ML13323B201 ML13323B202 ML13323B204 ML13323B207 ML13323B208 ML13323B209 NOC-AE-13003040, Attachment 1: CHLE-005, Rev. 1, Determination of the Initial Pool Chemistry for the Chle Test.
References
GSI-191, NOC-AE13003040, STI 33762096, TAC MF2400, TAC MF2401 CHLE-006, Rev 1
Download: ML13323B191 (20)

Text

NOC-AE-1 3003040 Attachment 2 CHLE-006: STP Material Calculations

PROJECT DOCUMENTATION COVER PAGE Document No: CHLE-006 Revision: 1 Page 1 of 14

Title:

STP Material Calculations Project: Corrosion/Head Loss Experiment (CHLE) Program Date: 15 August 2012 Client: South Texas Project Nuclear Operating Company Summary/Purpose of Analysis or Calculation:

A survey of materials within containment at South Texas Project Nuclear Operating Company (STP) was performed to identify material that may leach corrosion or dissolution constituents into the pool solution as a result of a Loss of Coolant Accident (LOCA). This survey was performed to identify materials to include in the Chemical Head loss Experiment (CHLE) analyses and to determine the ratio of material surface area to solution volume [1] for testing purposes.

Signatures: Name: Signature: Date:

Prepared by: Janet Leavitt/Kyle Hammond < signed electronically > 3/12/2012 UNM review: Kerry Howe < signed electronically > 8/15/2012 STP review: Ernie Kee < signed electronically > 1/15/2013 Soteria review: Zahra Mohaghegh < signed electronically > 5/11/2012 8/18/2012 Revision Date Description 0 3/12/2012 Original document 1 8/14/2012 Revised to resolve internal comments

___ I ___ .1___________________

i i

& J Rev 1 Page 1of 14 Document CHLE-006, Rev No: CHLE-006, Document No: 1 Page 1 of 14

Title:

STP Material Calculations Table of Contents List of Figures ................................................................................................................................................ 3 List of Tables ................................................................................................................................................. 3 Definitions and Acronyms ............................................................................................................................. 4 1 Purpose .................................................................................................................................................... 6 2 M ethodology ........................................................................................................................................... 6 3 Design Input and Analyses ............................................................................................................. 6 3.1 Alum inum ......................................................................................................................................... 7 3.1.1 STP Survey ............................................................................................................................. 7 3.1.2 CHLE Test Param eter ....................................................................................................... 8 3.2 Fiberglass insulation ......................................................................................................................... 8 3.2.1 STP Survey ............................................................................................................................. 8 3.2.2 CHLE Test Param eter ....................................................................................................... 8 3.3 Concrete ........................................................................................................................................... 8 3.3.1 STP Survey ............................................................................................................................. 8 3.3.2 CHLE Test Param eter ....................................................................................................... 9 3.4 Latent debris .................................................................................................................................... 9 3.4.1 STP Survey ............................................................................................................................. 9 3.4.2 CHLE Test Param eter ........................................................................................................ 9 3.5 Zinc (Galvanized Steel and Coating) ......................................................................................... 10 3.5.1 STP Survey ........................................................................................................................... 10 3.5.2 CHLE Test Param eter ..................................................................................................... 10 3.6 Copper ............................................................................................................................................ 10 3.6.1 STP Survey ........................................................................................................................... 10 3.6.2 CHLE Test Param eter ..................................................................................................... 10 3.7 Lead ................................................................................................................................................ 10 3.7.1 STP Survey ........................................................................................................................... 10 3.7.2 CHLE Test Param eter ..................................................................................................... 13 3.8 Uncoated Carbon Steel .................................................................................................................. 13 3.8.1 STP Survey ........................................................................................................................... 13 3.8.2 CHLE Test Param eter ..................................................................................................... 13 4 Sum m ary ................................................................................................................................................ 13 5 References ............................................................................................................................................. 15 Document No: CHLE-006, Rev 1 Page 2 of 14

Title:

