ML13038A487
| ML13038A487 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 01/24/2013 |
| From: | Sellers C - No Known Affiliation |
| To: | Nadiyah Morgan Plant Licensing Branch 1 |
| Morgan N NRR/DORL/LPL1-2 301-415-1016 | |
| References | |
| CCNPP-CHLE-001, Rev 0c | |
| Download: ML13038A487 (16) | |
Text
CHEMICAL EFFECTS HEAD LOSS EXPERIMENT (CHLE)
TEST PLAN for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001, Revision 0c January 24, 2013 Prepared by:
Reviewed by:
Craig D. Sellers Stephen Kinsey & Josh Wargo
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 i
REVISION HISTORY Log Revision Description 0c Issue for NRC Staff Review
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 ii Contents 1.0 Introduction................................................................................................................................................................ 1 2.0 Purpose......................................................................................................................................................................... 1 3.0 Overall experimental Plan..................................................................................................................................... 2 4.0 Sequence of Experiments....................................................................................................................................... 3 4.1 Initial Large Break LOCA................................................................................................................................... 3 4.1.1 Experimental Parameters....................................................................................................................... 3 4.1.1.1 Scaling Factor.......................................................................................................................................... 3 4.1.1.2 Debris Quantities................................................................................................................................... 4 4.1.1.3 Chemistry Conditions........................................................................................................................... 4 4.1.1.4 Reactive Material................................................................................................................................... 4 4.1.1.5 Temperature Conditions..................................................................................................................... 5 4.2 Second Large Break LOCA................................................................................................................................ 6 4.2.1 Experimental Parameters....................................................................................................................... 6 4.2.1.1 Scaling Factor.......................................................................................................................................... 6 4.2.1.2 Debris Quantities................................................................................................................................... 6 4.2.1.3 Chemistry Conditions........................................................................................................................... 6 4.2.1.4 Reactive Material................................................................................................................................... 7 4.2.1.5 Temperature Conditions..................................................................................................................... 7 4.3 Medium Break LOCA........................................................................................................................................... 8 4.3.1 Experimental Parameters....................................................................................................................... 8 4.3.1.1 Scaling Factor.......................................................................................................................................... 8 4.3.1.2 Debris Quantities................................................................................................................................... 8 4.3.1.3 Chemistry Conditions........................................................................................................................... 9 4.3.1.4 Reactive Material................................................................................................................................... 9 4.3.1.5 Temperature Conditions..................................................................................................................... 9 4.4 Small Break LOCA.............................................................................................................................................. 10 4.4.1 Experimental Parameters..................................................................................................................... 10 4.4.1.1 Scaling Factor........................................................................................................................................ 10 4.4.1.2 Debris Quantities................................................................................................................................. 10 4.4.1.3 Chemistry Conditions......................................................................................................................... 11 4.4.1.4 Reactive Material................................................................................................................................. 11 4.4.1.5 Temperature Conditions................................................................................................................... 11 5.0 References.................................................................................................................................................................. 12
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 iii List of Figures Figure 1: Temperature Profile AOR, 0 to 30 Days...................................................................................................... 5 Figure 2: Temperature Profile, Final Day...................................................................................................................... 5 Figure 3: Temperature Profile AOR, 0 to 30 Days...................................................................................................... 7 Figure 4: Temperature Profile, Final Day...................................................................................................................... 8 Figure 5: Temperature Profile MBL, 0 to 30 Days..................................................................................................... 9 Figure 6: Temperature Profile, Final Day.................................................................................................................... 10 Figure 7: Temperature Profile SBL, 0 to 30 Days..................................................................................................... 11 Figure 8: Temperature Profile, Final Day.................................................................................................................... 11 List of Tables Table 1: CCNPP Initial Large Break LOCA Debris Quantities................................................................................ 4 Table 2: CCNPP Initial Large Break LOCA Chemistry Conditions........................................................................ 4 Table 3: CCNPP Initial Large Break LOCA Reactive Material Quantities.......................................................... 4 Table 4: CCNPP Second Large Break LOCA Debris Quantities.............................................................................. 6 Table 5: CCNPP Second Large Break LOCA Chemistry Conditions..................................................................... 6 Table 6: CCNPP Second Large Break LOCA Reactive Material Quantities........................................................ 7 Table 7: CCNPP Medium Break LOCA Debris Quantities........................................................................................ 8 Table 8: CCNPP Medium Break LOCA Chemistry Conditions................................................................................ 9 Table 9: CCNPP Medium Break LOCA Reactive Material Quantities.................................................................. 9 Table 10: CCNPP Small Break LOCA Debris Quantities......................................................................................... 10 Table 11: CCNPP Small Break LOCA Chemistry Conditions................................................................................. 11 Table 12: CCNPP Small Break LOCA Reactive Material Quantities................................................................... 11
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 1 of 12
1.0 INTRODUCTION
Calvert Cliffs Nuclear Power Plant (CCNPP) is implementing a risk-informed approach to resolving GSI-191. The approach combines selected deterministic plant modifications with a risk-informed approach consistent with SECY-12-0093 Option 2b, and the South Texas Project pilot project.
