ML19003A299

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To Integrated Final Safety Analysis Report, Chapter 2, Site Characteristics
ML19003A299
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/21/2018
From:
Florida Power & Light Co
To:
Office of New Reactors
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ML19003A318 List: ... further results
References
L-2018-237
Download: ML19003A299 (10)


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2.0-1 Revision 0 Turkey Point Units 6 & 7 - IFSAR 2.0 Site Characteristics Chapter 2 describes the characteristics and site-related design parameters of Turkey Point Units 6 & 7. The site location, characteristics, and parameters, as described in the following sections, are provided in sufficient detail to support a safety assessment of the proposed site:

Section 2.1 Geography and Demography Section 2.2 Nearby Industrial, Transportation, and Military Facilities Section 2.3 Meteorology Section 2.4 Hydrologic Engineering Section 2.5 Geology, Seismology, and Geotechnical Engineering In this chapter, the following terms are used to describe the Turkey Point plant site and surrounding area:

Turkey Point Plant Site The Units 6 & 7 plant area is part of the larger Turkey Point plant property in unincorporated Miami-Dade County, Florida. The approximately 9400-acre Turkey Point plant property comprises two oil/gas-fired (Units 1 & 2), one gas-fired combined-cycle (Unit 5), and (with the addition of Units 6 & 7) four nuclear powered (Units 3, 4, 6 & 7) steam electric generating units.

Figure 2.1-201 shows the Turkey Point site and the surrounding area within 50 miles. Figure 2.1-202 shows the general location of the Turkey Point property and localities surrounding the site within 10 miles.

Vicinity The area from the center point of the power block footprint to a 5-mile radius. The vicinity includes a much larger tract of land than the Turkey Point plant property. The vicinity is located in Miami-Dade County. For descriptions within Section 2.5 only, vicinity is defined in accordance with RG 1.208 as a 40-kilometer (25-mile) radius.

Region The area from the center point of the power block footprint to a 50-mile radius. The Turkey Point plant property is located in a rural, sparsely populated area. For descriptions within Section 2.5 only, region is defined in accordance with RG 1.208 as a 320-kilometer (200-mile) radius.

Table 2.0-201 provides a comparison of site-related design parameters for which the AP1000 plant is designed and site characteristics specific to Units 6 & 7 in support of this safety assessment. The first two columns of Table 2.0-201 are a compilation of the site parameters. The third column of Table 2.0-201 is the corresponding site characteristic. The fourth column denotes the location where this data is presented. The last column indicates whether or not the site characteristic is bounded by the corresponding AP1000 site parameter. Yes indicates the site characteristic falls within the parameter, while No indicates it does not. Where a No is indicated, a justification is provided in the reference. Control room atmospheric dispersion values, expressed as X/Q for all applicable accident analyses, are presented in Table 2.0-202. All of the control room values fall within the AP1000 acceptance criteria.

2.0-2 Revision 0 Turkey Point Units 6 & 7 - IFSAR Table 2-1 Not Used

2.0-3 Revision 0 Turkey Point Units 6 & 7 - IFSAR Table 2.0-201 (Sheet 1 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No Air Temperature Maximum Safety(b) 115°F dry bulb/86.1°F coincident wet bulb(c) 103°F dry bulb/75.2°F coincident wet bulb (100-year return period)

Subsection 2.3.1.5 Yes 86.1°F wet bulb (noncoincident) 87.4°F wet bulb (non-coincident) (100-year return estimate of 2-hour duration)

Subsection 2.3.1.5 No(d)

Minimum Safety(b)

-40°F 17.9°F (100-year return period)

Subsection 2.3.1.5 Yes Maximum Normal(e) 101°F dry bulb /80.1°F coincident wet bulb 91.3°F dry bulb/79.3°F coincident wet bulb (0.4 percent annual exceedance)

Subsection 2.3.1.5 Yes 80.1°F wet bulb (noncoincident)(f) 81.5°F wet bulb (non-coincident)

(0.4 percent annual exceedance)

