ML20207S294
| ML20207S294 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 11/30/1986 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19292G939 | List:
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| References | |
| NUDOCS 8703190246 | |
| Download: ML20207S294 (302) | |
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6.0 ENGINEERED SAFETY FEATURES The following paragraphs describe the engineered safety features (ESF) that
( are related to the containment systems:
lO a) Primary containment functional design b) Containment heat removal systems c) Secondary containment functional design
, d) Containment isolation system e) Combustible gas control in containment f) Containment leakage testing j 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1.1 Metallic Materials j Typical materials specifications and descriptions are contained in Subsection I
6.1.1 of RESAR-SP/90 PDA Module 1, " Primary Side Safeguards Systems." A more complete list of materials will be provided at the final design stage.
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i l
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! e703190246 870309 PDR ADOCK 05000601 K PDR WAPWR-CS 6.1-1 NOVEMBER, 1986
, 5765e:1d
6.2 CONTAINMENT SYSTEMS 6.2.1 Primary Containment Functional Design The containment system design is based upon the requirement that the system ,
O' withstands the combined effects of the postulated design basis loss-of-coolant accident (LOCA) coincident with the postulated safe shutdown earthquake (SSE) to the extent that radioactivity released to the offsite environment is within the limits of 10 CFR, Part 100.
The containment must withstand the temperatures and pressures resulting from a spectrum of postulated LOCA's and secondary system pipe break accidents with-out leakage in excess of the design leak rate. The radiological consequences of the most severe hypothetical LOCA's are presented in Subsection 15.6.4 of RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System."
6.2.1.1 Containment Structure 6.2.1.1.1 Design Bases The containment structure performs a safety-related function. Design of the l containment structure conforms with the requirements of General Design Criteria (GDC). A discussion of conformance with GDC's is presented in Subsection 3.1 of RESAR-SP/90 PDA Module 7, " Structural / Equipment Design".
l Structural design of the reactor building is discussed in Subsection 3.8 of l RESAR-SP/90 PDA Module 7, " Structural / Equipment Design".
The design basis LOCA for containment design is a reactor coolant system double-ended hot leg (DEHL) rupture, assuming operation of maximum emergency core cooling system equipment and failure of one containment spray pump. This accident results in the highest reactor building pressure after a LOCA.
( However, for long-term conditions, a reactor coolant system double-ended pump suction guillotine (DEPSG) rupture, assuming operation of the minimum emergency core cooling system equipment and failure of one diesel generator, O
WAPWR-CS 6.2-1 NOVEMBER, 1986 4322e:1d 1
1
, p is the limiting case. Reactor building design pressure is 46.9 psig. The V calculated pressure resulting from the DEHL accident is 36.4 psig. Therefore, the design margin is 28.8 percent.
The worst case secondary system pipe ruptures are analyzed to ascertain Ov containment integrity, assuming conditions the same as previously specified for LOCA analysis (i.e., loss of offsite power and worst case single failure of active equipment).
_ Sources and amounts of energy that may be available for release to the containment are discussed in Subsection 6.2.1.1.3. Energy is added to the containment in the manner most detrimental to peak pressure response.
Therefore, all energy is added in the shortest time, except that due to spray from the emergency water storage tank (EWST). The slowest rate of spray energy addition is the most conservative.
- Engineered safety features (ESF) significant to containment energy removal are the residual heat removal system, containment fan coolers, and containment i
O spray system. During the recirculation phase, the decay heat removal system removes the heat from the containment sump water. Containment spray is used for rapid pressure reduction and, on its long-term recirculation mode, for containment iodine removal. Energy removal is accomplished by allowing
, containment spray water temperature to increase to the steam-air temperature.
The containment fan coolers remove energy from the containment atmosphere.
Active engineered safety features systems are 100 percent redundant and independent. For any single failure in any engineered safety features system, the redundant system is unaffected.
l 6.2.1.1.2 System Design Structural design of the containment and codes and standards applicable to the containment and containment internal structures are discussed in Subsections 3.8.2 and 3.8.3 of RESAR-SP/90 PDA Module 7, " Structural / Equipment Design".
O WAPWR-CS 6.2-2 NOVEMBER, 1986 4322e:1d t
Subsections 3.5 and 3.6 of RESAR-SP/90 PDA Modulo 7, " Structural / Equipment O Design", respectively, discuss missiles and postulated pipe rupture effects and the occurrences which may result in missile generation or postulated pipe rupture. .
The functional capability and frequency of operation of the containment fan cooling system during normal plant operations are discussed in Subsection 6.2.2.
O 6.2.1.1.3 Design Evaluation The short-term pressure subcompartment analysis is described in Subsection 6.2.1.2.
The results of the long-term pressure transient analysis of the containment for the loss-of-coolant accidents are shown in Figures 6.2-1 through 6.2-6.
Containment temperature curves are presented in Figures 6.2-7 through 6.2-12.
The cases examined in this analysis determine the effects of the full range of large reactor coolant break sizes up to and including a double-ended rupture.
Cases illustrating the sensitivity to break location are also shown. All of these cases show that the containment pressure will remain below design pressure with margin. After the peak pressure is attained, the performance of the safeguards system reduces the containment pressure. At the end of the first day following the accident, the containment pressure has been reduced to a low value. The peak pressures and margins are shown in Table 6.2-1.
The results of the pressure transient analysis of the containment for the O primary side breaks are presented in Table 6.2-1.
Calculation of containment pressure and temperature transients is accomplished by use of the digital computer code, C0C0 (Reference [1]). The C0C0 code has O been used and found acceptable to calculate containment pressure transients for the H. B. Robinson (Docket Number 50-261) and Zion (Docket Number 50-295) plants. Transient phenomena within the reactor coolant system affect O
WAPWR-CS 6.2-3 NOVEMBER, 1986 2I322e:1d
containment conditions by means of convective mass and energy transport through the pipe break.
For analytical rigor and convenience, the containment air-steam-water mixture i is separated into systems. The first system consists of the air-steam phase;9
' the second consists of the water phase. Sufficient relationships to describe
! the transient are provided by the equations of conservation of mass and energy as applied to each system, together with appropriate boundary conditions. As thermodynamic equations of state and conditions may vary during the transient, l
the equations have been derived for all possible cases of superheated or saturated steam and subcooled or saturated water. Switching between states is i
4 handled automatically by the code. The following are the major assumptions l made in the analysis:
l (a) Discharge mass and energy flow rates through the reactor coolant system break are established from the analysis in Subsection 6.2.1.3.
(b) For the steam break analysis and the blowdown portion of the LOCA
- analysis, the discharge flow separates into steam and water phases i at the break point. The saturated water phase is at the total
! containment pressure, while the steam phase is at the partial i
pressure of the steam in the containment. For the post-blowdown portion of the LOCA analysis, steam and water releases are input j separately.
l (c) Homogeneous mixing is assumed. The steam-air mixture and the water phase each have uniform properties. More specifically, thermal O equilibrium between the air and steam is assumed. This does not imply thermal equilibrium between the steam-air mixture and water phase.
O (d) Air is taken as an ideal gas, while compressed water and steam tables are employed for water and steam thermodynamic properties.
O WAPWR-CS 6.2-4 NOVEMBER, 1986 4322e:1d
(e) For large steam line ruptures, the saturation temperature at the partial pressure of the steam is used for heat transfer to the heat sinks and the fan coolers.
(f) For small steam line ruptures, the.model described in Section 2 of Reference (2) was utilized.
Subsection 6.2.1.3 presents the mass and energy releases used for the analysis.
6.2.1.1.4 Initial Conditions i
An analysis of containment response to the rupture of the reactor coolant system must start with knowledge of the initial conditions in the containment. The pressure, temperature, and humidity of the containment atmosphere prior to the postulated accident are specified in the analysis.
Also, values for the temperature of the service water and emergency water storage tank solution are assumed, along with the initial water inventory of O' the refueling water storage tank. All of these values are chosen conservatively, as shown in Table 6.2-2.
In each of the transients, the safeguards systems shown in Table 6.2-3 are assumed to operate at the times indicated in Table 6.2-4. The assumed spray flow rate is based on one of two trains operating.
6.2.1.1.5 Heat Removal The significant heat removal source during the early portion of the transient is structural heat removal. Provision is made in the containment pressure transient analysis for heat transfer through, and heat storage in, both interior and exterior walls. Every wall is divided into a large number of O nodes. For each node, a conservation of energy equation expressed in finite-difference form accounts for transient conduction into and out of the O
WAPWR-CS 6.2-5 NOVEMBER, 1986 T322e:1d
node and temperature rise of the node. Tables 6.2-5 and 6.2-6 are summaries of the containment structural heat sinks used in the analysis.
The heat transfer coefficient to the containment structure is calculated by the code based primarily on the work of Tagami (Reference [3]). From this work, it was determined that the value of the heat transfer coefficient increases parabolically to peak value at the end of blowdown for LOCA and increases parabolically to peak at the time of steam line isolation. The value then decreases exponentially to a stagnant heat transfer coefficient which is a function of steam-to-air-weight ratio.
Tagami presents a plot of the maximum value of h as a function of " coolant energy transfer speed," defined as follows:
total coolant energy transferred into containment (containment volume) (time interval to peak pressure)
From this, the maximum h of steel is calculated:
E0 .60 (6.2-1) l h,,x = tV P
I where:
i h = maximum value of h (Btu /hr ft2 7),
max tp = time from start of accident to end of blowdown for LOCA and steam line isolation for secondary breaks (sec).
3 V = containment volume (ft ).
O E = coolant energy discharge (Btu).
O 6.2-6 NOVEMBER, 1986 WAPWR-CS 4322e:1d
The parabolic increase to the peak value is given by:
0 <t <t (6.2-2) '
h s
=h max t --P 7"
J O where:
I h s
= heat transfer coefficient for steel (Btu /hr ft2*F).
j
! V
- t = time from start of accident (sec).