The deterministic plant modifications include focused insulation replacement and removal intended to benefit resolution of GSI-191 by reducing the overall fibrous insulation content in containment and reducing the quantity of insulation products that contribute significantly to chemical effects head loss considerations. Specifically, mineral wool insulation which exhibits poor thermal insulation performance and contributes a significant concentration of alumina to the containment sump pool is being replaced with stainless steel metal reflective insulation. Other fibrous insulation is being removed where it is not necessary for thermal performance or personnel protection.
The risk-informed approach considers a wide spectrum of pipe breaks from 1/2 break size up to the double-ended guillotine break of the largest reactor coolant loop. Therefore, the chemical effects head loss experiment (CHLE) program must consider a spectrum of debris source quantities and combinations, water level, and thermal hydraulic conditions consistent with the wide spectrum of breaks. This includes debris quantities and combinations, water level, and thermal hydraulic conditions associated with the design basis double-ended guillotine break and debris quantities and combinations, water level, and thermal hydraulic conditions from smaller breaks.
CCNPP also has the potential opportunity to resolve GSI-191 through deterministic means should the CCNPP CHLE program significantly reduce or eliminate chemical effects head loss affects. In this case, CCNPP will chose to resolve GSI-191 consistent with SECY-12-0093 Option 2a. For this reason, the CHLE program will begin with consideration of design basis break debris quantities and combinations, water level, and thermal hydraulic conditions and move into consideration of smaller breaks as needed to support the risk-informed approach.
2.0 PURPOSE The purpose of this document is to describe the experiments planned for the CCNPP CHLE program.
This plan presents the sequence for performing the experiments and the test conditions for each experiment. The protocol for performing these experiments and applying the results of the experiments is described in CCNPP-CHLE-002.
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 2 of 12 3.0 OVERALL EXPERIMENTAL PLAN The overall concept for the experiments is a long-term integrated chemical effects test with head loss measured throughout the test. A test duration of 30-days is considered long-term.
Materials used in the test will be representative of the materials submerged in the containment pool or exposed to containment spray. These include destroyed insulation, qualified/unqualified coatings, concrete, latent debris and other miscellaneous materials in containment. The material quantities will be scaled such that ratio of the test fluid volume to the volume of materials immersed in the pool fluid or the surface area of materials exposed to pool or spray fluid is consistent with the ratio of the volume of the post-LOCA pool to the submerged material volume or exposed material surface area at CCNPP. The total fluid volume of the experimental facility is 750 gallons at 70°F (100 ft3).
The test chemistry will begin with the initial post-LOCA pool chemistry expected at CCNPP. A scaled quantity of NaTB buffer will be allowed to dissolve in the test chamber to simulate the dissolution of buffer in the plant. Strong acids from the radiologic decomposition of water and electrical cables1 may be added periodically to the test at a rate similar to which these acids are expected to be produced at CCNPP. No additional chemical or pH control will occur. The test chemistry will be allowed to evolve as it would in the post-LOCA environment at CCNPP. Water chemistry will be periodically sampled and tested for chemical contents.
The test temperature conditions will replicate the CCNPP post-LOCA temperature profile for the specific break size being considered in the experiment. The last day of the test will be used to investigate low temperature chemical effects by reducing the temperature in stages until room temperature is achieved.
Head loss will be monitored throughout the test using a fiber and particulate debris bed formed on a flat perforated plate that has proven to be a good detector of head loss caused by chemical effects.
The debris bed will not be representative of the debris bed expected on the sump strainer or within the reactor core at CCNPP but it will include similar fibrous material. The flow rate through the debris bed will yield a higher approach velocity than that expected at the CCNPP sump strainer.
The flow rate used will be specified to increase the sensitivity of the debris bed for identification of head loss due to chemical effects.
1 The radiologic decomposition of water and electrical cable insulation and resulting production of strong acids assumes significant core damage. The assumption of core damage is not consistent with successful ECCS performance.