Subsection 2.3.1.5 No(d)

Minimum Normal(e)

-10°F 46.9°F (99.6 percent annual exceedance)

Subsection 2.3.1.5 Yes Wind Speed Operating Basis 145 mph (3-second gust); importance factor 1.15 (safety),

1.0 (nonsafety); exposure C; topographic factor 1.0 150 mph (3-second gust, 50-year return) 161 mph (3-second gust, 100-year return);

importance factor 1.15 (safety), 1.0 (nonsafety); exposure C; topographic factor 1.0 Subsection 2.3.1.3.1 No(d)

Tornado 300 mph 200 mph(m)

Subsection 2.3.1.3.2 Yes Maximum pressure differential of 2.0 lb/in2 0.9 lb/in2 Subsection 2.3.1.3.2 Yes

2.0-4 Revision 0 Turkey Point Units 6 & 7 - IFSAR Seismic CSDRS CSDRS free field peak ground acceleration of 0.30 g with modified Regulatory Guide 1.60 response spectra(g)(h)

(See DCD Tier 1 Figures 5.0-1 and 5.0-2). The SSE is now referred to as CSDRS. Seismic input is defined at finished grade except for sites where the nuclear island is founded on hard rock. If the site-specific spectra exceed the response spectra in DCD Tier 1 Figures 5.0-1 and 5.0-2 at any frequency, or if soil conditions are outside the range evaluated for AP1000 design certification, a site-specific evaluation can be performed. This evaluation will consist of a site-specific dynamic analysis and generation of in-structure response spectra at key locations to be compared with the floor response spectra of the certified design at 5-percent damping. The site is acceptable if the floor response spectra from the site-specific evaluation do not exceed the AP1000 spectra for each of the locations or the exceedances are justified.

Peak ground acceleration:(g) 0.06g horizontal 0.06g vertical GMRS peak ground acceleration defined at 100 Hz.

Ground Motion Response Spectra:

The horizontal and vertical GMRS are bounded by the certified seismic design response spectra (CSDRS)

Subsection 2.5.2.6 Figure 2.5.2-253 Figure 2.5.2-254 Figure 3.7-202 Yes The hard rock high frequency (HRHF) envelope response spectra are shown in DCD Tier 1 Figure 5.0-3 and Figure 5.0-4 defined at the foundation level for 5% damping. The HRHF envelope response spectra provide an alternative set of spectra for evaluation of site specific GMRS. A site is acceptable if its site specific GMRS fall within the AP1000 HRHF envelope response spectra. Evaluation of a site for application of the HRHF envelope response spectra includes consideration of the limitation on shear wave velocity identified for use of the HRHF envelope response spectra. This limitation is defined by a shear wave velocity at the bottom of the basemat equal to or higher than 7,500 fps, while maintaining a shear wave velocity equal to or above 8,000 fps at the lower depths.

Table 2.0-201 (Sheet 2 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-5 Revision 0 Turkey Point Units 6 & 7 - IFSAR Fault Displacement Potential No potential fault displacement considered beneath the seismic Category I and seismic Category II structures and immediate surrounding area. The immediate surrounding area includes the effective soil supporting media associated with the seismic Category I and seismic Category II structures.

No fault displacement potential within the investigative area.

Subsection 2.5.3.8 Yes Soil Average Allowable Static Bearing Capacity The allowable bearing capacity, including a factor of safety appropriate for the design load combination, shall be greater than or equal to the average bearing demand of 8,900 lb/ft2 over the footprint of the nuclear island at its excavation depth.

Static bearing capacity: 39,000 lb/ft2.

Subsection 2.5.4.10 Yes Dynamic Bearing Capacity for Normal Plus Safe Shutdown Earthquake (SSE)

The allowable bearing capacity, including a factor of safety appropriate for the design load combination, shall be greater than or equal to the maximum bearing demand of 35,000 lb/ft2 at the edge of the nuclear island at its excavation depth, or site-specific analyses demonstrate factor of safety appropriate for normal plus safe shutdown earthquake loads.