For concrete, the heat transfer coefficient is taken as 40 percent of the j value calculated for steel.
i The exponential decrease of the heat transfer coefficient is given by:
I h3 =hstag + (h ,,x - hstag) e (t-t p) t > tp O where: l
=
h stag 2 + 50X 0 1 X $ 1.4.
h = h for stagnant conditions (Btu /hr ft2 .p),
stag 1
l X = steam-to-air weight ratio in containment.
The steel heat transfer coefficients calculated for the double-ended pump l
suction case is shown in Figure 6.2-13.
i.
For a large break, the safety features are quickly brought into operation. i j Because of the brief period of time required to depressurize the reactor 4 coolant system, the safeguards are not a major influence on the blowdown peak i
!O i WAPWR-CS 6.2-7 NOVEMBER, 1986 1322e:1d ;
3
pressure; however, they reduce the containment pressure after the blowdown and maintain a low long-term pressure. Also, although the containment structure is not as effective a heat sink as during the reactor coolant system blowdown, it still contributes significantly as a form of heat removal during the long-term cooling period.
During the injection phase of post-accident operation, the emergency core cooling system pumps water from the emergency water storage tank into the reactor vessel. Since this water enters the vessel at emergency water storage tank temperature, which is less than the temperature of the water in the vessel, it can absorb heat from the core until saturation temperature is reached. During the recirculation phase of operation, water is taken from the containment sump and cooled in the residual heat exchanger. The cooled water is then pumped back to the reactor vessel to absorb more decay heat. The heat is removed from the residual heat exchanger by component cooling water.
Another containment heat removal system is the containment spray. During the injection phase of operation, the containment spray pumps draw water from the emergency water storage tank and sprays it into the containment through nozzles mounted high above the operating deck. As the spray droplets fall, they absorb heat from the containment atmosphere. Since the water comes from the emergency water storage tank, the entire heat capacity of the spray from the emergency water storage tank temperature to the temperature of the containment atmosphere is available for energy absorption. During the recirculation phase of post-accident operation, water is drawn from the sump and sprayed into the containment atmosphere.
( When a spray drop enters the hot, saturated, steam-air containment environment following a loss-of-coolant accident, the vapor pressure of the water at its surface is much less than the partial pressure of the steam in the atmosphere. Hence, there will be diffusion of steam to the drop surface and O condensation on the drop. This mass flow will carry energy to the drop.
Simultaneously, the temperature difference between the atmosphere and the drop will cause the drop temperature and vapor pressure to rise. The vapor O
WAPWR-CS 6.2-8 NOVEMBER, 1986 4322e:1d
pressure of the drop will eventually become equal to the partial pressure of the steam, and the condensation will cease. The temperature of the drop will essentially equal the temperature of the steam-air mixture.
The equations describing the temperature rise of a falling drop are as follows:
d +q (6.2-3)
M (Mu) = mh 9 O d =m (6.2-4)
E (M) where:
q =
bc A (T, - T).
m= Kg A (P 3 - Py ).
O The coefficients of heat transfer (hc) and mass transfer (kg) are calculated from the Nusselt number for heat transfer, N_u, and the Nusselt number for mass transfer, Nu'.
Both Nu and Nu' may be calculated from the equations of Ranz and Marshall (Reference (4]).
Nu = 2 + 0.6 (Re)I/2 (Pr)I/3 (6.2-5)
Nu' = 2 + 0.6 (Re)1/2 (3c)1/3 (6.2-6)
Thus, Equations 6.2-3 and 6.2-4 can be integrated numerically to find the internal energy and mass of the drop as a function of time as it falls through O the atmosphere. Analysis shows that the temperature of the (mass) mean drop produced by the spray nozzles rises to a value within 99 percent of the bulk containment temperature in less than 2 seconds.
O 6.2-9 NOVEMBER, 1986 WAPWR-CS 4322e:1d
Drops of this size will reach temperature equilibrium with the steam-air containment atmosphere after falling through less than half the available spray fall height.
Detailed calculations of the heatup of spray drops in post-ac'cident containment atmospheres by Parsly (Reference [5]) show that drops of all sizes encountered in the containment spray reach equilibrium in a fraction of their residence time in a typical pressurized water reactor containment.
O These results confirm the assumption that the containment spray will be 100 percent effective in removing heat from the atmosphere.
6.2.1.1.6 Nomenclature A = area.
h' = coefficient of heat transfer.
O* k g
= coefficient of mass transfer.
h = steam enthalpy.
g M = droplet mass.
m = diffusion rate.
Nu = Nusselt number for heat transfer.
Nu' = Nusselt number for mass transfer, i
P = steam partial pressure.
s 1
P y = droplet vapor pressure.
O WAPWR-CS 6.2-10 NOVEMBER, 1986 1322e:1d
g = Prandtl number.
q = heat flow rate.
M = Reynolds number.
c Se, = Schmidt number.
= droplet temperature.
O T, T = steam temperature.
t = time.
u = internal energy.
The reactor containment fan coolers are a final means of heat removal. The main aspect of a fan cooler from the heat removal standpoint are the fan and O the banks of cooling coils. The fans draw the dense atmosphere through banks of finned cooling coils and mix the cooled steam / air mixture with the rest of l the containment atmosphere. The coils are supplied cooling water from the componentcoolingwatersystem(CCWS), as described in Subsection 9.2.2 of RESAR-SP/90 PDA Module 13, " Auxiliary Systems." Since this system does not use water from the emergency water storage tank, the mode of operation remains -
the same both before and after the spray system and emergency core cooling system change to the recirculation mode.
6.2.1.1.7 Accident Chronology
- For the double-ended pump suction loss-of-coolant accidents, the major events
! and their times of occurrence are shown in Table 6.2-4.
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6.2-11 NOVEMBER, 1986 l
WAPWR-CS 4322e:1d ,
f
.-,...-.---.,,.._,---_,,_-__,--L._. . - . . . _ - - _ . _ _ - - - _ _ - - . , . . , . . . .
O 6.2.1.2 Containment Subcompartments d
6.2.1.2.1 Design Bases Subcompartments within containment (not part of the containment boundary) are O designed to withstand the transient differential pressures and jet impingement forces of postulated pipe breaks. Venting of these chambers is employed to keep the differential pressures within structural limits. In addition, restraints on pipes, components, etc. are designed to limit pipe whip effects and forces transmitted through component supports to ensure the integrity of i
subcompartments and the containment structures.
6.2.1.2.1.1 Summary of Subcompartment Pipe Break Analyses The postulated breaks in high-energy lines that are analyzed to determine the differential pressure across the subcompartment walls are specified in Section 3.6 of RESAR-SP/90 PDA Module 7. " Structural / Equipment Design."
l 6.2.1.2.1.2 Design Features i
The effects of high-energy line breaks in containment subcompartments will be
- analyzed in the FDA to establish criteria for the structural design of the
, compartment walls. ,
6.2.1.3 Mass and Energy Release Analyses for Postulated Loss-of-Coolant Accidents s
This analysis presents the mass and energy releases to the containment subsequent to a hypothetical loss of-coolant accident (LOCA). The release i
rates are calculated for pipe failure at three distinct locations: p l
l 1. Hotleg(betweenvesselandsteamgenerator)
- 2. Pump suction (between stet.m generator and pump)
- 3. Coldleg(betweenpumpandvessel) i O
6.2-12 NOVEMBER, 1986 WAPWR-CS 4322e:1d , 1
~
l During the reflood phase, these breaks have the following different characteristics. For a cold leg pipe break, all of the fluid which leaves the core must vent through a steam generator and becomes superheated. However, relative to breaks at the other locations, the core flooding rate (and therefore the rate of fluid leaving the core) is low, because all the core vent paths include the resistance of the reactor coolant pump. For a hot leg pipe break, the vent path resistance is relatively low, which results in a high core flooding rate, but the majority of the fluid which exits the core bypasses the steam generators in venting to the containment. The pump suction break combines the effects of the relatively high core flooding rate, as in the hot leg break, and steam generator heat addition, as in the cold leg break. As a result, the pump suction break yields the highest energy flow rates during the post-blowdown period.
The spectrum of breaks analyzed includes the largest cold and hot leg breaks, reactor inlet and outlet, respectively, and a range of pump suction breaks 2 2 Because of the phenomena fromthelargest(10.48ft)toa3.0 ft break.
of reflood as discussed above, the pump suction break location is the worst l
case for long term containment depressurization. This conclusion is supported by studies of smaller hot leg breaks which have been shown on similar plants
' to be less severe than the double-ended hot leg. Cold leg breaks, however, are lower both b the blowdown peak and in the reflood pressure rise. Thus, an analysis of smaller pump suction breaks is representative of the spectrum of break sizes. The hot leg break is the worst case for containment pressure.
The LOCA transient is typically divided into four phases:
0 G
j 1. Blowdown - which includestheperiodfromaccidentoccurrence(when the reactor is at steady state operation) to the time when the total break flow stops.
O i 2. Refill - the period of time when the lower plenum is being filled by accumulator and safety injection water. (This phase is I
(O 6.2-13 NOVEMBER, 1986
, WAPWR-CS
- 4322e
- 1d
i f
l conservatively neglected in computing mass and energy releases for containmentevaluations.) .
- 3. Reflood -
begins when the water from the lower plenum enters the core and ends when the core is completely quenched.
- 4. Post-Reflood -
describes the period following the reflood 4
transient. For the pump suction and cold leg breaks, a two phase
- mixture exits the core, passes through the hot legs, and is superheated in the steam generators. After the broken loop steam
{
generator cools, the break flow becomes two phase.