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 3 of 12 4.0 SEQUENCE OF EXPERIMENTS The CCNPP CHLE program will begin with the design basis large break LOCA case and proceed into smaller break LOCA cases as needed.
4.1 Initial Large Break LOCA The Initial Large Break LOCA experiment will be designed using the plant configuration planned after selected insulation replacement and removal modifications. These modifications include replacement of mineral wool insulation with stainless steel metal reflective insulation and removal of fibrous insulation not necessary for thermal performance or personnel protection. This plant configuration is planned to be complete by the end of the 2015 and 2016 refueling outages.
The mineral wool insulation replacement is planned in two stages. The first stage is the mineral wool insulation in lower radiation dose locations which represents the majority of the mineral wool insulation. The second stage is located in high radiation dose areas on the regenerative heat exchanger and related charging and letdown piping. Replacement of this mineral wool insulation is tentatively planned for the refueling outages in 2017 and 2018 and will be done only if the initial large break LOCA experiment indicates the need for this replacement.
4.1.1 Experimental Parameters 4.1.1.1 Scaling Factor The best estimate water mass in containment for the design basis large break LOCA is 4,016,123 lbm with a volume of 64,360 ft3 at 70°F. This results in a test scaling factor of 100 ft3 / 64,360 ft3 =
0.001558.
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 4 of 12 4.1.1.2 Debris Quantities Table 1: CCNPP Initial Large Break LOCA Debris Quantities Fibrous Debris Plant Quantity Test Scaled Quantity Reference Transco Thermal Wrap (LDFG) 2112.0 lbm 3.29 lbm These are NUKON (LDFG) 612 lbm 0.95 lbm fabricated Generic Fiberglass (LDFG) 1237.5 lbm 1.93 lbm values that Temp-Mat 590 lbm 0.92 lbm are currently Mineral Wool 400.0 lbm 0.62 lbm being Lead Blanket Jacket 300 lbm 0.47 lbm determined Latent Fiber 50 lbm 0.08 lbm Metallic Insulation Debris Transco SS RMI 406 lbm (0.811 ft3) 0.62 lbm Particulate Insulation Debris Marinite Board (Calcium Silicate) 5 lbm (0.104 ft3) 0.01 lbm Dirt & Dust 150 lbm 0.23 lbm Coatings Debris Inorganic Zinc TBD ft2 TBD ft2 Epoxy TBD ft2 TBD ft2 Alkyd Enamel TBD ft2 TBD ft2 4.1.1.3 Chemistry Conditions Table 2: CCNPP Initial Large Break LOCA Chemistry Conditions Containment Pool Buffer & pH Reference Boron Concentration (H3BO3) 1936 ppm to 3105.5 ppm These are Lithium
<4.1 ppm fabricated Silica Initial pH 4.5 values that Sodium Tetra Borate (NaTB) (min) 13750 lbm (21.42 lbm scaled) are currently Sodium Tetra Borate (NaTB) (max) 14120 lbm (22.00 lbm scaled) being Hydrochloric Acid (HCl) 6.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) determined Nitric Acid (HNO3) 8.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) 4.1.1.4 Reactive Material Table 3: CCNPP Initial Large Break LOCA Reactive Material Quantities Material Description Plant Quantity Scaled Quantity Reference Metallic Aluminum 90 ft2 0.14 ft2 These are Galvanized Steel 95,583 ft2 148.9 ft2 fabricated Copper TBD ft2 TBD ft2 values Exposed Concrete TBD ft2 TBD ft2
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 5 of 12 4.1.1.5 Temperature Conditions The temperature conditions for the Large Break LOCA experiment will be based on the design basis Analysis of Record (AOR). The temperature profile of the experimental fluid is shown below:
Figure 1: Temperature Profile AOR, 0 to 30 Days The last day of the test will be used to investigate low temperature chemical effects by reducing the temperature in stages until room temperature is achieved.
Figure 2: Temperature Profile, Final Day 100 150 200 250 300 0.1 10 1000 100000 10000000 Temp (F)
Time (s)
Sump AOR Experiment Temp 50 60 70 80 90 100 110 120 130 140 150 720 725 730 735 740 745 750 Temp (F)
Time (Hr)
Experiment
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 6 of 12 4.2 Second Large Break LOCA The Second Large Break LOCA experiment will be performed if the results of the initial large break LOCA experiment indicate it is necessary. This experiment will be based on the plant configuration after the second stage of mineral wool replacement which is tentatively planned for the refueling outages in 2017 and 2018.