Dynamic bearing capacity: 41,000 lb/ft2.

Subsection 2.5.4.10 Yes Shear Wave Velocity Greater than or equal to 1,000 ft/sec based on minimum low-strain soil properties over the footprint of the nuclear island at its excavation depth.

Materials below nuclear island subgrades have VS greater than 1000 ft/sec.

Subsection 2.5.4.2 Table 2.5.4-215 Yes Lateral Variability Soils supporting the nuclear island should not have extreme variations in subgrade stiffness. This may be demonstrated by one of the following:

The natural soil conditions along with the placement of lean concrete fill over the Key Largo Limestone provide uniform soil conditions under all Category 1 structures as defined by RG 1.132.

Subsection 2.5.4.10 Yes Table 2.0-201 (Sheet 3 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-6 Revision 0 Turkey Point Units 6 & 7 - IFSAR Soil (cont.)

Lateral Variability (cont.)

1. Soils supporting the nuclear island are uniform in accordance with Regulatory Guide 1.132 if the geologic and stratigraphic features at depths less than 120 feet below grade can be correlated from one boring or sounding location to the next with relatively smooth variations in thicknesses or properties of the geologic units, or
2. Site-specific assessment of subsurface conditions demonstrates that the bearing pressures below the footprint of the nuclear island do not exceed 120% of those from the generic analyses of the nuclear island at a uniform site, or
3. Site-specific analysis of the nuclear island basemat demonstrates that the site specific demand is within the capacity of the basemat.

As an example of sites that are considered uniform, the variation of shear wave velocity in the material below the foundation to a depth of 120 feet below finished grade within the nuclear island footprint and 40 feet beyond the boundaries of the nuclear island footprint meets the criteria in the case outlined below:

Case 1: For a layer with a low strain shear wave velocity greater than or equal to 2500 feet per second, the layer should have approximately uniform thickness, should have a dip not greater than 20 degrees, and should have less than 20 percent variation in the shear wave velocity from the average velocity in any layer.

Table 2.0-201 (Sheet 4 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-7 Revision 0 Turkey Point Units 6 & 7 - IFSAR Soil (cont.)

Limits of Acceptable Settlement Without Additional Evaluation(k)

Differential Across Nuclear Island Foundation Mat 1/2 inch in 50 ft 0.2 inch in 50 ft (projected)

Subsection 2.5.4.10 Yes (projected)

Total for Nuclear Island Foundation Mat 6 inches 2.5 inches (projected)

Differential Between Nuclear Island and Turbine Building(l) 3 inches 0.6-0.8 inches (projected)

Differential Between Nuclear Island and Other Buildings(l) 3 inches 1.6-2.0 inches (projected)

Liquefaction Potential No liquefaction considered beneath the seismic Category I and seismic Category II structures and immediate surrounding area. The immediate surrounding area includes the effective soil supporting media associated with the seismic Category I and seismic Category II structures.

None at the site-specific SSE.

Subsection 2.5.4.10 Yes Minimum Soil Angle of Internal Friction Minimum soil angle of internal friction is greater than or equal to 35 degrees below the footprint of nuclear island at its excavation depth. If the minimum soil angle of internal friction is below 35 degrees, a site specific analysis shall be performed using the site specific soil properties to demonstrate stability.

Nuclear island excavations are backfilled with lean concrete up to the foundation level of the structures.

Subsection 2.5.4.10 Table 2.5.4-215 Not Applicable Missiles(n)

Tornado 4000-lb automobile at 105 mph horizontal, 74 mph vertical 4000-lb automobile at 105 mph horizontal, 74 mph vertical APP-GW-GLR-020, Wind and Tornado Site Interface

Criteria, Westinghouse Electric Company, LLC.(i)

Subsection 3.5.1.5 Yes 275-lb, 8-in. shell at 105 mph horizontal, 74 mph vertical 275-lb, 8-in. shell at 105 mph horizontal, 74 mph vertical Yes 1-in.-diameter steel ball at 105 mph in the most damaging direction 1-in.-diameter steel ball at 105 mph in the most damaging direction Yes Table 2.0-201 (Sheet 5 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-8 Revision 0 Turkey Point Units 6 & 7 - IFSAR Flood Level Less than plant elevation 100 DCD plant elevation of 100 ft. = 26 ft. North American Vertical Datum 1988 (NAVD 88)

(design grade floor elevation)

The maximum total (surge and wave action) water elevation from a probable maximum hurricane is 24.8 ft. NAVD 88.

