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Category:Final Safety Analysis Report (FSAR)
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2010-12-22
[Table view]
Category:License-Application for Combined License (COLA)
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[Table view] |
Text
CHAPTER 15 ACCIDENT ANALYSES TABLE OF CONTENTS Section Title Page 15.0 ACCIDENT ANALYSES .................................................................... 15.0-1 15.0.3.2 Initial Conditions .................................................................... 15.0-1 15.1 INCREASE IN HEAT REMOVAL FROM THE PRIMARY SYSTEM............................................................................................ 15.1-1 15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM............................................................................................ 15.2-1 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE ....... 15.3-1 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES.............. 15.4-1 15.5 INCREASE IN REACTOR COOLANT INVENTORY......................... 15.5-1 15.6 DECREASE IN REACTOR COOLANT INVENTORY ....................... 15.6-1 15.6.5.3.1.2 Core Release ............................................................. 15.6-1 15.6.5.3.7.3 Atmospheric Dispersion Factors ................................ 15.6-1 15.7 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT ................................................................................... 15.7-1 15.7.6 COMBINED LICENSE INFORMATION....................................... 15.7-1 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM ........................... 15.8-1 APP. 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS ...........................................................................15A-1 15A.3.1.3 Core Source Team .................................................................15A-1 15A.3.3 Atmospheric Dispersion Factors.............................................15A-1 APP. 15B REMOVAL OF AIRBORNE ACTIVITY FROM THE CONTAINMENT ATMOSPHERE FOLLOWING A LOCA ......15B-1 15-i Revision 3
LIST OF TABLES Number Title 15.0-201 BLN Summary of Initial Conditions and Computer Codes Used 15.6-201 BLN Assumptions and Parameters Used in Calculating Radiological Consequences of a Loss-of-Coolant Accident 15.6-202 BLN Radiological Consequences of a Loss-of-Coolant Accident with Core Melt 15A-201 BLN Reactor Core Source Term 15A-202 BLN Offsite Atmospheric Dispersion Factors (/Q) for Accident Dose Analysis 15-ii Revision 3
CHAPTER 15 ACCIDENT ANALYSES 15.0 ACCIDENT ANALYSES This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
15.0.3.2 Initial Conditions DEP 2.3-1 Replace the third paragraph of DCD Subsection 15.0.3.2 with the following:
Core Power +/-2 percent allowance for calorimetric error. The main feed water flow measurement supports a 1-percent power uncertainty; use of a 2-percent power uncertainty is conservative. Accidents use 2% core power uncertainty unless identified in Table 15.0-2.
15.0-1 Revision 3
Part 2, FSAR TABLE 15.0-201 2.3-1 BLN
SUMMARY
OF INITIAL CONDITIONS AND COMPUTER CODES USED Section Faults Computer Reactivity Coefficients Assumed Initial Thermal Codes Used Moderator Moderator Doppler Power Output Density Temperature Assumed (pcm/°F) (MWt)
(k/gm/cm3)
LOCAs NOTRUMP See subsection - See subsection 3468.0 resulting from WCOBRA/ 15.6.5 references 15.6.5 (SBLOCA) the spectrum of TRAC references 3434.0 postulated HOTSPOT (LBLOCA) piping breaks 3434.0 (BLN within the Dose) reactor coolant pressure boundary Note: This table supplements DCD Table 15.0-2.
15.0-2 Revision 3
15.1 INCREASE IN HEAT REMOVAL FROM THE PRIMARY SYSTEM This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.1-1 Revision 3
15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.2-1 Revision 3
15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.3-1 Revision 3
15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.4-1 Revision 3
15.5 INCREASE IN REACTOR COOLANT INVENTORY This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.5-1 Revision 3
15.6 DECREASE IN REACTOR COOLANT INVENTORY This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
15.6.5.3.1.2 Core Release DEP 2.3-1 Replace the first two sentences of the second paragraph of DCD Subsection 15.6.5.3.1.2 with the following sentence:
The core fission product inventory at the time of the most accidents is based on operation near the end of a fuel cycle is provided in Table 15A-3 of DCD Appendix 15A and in Table 15A-201 of FSAR Appendix 15A.
15.6.5.3.7.3 Atmospheric Dispersion Factors Add the following paragraph at the end of DCD Subsection 15.6.5.3.7.3.
COL 2.3-4 Site-specific /Q values provided in Subsection 2.3.4 are not bounded by the values given in DCD Tables 15A-5 and 15A-6. Therefore, a site-specific dose consequence analysis was performed as discussed in Subsection 15.6.5.
15.6-1 Revision 3
TABLE 15.6-201 DEP 2.3-1 BLN ASSUMPTIONS AND PARAMETERS USED IN CALCULATING RADIOLOGICAL CONSEQUENCES OF A LOSS-OF-COOLANT ACCIDENT BLN Containment leakage release data
- Containment leak rate, 0-24 hr (% per day) 0.09 (for EAB) 0.10 (for LPZ and Control Room)
Note: This table supplements DCD Table 15.6.5-2.