4.2.1 Experimental Parameters 4.2.1.1 Scaling Factor The best estimate water mass in containment for large break LOCA is 4,016,123 lbm with a volume of 64,360 ft3 at 70°F. This results in a scaling factor of 100 ft3 / 64,360 ft3 = 0.001558.
4.2.1.2 Debris Quantities Table 4: CCNPP Second Large Break LOCA Debris Quantities Fibrous Debris Plant Quantity Scaled Quantity Reference Transco Thermal Wrap (LDFG) 2112.0 lbm 3.29 lbm These are NUKON (LDFG) 612 lbm 0.95 lbm fabricated Generic Fiberglass (LDFG) 1237.5 lbm 1.93 lbm values that Temp-Mat 590 lbm 0.92 lbm are currently Mineral Wool 0.0 lbm 0.00 lbm being Lead Blanket Jacket 300 lbm 0.47 lbm determined Latent Fiber 50 lbm 0.08 lbm Metallic Insulation Debris Transco SS RMI 650 lbm (0.811 ft3) 1.01 lbm Particulate Insulation Debris Marinite Board (Calcium Silicate) 5 lbm (0.104 ft3) 0.01 lbm Dirt & Dust 150 lbm 0.23 lbm Coatings Debris Inorganic Zinc TBD ft2 TBD ft2 Epoxy TBD ft2 TBD ft2 Alkyd Enamel TBD ft2 TBD ft2 4.2.1.3 Chemistry Conditions Table 5: CCNPP Second Large Break LOCA Chemistry Conditions Containment Pool Buffer & pH Reference Boron Concentration (H3BO3) 1936 ppm to 3105.5 ppm These are Lithium
<4.1 ppm fabricated Silica Initial pH 4.5 values that Sodium Tetra Borate (NaTB) (min) 13750 lbm (21.42 lbm scaled) are currently Sodium Tetra Borate (NaTB) (max) 14120 lbm (22.00 lbm scaled) being
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 7 of 12 Hydrochloric Acid (HCl) 6.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) determined Nitric Acid (HNO3) 8.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) 4.2.1.4 Reactive Material Table 6: CCNPP Second Large Break LOCA Reactive Material Quantities Material Description Plant Quantity Scaled Quantity Reference Metallic Aluminum 90 ft2 0.14 ft2 These are Galvanized Steel 95,583 ft2 148.9 ft2 fabricated Copper TBD ft2 TBD ft2 values Exposed Concrete TBD ft2 TBD ft2 4.2.1.5 Temperature Conditions The temperature conditions for the Large Break LOCA experiment will be based on the design basis Analysis of Record (AOR). The temperature profile of the experimental fluid is shown below:
Figure 3: Temperature Profile AOR, 0 to 30 Days The last day of the test will be used to investigate low temperature chemical effects by reducing the temperature in stages until room temperature is achieved.
100 150 200 250 300 0.1 10 1000 100000 10000000 Temp (F)
Time (s)
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 8 of 12 Figure 4: Temperature Profile, Final Day 4.3 Medium Break LOCA The Medium Break LOCA experiment will be designed using the plant configuration planned after selected insulation replacement and removal modifications. These modifications include replacement of mineral wool insulation with stainless steel metal reflective insulation and removal of fibrous insulation not necessary for thermal performance or personnel protection. This plant configuration is planned to be complete by the end of the 2015 and 2016 refueling outages.