STP Material Calculations List of Figures Figure 1: Simplified CAD image showing locations of lead insulated pipes are indicated in yellow .......... 11 List of Tables Table 1: Ranges of ratio values for volume of materials to pool solution as a function of break type ........ 8 Table 2: Ratio of volume of materials to pool solution in the CHLE analyses ......................................... 8 Table 3: Calcium concentration required to form precipitation ............................................................. 9 Table 4: Volume and mass of lead insulation within STP containment ................................................. 11 Table 5: Lead precipitate and associated thermodynamic data associated with solubility .................. 12 Table 6: Lead concentration to form lead phosphate precipitate using STP representative chemistry .... 12 Table 7: Surface area of materials in the CHLE analyses ...................................................................... 14 Table 8: Volume of materials in the CHLE analyses ............................................................................... 14 Document No: CHLE-006, Rev 1 Page 3 of 14

Title:

STP Material Calculations Definitions and Acronyms RCB Reactor Containment Building RCS Reactant Cooling System RWST Refueling Water Storage Tank SI Safety Injection ECCS Emergency Core Cooling System LOCA Loss of Coolant Accident STP South Texas Project CHLE Chemical Head Loss Experiments ICE Integrated Chemical Effects Rev 1I Page 4 of 14 Document Document No: CHLE-006, Rev No: CHLE-006, Page 4 of 14

Title:

STP Material Calculations 1 Purpose A survey of materials within containment at South Texas Project Nuclear Operating Company (STP) was performed to identify materials that may leach corrosion or dissolution constituents into the containment pool solution as a result of a Loss of Coolant Accident (LOCA). This survey was performed to identify materials to include in the Chemical Head loss Experiment (CHLE) analyses and to determine the ratio of material surface area to solution volume [1] for testing purposes. These values are important in conducting a risk informed approach in evaluation of potential safety issues after a LOCA.

The initial pool chemistry and the corrosion or dissolution constituents within the pool solution may react to form chemical precipitates that may negatively impact head loss across the sump strainer, resulting in failure of the Emergency Core Cooling System (ECCS). An accurate assessment of materials that will leach corrosion or dissolution constituents into the pool solution and the ratio of material surface area to volume within containment will allow the CHLE analyses to investigate the most probable pool chemistry of a LOCA; thus determining the most realistic consequence of chemical reactions on head loss across the sump strainer as a result of LOCA conditions 2 Methodology A survey of materials in containment was conducted at STP. Surface areas or volumes of materials within containment were determined and reviewed for possible exposure to the containment pool solution. Materials with very low surface area or probability of exposure to the pool solution were eliminated from the list of materials to be included in the CHLE analyses. For materials to be included in the CHLE analyses, ratio of surface areas or volumes of materials to the pool volume [1] were determined using the following equation.

Mchle

=

Mchle -7 Vs--- mstp Where Mchle is the material surface area or volume to be included in the CHLE analyses, Vchle is the volume of the solution in the tank for the CHLE analyses, Vtp is the steady-state volume of the pool within the STP containment, and Mstp is the material surface area or volume in containment.

3 Design Input and Analyses The following data was obtained from a survey of material identified to be present in containment at STP. Materials within containment that can leach metals into the containment pool are divided between non-submerged and submerged surfaces. Non-submerged material surfaces are those exposed to the containment spray during a LOCA. Although some condensation may remain on equipment and material above the containment flood level, the amount of corrosion products contributed from this material is relatively small compared to the corrosion product generated by submerged materials. With the exception of fiberglass insulation, the division of submerged and non-submerged materials is not affected by break type. Materials found to exist within containment at STP are as listed below:

Document No: CHLE-006, Rev 1 Page 6 of 14

Title:

STP Material Calculations

• Aluminum - from valve actuator components and scaffolding

• Fiberglass (Nukon and Microtherm) -used as insulation on pipes

" Concrete - represented exposed concrete surfaces

• Zinc - in galvanized steel and in zinc-based protective coatings

• Lead - permanent lead shielding blankets

• Copper - wiring, cables, and tubes of the fan coolers

" Latent debris - dirt and lint for air flowing into containment vents

• Carbon steel - component of structural steel, steam generators, piping, etc.