1 6.2.1.3.1 Wass and Energy Release Data
[
l l
Blowdown Mass and Eneray Release Data l
Tables 6.2-7, 6.2-8, 6.2-9, 6.2-10, and 6.2-11 present the calculated mass and energy releases for the blowdown phase of the various breaks analyzed.
l The mass and energy releases for the pump suction double-ended break, given in Table 6.2-7, terminate 31.6 seconds after the postulated accident. Since safety injection does not become effective until about the time blowdown terminates, these releases apply for both maximum and minimum safety injection.
Reflood Mass and Eneray Release Data Tables 6.2-12, 6.2-13, 6.2-14, and 6.2-15 present the calculated mass and O energy releases for the reflood phase of the various breaks analyzed along with the corresponding safety injection assumption (maximum or minimum).
Two Phase Post-Reflood Mass and Eneray Release Data Tables 6.2-16and6.2-17presentthetwophase(froth)massand energy release data for a double-ended pump suction break using maximum and minimum safety O
WAPWR-CS 6.2-14 NOVEMBER, 1986 4322e:1d
injection assumptions, respectively. The data was generated using an assumed 3,600 second containment depressurization transient.
Table 6.2-18 presents the post-reflood mass and energy release data for 0.6 double ended pump suction break using minimum safety injection.
Equilibrium and Depressurization Energy Release Data 4
The equilibrium and depressurization energy release has been incorporated in the post-reflood mass and energy release data. This eliminates the need to
- determine additional releases due to the cooling of steam generator secondaries and primary metal.
' 6.2.1.3.2 Energy Sources The energy inventories considered in the LOCA mass and energy release analysis are given in Tables 6.2-19 through 6.2-23. The energy sources include:
- 2. Accumulators
- 3. Pumpedinjection I
i 4. Decay heat S. Core stored energy l ,
! 6. Primary metal energy
- 7. Secondary metal energy
- 8. Steam generator secondary energy lO i WAPWR-CS 6.2-15 NOVEMBER, 1986 1322e:1d l
_ ~ _ - -
I
(
1 4
I l 1 i
- 9. Secondary transfer of energy (feedwater into and steam out of the i steam generator secondary) j i c l
The inventories are presented at the following times, as appropriate:
l O 1. Time zero (initial conditions) i 2. End of blowdown time iO i 3. End of refill time I '
j 4. End of reflood time
- 5. Time of full depressurization 1
i
- 6. End of analysis l .
i !
The methods and assumptions used to release the various energy sources are [
l
'givenincorrespondenceNS-TMA-2075(1979). ,
The following items ensure that the core energy release is conservatively l analyzed for maximum containment pressure:
- 1. Maximum expected operating temperature
- 2. Allowance in termperature for instrument error and dead band (+4*F) f
!O j 3. Margininvolume(1.4 percent)
- 4. Allowance in volume for thermal expansion (1.6 percent) -
l
- 5. Margin in core power associated with use of engineered safeguards !
designrating(ESDR) ;
! i i O !
WAPWR-CS 6.2-16 NOVEMBER, 1986 1322e:1d
- 6. Allowance for calorimetric error (2 percent of ESDR)
- 7. Conservatively modified coefficients of heat transfer
- 8. Allowance in core stored energy for effect of fuel densification
- 9. Marginincorestoredenergy(+15 percent) 6.2.1.3.3 Blowdown Model Description The model used for blowdown transient (SATAN-VI) is the same as that used for the emergency core cooling system (ECCS) calculation. This model is described in WCAP-9220 and WCAP-6174. NS-TMA-2075(1979) provides the method by which the model is used. ,
6.2.1.3.4 Refill Model Description l At the end of blowdown, a large amount of water remains in the cold legs, f downcomer, and lower plenum. To conservatively model the refill period for l the purpose of containment mass and energy releases, this water is f to the lower plenum along with sufficient I. instantaneously transferred i
j- accumulator water to completely fill the lower plenum. Thus, the time j required for refill is conservatively neglected.
j 6.2.1.3.5 Reflood Model Description j i
f The model used for the reflood transient (WREFLOOD)isaslightlymodified version of that used in the ECCS calculation. This model is described in r WCAP-9220 and WCAP-8170, NS-TMA-2075 (1979) describes the method by which this model is used and the modifications. Transients of the principal parameters during reflood are given in Tables 6.2-24 and 6.2-25 for the
(
double-ended pump suction break with maximum and minimum safety injection. r o ;
i WAPWR-CS 6.2-17 NOVEMBER, 1986 T322e:1d
6.2.1.3.6 Post-Reflood Model Description Two-Phase (FROTH)
The transient model (FROTH), along with its method of use, is described in WCAP-8312-A. The mass and energy rates calculated by FROTH are utilized in the containment analysis to the time of containment depressurization. Refer to Subsection 6.2.1.1.3 for a discussion of how the mass and energy release, including ECCS spillage, for the loss-of-coolant accident are determined.
Long Term (Dry Steam)
After depressurization, the mass and energy release from decay is based on ANS (1978) and the following input:
- 1. Decay heat sources considered are fission product decay and heavy element decay of U-239 and Np-239.
O 2. Decay heat power from fissioning isotopes other than U-235 is assumed to be identical to that of U-235.
- 3. Fission rate is constant over the operating history of maximum power level.
- 4. The factor accounting for neutron capture in fission products has been taken from Table 10 of ANS (1978).
- 5. Operation time before shutdown is 3 years.
2 i 6. The total recoverable energy associated with one fission has been assumed to be 200 MeV/ fission, j 7. Two sigma uncertainty has been applied to the fission product decay.
O '
f NOVEMBER, 1986 WAPWR-CS 6.2-18 4322e:1d
6.2.1.3.7 Single Failure Analysis The effect of single failures of various ECCS components on the mass and energy releases is included in these data. Two analyses bound this effect for the pump suction double-ended rupture.
No single failure is assumed in determining the mass and energy releases for the maximum safeguards case. For the minimum safeguards case, the single failure assumed is the loss of one emergency diesel. This failure results in the loss of one pumped safety injection train. The analysis of both maximum and minimum safeguards cases ensure that the effect of all credible single failures is bounded.
A single failure analysis is 'not performed for the hot leg double-ended rupture since the ECCS has no effect on the maximum containment pressure, which occurs at the end of blowdown.
6.2.1.3.8 Metal-Water Reaction In the mass and energy release data presented, no Zr-H O2 reaction heat was considered because the clad temperature did not rise high enough for the rate of Zr-H2O to be of any significance.
6.2.1.3.9 Additional Information Required for Confirmatory Analysis System parameters needed to perform confirmatory analyses are provided in Table 6.2-26.
6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary Pipe Ruptures Inside Containment Steam line ruptures occurring inside a reactor containment structure may result in significant releases of high energy fluid to the containment environment, possibily resulting in high containment temperatures and O
WAPWR-CS 6.2-19 NOVEMBER, 1986 1322e:1d
pressures. The quantitative nature of the releases following a steam line rupture is dependent upon the many possible configurations of the plant steam system and containment designs as well as the plant operating conditions and the size of the rupture. These variations make a reasonable determination of the single absolute " worst case" for both containment pressure and temperature evaluations following a steambreak difficult. This section describes the methods used in determining the containment responses to a variety of postulated pipe breaks encompassing wide variations in plant o>eration, safety system performance, and break size. The spectrum of breaks analyzed is listed in Table 6.2-27.
6.2.1.4.1 Significant Parameters Affecting Steam Line Break Mass and Energy Releases There are four major factors that influence the release of mass and energy following a steam line break: steam generator fluid inventory, primary to secondary heat transfer, protective system operation, and the state of the secondary fluid blowdown. The following is a list of those plant variables which determine the influence of each of these factors:
- a. Plant power level
- b. Main feedwater system design
- c. Emergency feedwater system design
- d. Postulated break type, size, and location
- e. Availability of offsite power
- f. Safety system failures
- g. SG reverse heat transfer and reactor coolant system metal heat capacity i
The following is a discussion of each of these variables.
lO i
l i O l
l WAPWR-CS 6.2-20 NOVEMBER, 1986 1322e:1d
l 6.2.1.4.1.1 Plant Power Level Steam line breaks can be postulated to occur with the plant in any operating condition ranging from hot shutdown to full power. Since steam generator mass decreases with increasing power level, breaks occurring at lower power will generally result in a greater total mass release to the plant containment.
However, because of increased energy storage in the primary plant, increased heat transfer in the steam generators, and the additional energy generation in the nuclear fuel, the energy release to the containment from breaks postulated to occur during power operation may be greater than for breaks occurring with the plant in a hot shutdown condition. Additionally, steam pressure and the dynamic conditions in the steam generators change with increasing power and have significant influence on both the rate of blowdown and the amount of moisture entrained in the fluid leaving the break following a steambreak event.
il Because of the opposing effects of changing power level on steam line break releases, no single power level can be singled out as a worst case initial 4 condition for a steam line break event. Therefore, several different power levels spanning the operating range as well as the hot shutdown condition have l
been analyzed.
i 6. 2.1. 4.1. 2 Main Feedwater System Design The rapid depressurization which occurs following a rupture may result in largo amounts of water being added to the steam generators through the main i feedwater system. Rapid closing isolation valves are provided in the main feedwater lines to limit this effect. Also, the piping layout downstream of O the isolation valves affects the volume in the feedwater lines that cannot be isolated from the steam generators. As the steam generator pressure decreases, some of the fluid in this volume will flash into the steam generator, providing additional secondary fluid which may exit out the rupture.
i The feedwater addition which occurs prior to closing of the feedwater line
! isolation valves influences the steam generator blowdown in several ways.
