ML110040892

Bellefonte Units 3 & 4 Cola (Final Safety Analysis Report), Rev. 3 - FSAR Chapter 15 Accident Analyses - Sections 15.00 - 15.08, Appendices 15.A, 15.B

ML110040892
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Site:	Bellefonte
Issue date:	12/22/2010
From:	Arent G Tennessee Valley Authority
To:	Document Control Desk, Office of New Reactors
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BELLEFONTE.P02.NP, BELLEFONTE.P02.NP.3, TENNVALLEY, TENNVALLEY.SUBMISSION.6, +reviewedmmc1
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Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15-i 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

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR LIST OF TABLES Number Title Revision 3 15-ii 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

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.0-1 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 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.

BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.0-2 Note: This table supplements DCD Table 15.0-2.

TABLE 15.0-201 BLN

SUMMARY

OF INITIAL CONDITIONS AND COMPUTER CODES USED Section Faults Computer Codes Used Reactivity Coefficients Assumed Initial Thermal Power Output Assumed (MWt)

Moderator Density (k/gm/cm3)

Moderator Temperature (pcm/°F)

Doppler LOCAs resulting from the spectrum of postulated piping breaks within the reactor coolant pressure boundary NOTRUMP WCOBRA/

TRAC HOTSPOT See subsection 15.6.5 references See subsection 15.6.5 references 3468.0 (SBLOCA) 3434.0 (LBLOCA) 3434.0 (BLN Dose)

BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.1-1 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.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.2-1 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.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.3-1 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE This section of the referenced DCD is incorporated by reference with no departures or supplements.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.4-1 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES This section of the referenced DCD is incorporated by reference with no departures or supplements.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.5-1 15.5 INCREASE IN REACTOR COOLANT INVENTORY This section of the referenced DCD is incorporated by reference with no departures or supplements.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.6-1 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 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.

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.

BLN DEP 2.3-1 BLN COL 2.3-4

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.6-2 Note: This table supplements DCD Table 15.6.5-2.

TABLE 15.6-201 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)

BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.6-3 Notes:

1.

This table supplements DCD Table 15.6.5-3.

TABLE 15.6-202 BLN RADIOLOGICAL CONSEQUENCES OF A LOSS-OF-COOLANT ACCIDENT WITH CORE MELT TEDE Dose (rem)

BLN Exclusion zone boundary dose (1.4 - 3.4 hr)(1) 23.8 BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.7-1 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 This COL item is addressed in Subsection 2.4.13.

BLN COL 15.7-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15.8-1 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM This section of the referenced DCD is incorporated by reference with no departures or supplements.

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15A-1 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 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:

[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.)]

BLN DEP 2.3-1 BLN COL 2.3-4

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15A-2 TABLE 15A-201 (Sheet 1 of 2)

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 BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15A-3 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.

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 TABLE 15A-201 (Sheet 2 of 2)

BLN REACTOR CORE SOURCE TERM(1)

Nuclide Inventory (Ci)

BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15A-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.

TABLE 15A-202 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 BLN DEP 2.3-1

Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 15B-1 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.