Aluminum and zinc, primarily in the form of galvanized steel or non-top coated inorganic zinc based primer, have been identified as the materials most susceptible to corrosion following a LOCA [2-4]. Lead

[5] and carbon steel [4] may also corrode within the expected pH range of about 4.5 - 7.5 [6] following a LOCA, releasing metal ions into the pool solution. Fiberglass and concrete can leach constituents such as calcium and silicon into solution [4], which may produce chemical precipitates in the tri-sodium phosphate (TSP) buffered pool solution. Copper and iron (from steel) are relevant because they may affect the corrosion rates of other materials, such as aluminum [7]. Since all the above materials exist within STP containment and are expected to be present within the pool chemistry if exposed to the pool solution, all were evaluated to determine available surface area and probable exposure to the pool solution.

The pool volume at STP varies depending on the volume of water in the reactor cooling system (RCS),

refueling water storage tanks (RWST), and safety injection accumulators. The RCS and RWST contribute to the pool volume in all LOCAs. The accumulators do not discharge in small break LOCAs (SBLOCAs),

and therefore SBLOCAs technically have a smaller pool volume and therefore larger ratio of material to pool volume than other sizes of LOCAs. However, the accumulators only contribute about 4 percent of the pool volume so the effect is relatively minor. The pool volume for LBLOCA and MBLOCA were 3 3 calculated to be 71,778 ft at 21 °C [H. The pool volume for a SBLOCA was calculated to be 61,949 ft at 21 °C El]

3.1 Aluminum 3.1.1 STP Survey Sources of aluminum in containment include structures such as scaffolding and small components such as valves and aluminum coatings. Most of these materials are above the containment pool elevation, but may be exposed to containment sprays. Both integrated and separate effects tests have shown that 2

the corrosion of aluminum can be significant and may cause precipitates [4, 8, 9]. There are 5,567 ft (10% submerged and 90% non-submerged) of aluminum in containment at STP[10]. This corresponds to a ratio of aluminum surface area to pool volume of 0.078 ft 2/ft 3 .

Rev 1 Page 7 of 14 Document No:

Document CHLE-006, Rev No: CHLE-006, 1 Page 7 of 14

Title:

STP Material Calculations 3.1.2 CHLE Test Parameter Based on the information obtained from the STP survey for aluminum, the surface area of aluminum in 2

the CHLE tests will be 2.64 ft 2 in the vapor space (unsubmerged, subjected to sprays) and 0.47 ft submerged in the pool solution.

3.2 Fiberglass insulation 3.2.1 STP Survey There are two type of fiberglass insulation in solution: (1) Nukon and (2) Microtherm. Nukon insulation is classified as E-glass which is an amorphous material containing silicon dioxide, calcium oxide, aluminum oxide and boric oxide[4]. Microtherm insulation is classified as amorphous silica material which contains materials made up of predominately amorphous silica with a small percentage of E-glass[4]. The amount of fiberglass insulation within containment is determined by break type and is listed in Table 2.

Table 1: Ranges of ratio values for volume of materials to pool solution as a function of break type Break type Nukon Ratio (ft3/ ft3) Microtherm Ratio (ft3 / 3 ft )

SBLOCA Awaiting information MBLOCA 8.36E-04 0 LBLOCA 3.2.2 CHLE Test Parameter The amount of insulation is a function of break type which results in a range of material volumes. This range is dictated by the break sizes that fall within the category of LOCA scenarios. The amount of insulation material to be used in each of the 30 Day tank test is determined by debris generation calculations by the CASA Grande program.

Table 2: Ratio of volume of materials to pool solution in the CHLE analyses Fiberglass Type SBLOCA (ft3 ) MBLOCA (ft3 ) LBLOCA (ft3 )

Nukon 60 Microtherm 0 3.3 Concrete 3.3.1 STP Survey Most concrete surfaces in within containment are coated [11]. However, some uncoated surfaces could be exposed to the pool or spray water by direct jet impingement within the zone of influence (ZOI). Also, there are some concrete surfaces with unqualified or degraded qualified coatings which may fail.