Subsection 2.4.1.1 Subsection 2.4.5.3.3 Yes Groundwater Level Less than plant elevation 98 DCD groundwater elevation of 98 ft. =

24 ft. NAVD 88.

Post-construction groundwater conditions indicate an average elevation of approximately -0.4 feet NAVD 88 in the power block area.

Subsection 2.4.12.5 Yes Plant Grade Elevation Less than plant elevation 100 except for portion at a higher elevation adjacent to the annex building The design grade floor elevation is 26 feet NAVD 88, which corresponds to AP1000 elevation of 100 feet.

The actual plant grade is lower and varies to accommodate site grading, drainage, and local site flooding.

The finished grade elevation is 25.5 feet NAVD 88.

Subsection 2.4.1.1 Yes Precipitation Rain 20.7 in./hr [1-hr 1-mi2 PMP]

19.4 in./hr Subsection 2.4.2.3.1 Table 2.4.2-207 Yes Snow/Ice 75 pounds per square foot on ground with exposure factor of 1.0 and important factor of 1.2 (safety) and 1.0 (non-safety)

Based on historical data, the recurrent ground snow load for all monitoring stations is 0.026 lb/ft2; therefore, estimations of the weight of snowpack are not necessary for the Turkey Point plant site.

Subsection 2.3.1.3.4 Yes Atmospheric Dispersion Values X/Q(j)

Site Boundary (0-2 hours) 5.1x10-4 sec/m3 4.19E-04 sec/m3 (EAB)

Subsection 2.3.4.2 Yes Site Boundary (annual average) 2.0x10-5 sec/m3 1.7E-05 sec/m3 (EAB)

Subsection 2.3.5.2 Yes Table 2.0-201 (Sheet 6 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-9 Revision 0 Turkey Point Units 6 & 7 - IFSAR Low Population Zone Boundary 0-8 hours 2.2x10-4 sec/m3 1.87E-05 sec/m3 Subsection 2.3.4.2 Yes 8-24 hours 1.6x10-4 sec/m3 1.25E-05 sec/m3 Subsection 2.3.4.2 Yes 24-96 hours 1.0x10-4 sec/m3 5.25E-06 sec/m3 Subsection 2.3.4.2 Yes96-720 hours 8.0x10-5 sec/m3 1.51E-06 sec/m3 Subsection 2.3.4.2 Yes Population Distribution Exclusion area (site)(j) 0.5 mi The minimum distance from the source boundary to the exclusion area boundary is 1427 ft. (0.27 mi)

Subsection 2.1.1.3 No(d)

(a)

AP1000 DCD Site Parameters are a compilation of DCD Tier 1 Table 5.0-1 and DCD Tier 2 Table 2-1.

(b)

Maximum and minimum safety values are based on historical data and exclude peaks of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.

(c)

The containment pressure response analysis is based on a conservative set of dry-bulb and wet-bulb temperatures. These results envelop any conditions where the dry-bulb temperature is 115°F or less and wet-bulb temperature of less than or equal to 86.1°F.

(d)

These Site Characteristics and comparison evaluation are discussed in the corresponding referenced subsection.

(e)

The maximum normal value is the 1 percent seasonal exceedance temperature. The minimum normal value is the 99 percent seasonal exceedance temperature. The minimum temperature is for the months of December, January, and February in the northern hemisphere. The maximum temperature is for the months of June through September in the northern hemisphere. The 1 percent seasonal exceedance is approximately equivalent to the annual 0.4 percent exceedance. The 99 percent seasonal exceedance is approximately equivalent to the annual 99.6 percent exceedance.

