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| number = ML18024A349
| number = ML18024A349
| issue date = 10/05/2017
| issue date = 10/05/2017
| title = Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.9 Table - Dose Sensitivity Evaluation
| title = Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.9 Table - Dose Sensitivity Evaluation
| author name =  
| author name =  
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
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| page count = 5
| page count = 5
}}
}}
=Text=
{{#Wiki_filter:BFN-18 TABLE 14.9-1 DESIGN BASIS ACCIDENT RADIOLOGICAL DOSES (REM)
WHOLE BODY                    THYROID 2 hour          30 day        2 hour        30 day Accident          (1400 m)        (3218 m)      (1400 m)      (3218 m)
Loss of Coolant    2.2 x 10-1      6.1 x 10-1    2.9 x 100        3.6 x 101 Refueling          4.9 x 10-2      1.9 x 10-2    3.1 x 101        4.2 x 10-1 Control Rod Drop  1.2 x 10-2      4.3 x 10-2    6.1 x 100        7.0 x 100 Steam Line Break  1.7 x 10-2      8.0 x 10-3    3.0 x 101        1.0 x 101
BFN-18 Table 14.9-2 (Sheet 1)
SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS LOSS-OF-COOLANT ACCIDENT Factor Affecting Design "Base"                                Assumed AEC Assumptions                                Case                                          Case                                Thyroid Dose                Whole Body Dose Fission products                      1.8 percent noble gases1                      100 percent noble gases                      625                      220 released to drywell                  0.32 percent iodines                          50 percent iodines and from 25 percent of the                        1 percent solids in fuel rods which are                          total core inventory.
assumed to be perforated.                    5 percent of total 1 percent of total iodine                    iodines in organic form.
in organic form. Negligible solids.
Iodine retained                      Based on partition factor                    None                                          12.53                    1 in water                              of 100 between the volumes of air and water in pressure suppression chamber and drywell.
Elemental iodine                      50 percent                                    50 percent                                    1                        1 plateout in drywell Leakage rate from                    Function of drywell                          0.635 percent volume per                      1.3 (2-hr)2              1.3 (2-hr) primary containment                  pressure; peaks close                        day, constant                                ~1 (30-day)              ~(30-day) to 0.5 percent volume                        throughout accident per day Uniform mixing                        Yes                                          No                                            22 (2-hr)                28 (2-hr) in Reactor Building                                                                                                              1.2 (30-day)              1.1 (30-day)
Iodine filter                        99 percent                                    90 percent                                    10                        1 efficiency                            (95 percent for solids)
Effectiveness of stack                Yes                                          Yes                                          1                        1 NOTE:
1 1 percent of iodines released in organic form, which is not reduced by fallout or drywell and reactor building. Elemental iodines are carried into pressure suppression pool during blowdown, and a fraction retained according to the assumed equilibrium partition factor of 100.
Iodines become airborne in the pressure suppression chamber and drywell before leaking out to the secondary containment.
2 2-hr dose is evaluated at site boundary of 1400 meters; 30-day dose is evaluated at low-population zone of 3218 meters.
3 Takes into account the organic iodine fraction.
BFN-18 Table 14.9-2 (Sheet 2)
SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS REFUELING ACCIDENT Factor Affecting Design "Base"                              Assumed AEC Assumptions                                Case                                        Case                                  Thyroid Dose            Whole Body Dose Fission product                      1.8 percent noble gases,                    20 percent noble gases,                        13.8                        4.9 release to reactor                    0.32 percent iodines from                  10 percent iodines from 1
water                                111 perforated fuel                        49 perforated fuel 2
rods, solids negligible                    rods 4                                2 Iodines retained                      Equilibrium partition                      90 percent                                      0.4                        1 in water                              factor of 100 for iodines and water Plateout of iodines                  None                                        50 percent                                      0.5                        1 in Reactor Building 3
Uniform mixing in                    Yes                                        No                                              14 (2-hr)                  18 (2-hr) refueling chamber                                                                                                                ~1.3 (30-day)              ~1.1 (30-day)
Fission Products                            Fission products exponentially released                      exponentially released from water to Reactor                      from water in 2 hours Building till exhausted Iodine filter                        99 percent                                  90 percent                                      10                          1 efficiency                                                                        (95 percent for solids)
Effectiveness of                      Yes                                        Yes                                            1                          1 stack NOTE:
1 Accident occurs 24 hours after shutdown.
2 Assumptions in Hatch (Docket No. 50.321) evaluation.
3 2-hr dose is evaluated at site boundary of about 1400 meters. 30-day dose is evaluated at low-population zone of 3128 meters.
4 Amount of retention depends on the ratio of air space to water space. In this case, the equivalent value of 75 percent is obtained.
BFN-18 Table 14.9-2 (Sheet 3)
SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS CONTROL ROD DROP ACCIDENT Factor Affecting Design "Base"                            Assumed AEC Assumptions                            Case                                      Case                          Thyroid Dose              Whole Body Dose Fission products                  1.8 percent noble gases,                  100 percent noble gases,            156                        55 released to water                  0.32 percent iodines from                50 percent iodines from 330 perforated fuel                      330 perforated rods, solids negligible                  fuel rods Noble gases carry-                Uniformly mixed with                      100 percent                          1                          10 over to condenser                  steam, carried over hotwell                            at 5.0 percent steam flow rate, isolation valve closure at 10.5 sec.
1 Iodine carryover to                Retention in water,                      10 percent                          2700                      1.0 condenser hotwell                  uniform mixing in steam dome, carryover at 5.0 percent steam flow, and isolation at 10.5 seconds Iodine plateout in                None                                      50 percent                          0.5                        1 condenser hotwell
                                                                                                                          -4                          -4 Release mechanism                  1800 cfm from vapor                      Leak rate of 0.5 percent per        5.5 X 10 (2-hrs)            5.5 X 10 (2-hrs)
                                                                                                                            -2                        -2 space of condenser and                    day from condenser                  1.13 X 10 (30-days)        1.13 X 10 (30-days) turbine, stack release                    to environs NOTE:
1 Amount of retention in condenser hotwell water depends on relative ratio of steam space to water space. The "base" case uses an equilibrium partition factor of 100 and a
steam-water space ratio of about 12.
BFN-18 Table 14.9-2 (Sheet 4)
SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS STEAM LINE BREAK ACCIDENT Factor Affecting Design "Base"                            Assumed AEC Assumptions                            Case                                    Case                            Thyroid Dose            Whole Body Dose Steam and Water                    185,000 lb                              185,000 lb                                1                            1 Mass Lost in                        (25,000 lb steam blowdown (10.5                      160,000 lb water) sec. closure) 2 Total fission                      146 curies iodines                      Proportional to                          10.5                        10.5 gases released                      and 5.7 curies                          operating limit, 1
noble gases                              10.5 times the base case value Concentration in                    Equilibrium separation                  Equilibrium separation                    1                            1 water and steam Steam cloud rise                    No                                      No                                        1                            1 NOTE:
1 Based on fission product concentrations in coolant such that the offgas release rate at stack reaches the maximum expected value of 10,000 FCi/sec.
2 In the steamline break accident, the noble gases contribution to the whole body dose is insignificant.}}