Awaiting calculation from Alion Document No: CHLE-006, Rev 1 Page 8 of 14

Title:

STP Material Calculations Also, bench test will be done to characterize metals leaching from concrete. As shown by the evaluation of Table 3 (Appendix A) very little calcium (<0.5 mg/L) in solution theoretically may be required to form a calcium phosphate precipitate in a TSP buffered system, but depends on temperature and pH.

Therefore evaluating leaching rates of metals, specifically calcium, from the concrete is necessary.

Table 3: Calcium concentration required to form precipitation.

TSP Boron Calcium Test Concentration Concentration Concentration Case (mg/L) (mg/L) pHa (mg/L) 1 4032 2486 7.33 0.36 2 4032 2659 7.26 0.41 3 4032 2897 7.18 0.48 4 4435 2486 7.36 0.31 aValue reference to 21 C., value determined using STP operating median boron concentration and STP representative TSP concentration BLog K= -28.92 [12]

3.3.2 CHLE Test Parameter The concrete used for the CHLE tests will be made at the University of New Mexico (UNM)following the procedure provided by Westinghouse and used for the ICET tests [13]. The UNM concrete was be subjected to leaching bench test for comparison with a concrete core obtained from a nuclear power plant to evaluate leaching differences due to material preparation.

3.4 Latent debris 3.4.1 STP Survey This material type accounts for dust and fibers that exist in containment as a result of environmental conditions. The maximum value of latent debris in STP containment has been determined to be 170 lb.

dirt/dust and 30 lb. fiber [14]. This corresponds to a mass to volume ratio of 0.002 lb/ft3 for dirt/dust and 0.0004 lb/ft3 for fiber in containment. While it is known that the TSP buffered system may be sensitive to the addition of metals to solution, it is unknown if the soil leaches any attributable concentration of metals. Therefore, bench test will be done to evaluate metal leaching from the STP soil.

3.4.2 CHLE Test Parameter Latent debris is defined as fiber and dust. The fiber used for Latent debris is Nukon insulation and will be taken into account within the total fiberglass added to tests. The dust used in the CHLE analyses is soil obtained from the STP site using the standard environmental sampling procedure [15]. The use of the material within the 30 Day CHLE test will be evaluated by bench test that investigate metal leaching.

Any detectable metal leaching will be incorporated as a salt in the CHLE tank test.

Document No: CHLE-006, Rev I Page 9 of 14

Title:

STP Material Calculations 3.5 Zinc (Galvanized Steel and Coating) 3.5.1 STP Survey Galvanized steel and zinc based paints or coatings are sources of zinc within containment. There are 273,749 ft 2 (10% submerged and 90% non-submerged) of galvanized steel in STP containment [10]. This quantity corresponds to a surface area to volume ratio 3.81 ft 2/ft 3. There are 417,839 ft 2 (10%

submerged and 90% non-submerged) of inorganic coated zinc steel within containment at STP [16]. This quantity corresponds to a surface area to volume ratio of 5.82ft 2/ft 3.

These numbers are the conservative quantities. They are currently under review by the team to determine nominal quantities.

3.5.2 CHLE Test Parameter The inclusion of galvanized steel and zinc coated material in the LBLOCA 30-day test is currently under review by the project team. Ifthey are included, the surface area of galvanized steel in the CHLE tests will be X ft 2 in the vapor space (unsubmerged, subjected to sprays) and X ft 2 submerged in the pool solution. The surface area of zinc coated material in the CHLE tests will be Xft 2 in the vapor space (unsubmerged, subjected to sprays) and Xft 2 submerged in the pool solution.

3.6 Copper 3.6.1 STP Survey Various source of copper are found in containment at STP. These sources include wiring, cables, and tubes of the fan coolers [17].

3.6.2 CHLE Test Parameter While copper is present in STP containment, none of it will be submerged during a LOCA. In addition, significant quantities of the unsubmerged copper will be protected from spray impingement. Copper cable and wiring will not be subjected to spray as long as some insulation is in place.

As a result of all these factors, copper is excluded from the long-term CHLE tests. However since it is known that copper ma y accelerate aluminum corrosion [7], the effects of copper on aluminum corrosion under STP conditions will be investigated in short-term bench-scale corrosion tests.