2 O
6.2-21 NOVEMBER, 1986
- WAPWR-CS
- 1322e
- 1d i
c ;
4 L
i First, the rapid aedition increases the amout of entrained water in large-break cases by lowering the bulk quality of the steam generator
' inventory. Secondly, because the water entering the steam generator is I
! 'subcooled, it lowers the steam pressure, thereby reducing the flow rate out of the break. Finally, tne increased flow rate causes an increase in the heat transfer rate from the primary to secondary system resulting in greater energy being released out the break. Since these are competing effects on the total ;
- mass and energy release, no " worst case" feedwater transient can be defined for all plant conditions. In the results presented, the worst effects of each variable have been used. For example, moisture entrainment for each break is i
calculated, assuming conservatively small feedwater additions so that the entrained water is minimized. Determination of total steam generator 7
- inventory, however, is based on conservatively large feedwater additions, as
} explained in Subsection 6.2.1.4.3.2.
The unisolated feedwater line volumes between the steam generator and the i isolation valves serve as a source for additional high energy fluid to be l discharged through the pipe break. This volume is accounted for in the mass [
f ' and energy release data presented in Subsection 6.2.1.4.3.2.
6.2.1.4.1.3 Emergency Feedwater System Design ,
i i Within the first minute following a steam line break, the emergency feed -
l system is initiated on any one of several protection system signals. Addition of emergency feedwater to the steam generators increases the secondary mass
}
available for release to the containment, as well as increases the heat ;
I transferred to the secondary fluid. The effects on steam generator mass are !
maximized in the calculation described in Subsection 6.2.1.4.3.2 by assuming j j full emergency feed flow to the faulted steam generator starting at time zero j
! and continuing until manually stopped by the plant operator at 30 minutes. ;
O !
lO i
6.2-22 NOVEMBER, 1986
! WAPWR-CS U22e:1d
---w--w,,m-mw w-,--,nn-rw,,,w--e---,- ~-y,,---,c.,-~ ,ym.-gsm-.wmy,=-v
6.2.1.4.1.4 Postulated Break Type, Size, and Location
- a. Postulated Break Type Two types of postulated pipe ruptures are considered in evaluating r.Leam line breaks.
First is a split rupture in which a hole opens at some point on the side of the steam pipe or steam header but dcasnotrsuitinacomp1st( ~
severance of tLospipe. A single, distinct break area is fed uniformly by all steam generators until steam line isolation occurs. The blowdown
' flow rates from the individual steam generr. tors are interdependent, since
' fluid coupling exists between all steam lines. Because flow limiting orifices are provided in each steam generator, the largest rsssibie split rupture can have an effective area prior to isolation that is no greater than the throat area of the flow restrictor times tha nu:ser of plant _
primary coolant loops. Following isolation, the effective break area for the steam generator with the broken line can be no greator than the flow restrictor throat area.
The second break type is the double-ended guillotine rupture in which the l steam pipe is completely severed anst the ends of the creak displace from each other. Guillotine ruptures are characterized by two distinct break locations, each of equal area but being fed by different steam generators. The largest possible guillotine rupture can have an i effective area per steam generator no greator than ti,a th'roat., area ,of one ,
steamline flow restrictor.
- l l The type of break influences the mass and energy releases to containment t
by altering both the nature of the steam blowdown from the piping in the steam plant and the offective break area fed by each steam generator l prior to steam line isolation. For example, a double-ended rupture in a '
pipe having a cross-sectional area of ?.4 square feet would appear as a l
O b
WAPWR-CS 6.2-23 NOVEM.1ER,1986 4322e:1d ,
c '
,.l k f
1.4-square-foot rupture to a single steam generator feeding one end of the break, but would appear as a 0.8-square-foot rupture to each of the steam generators feeding the other end of the break.
- b. Postulated Size iI .
Break area is also important when evaluating steam line breaks. It eJ$
controls the rate of releases to the containment as well as exerts significant influence on the steam pressure decay and the amount of entrained water in the blowdown flow. The data presented in this section
-- include releases for both a full double-ended rupture and the limiting split break area at each of five initial power levels as follows:
- 1. A full double-ended pipe rupture downstream of the steam line flow
- restrictor, For this case, the actual break ' area equals the cress-sactional area of the steam line, but the blowdown from the
- . steam generator with the broken line is controlled by the flow restrictor throat area (1.4 square feet). The reverse flow from the intact steam generators is controlled by the smaller of the pipe r.ross sectics, the steam stop valve seat area, or the total flow
! restrictor throat area in the intact loops. In this analysis, the reverse flowri: controlled by the flow restrictors in each of the intact steam generators since the total pipe cross-sectional area is
'4.54 ft2 ,
l l
- 2. A spitt breek' that represents the largest break ares that does not
,( -
genente, 3 - steam line isolation from the primary protection system.
L Steam and feedwater isolation will be actuated by high containment L pressure signals for these cases, b
. For both break types, it is conservatively assumed that no moisture f; entrainment occurs. Detailed steam generator analyses using the NOTRUMP l ,
computer code (Reference (6)) show no entrainment for double-ended ruptures frca power levels greater than 50 percent of hot full power.
O WAPWR-CS 6.2-24 NOVEMBER, 1986
, D22e:1e
!)
s Sensitivity studies have shown that entrainment has only a small affect on calculated peak containment pressure. Therefore, dry blowdowns are conservatively assumed for all power levels. For large split ruptures, i moisture entrair. ment could occur following steam line isolation since the c
effective break area seen by the faulted steam generator increases by a factor of 4. However, since steam'line isolation generally does not occur until after 30 seconds,. it is conservatively assumed that the
! pressure has decreased sufficiently in the affected steam generator to preclude any moisture carryover.
i
- c. Postulated Break Location Break location affects steam line blowdowns by virture of the pressure j j losses which would occur in the length of piping between the steam generator and!the break. The effect of the preissure loss is to reduce l
the effective break area seen by the steam generator. Although this
' would reduce the rate of U owdown, it would not significantly change the total release of energy to the containment. .For the double-ended 1
3 ruptures, the piping loss offects area conservatively ignored. For the split breaks, it is modeled before steam line isolation since it acts to increase the limiting split b uak area.
l 6.2.1.4.1.5 Availability of Offsite Power The effects of the assumption of the availability of offsite power has been enveloped in the analysis. Loss of offsite power has been assumed where it delays- the actuation of the containment heat removal systems (i.e.,
O containment sprays and containment air coolers) and safety injection actuation due to the time required to start the emergency diesel generators. Offsite power has been assumed to be available where it maximizes the mass and energy released from the break due, to 1) the continued operation of the reactor coolant pumps which maximizes the energy transferred from the reactor coolant system to the steam generators and 2) continued operation of the feedwater 1 pubps and actuation of the emergency feedwater system which maximizes the
! steam generator inventories available for release.
WAPWR-CS 6.2-25 NOVEMBER, 1986 l
! T322e:1d
i a
6.2.1.4.1.6 Safety System Failures In addition to assuming a loss of offsite power, the following single active failures were considered:
O a. Loss of one emergency diesel
- b. Failure of one main steam isolation valve
- c. Failure of one main feedwater isolation valve O The loss of one diesel results in the loss of one train of each of the containment heat removal systems and safety injection. As discussed in Subsection 6.2.1.4.3.3, this is the most severe single active failure. 1 The effect of a main steam isolation valve failure is to provide additional fluid which may be released to the containment via the break.- This results
- from the blowdown of all the steam piping between the break location and the isolation valves in the intact loops.
O The failure of a main feedwater isolation valve will result in additional fluid being released to the containment following a main steam line break.
The additional fluid to be released will be the volume between the isolation valve and the feedwater control valve.
6.2.1.4.1.7 Steam Generator Reverse Heat Transfer and Reactor Coolant System Metal Heat Capacity i
Once steam line isolation is complete, those steam generators in the intact O steam loops become sources of energy which can be transferred to the steam generator with the broken line. This energy transfer occurs via the primary coolant. As the primary plant cools, the temperature of the coolant flowing l in the steam generator tubes drops below' the temperature of the secondary fluid in the intact units, resulting in energy being returned to the primary coolant. This energy is then available to be transferred to the steam I generator.with the broken steamline.
i WAPWR-CS 6.2-26 NOVEMBER, 1986
'4322e:1d I
)
Similarly, the heat stored in the metal of the reactor coolant piping, the reactor vessel, and the reactor coolant pumps will be transferred to the primary coolant as the plant cooldown progresses. This energy also is vailable to be transferred to the steam generator with the broken line.
O The effects of both the reactor coolant system metal and the reverse steam generator heat transfer are included in the results presented in this document.
6.2.1.4.2 Description of Blowdown Model The blowdown model consists of two computer codes. First, the NOTRUMP code (Reference [6]) is used to predict the amount of moisture entrainment following a full double-ended steamline rupture. The break quality versus time transient is input into the LOFTRAN code (Reference [7]) which then predicts mass and energy releases to be transferred for use in the containment response analysis.
i 6.2.1.4.3 Containment Response Analysis The C0C0 computer code (Ref. 1), which is discussed in Subsection 6.2.1.1.3, was used to determine the containment responses following the postulated main
, steam line breaks. The following assumptions were made to obtain these responses.
l l 6.2.1.4.3.1 Initial Conditions l
The initial containment conditions are the same as those used in the containment response analysis for the postulated reactor coolant system pipe ruptures (see Table 6.2-28).
6.2.1.4.3.2 Mass and Energy Release Data O
The mass and energy release data shown in Tables 6.2-29 through 6.2-40 were determined using similar methodology as described in (Reference (8]). The key A assumptions are described below:
O WAPWR-CS 6.2-27 NOVEMBER, 1986 4322e:1d
- l. _. . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ , _ _ _ _ _ _ _
r a) Power levels of 102, 75, 50, 25 and 0 percent power were assumed.
b) The initial steam generator mass is assumed to be 110 percent of the value corresponding to nominal level plus 5 percent narrow range span.
c) The core shutdown margin and reactivity coefficients are based on the assumption of the most reactive RCCA stuck in its fully with-drawn position.
d) The initial reactor coolant inlet temperature is 4*F higher than the steady state value for each power level.
e)- 450 gpm of emergency feedwater is delivered to each steam generator. This value corresponds to the maximum flow to a depressurized steam generator.
f) Maximum main feedwater flow rates are assumed. For the double-ended
- cases, a value of 5 times the nominal full power rated flow is assumed for all power levels. This value is based on the main feedwater pumps operating at maximum speed, the feedwater control valve in the broken loop wide open, and the faulted steam generator at atmospheric pressure.