Latest revision as of 03:11, 22 October 2019

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.9 Table - Dose Sensitivity Evaluation
ML18024A349
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Text

BFN-18 TABLE 14.9-1 DESIGN BASIS ACCIDENT RADIOLOGICAL DOSES (REM)

WHOLE BODY THYROID 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 30 day 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 30 day Accident (1400 m) (3218 m) (1400 m) (3218 m)

Loss of Coolant 2.2 x 10-1 6.1 x 10-1 2.9 x 100 3.6 x 101 Refueling 4.9 x 10-2 1.9 x 10-2 3.1 x 101 4.2 x 10-1 Control Rod Drop 1.2 x 10-2 4.3 x 10-2 6.1 x 100 7.0 x 100 Steam Line Break 1.7 x 10-2 8.0 x 10-3 3.0 x 101 1.0 x 101

BFN-18 Table 14.9-2 (Sheet 1)

SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS LOSS-OF-COOLANT ACCIDENT Factor Affecting Design "Base" Assumed AEC Assumptions Case Case Thyroid Dose Whole Body Dose Fission products 1.8 percent noble gases1 100 percent noble gases 625 220 released to drywell 0.32 percent iodines 50 percent iodines and from 25 percent of the 1 percent solids in fuel rods which are total core inventory.

assumed to be perforated. 5 percent of total 1 percent of total iodine iodines in organic form.

in organic form. Negligible solids.

Iodine retained Based on partition factor None 12.53 1 in water of 100 between the volumes of air and water in pressure suppression chamber and drywell.