3.7 Lead 3.7.1 STP Survey Lead exists in STP containment in two forms: (1) lead blankets and (2) lead pipe insulation. There are approximately 500 lead blankets (1 ft x 3 ft) in containment (45 % are submerged and 55% not submerged) [18]. The equivalent thickness for a lead sheet in the blanket is 3/16 [19]. These lead Document No: CHLE-006, Rev 1 Page 10 of 14

Title:

STP Material Calculations blankets are stored in drums with holes to prevent them from floating away if containment floods, but the sources of lead are sealed within vinyl-laminated nylon covers which provide a protection barrier between the material and pool solution.

The lead pipe insulation is sparsely present in containment as illustrated by Figure 1. The volume/mass values associated with the locations as listed in Figure 1 are listed in Table 1. Give that only three locations within containment have lead pipe insulation, the probability that they will be in the zone of influence is relatively low [20]. Since the contribution of lead from the pipe insulation is not a likely occurrence in a LOCA, the probable contribution from this material to the pool solution is neglected.

F-igure 1: Simplitmed LAD image snowing locations ot lead insulated pipes are indicated in yellow.

Table 4: Volume and mass of lead insulation within STP containment Number Official Name Mass (Ibm) Volume (ft3) 1 4CV-10010-BB1 930.7771 14.90962 2 4RC-1123-BB1 1437.241 23.02239 3 4RC-1422-BB1 1399.997 22.42536 Total Lead Blanket Insulation 3768.015 60.35737 Document No: CHLE-006, Rev 1 Page 11 of 14

Title:

STP Material Calculations A literature search of lead precipitate using ions known to exist in solution as a guide (regardless of concentration) was done to identify possible precipitates and gather thermodynamic information associated with the solubility limits, Table 5. Since lead can form a variety of precipitate products in the pool with, some which theoretically require very little soluble lead (lead phosphates and lead chlorides) in solution (Table 6), it was determined that bench test will be performed to characterize lead corrosion in the CHLE pool chemistry and the formation of precipitates. It should also be noted, however, that phosphate is commonly used as a corrosion inhibitor for lead.

Table 5: Lead precipitate and associated thermodynamic data associated with solubility Solids Log K Sources Pb(B0 2 )2(s) 6.5192 NIST [12]

Pb(OH)2 (s) 8.15 MTQ3.11[21]

Pb 2 0O(OH) 2(s) 26.19 NIST [12]

Pb 3 (PO4)2(s) -43.53 NIST[12]

PbHPO 4 (s) -23.805 NIST [12]

PbO:0.3H 20(s) 12.98 MTQ3.11[21]

PbCI2 -4.78 NIST [12]

PbSO4 -7.79 NIST [12]

Solubility 1 A Solubility 2 B Solid (mg/L) (mg/L)

Pb(C2H30 2)2[22] 551,006 2,185,084 Pb(N0 3)2 [23] 565,000 1,270,000 Solubility 1 for lead acetate is at 25 C and for Lead Nitrate it is at 20 C Solubility 2 for lead acetate is at 50 C and for Lead Nitrate is at 100 C Table 6: Lead concentration to form lead phosphate precipitate using STP representative chemistry TSP Boron lead Concentration Concentration Concentration Test Case (mg/L) (mg/L) pH (mg/L) 1 4032 2486 7.33 2.50E-05 2 4032 2659 7.26 2.87E-05 3 4032 2897 7.18 3.38E-05 4 4435 2486 7.36 2.14E-05 Document No: CHLE-006, Rev 1 Page 12 of 14

Title:

STP Material Calculations 3.7.2 CHLE Test Parameter While there is a significant surface area of lead and copper available in containment, lead will be excluded from the CHLE analyses since it is not directly exposed to spray or pool solution and the probability of material exposure due to destruction of protective outer layers is very low. However, since lead is highly insoluble, bench test will be performed to investigate lead corrosion under STP conditions.

3.8 Uncoated Carbon Steel 3.8.1 STP Survey Uncoated carbon steel is generally present in containment as structural supports. 168,836 ft 2 (10%

submerged and 90% non-submerged) is present in STP containment [16]. This quantity corresponds to a surface area to volume ratio of 2.35 ft 2/ft 3.