(f)

The noncoincident wet-bulb temperature is applicable to the cooling tower only.

(g)

With ground response spectra as given in Figures 3.7.1-1 and 3.7.1-2. Seismic input is defined at finished grade except for sites where the nuclear island is founded on hard rock.

(h)

Sites that fall within the hard rock high frequency GMRS given in Figures 3I.1-1 and 3I.1-2 are acceptable.

(i)

Per APP-GW-GLR-020, the kinetic energies of the missiles discussed in Section 3.5 are greater than the kinetic energies of the missiles discussed in Regulatory Guide 1.76 and result in a more conservative design.

(j)

For AP1000, the term site boundary and exclusion area boundary are used interchangeably. Thus, the X/Q specified for the site boundary applies whenever a discussion refers to the exclusion area boundary. At Turkey Point the site boundary and exclusion area boundary are not interchangeable. See Figures 2.1-202 and 2.1-204.

(k)

Additional evaluation may include evaluation of the impact of the elevated estimated settlement values on the critical components of the AP1000, determining a construction sequence to control the predicted settlement behavior, or developing an active settlement monitoring system throughout the entire construction sequence as well as a long-term (plant operation) plan.

(l)

Differential settlement is measured at center of Nuclear Island and center of adjacent structures.

(m) A 204 mph maximum hurricane wind was calculated for Hurricane Andrew based on a post-event reanalysis (Subsection 2.3.1.3.1).

(n)

The effects of hurricane missiles are discussed in Subsection 3.5.2.

Table 2.0-201 (Sheet 7 of 7)

Comparison of AP1000 DCD Site Parameters and Turkey Point Units 6 & 7 Site Characteristics AP 1000 DCD Site Parameters(a)

Units 6 & 7 Site Characteristics Units 6 & 7 Site Characteristic Reference Bounding Yes/No

2.0-10 Revision 0 Turkey Point Units 6 & 7 - IFSAR Table 2.0-202 Comparison of Predicted Units 6 & 7 Control Room X/Q Values with AP1000 DCD Acceptance Criteria X/Q (sec/m3) at HVAC Intake for the Identified Release Points(a)

(a)

These dispersion factors are to be used 1) for the time period preceding the isolation of the main control room and actuation of the emergency habitability system, 2) for the time after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the compressed air supply in the emergency habitability system would be exhausted and outside air would be drawn into the main control room, and 3) for the determination of control room doses when the non-safety ventilation system is assumed to remain operable such that the emergency habitability system is not actuated.

Release Time Plant Vent or PCS Air Diffuser(b)

(b)

These dispersion factors are used for analysis of the doses due to a postulated small line break outside of containment. The plant vent and PCS air diffuser are potential release paths for other postulated events (Ioss-of-coolant accident, rod ejection accident, and fuel handling accident inside the containment); however, the values are bounded by the dispersion factors for ground level releases.

Plant Vent PCS Air Diffuser Ground Level Contain-ment Release Points(c)

(c)

The listed values represent modeling the containment shell as a diffuse area source, and are used for evaluating the doses in the main control room for a loss-of-coolant accident, for the containment leakage of activity following a rod ejection accident, and for a fuel handling accident occurring inside the containment.

Ground Level Contain-ment Release Points PORV and Safety Valve Releases(d)

(d)

The listed values bound the dispersion factors for releases from the steam line safety and power-operated relief valves. These dispersion factors would be used for evaluating the doses in the main control room for a steam generator tube rupture, a main steam line break, a locked reactor coolant pump rotor, and for the secondary side release from a rod ejection accident.

PORV and Safety Valve Releases Condenser Air Removal Stack(e)

(e)

This release point is included for information only as a potential activity release point. None of the design basis accident radiological consequences analyses model release from this point.