For the split breaks, feedwater flow is assumed to equal steam flow until feedwater is isolated on a high containment pressure signal.
6.2.1.4.3.3 Containment Pressure-Temperature Results Figures 6.2-14 through 6.2-37 provide curves of the resultant containment pressure-temperature transients for all cases. Table 6.2-28 summarizes the results of all the cases analyzed and indicates the times at which dryout occurs and the various containment pressure setpoints are reached. The ,
i O l WAPWR-CS 6.2-28 NOVEMBER, 1986 i 4322e:1d
sequence of events following a postulated main steam line break is listed in Tables 6.2-41 and 6.2-42 for worst pressure and temperature cases, respectively.
1
! The worst single active failure is the loss of an emergency diesel. This is evident by comparing the results given in Table 6.2-28 for cases 5 and 10 which assume a loss of an emergency diesel, and cases 11 and 12 which assume the failure of a main steam isolation valve. The comparisons are made for both a full double-ended rupture and split rupture at hot zero power. The failure of a main feedwater isolation valve was not specifically analyzed.
The additional fluid which would be released is that contained in the volume ,
between the main faedwater isolation valve and the feedwater control valve.
3
! This volume is less than 10 ft and would not significantly affect the containment response. For all cases analyzed a conservatively high' value of feedwater piping volume is assumed.
As illustrated in Figure 6.2-22 (Case 5], a full double-ended rupture from hot zero power, results in a peak containment pressure of 33.22 psig. This case represents the peak containment pressure calculated for the spectrum of breaks analyzed.
For all cases analyzed the peak containment pressure occurs at the time of steam generator dryout. At that time, the break flow is reduced to the point where the containment heat removal is greater than the energy added from the break. After steam generator dryout the break flow matches the emergency feedwater flow until the operator terminates emergency feedwater at 30
! minutes. In all cases, the peak calculated containment pressure demonstrates i considerable margin below the containment design pressure of 46.9 psig. The -
peak pressure is also less than that calculated following the i miting loss of coolant accident described in Subsection 6.2.1-3.
As illustrated in Figure 6.2-25 (Case 6], a 1.1 ft 2 split rupture at 102 l percent of hot full power, results in a peak containment vapor pressure of 315'F. This case represents the peak containment pressure calculated for the spectrum of breaks analyzed.
WAPWR-CS 6.2-29 NOVEMBER, 1986 T322e:1d
. - _ . _ _ _ _ _ . ~ _ . _ _ - . _ -_ __ __ _ _ _ _ . _ _ . - - _ . _ _ _ _ _ _ _ . . __ . _ . _ . -
i For the split breaks analyzed, the peak containment vapor temperature is reached just after the fan cooler operation is initiated. The fan coolers act
] to de-superheat the vapor and thus reduce the containment temperature. ;
iO f
!O t
O l'
I r t
l l
O ,
O O
WAPWR-CS 6.2-30 NOVEMBER, 1986 T322e:1d
REFERENCES (1) Bordelon, F. M., Nurphy, E. T., " Containment Pressure Analysis Code (C0CO)," WCAP-8326 (Westinghouse) July,1974. l l
l (2) Barlow, R. T., Hsieh, T., Julian, H. V., " Environmental Qualification:
Instrument Transmitter Temperature Transient Analysis," WCAP-8936 (Westinghouse Proprietary), February 1977.
(3) Tagami, Takashi, " Interim Report on Safety Assessments and Facilities, Establishment Project in Japan for Period Ending June 1965," No.1.
(4) Marshall, Jr., W. R., Ranz, E. W., " Evaporation for Drops," Chemical Engineering Progress, 48141-146, March 1952.
(5) Parsly, L. F., " Spray Tests at the Nuclear Safety Pilot Plant," Nuclear Safety Program Annual Progress Report for Period Ending December, 1970, ORNL-4647, 1971, p, 82.
(6) Heyer, P. E., "NOTRUMP A Nodal Transient Small Break and General Network '
Code," WCAP-10079 (Westinghouse Proprietary) August 1975.
(7) Burnett, T. W. T., et. al. "LOFTRAN Code Description," WCAP-7907 (WestinghouseProprietary), April 1984.
(8) Land, R. E., " Mass and Energy Releases Following a Steamline Rupture, "WCAP-8822 (Westinghouse Proprietary) and WCAP-8860 (Westinghouse Non-Proprietary), September 1976.
O O
WAPWR-CS 6.2-31 NOVEMBER, 1986 T322e:1d
. _ _ _ . ~ _ _ _ . . . . _ _ . . _ _ _ _ . . . -
l l
l TABLE 6.2-1 l
CONTAINMENT PEAK PRESSURE AND TEMPERATURE I
Peak Available Peak Pressure Margin Temperature Break (psig) (psi) *C (*F) l Primary Side Ruptures l Double-ended pump suction - Max SI 35.9 11.0 121.6 (253)
Double-ended pump suction - Min SI 34.6 12.3 121.6 (250) 0.6 double-ended pump suction 32.9 14.0 121.1 (250) i 2
3-ft pump suction 34.2 12.7 120.5(249)
O Double-ended hot leg 36.4 10.5 123.8 (253) s Double-ended cold leg 35.7 11.2 122.2 (252)
O i
O i
i O WAPWR-CS 6.2-32 NOVEMBER, 1986
. T322e:1d
TABLE 6.2-2 ASSUMPTIONS FOR CONTAINMENT ANALYSIS - PART 1 Service water temperature 'C (*F) 37.7 (86)
Refueling water temperature 'C ('F) 32.2 (120)
RWST water volume (gal) 560,000 Initial containment temperature 'C (*F) (120'F)
Initial pressure (psia) 16.1 i
Initial relative humidity (%) 20 3
Net free volume (ft ) 3.09 x 106 O
O O
O WAPWR-CS 6.2-33 NOVEMBER, 1986 T322e:1d
.- . . . . - . - - . _ _ _ _ . . . _ . - . = . .. . - - .- ._ _ -- - - ..
i TABLE 6.2-3 ASSUMPTIONS FOR CONTAINMENT ANALYSIS - PART 2 1
Number of Fan Coolers Total 2 i
Operating maximum 2 Operating minimum 1 Number of spray pumps Maximum safeguards spray flow (gpm) 5720 l ,
i Minimum safeguards spray flow (gpm) 5720 ,
L I
i i
O O
WAPWR-CS 6.2-34 NOVEMBER, 1986 4322e:1d^
1
.,-...,......,,.._-._..4- - . . . _ , _ , _ _ _ , _ . . . . _ _ _ . _ . _ - . . _ . _ _ . _ _ . _ _ - _ . . --
i
- i TABLE 6.2-4 DESIGN BASIS ACCIDENT CHRONOLOGY OF EVENTS r
(
Time (Seconds) Event 4
0.0 Start of accident l' -26.0 Peak pressure reached l
31.6 End of blowdown phase r
I 70.2 Containment sprays start l
i 73.0 Containment fan coolers start j!
i i 167.5 End of reflood phase i
O 3760.0 RWST empties 3760.0 Sump recirculation starts j 4
i i
Lo
}
lO
) .
I t
!O !
6.2-35 NOVEMBER, 1986 WAPWR-CS l 4322e:1d
TABLE 6.2-5 CONTAINMENT HEAT SINKS Heat Transfer O Na Wall Description Material 2 Area (m ) ft 2 Thickness (mm) ft 1 SteelContainment(Thin) Carbon Steel (5400) (38) 58125.1 0.1247 2 SteelContainment(Thick) Carbon Steel (2250) (45) 24218.8 0.1476 3 Inner Concrete (Thick) Concrete (12600) (530) 135625.1 1.7388 4 Inner Concrete (Thin) Concrete (220) (240) 2368.1 0.7874 5 Inner Concrete with SUS (6)
Stainless Steel Liner (1630) 0.0197 Concrete 17545.2 (670)
O 2.1981 6 Missile Shield and Inner Carbon Steel (14)
Concrete with Thick (690) 0.0459 Carbon Steel Liner Concrete 7427.1 (610) 2.0013 7 Inner Concrete with Thin Carbon Steel (2)
Carbon Steel Liner (3290) 0.0066 Concrete 35413.2 (300) 0.9842 8 H/C Support, Acc. Tank Carbon Steel (1950) (57)
- 20989.6 0.1870 9 C/V Equipment Hatch Carbon Steel (100) (39) 1076.4 0.1280 10 Ring Girder, Polar Crane, Carbon Steel (15000) (11)
CRT, MS FW Rupture Restraint 161458.5 0.0361 11 Conduit, Duct Support, Carbon Steel (20000) (5) l Pipe Support 215278.0 0.0164 l 12 Duct, Grating, H&V Unit Carbon Steel (18000) (1) 193750.2 0.0033 i
WAPWR-CS 6.2-36 NOVEMBER, 1986
'4322e:1d
.c - -. __ - - __ - . _ ._ - .. _ ._.
I o
TABLE 6.2-5 (Continued)
' CONTAINMENT HEAT SINKS Heat Transfer O No. Wall Description Material A
2 rea2 (m ) ft Thickness (mm) ft i
1 13 Instrument Tube, SUS (370) (14)
Pressurizer Relief Tank 3982.6 0.0459 14 Fin, Tube Copper (19000) (0.3) 204514.1 0.00098 15 Stainless Steel Pipe SUS (1000) (9) with Water (water 10763.9 0.0295 neglected)
! 16 Stainless Steel Pipe SUS (340) (5)
Without Water 3659.7 0.0164 17 Carbon Steel Pipe with Carbon Steel (110) (G) i Water (Water 1184.0 0.0197 neglected) 18 Carbon Steel Pipe Carbon Steel (880) (4)
Without Water 9472.2 0.0131 1
- 19 Instrumentation Equipment Aluminum (5) (11) 53.8 0.0361 NOTE:
All carbon steel is modeled with a layer of paint with a thickness equaling O .00025 ft.