3.8.2 CHLE Test Parameter While there is a significant amount of carbon steel in containment, previous research found that carbons steel corrosion occurred in insignificant amounts [9]. The ICET tests contained 0.15 ft2/ft 3 of carbon steel, with 34 percent of the material submerged and 66 percent in the vapor space. The unsubmerged uncoated steel coupons had very little change in weight, with changes ranging from +1.3 to -0.4 g, compared to a mean pre-test weight of 1025 g. The submerged uncoated steel coupons in Test #1 (high pH) had a weight change of -23.3 g, but had very little weight change in the remainder of the tests (ranging from +1.4 to -1.1 g). In ICET Test #2, which corresponded most closely to the STP conditions, the unsubmerged coupons gained 1.3 g and the submerged coupons gained 1.4 g of weight. Iron concentrations remained nearly undetectable throughout the full duration of all the ICET tests. The highest concentrations of iron were less than 0.1 mg/L, during the first few days of ICET Test #3. Iron was undetectable during the entire ICET Test #2.

Based on the previously mentioned results, uncoated carbon steel will not be included in the CHLE tank tests.

4 Summary A survey of material in containment at STP was performed. For materials that are expected to contribute to the containment pool chemistry, a ratio of surface area or volume of material to the volume of solution in containment at STP was determined. These ratios were used to determine the quantity of materials to include in the 30 Day CHLE tank test, Tables 4 and 5. This approach provides accurate materials and quantities to include in the integrated test as compared to previous evaluations.

This approach allows for focus on materials of concern and probable chemical reactions associated with those materials.

Rev 1 Page 13 of 14 Document CHLE-006, Rev No: CHLE-006, Document No: 1 Page 13 of 14

Title:

STP Material Calculations Table 7: Surface area of materials in the CHLE analyses Material Surface area(ft 2 )

Submerged Non-submerged Aluminum 0.47 ft 2 2.64 ft 2 Galvanized Steel Zinc coating Concrete TBD TBD Latent debris Latent debris dirt contribution Table 8: Volume of materials in the CHLE analyses Fiberglass Type SBLOCA (ft3) MBLOCA (ft3) LBLOCA (ft3 )

Nukon 60 Microtherm 0 Page 14 of 14 Document No:

Document Rev 1 CHLE-006, Rev No: CHLE-006, 1 Page 14 of 14

Title:

STP Material Calculations 5 References

1. Alion, STP Post-LOCA Water Volume Analysis, 2012, Alion Science and Technology: Albuquerque, NM.

2. Burchell, R.C. and W.D. D., CorrosionStudyfor Determining Hydrogen Generationfrom Aluminum and Zinc During PostAccident Conditions, 1976: Pittsburgh, Pennsylvania.

3. Griess, J.C. and B.A. L., Design Considerationsof Reactor ContainmentSpray Systems -Part III.

The Corrosionof Materials in Spray Solutions, 1969: Oak Ridge, Tennessee.

4. Lane, A.E., et al., Evaluation of Post-Accident Chemical Effects in ContainmentSump Fluids to Support GSi-191, 2006, Westinghouse Electric Company: Pittsburge, PA.

5. Revie, R. and W. C., Corrosion and Corrosion Control : An Introduction to CorrosionScience and Engineering. 2008, Hoboken, NJ: Wiley.

6. STP, TGX - Required Mass of TSP for LOCA Sump Solution pH Adjustment, 2001, South Texas Project Nuclear Operating Company.

7. Davis, J.R., ed. Corrosionof Aluminum and Aluminum Alloys. 1999, ASM International.

8. Reid, R.D., K.R. Crytzer, and A.E. Lane, Evaluations of Additional Inputs to the WCAP-16530-NP Chemical Model, 2007, Westinghouse Electric Company Pitssburge, PA.

9. Dallman, J., et al., IntegratedChemical Effects Test Project:ConsolidatedData Report, 2006, Los Alamos National Laboratory: NM.