15.6-2 Revision 3
TABLE 15.6-202 DEP 2.3-1 BLN RADIOLOGICAL CONSEQUENCES OF A LOSS-OF-COOLANT ACCIDENT WITH CORE MELT TEDE Dose (rem)
(1)
BLN Exclusion zone boundary dose (1.4 - 3.4 hr) 23.8 Notes:
- 1. This table supplements DCD Table 15.6.5-3.
15.6-3 Revision 3
15.7 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
15.7.6 COMBINED LICENSE INFORMATION COL 15.7-1 This COL item is addressed in Subsection 2.4.13.
15.7-1 Revision 3
15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM This section of the referenced DCD is incorporated by reference with no departures or supplements.
15.8-1 Revision 3
APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.
15A.3.1.3 Core Source Team DEP 2.3-1 Replace the first sentence of DCD Subsection 15A.3.1.3 with the following sentence:
Table 15A-3 and FSAR Table 15A-201 list the core source terms at shutdown.
15A.3.3 Atmospheric Dispersion Factors Replace the third paragraph in DCD Subsection 15A.3.3 with the following:
COL 2.3-4 [Site-specific /Q values provided in Subsection 2.3.4 are bounded by the values given in DCD Tables 15A-5 and 15A-6. (This text to be revised in a future amendment.)]
15A-1 Revision 3
TABLE 15A-201 (Sheet 1 of 2)
DEP 2.3-1 BLN REACTOR CORE SOURCE TERM(1)
Nuclide Inventory (Ci)
Iodines I-130 1.84E+06 I-131 9.29E+07 I-132 1.36E+08 1-133 1.92E+08 I-134 2.15E+08 I-135 1.82E+08 Cs Group Cs-134 1.62E+07 Cs-136 3.79E+06 Cs-137 1.07E+07 Cs-138 1.78E+08 Rb-86 1.77E+05 Te Group Te-127m 1.35E+06 Te-127 8.28E+06 Te-129m 4.65E+06 Te-129 2.45E+07 Te-131m 1.85E+07 Te-132 1.33E+08 Sb-127 8.54E+06 Sb-129 2.62E+07 Ru Group Ru-103 1.41E+08 Ru-105 9.73E+07 Ru-106 4.45E+07 Rh-105 9.03E+07 Mo-99 1.74E+08 Tc-99m 1.53E+08 Noble Gases Kr-85m 2.47E+07 Kr-85 1.05E+06 Kr-87 4.86E+07 Kr-88 6.53E+07 Xe-131m 1.01E+06 Xe-133m 5.95E+06 Xe-133 1.88E+08 Xe-135m 4.00E+07 Xe-135 3.80E+07 Xe-138 1.63E+08 Sr & Ba Sr-89 9.30E+07 Sr-90 8.18E+06 15A-2 Revision 3
TABLE 15A-201 (Sheet 2 of 2)
DEP 2.3-1 BLN REACTOR CORE SOURCE TERM(1)
Nuclide Inventory (Ci)
Sr-91 1.14E+08 Sr-92 1.22E+08 Ba-139 1.70E+08 Ba-140 1.64E+08 Ce Group Ce-141 1.56E+08 Ce-143 1.45E+08 Ce-144 1.20E+08 Pu-238 2.18E+05 Pu-239 2.48E+04 Pu-240 3.88E+04 Pu-241 9.90E+06 Np-239 1.95E+09 La Group Y-90 8.55E+06 Y-91 1.21E+08 Y-92 1.24E+08 Y-93 1.40E+08 Nb-95 1.62E+08 Zr-95 1.60E+08 Zr-97 1.59E+08 La-140 1.74E+08 La-141 1.54E+08 La-142 1.49E+08 Pr-143 1.41E+08 Nd-147 6.00E+07 Am-241 1.02E+04 Cm-242 2.76E+06 Cm-244 2.38E+05 Notes:
- 1. The following assumptions apply:
- Core thermal power of 3434 MWt (1 percent above the design core power of 3400 MWt).
- Three-region equilibrium cycle core at end of life.
- These source terms applied only for the EAB doses.
15A-3 Revision 3
TABLE 15A-202 DEP 2.3-1 BLN OFFSITE ATMOSPHERIC DISPERSION FACTORS (/Q)
FOR ACCIDENT DOSE ANALYSIS(1)
BLN Site Boundary /Q (s/m3) 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />(2) 5.85 x 10-4 Notes:
- 1. The LOCA dose analysis models the bounding atmospheric dispersion factors listed above. Other analyses model more conservative values.
- 2. Nominally defined as the 0- to 2-hour interval but is applied to the 2-hour interval having the highest activity releases in order to address 10 CFR Part 50.34 requirements.
- 3. This table supplements DCD Table 15A-5.
15A-4 Revision 3
APPENDIX 15B REMOVAL OF AIRBORNE ACTIVITY FROM THE CONTAINMENT ATMOSPHERE FOLLOWING A LOCA This section of the referenced DCD is incorporated by reference with no departures or supplements.
15B-1 Revision 3