O lO WAPWR-CS 6.2-37 NOVEMBER, 1986 4322e:1d
k TABLE 6.2-6 THERM 0 PHYSICAL PROPERTIES OF CONTAINMENT HEAT SINKS 4 Thermal Conductivity VolumetricgeatCapacity l
Material (Btu /hr-ft 'F) (Btu /ft 'F)
Paint 0.63 23.0 l
! I Carbon Steel 26.0 56.0 [
l l O i I Stainless Steel 10.0 55.7 1
Concrete 0.90 30.0 i
L 4
O ,
t i
i O .
i I
i O !
I O
WAPWR-CS 6.2-38 NOVEMBER, 1986 4322e:Id
(N b TABLE 6.2-7 APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI BLOWDOWN MASS AND ENERGY RELEASES O
G T!nE BREAK PATM NO.1 FLOW BREAK PATM NO.2 rLOW THOUSAMO THOUSAne SECONOS LBM/SEC STU/5EC LSM/SEC STU/SEC 0.000 0.0 0.0 0.0 0.0 O 100
.200 401
.600 50405.9 51241.5 46914.6 46480.2 28550.5 29436.2 27659.0 27864.3 23137.2 25557.8 27134.0 26882.1 12953.1 14318.4 15289.7 15451.6 900 43737.3 26540.4 23015.6 13342.8 1.40 40848.5 25066.2 22222.1 12607.3 2.10 36022.8 22430.8 22431.7 12642.0 3.30 27632.5 17941.1 20881.6 11754.9 3.50 24262.6 15928.0 2047.7 11514.8 3.80 21830.4 14514.5 19752.9 11096.0 5.60 14970.3 10184.2 16042.2 8798.6 6.20 13791.8 9290.7 15216.5 8254.9 6.60 14948.4 10069.6 14996.6 8080.9 7.00 10049.5 8280.3 14742.6 7896.8 8.00 11164.3 8120.1 14104.2 7478.2 9.00 13868.4 9173.5 13458.7 7100.6 9.40 14599.1 9460.8 13111.3 6907.5 10.0 1452.8 9442.5 142 4 .3 7503.7 11.0 13635.3 8761.8 13608.7 7171.2 12.2 11024.8 7257.7 12901.4 6821.9 1
i 0 13.6 15.0 16.2 17.2 8708.9 8333.3 7121.1 6776.0 6255.8 5936.7 5475.1 5174.4 12069.2 11273.1 10600.0 9939.5 6414.0 6010.0 5675.6 5339.0 20.2 5174.3 4387.1 7924.8 4324.8 21.8 4074.2 4148.2 7082.9 3507.9 22.8 3098.7 3584.8 5553.1 2567.0 24.4 2070.0 2562.1 4909.3 2023.7 25.2 1673.9 2084.1 3535.9 1400.1 25.8 1354.4 1693.4 4518.3 1620.4 27.2 912.6 1149.1 3359.4 1060.7 29.4 483.5 610.9 54.4 149.6 30.0 418.2 528.8 39.0 10.4 31.6 0.0 0.0 0.0 0.0 i
l i
O WAPWP-C,S 6.2-39 NOV TB 9. 1986 e
5 a e. . . .,
TABLE 6.2-8 APWR/0.6 DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI i BLOWDOWN MASS AND ENERGY RELEASES O TIME SAEAK PATH N0.1 FLOW bAEAK PATH N0.2 FLOW TM005AND THOUSAND SECONDS LBM/SEC BTU /SEC LBM/SEC BTU /SEC 0.000 0.0 0.0 0.0 0.0 I 100 42241.3 23902.5 21023.3 11768.1 I 201 41751.7 23885.7 22916.9 12840.3
. .501 36355.5 21394.9 24843.5 14057.4 l 701 33524.1 19955.0 24052.9 13845.4
.900 31919.0 19111.0 21747.1 12618.0 1.40 30712.4 15433.4 21278.9 12124.7 2.70 28793.3 17219.0 21404.4 12057.8 3.50 28255.7 16880.5 20439.0 11503.2 4.00 27121.9 16294.4 19520.8 10960.4 4.60 24576.8 14983.0 18360.9 10250.6 5.20 20780.7 13034.7 17292.8 9569.6 3
i 6.00 15136.2 9932.8 16130.7 4796.5 6.60 13007.4 8669.0 15453.2 8334.5 7.00 13457.1 8946.2 15191.4 8140.5 7.20 12549.7 8635.0 15035.5 8033.3 7.60 8612.7 7048.7 14812.7 7875.8 8.40 8768.9 6720.8 14305.4 7558.6 9.60 10646.5 7248.1 13511.5 7115.1 10.8 10223.2 6813.9 13001.6 6854.6 11.0 10049.9 6722.2 14042.7 7411.0 12.4 9682.4 6478.1 13506.1 7165.4 13.6 8608.3 5941.8 12908.0 6879.0 O* 17.8 22.6 23.6 25.2 6331.2 4397.8 3826.6 2456.6 1651.5 4768.0 3668.2 3489.4 2768.4 2042.8 10430.1 7464.3 7443.9 5616.0 4400.2 5650.7 4167.3 3919.4 2728.4 1833.1 27.0 1855.1 27.4 1506.9 1870.3 4584.4 28.2 1254.4 1565.3 3733.9 1454.0 29.0 952.2 1194.7 4399.7 1569.0 30.0 714.5 901.4 3365.2 1106.3 32.6 452.0 572.9 265.4 74.2 34.0 365.1 465.1 0.0 0.0 35.5 0.0 0.0 0.0 0.0 i
l O .
l i
l 6.2-40 NOVEMBER, 1986 I WAPWR-CS
, 1322e:1d
s TABLE 6.2-9 2
APWR/3 FT PUMP SUCTION SPLIT BREAK MIN SI BLOWDOWN MASS AND ENERGY RELEASES l
i 7IME BREAK PATH NO.1 FLOW THOUSAND
$ECONOS LBM/SEC B7U/SEC O.000 O.O O.O 100 46833.5 26403.9
.500 43313.5 25019.2 4.10 39998.2 235f4.1 1.50 38209.T 23083.1 2.70 39480.8 23007.7 3.40 38432.8 22304.7 4.20 34821.2 20258.0 5.40 26833.8 15688.4 .
7.40 22729.9 13261.2
' 7.40 23139.9 13538.3 i '
8.60 20373.I 12052.3 ,
- . 9.00 18429.6 11074.8 ,
! 10.2 17125.2 10316.4 12.0 17050.3 100 t 'J . 7 14.4 16238.5 0859.4 15.2 18t30.5 9461.2 18.0 14519.7 8710.2 27.2 11292.2 7020.1 0 29.0 35.6 38.0 39.8 10264.1 5279.0 8956.2 3476.0 6510.6 4718.6 3450.4 2888.4 40.4 4051.8 2905.4 41.8 4155.2 2497.8 42.4 3655.7 2201.4 43.0 2220.9 1718.7 44.0 2342.0 1804.2 45.2 3688.4 1798.8 45.8 3980.3 1779.2 46.5 3480.3 1475.3 47.8 2337.1 1117.6 49.2 2506.0 '973.0 49.6 1824.6 809.0 50.0 2251.8 877.2 r
1 t
6.2-41 NOVEMBER, 1986 WAPWR-CS 1322e:1d l
TABLE 6.2-10 O
APWR/ DOUBLE ENDED PUMP COLD LEG MIN SI BLOWDOWNMASSANDENERGYRELEfSES TIME 8REAK PATH NO.1 FLOW 8REAK PATH N0.2 FLOW THOUSAND THOUSAND SECONDS LBM/SEC STUISEC L8M/SEC STU/SEC O 0.000 101
.201 400 0.0 28494.7 26452.1 25504.5 0.0 15999.5 14866.4 14358.3 0.0 54482.3 52529.1 60237.9 0.0 32730.5 31669.2 34586.1 600 25270.4 14299.1 62228.2 35243.4 1.00 23838.6 13698.3 61094.8 34446.0 1.40 22670.2 13184.2 58497.8 33023.9 1.80 21770.9 12719.8 53778.5 30457.4 2.70 19644.0 11417.4 42445.3 24277.3 3.00 17759.0 10292.4 39389.4 22571.6 3.70 15434.0 8877.9 33878.2 19353.9 4.20 14446.1 8258.1 29027.7 16393.0 5.60 12504.4 7060.7 27010.5 14809.7 6.00 12057.6 6798.7 26803.2 14567.1 6.40 12338.6 6958.7 27663.3 14952.6 7.20 11366.4 6434.3 26000.2 13851.1 8.20 10482.9 6004.9 23286.7 12280.4 9.00 9141.1 5762.1 21444.4 11283.4 9.80 6020.2 5097.2 19596.0 10330.7 11.2 5460.1 4696.5 18417.6 9875.4 O 14.2 15.6 18.4 4451.1 4117.8 3083.7 3715.0 3407.4 3146.2 14211.9 8510.1 5364.0 4446.4 8464.8 6237.0 4780.2 3731.8 19.8 201T.6 2471.7 22.0 1333.8 1669.0 5669.1 2469.7 2?. 2 1005.3 1264.7 5400.7 2072.1 23.8 819.6 1034.8 5387.4 1936.4 2(.4 672.7 853.9 3258.7 1136.1 24.8 561.6 714.3 12191.6 4040.9 25.4 473.6 605.7 12262.1 4033.0 25.8 340.4 434.0 2554.0 811.8 26.6 153.1 196.9 1180.8 356.1 27.0 107.6 138.4 3452.0 939.9 27.6 28.9 37.5 0.0 0.0 28.2 0.0 0.0 0.0 0.0 O
O O
6.2-42 NOVEMBER, 1986 WAPWR-CS 4322e:1d