10. STP, Added Commodities Inside The RCB, 2003, South Texas Project.

11. Sande, T., K.H. Howe, and J.J. Leavitt, Expected Impact of Chemical Effects on GSI-191 Risk-Informed Evaluationfor South Texas Project,2011, Alion Science and Technology: Albuqueruqe, NM.

12. NIST, NIST CriticallySelected Stability Constantsof Metal Complexes: Version 8.0, 2008, National Institute of Standards and Technology: Gaithersburg, MD.

13. STP, STPEGS UFSAR, in Concrete.

14. Alion, GSI 191 ContainmentSump Evaluation: Debris Generation,2008.

15. STP, REMP Sample Collection, in Soil Surface Sample2009. p. 26.

16. Schulz, W., Zinc and Galvanized Steel inside containment,J. Leavitt, Editor 2012, G-Mail.

17. STP, RCB HVAC HeatSink Area Estimate, South Texas Project.

18. Schulz, W., Lead inside containment,J. Leavitt, Editor 2012, G-Mail.

19. Industries, L. Lead Blankets. 2012; Product specifications]. Available from:

http://www.lancsindustries.com/lead-wool-blankets/.

20. Mertens, A., CAD Model Summary: Sourth Texas Reactor Building CAD Modelfor Use in GSI-191 Analyses, 2011, Alion Science and Technology: Albuquerque, NM.

21. Allison, J.D., D.S. Brown, and K.J. Novo-Gradac, MINTEQA2/PRODEFA2, A Geochemical Assessment Modelfor EnvironmentalSystems: Version 3.0 User's Manual, 1991, Environmental Protection Agency, Office of Research and Development: Washington, DC.

22. Dundon, M.L. and W.E. Henderson, Measurement of Solubility byfloating Equilibrium. The solubility of Lead Acetate. Journal of the American Chemical Society, 1922. 44(6): p. 1196-1203.

23. Lide, D.R., ed. CRC Handbook of Chemistry and Physics 80th Edition. 1999.

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Document CHLE-006, Rev No: CHLE-006, Page 15 of 14

CHLE-006 STP Material Calculation Appendix A

So~eoone.18.900~aMT CoreCtrS9 CoenlewCCIC ofSTP aldn r8.~oerd onoE b i

M.8ISTSPMedednM I'l MntMC-CCHC M(. C)C2.CC wi I f-nS 54

-. -1 AOCCOC225 22Cc C 90 24 98 92Mn C Old55 24 64430339R R(, 14' 2781_ 3MTs .23 26531 Sooo 1 Wan2o I U.

.91 5211 2W50.

879 CR Median Medil i .edlW M n il r nonp,l W

.6 2725.. 2706.0 A0A .7 3,29 RCS 81.6 16.9 875 315487 35319CCB Cor Acd CKL) 15C8 8 7% 0294 c R ACA 94n 9-V3 5,W 1ý17,71 AccC A1,P 35,029 AU iiB 17,3 271.91 RcO 319.78 9493,2iC, d L1, RW! 1% 1,649.21 I-C 270,5 270,46 AccC %M7.41 W473,F4 aC,, 1 03 eood CR57 80.9 W 44612 4R 448.62315 PoCold 1 45846+7 512R07C 8,W4WI52 Unit1i nIt 2 i77 B.n 23L4 2321 232.1 mI. MI. MI RCa 3.4 .3M rCS M

w01= 95.25 8-Bp

.. (-rgL)

BoriAcid(g*.)

L 01, I

2S904r 14,M07 25 217.

1, 25M.3j ACA 2S5.94 2695ý JcCA N96.52 4441.83 269i c8 9415.91 9451.5 Acc 268.80 2"8,F26 01

.cC man,9 94].4 818T 26778 269.7 8 44 0.26 444 2

.- 473-7.67 Un,0t 0U02 U,.... U.4 1 102 5--uCI 2 10 8000 0271.5 275.7 M. M. Ma Me M M. M. 8-C~n80 f2):E 2935.1 2981.0 29%80 872 2797.5i 31 .W Ct 2%.72 287.25 R78 723002 73 338.53 8- Ad4e/L) 18,786 17,049 16907.5 ccA 2947.00 29351,Z ,cA 272.59 2726 ccA954.7 9561.70 cCB 2933.w 2950w ,CEI 271.M 2727 C8 950"30. 995W.47 0C C 292 .52.W Cc

- 273 cC 2.1 C C 9532.55 9564.95 T 298. 2962. T 273.61 273.98 R 45121635 451021.50 M I' I 1348,351 138,08 JýIToIA I SS-7137 *38

MaM U.0 20 95ýIU.