Condenser Air Removal Stack Steam Line Break Releases Steam Vent Fuel Handling Area(f)

(f)

The listed values bound the dispersion factors for releases from the fuel storage and handling area. The listed values also bound the dispersion factors for releases from the fuel storage area in the event that spent fuel boiling occurs and the fuel building relief panel opens on high temperature. These dispersion factors are used for the fuel handling accident occurring outside containment and for evaluating the impact of releases associated with spent fuel pool boiling.

Fuel Handling Area Blowout Panel Fuel Handling Area Truck Bay Door DCD Units 6 & 7 Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 Units 6 & 7 0-2 hours 3.0E-03 1.7E-03 1.3E-03 6.0E-03 1.6E-03 2.0E-02 1.2E-02 6.0E-03 1.6E-03 2.4E-02 1.3E-02 6.0E-03 1.4E-03 1.2E-03 2-8 hours 2.5E-03 1.1E-05 7.5E-03 3.6E-03 9.6E-04 1.8E-02 7.3E-03 4.0E-03 1.2E-03 2.0E-02 7.4E-03 4.0E-03 9.7E-04 8.9E-04 8-24 hours 1.0E-03 5.1E-04 3.4E-04 1.4E-03 4.8E-04 7.0E-03 3.1E-03 2.0E-03 5.2E-04 7.5E-03 3.3E-03 2.0E-03 4.3E-04 3.9E-04 1-4 days 8.0E-04 3.2E-04 2.1E-04 1.8E-03 3.3E-04 5.0E-03 2.3E-03 1.5E-03 4.0E-04 5.5E-03 2.5E-03 1.5E-03 3.1E-04 2.9E-04 4-30 days 6.0E-04 2.0E-04 1.2E-04 1.5E-03 2.0E-04 4.5E-03 1.4E-03 1.0E-03 3.0E-04 5.0E-03 1.4E-03 1.0E-03 2.0E-04 1.9E-04 X/Q (sec/m3) at Annex Building Door for the Identified Release Points(g)

(g)

These dispersion factors are to be used when the emergency habitability system is in operation and the only path for outside air to enter the main control room is that due to ingress/egress.

Release Time Plant Vent or PCS Air Diffuser(b)

Plant Vent PCS Air Diffuser Ground Level Contain-ment Release Points(c)

Ground Level Contain-ment Release Points PORV and Safety Valve Releases(d)

PORV and Safety Valve Releases Condenser Air Removal Stack(e)

Condenser Air Removal Stack Steam Line Break Releases Steam Vent Fuel Handling Area(f)

Fuel Handling Area Blowout Panel Fuel Handling Area Truck Bay Door DCD Units 6 & 7 Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 DCD Units 6 & 7 Units 6 & 7 0-2 hours 1.0E-03 3.7E-04 3.6E-04 1.0E-03 3.4E-04 4.0E-03 8.3E-04 2.0E-02 3.0E-03 4.0E-03 8.1E-04 6.0E-03 3.5E-04 3.5E-04 2-8 hours 7.5E-04 2.3E-04 2.1E-04 7.5E-04 2.0E-04 3.2E-03 4.7E-04 1.8E-02 1.7E-03 3.2E-03 4.6E-04 4.0E-03 2.2E-04 2.3E-04 8-24 hours 3.5E-04 1.1E-04 9.9E-05 3.5E-04 9.7E-05 1.2E-03 2.2E-04 7.0E-03 8.1E-04 1.2E-03 2.1E-04 2.0E-03 1.0E-04 1.0E-04 1-4 days 2.8E-04 6.9E-05 6.0E-05 2.8E-04 6.1E-05 1.0E-03 1.3E-04 5.0E-03 5.3E-04 1.0E-03 1.2E-04 1.5E-03 6.8E-05 7.1E-05 4-30 days 2.5E-04 4.4E-05 3.9E-05 2.5E-04 3.8E-05 8.0E-04 8.2E-05 4.5E-03 2.7E-04 8.0E-04 7.9E-05 1.0E-03 4.1E-05 4.4E-05