1 i
TABLE 6.2-11 APWR/ DOUBLE ENDED HOT LEG MIN SI BLOWDOWN MASS AND ENERGY RELEASES i
I BREAK PATH NO.1 FLOW BREAK PATH NO.2 FLOW 71ME 7HOUSAND fHOUSHC 57U/SEC L8M/SEC BTU /SEC SEC0485 LBM/SEC 0.0 0.0 0.0 0.0 O.000 28460,1 30170.9 19748.6
.500 42972.3 26158.0 17070.5
.200 36853.8 24559.1 13571.3 36160.9 24281.3 21460.8
.500 23565.7 18224.8 10775.2 f.10 34941.5 18284.6 10272.5 1.70 34227.2 23214.7 10338.7 3t363.5 21695.9 19235.0 2.60 19599.5 19435.7 10222.5 3.50 26423.5 19358.8 10128.2 4.20 23725.4 16767.4 9857.6 21559.3 14887.7 18893.1 5.00 13322.3 19245.8 18426.4 9612.6 5.40 11555.9 14445.4 7724.5 7.80 17584.0 13062.9 706f.O 8.60 16958.3 11059.4 6571.7 14973.0 f0016.7 12100.3 9.40 10493.9 19495.9 6247.3 10.0 16112.7 10342.2 5618.6 11.2 15274.0 9999.0 5320.6 13418.5 9074.3 9782.1 11.8 9141.8 8601.3 4812.5 13.0 13802.9 7878.2 4345.9 l
f4.2 11814.4 8057.0 3876.2 11739.4 7837.3 6917.2 15.6 7076.2 6310.0 3584.1 16.6 10349.3 5566.1 3238.3 18.0 9764.7 6755.5 2942.4 7888.0 5892.3 4914.6 19.4 4745.0 5359.0 4025.2 2568.7 20.8 4174.2 2917.0 2029.9 22.8 4099.8 2361.6 1757.6 24.6 2673.7 3068.5 f450.4 1718.0 2153.1 1347.5 j 26.6 1D93.8 792.5 971.3 i 28.8 1293.8 620.0 766.9 32.0 996.7 543.5 O.0 e66.9 370.6 0.C 35.0 504.8 0.0 0.0 40.2 1021.7 487.6 607.5 41.8 838.4 357.4 757.8 1989.8 462.7 623.6 45.0 524.0 249.0 309.7 45.8 1332.2 254.1 315.5 50.0 1939.4 634.1 l
-]
6.2-43 NOVEMBER, 1986 WAPWR-CS 4322e:1d
TABLE 6.2-12 APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MAX SI REFLOOD MASS AND ENERGY RELEASES TIME OREAK PATH NO.t FLOW BREAK PATH NO.2 FLOW 1HOUSAND THOUSAND L8M/SEC Blu/SEC LBM/5EC 81U/SEC 5FC0405 0.0 0.0 s
38.6 0.0 0.0
) .O .O .O .O 32.3 y 33.0 70.9 83.5 .O .O
.O i
38.7 248.7 293.6 .O 39.0 267 7 316.1 809.1 130.0 512.8 611.0 6575.5 1385.0 40.1 1385.3 4f.9 50f.5 597.5 6524.4 G38.1 831.5 6272.8 1162.9 42.t 6165.1 1962.2 42.6 669.2 797.5 687.3 818.5 6205.5 1151.3 43.f 1125.5 45.1 663.6 790.0 6054.0 i
705.7 839.9 5895.0 1125.4 46.1 1825.1 47.t 675.4 803.7 5799.4 696.0 828.2 5817.3 1112.7 47.t 1089.7 49.1 678.6 807.2 5671.0 627.9 745.2 5226.2 9020.0 56.t 5007.9 986.1 60.1 602.5 716.1 566.7- 672.7 4674.9 934.5 67.t 908.7 7t.t 549.8 651.3 4507.6 544.6 646.3 4468.0 902.6 72.1 626.7 4314.3 878.4 76.1 528.3 866.5 78.t 520.6 687.4 4240.9 i 505.8 599.8 4101.1 844.5 82.1 3873.2 807.6 i
89.1 482.f 571.4 93.1 469.9 556.8 3754.4 788.3 447.7 530.3 3537.2 753.0 101.1 474.8 2862.4 674.3 103.1 409.0 104.5 603.6 716.9 267.9 318.0 i
105.1 613.1 728.4 272.7 323.8 107.1 604.5 722.9 270.5 321.0 555.8 659.6 244.2 289.5 915.9 233.4 276.7 121.1 533.5 632.0 210.5 249.6 484.4 574.2 147.t 479.0 567.7 208.3 246.7 55t.1 545.5 199.9 236.7 167.5 460.4 6.2-44 NOVEMBER,1986 WAPWR-CS 4322e:1d
TABLE 6.2-13 O .
APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI REFLOOD MASS AND ENERGY RELEASES O
TIME BREAK PA7H N0.1 FLOW SAEAK PATH N0.2 FLOW THOU$AND THOUSAND SECONDS LBM/SEC STU/SEC LBM/SEC STU/SEC 31.6 0.0 0.0 0.0 0.0 O 32.3 33.0 39.1 40.1
.0 69.1 252.5 709.1
.0 81.4 298.2 844.5
.0
.0
.0 6231.1
.0
.0
.0 1191.7 41.1 690.6 822.6 6216.9 1158.7 42.1 660.2 809.9 6150.9 1148.3 42.7 457.0 544.0 6321.6 1372.2 43.1 668.0 795.4 6074.7 1135.6 44.1 563.6 672.2 5869.5 1156.3 45.1 420.9 500,8 6129.7 1361.7 46.1 689.7 820.6 5760.8 1109.6 49.1 662.5 787.8 5532.7 1073.7 51.1 646.5 768.5 5395.9 1052.2 55.1 617.8 734.0 5144.7 1012.9 59.1 592.8 704.1 4919.7 978.0 63.1 570.8 677.7 4716.9 946.6 67.1 551.2 654.1 4532.8 918.3 75.1 517.0 613.1 4207.4 867.8 83.1 487.1 577.4 3919.5 821.9 85.1 480.3 569.2 3852.4 811.1 O 89.3 97.1 101.1 103.1 466.7 444.0 433.4 755.6 553.0 525.9 513.2 902.2 3718.7 3492.8 3386.5 360.7 789.6 753.1 735.9 429.6 104.8 896.0 1072.0 507.1 606.5 107.2 727.2 869.1 457.6 546.6 109.2 767.8 916.9 403.9 481.7 111.2 557.2 661.4 250.5 297.1 113.2 522.9 620.2 233.6 276.9 125.2 457.9 542.5 202.9 240.2 135.2 427.1 505.8 188.6 223.2 139.2 417.7 494.5 184.2 218.0 171.2 368.8 436.3 161.7 191.1 176.9 362.9 429.2 158.9 187.8 O
6.2-45 NOVEMBER, 1985 WAPWR-CS j T322e:1d
. - - _ .__ _ _ - _. _~_ _ ~. _-
l TABLE 6.2-14 APWR/0.6 DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI REFLOOD MASS AND ENERGY RELEASES O
TIME SREAK PATH No.1 FLOW SAEAK PATH NO.2 FLOW THOU$AND THOUSAND LBM/3EC BTU /SEC LBM/SEC BTU /SEC SECOND$ 0.0 35.5 0.0 0.0 0.0 36.2 .0 .0 .0 .0 i
36.9 66.9 78.8 .0 .0 38.9 151.5 178.6 .0 .0 42.9 249.1 294.0 .0 .0 575.7 686.6 5967.8 1139.7 44.0 5999.3 1172.6 45.0 587.8 701.1 374.1 684.8 5926.0 1162.2 46.0 5920.9 1133.7 46.8 710.3 845.3 687.7 818.5 5873.6 1141.7 47.1 5794.0 1129.4 48.1 676.9 805.5
49.1 687.9 818.3 5741.6 1105.4 50.1 678.6 807.2 5665.4 1093.6 645.4 767.3 5386.9 1049.8 54.1 5136.9 1010.7 58.1 616.7 732.8 62.1 591.7 702.8 4912.4 975.8 63.1 586.0 695.9 4859.8 967.6 67.1 564.6 670.2 4662.1 937.0 71.1 545.5 647.3 4482.2 909.3 l
75.1 528.3 626.7 4317.6 884.0 83.1 497.4 589.7 4019.7 837.4 91.1 470.1 557.1 3753.3 794.6 95.1 457.8 542.4 3631.7 774.9
- 103.1 435.6 515.9 3409.4 739.0 105.1 454.7 538.1 1041.1 316.3 107.2 1001.3 1199.0 541.2 647.9 107.9 944.2 1130.2 522.9 625.7 111.2 693.3 828.4 449.2 536.5 113.2 586.2 696.2 264.9 314.3 115.2 525.6 623.4 234.8 278.4 117.2 509.7 604.4 227.2 269.2 135.2 431.8 511.3 190.6 225.5 145.2 409.0 484.2 180.1 213.0 374.9 443.5 164.3 194.2 167.2 187.0 179.3 361.7 427.7 158.2 0
6.2-46 NOVEMBER, 1986 WAPWR-CS 4322e:1d i
_ _ _ ~ _ _ . _ . . , . . _ _ . . _ _ _ _ . _ . . . _ _ . _ _ . _ _ _ , . , , _ . , _ , . _ _ , _ . _ . . . . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _
I l
TABLE 6.2-15 O
v i