IIIý

(-dteM)~aatdu80EaB b dtt~dou a TIý -10 - -

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7,I . N.(M.) ..

.- 4. M [2 2W.49__ 7___

1._

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Water summary used in analysis Best Estimate Mass (Ibs) from Alion Source SBLOCA MBLOCA LBLOCA RWST 3630265 3630265 3630265 RCS 612644 612644 612644 Sl Accumulators 0 231334 231334 Total Water in Containment 4242909 4474243 4474243 MBLOCA and Source SMBLOCA (lb)  % contribution  % contribution LBLOCA (Ib)

RWST 3,630,265 86% 3,630,265 81%

Accum 0 0% 231,334 5%

RCS 612,644 14% 612,644 14%

Total Mass 4,242,909 100% 4,474,243 100%

Source Ibs Kg m3 ft3 Liters Contribution RWST 3,630,265 1,645,814 1,649 58,238 1,649,121 81%

RCS 612,644 277,748 278 9,828 278,306 14%

Accum 231,334 104,877 105 3,711 105,088 5%

Total 4,474,243 2,028,439 2,033 71,7781 2,032,515 100%

21.0 °C Density of water 9.74 997.9948 kg/m 3 or g/L 0.45335924 kg/lb 453.35924 g/lb 0.02831685 ft3/m3 3

T-meSlep Runt. Tall A ot o-ad-edal eade Amoutoradded .eaopep Am ,lor .I.raelOa3dd

.ol h-, ay 8NO3)M H(0(M) a 3N4 w mM) t(M) 0NO370M)

(a H ImM) 3N03)0) QtH(m4 53 ToTa1(M) 1 3-04 B,19108 2,695920E3635 3.0082 OD270 8.D19303 3.7332 0059 2.53 3,521E5 2 0.33 1,128WX-35 4.42 8-35 0., 31 0.00173 3.01-303 ,73332 0.22 1.62 5.551-35 Con~ntm.DO Manofamture PaTrt numer Molas8~

5 020 1.76750M05 8.(06920-05 0. 4 0O0354 6.406-33 3.58-02 0.4- 3.36 9.770-0s NITO*

A03 EMO NX041P-S 15.7 12 O.S 2.810MM.05 1.294213 .O001 0.ý805 1053-32 4.9W4-02 0.7 4.6 0.56-a34 8y,drohbrkli toO 160 D 303-5 12.0 24 1 4.2120 14444606-04 0a 0139 &500 1.3-E-32 5.50 6-2 0.01 S.06 2.27E-04 72 3 8.134060 3.341633-04 0.0302 0.=1497 3.92E-02 1.50-O0 2.84 14Th5 4.16-34 2 10 0.538801-346.104320334 4.0723 0.00=2763 7.23-02 2.768-0 .23 2533 -34 7.6S2 M2 1.99350M-047.48*fý,- 0.0457 0.=1376 4.571-02 1.38831 3.M 12392 9.47E-04 720 3 2.247401-4 4.118860m O.W0294 O.AOD63 2.941-02 6.316-32 2013 5.99 0.04-03 Total 0.=2287 0.08119 2.291-01 8.12Ej1 16055 76.20 Day 040 8rE3) 300(mM) 008 3+9 3 1.73M 1 0.59 23m 0.2i 6.40*J 3,58E-0 2 0.22 1.62

• *10 ddIM 1.39E 2 54W42* 12 0+76 4,*

3M 1.2-2 1.-45 24 i01 5,16 Iom 7.23-430 2.733-1 r n S f24 3.M 17.31 j O,8~-0 4*e*lOS J

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10 2.M4 S.23 14,.M 2S.93 D"-l0O IM3 U.92 Da.20 - M 213 59

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