Elemental iodine 50 percent 50 percent 1 1 plateout in drywell Leakage rate from Function of drywell 0.635 percent volume per 1.3 (2-hr)2 1.3 (2-hr) primary containment pressure; peaks close day, constant ~1 (30-day) ~(30-day) to 0.5 percent volume throughout accident per day Uniform mixing Yes No 22 (2-hr) 28 (2-hr) in Reactor Building 1.2 (30-day) 1.1 (30-day)

Iodine filter 99 percent 90 percent 10 1 efficiency (95 percent for solids)

Effectiveness of stack Yes Yes 1 1 NOTE:

1 1 percent of iodines released in organic form, which is not reduced by fallout or drywell and reactor building. Elemental iodines are carried into pressure suppression pool during blowdown, and a fraction retained according to the assumed equilibrium partition factor of 100.

Iodines become airborne in the pressure suppression chamber and drywell before leaking out to the secondary containment.

2 2-hr dose is evaluated at site boundary of 1400 meters; 30-day dose is evaluated at low-population zone of 3218 meters.

3 Takes into account the organic iodine fraction.

BFN-18 Table 14.9-2 (Sheet 2)

SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS REFUELING ACCIDENT Factor Affecting Design "Base" Assumed AEC Assumptions Case Case Thyroid Dose Whole Body Dose Fission product 1.8 percent noble gases, 20 percent noble gases, 13.8 4.9 release to reactor 0.32 percent iodines from 10 percent iodines from 1

water 111 perforated fuel 49 perforated fuel 2

rods, solids negligible rods 4 2 Iodines retained Equilibrium partition 90 percent 0.4 1 in water factor of 100 for iodines and water Plateout of iodines None 50 percent 0.5 1 in Reactor Building 3

Uniform mixing in Yes No 14 (2-hr) 18 (2-hr) refueling chamber ~1.3 (30-day) ~1.1 (30-day)

Fission Products Fission products exponentially released exponentially released from water to Reactor from water in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Building till exhausted Iodine filter 99 percent 90 percent 10 1 efficiency (95 percent for solids)

Effectiveness of Yes Yes 1 1 stack NOTE:

1 Accident occurs 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown.

2 Assumptions in Hatch (Docket No. 50.321) evaluation.

3 2-hr dose is evaluated at site boundary of about 1400 meters. 30-day dose is evaluated at low-population zone of 3128 meters.

4 Amount of retention depends on the ratio of air space to water space. In this case, the equivalent value of 75 percent is obtained.

BFN-18 Table 14.9-2 (Sheet 3)

SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS CONTROL ROD DROP ACCIDENT Factor Affecting Design "Base" Assumed AEC Assumptions Case Case Thyroid Dose Whole Body Dose Fission products 1.8 percent noble gases, 100 percent noble gases, 156 55 released to water 0.32 percent iodines from 50 percent iodines from 330 perforated fuel 330 perforated rods, solids negligible fuel rods Noble gases carry- Uniformly mixed with 100 percent 1 10 over to condenser steam, carried over hotwell at 5.0 percent steam flow rate, isolation valve closure at 10.5 sec.

1 Iodine carryover to Retention in water, 10 percent 2700 1.0 condenser hotwell uniform mixing in steam dome, carryover at 5.0 percent steam flow, and isolation at 10.5 seconds Iodine plateout in None 50 percent 0.5 1 condenser hotwell

-4 -4 Release mechanism 1800 cfm from vapor Leak rate of 0.5 percent per 5.5 X 10 (2-hrs) 5.5 X 10 (2-hrs)

-2 -2 space of condenser and day from condenser 1.13 X 10 (30-days) 1.13 X 10 (30-days) turbine, stack release to environs NOTE:

1 Amount of retention in condenser hotwell water depends on relative ratio of steam space to water space. The "base" case uses an equilibrium partition factor of 100 and a

steam-water space ratio of about 12.

BFN-18 Table 14.9-2 (Sheet 4)

SENSITIVITY OF DOSES TO VARIATION OF ASSUMPTIONS STEAM LINE BREAK ACCIDENT Factor Affecting Design "Base" Assumed AEC Assumptions Case Case Thyroid Dose Whole Body Dose Steam and Water 185,000 lb 185,000 lb 1 1 Mass Lost in (25,000 lb steam blowdown (10.5 160,000 lb water) sec. closure) 2 Total fission 146 curies iodines Proportional to 10.5 10.5 gases released and 5.7 curies operating limit, 1

noble gases 10.5 times the base case value Concentration in Equilibrium separation Equilibrium separation 1 1 water and steam Steam cloud rise No No 1 1 NOTE:

1 Based on fission product concentrations in coolant such that the offgas release rate at stack reaches the maximum expected value of 10,000 FCi/sec.

2 In the steamline break accident, the noble gases contribution to the whole body dose is insignificant.