4.3.1 Experimental Parameters 4.3.1.1 Scaling Factor TBD.
4.3.1.2 Debris Quantities Table 7: CCNPP Medium Break LOCA Debris Quantities Fibrous Debris Plant Quantity Scaled Quantity Reference Transco Thermal Wrap (LDFG)
TBD lbm TBD lbm Generic Fiberglass (LDFG)
TBD lbm TBD lbm Temp-Mat TBD lbm TBD lbm Mineral Wool TBD lbm TBD lbm Lead Blanket Jacket TBD lbm TBD lbm 50 60 70 80 90 100 110 120 130 140 150 720 725 730 735 740 745 750 Temp (F)
Time (Hr)
Experiment
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 9 of 12 Latent Fiber 50 lbm 0.08 lbm Metallic Insulation Debris Transco SS RMI TBD lbm TBD lbm Particulate Insulation Debris Marinite Board (Calcium Silicate)
TBD lbm TBD lbm Dirt & Dust 150 lbm 0.23 lbm Coatings Debris Inorganic Zinc TBD ft2 TBD ft2 Epoxy TBD ft2 TBD ft2 Alkyd Enamel TBD ft2 TBD ft2 4.3.1.3 Chemistry Conditions Table 8: CCNPP Medium Break LOCA Chemistry Conditions Containment Pool Buffer & pH Reference Boron Concentration (H3BO3) 1936 ppm to 3105.5 ppm These are Lithium
<4.1 ppm fabricated Silica Initial pH 4.5 values that Sodium Tetra Borate (NaTB) (min) 13750 lbm (21.42 lbm scaled) are currently Sodium Tetra Borate (NaTB) (max) 14120 lbm (22.00 lbm scaled) being Hydrochloric Acid (HCl) 6.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) determined Nitric Acid (HNO3) 8.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) 4.3.1.4 Reactive Material Table 9: CCNPP Medium Break LOCA Reactive Material Quantities Material Description Plant Quantity Scaled Quantity Reference Metallic Aluminum 90 ft2 0.14 ft2 These are Galvanized Steel 95,583 ft2 148.9 ft2 fabricated Copper TBD ft2 TBD ft2 values Exposed Concrete TBD ft2 TBD ft2 4.3.1.5 Temperature Conditions The temperature conditions for the Medium Break LOCA experiment will be based on thermal hydraulic analyses performed specifically for this experimental program. The temperature profile of the experimental fluid is shown below:
Figure 5: Temperature Profile MBL, 0 to 30 Days TBD
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 10 of 12 The last day of the test will be used to investigate low temperature chemical effects by reducing the temperature in stages until room temperature is achieved.
Figure 6: Temperature Profile, Final Day TBD 4.4 Small Break LOCA The Small Break LOCA experiment will be designed using the plant configuration planned after selected insulation replacement and removal modifications. These modifications include replacement of mineral wool insulation with stainless steel metal reflective insulation and removal of fibrous insulation not necessary for thermal performance or personnel protection. This plant configuration is planned to be complete by the end of the 2015 and 2016 refueling outages.
4.4.1 Experimental Parameters 4.4.1.1 Scaling Factor TBD 4.4.1.2 Debris Quantities Table 10: CCNPP Small Break LOCA Debris Quantities Fibrous Debris Plant Quantity Scaled Quantity Reference Transco Thermal Wrap (LDFG)
TBD lbm TBD lbm Generic Fiberglass (LDFG)
TBD lbm TBD lbm Temp-Mat TBD lbm TBD lbm Mineral Wool TBD lbm TBD lbm Lead Blanket Jacket TBD lbm TBD lbm Latent Fiber 50 lbm 0.156 lbm Metallic Insulation Debris Transco SS RMI TBD lbm TBD lbm Particulate Insulation Debris Marinite Board (Calcium Silicate)
TBD lbm TBD lbm Dirt & Dust 150 lbm 0.467 lbm Coatings Debris Inorganic Zinc TBD ft2 TBD ft2 Epoxy TBD ft2 TBD ft2 Alkyd Enamel TBD ft2 TBD ft2
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 11 of 12 4.4.1.3 Chemistry Conditions Table 11: CCNPP Small Break LOCA Chemistry Conditions Containment Pool Buffer & pH Reference Boron Concentration (H3BO3) 1936 ppm to 3105.5 ppm These are Lithium
<4.1 ppm fabricated Silica Initial pH 4.5 values that Sodium Tetra Borate (NaTB) (min) 13750 lbm (21.42 lbm scaled) are currently Sodium Tetra Borate (NaTB) (max) 14120 lbm (22.00 lbm scaled) being Hydrochloric Acid (HCl) 6.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) determined Nitric Acid (HNO3) 8.4 ppm (after 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />) 4.4.1.4 Reactive Material Table 12: CCNPP Small Break LOCA Reactive Material Quantities Material Description Plant Quantity Scaled Quantity Reference Metallic Aluminum 90 ft2 0.28 ft2 These are Galvanized Steel 95,583 ft2 288.5 ft2 fabricated Copper TBD ft2 TBD ft2 values Exposed Concrete TBD ft2 TBD ft2 4.4.1.5 Temperature Conditions The temperature conditions for the Large Break LOCA experiment will be based on thermal hydraulic analyses performed specifically for this experimental program. The temperature profile of the experimental fluid is shown below:
Figure 7: Temperature Profile SBL, 0 to 30 Days TBD The last day of the test will be used to investigate low temperature chemical effects by reducing the temperature in stages until room temperature is achieved.
Figure 8: Temperature Profile, Final Day TBD
Chemical Effects Head Loss Experiment (CHLE)
Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-001 Revision 0c, January 24, 2013 Page 12 of 12