APWR/ DOUBLE ENDED COLD LEG MIN SI REFLOOD MASS AND ENERGY RELEASES O TIP.E BREAK PATH NO.1 FLOW BREAK PATH NO.2 FLOW THOUSAND THOUSAND STU/SEC LBM/SEC 57U/SEC SECONDS LBM/SEC 0.0 0.0 0.0 0.0 28.2 .0 0 0 28.9 0 0 66.9 78.8 .0 29.6 159.9 0 0 31.2 135.6 .0 0 35.7 246.2 2M.7 1359.3 313.9 371.0 8194.6 36.7 368.6 8084.7 1347.5 37.7 311.9 7804.8 1311.7 39.7 '307.0 362.8 1294.6 304.8 360.2 7671.3 40.7 355.2 7418.5 1262.0 42.7 300.6 7183.9 1231.6 44.7 296.8 350.7 1203.3 293.4 346.6 4966.0 i 46.7 342.9 6763.2 1176.9 48.7 290.2 1174.4 289.9 342.5 6743.7 48.9 336.3 6396.2 1129.0 52.7 284.7 1107.2 282.2 333.4 6229.3 54.7 328.2 5923.5 1067.2 58.7 277.9 1031.2 274.1 323.8 5649.1 62.7 319.9 5400.8 998.6 66.7 270.8 968.9 267.9 316.4 5174.4 70.7 313.4 4966.7 941.7 74.7 265.4 916.5 263.1 310.7 4774.9 78.7 4597.2 893.3 82.7 261.0 308.3 871.8 259.2 306.1 4432.1 4
86.7 1356.6 451.8 87.7 319.4 377.6 444.7 321.0 379.4 1300.2 91.7 340.8 418.3 341.0 93.7 288.5 410.5 339.6 97.7 287.3 339.4 334.0 382.2 333.1 107.7 282.7 327.9 278.6 329.0 358.5 119.7 338.2 323.6 135.7 274.2 323.9 269.9 318.7 323.5 320.2 153.7 295.3 312.0 171.7 263.2 310.8 296.4 248.9 293.8 251.4 219.7 284.4 245.7 289.6 252.2 240.9 O
O O
A 6.2-47 NOVEMBER, 1986 k3
. ._ _ .. .. _ _ . - _ . _ _ _ . _ _ . __ _. . . . . _ ..__m.. __
r i
TABLE 6.2-16 1
APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MAX SI POST-REFLOOD MASS AND ENERGY RELEASES BRE AK PATH NO.2 FLOW 11pst BREAK PATH 940.1 FLOW THOU5AldO THOUSAND STU/Stc 810/5tc LBM/SEC SECONOS LBM/Stc 260.3 121.5 300.2
, O 167.5 177.5 182.5 187.5 248.9 24% 1 243.2 241.6 295.6 293.3 298.3 288.9 268.6 262.3 262.8 263.6 119.7 118.8 117.8 117.0 192.5 239.6 264.1 116.0 197.5 237.9 296.9 115.2 284.6 264.9 202.5 236.0 266.3 193.6 212.5 232.4 280.2 191.9 276.4 267.3 222.5 229.2 268.6 110.3 225.8 272.3 109.6 232.5 270.9 269.4 237.5 224.0 271.9 106.7 257.5 217.6 262.4 106.1 260.3 272.7 262.5 215.9 256.5 274.1 104.7 272.5 212.7 276.8 102.3 206.5 249.0 100.0 292.5 200.4 249.7 279.6 312.5 24f.7 279.6 100.0 977.5 200.4 345.4 126.2 91.1 109.7 129.3 977.6 108.5 345.6 1017.5 90.2 106.6 346.0 140.0 8097.5 SR.6 346.6 145.1 1177.5 87.1 104.8 149.3 103.0 347.4 1257.5 85.6 108.2 348.4 152.5 1337.5 84.1 350.5 159.1 81.2 97.7 158.0 1497.5 97.6 350.6 1507.5 81.1 96.9 351.0 161.2 1547.5 80.6 351.8 161.4 79.6 95.7 163.2 1627.5 93.3 353.5 1787.5 77.5 353.5 163.2 77.5 93.3 30.9 2055.0 91.9 350.8 2055.9 79.9 61.4 377.3 33.2 9999.0 53.3 385.1 33.9 9999.1 45.5 52.4 33.9 45.5 52.4 385.t 35.8 10000.0 27.3 406.9 100000,0 23.7 419.3 36.9 11.4 13.t 1000000.0 I
l
. O 6.2-48 NOVEMBER, 1985 h,
I l
I TABLE 6.2-17 APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI POST-REFLOOD MASS AND ENERGY RELEASES O
SAEAK PATH N0.1 FLW SAEAK PATH N0.2 FL W T1HE THOU$AND THOUSAND BTU /SEC LSM/SEC STU/$EC SECOND$ LBM/$EC 102.7 179.7 216.9 170.8 i
O 176.9 216.9 286.9 326.9 169.3 153.9 145.9 204.4 185.7 176.1 175.3 172.0 174.0 175.6 175.4 94.7 82.9 77.4 76.7 331.9 145.2 175.8 75.5 341.9 143.4 -173.1 139.7 168.6 176.7 73.2 361.9 167.9 176.6 72.5 366.9 139.1 71.5 137.3 165.8 177.1 376.9 165.0 177.1 70.9 381.9 136.7 68.3 132.8 160.4 177.9 606.9 157.0 178.4 66.4 426.9 130.1 65.8 129.7 156.5 178.3 631.9 154.1 178.7 64.5 446.9 127.7 178.6 64.0 '
651.9 127.3 153.6 61.1 123.3 144.8 179.2 686.9 147.9 179.1 60.3 696.9 122.5 56.6 118.1 142.6 179.4 546.9 141.9 179.7 56.4 551.9 117.5 54.1 115.1 138.9 179.7 566.9 137.2 179.5 52.7 O 611.9 616.9 621.9 636.9 113.7 113.6 98.3 97.7 137.1 118.7 118.0 114.3 179.3 194.3 194.0 193.1 52.3 56.0 55.1 51.3 716.9 94.7 192.9 38.5 796.9 91.8 110.8 109.4 192.8 53.8 836.9 90.6 193.5 87.3 996.9 86.2 104.1 85.8 103.6 193.6 92.0 1016.9 99.8 194.6 113.1 1176.9 82.7 198.5 128.6 1496.9 76.9 92.8 92.4 198.7 127.5 1516.9 76.6 200.3 135.0 1676.9 74.5 90.0 137.6 70.5 85.1 203.9 1996.9 i
84.4 204.5 137.5 l
l 2076.9 69.9 l
)
O O
6.2-49 NOVEMBER, 1986 WAPWR-CS ,
T322e:Id
I TABLE 6.2-18 APWR/0.6 DOUBl.E ENDED PUMP SUCTION GUILLOTINE MIN SI POST-REFLOOD MASS AND ENERGY RELEASES
, 3 BREAK PATH No.1 FLOW BREAK PATH No.2 FLOW TIME THOUSAND THOUSAND LBM/SEC BTU /SEC LBM/5EC BTU /5EC SECONDS 218.5 130.4 95.0 179.4 180.1 113.4 63.8 329.4 149.4 181.3 46.2 139.6 169.3 106.1 469.4 0 604.4 609.4 799.4 859.4 136.3 98.8 91.7 90.0 165.3 119.9 111.3 109.2 98.8 135.9 134.2 134.1 146.8 34.6 47.5 95.3 97.8 114.2 914.4 88.5 107.3 117.7 87.0 105.5 149.7 969.4 104.4 159.0 128.7 1004.4 86.0 157.6 126.9 1034.4 85.4 103.7 137.6 84.8 102.8 166.6 1069.4 102.0 164.8 135.4
, 1104.4 84.1 169.9 141.4 1109.4 84.0 101.9 139.2 83.3 101.1 168.0 1144.4 100.9 172.9 145.0 1149.4 83.2 171.0 142.7 1184.4 82.6 100.1 148.5 82.5 100.0 175.9 1189.4 99.1 178.6 151.7 1229.4 81.7 176.0 148.7 1269.4 81.0 98.2 154.3 80.9 98.1 180.8 1274.4 97.2 178.1 151.1 l
1314.4 80.1 182.7 156.5 80.1 97.1 O 1319.4 1359.4 1364.4 1404.4 79.3 79.2 78.5 78.4 96.2 96.1 95.2 95.1 179.8 184.3 181.2 185.6 153.1 158.4 154.8 159.9 1409.4 92.2 185.4 159.7 l 1559.4 76.0 190.2 165.3 1594.4 75.6 91.7 161.1 75.2 91.2 186.6 1624.4 90.8 191.0 166.3 1654.4 74.8 187.5 162.2 1679.4 74.5 90.4 167.0 73.9 89.6 191.6 1729.4 88.8 188.9 163.9 1784.4 73.2 192.0 167.5 1869.4 72.1 87.5 O
I s
O 6.2-50 NOVEMBER, 1986 WAPWR-CS 4322e:1d
,=
4 i
I
' TABLE 6.2-19 J
l APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI j -t I -
EMERcv sALAnct 621.86 2081.56
.00 31.60 31.60 174.86 i
TIM (SECONDS)
ENERGT fMILLION STU) '
1328.14 1328.14 1328.14 1328.14 1328.14 l INITIAL EMEI.GT IN RCS,ACC,$ GEN 1328.14
)
0.00 0.00 0.00 2.71 13.45 48.68 1 CED EmotGY PUMPED INJECTION 0.00 10.19 13.19 29.57 75.05 '87.66 ,
DECAY MEAT '
( --
0.00 -77.'.0 -77.40 -77.40 -68.79 -59.88 e seCAT FROM SECOseDART 0.00 6 7.21 -67.21 -45.12 19.71 176. 4 TOTAL AeDED 1260.92 1260.92 1283.02 1347.85 1504.60 l *** W TA AVAILAsLE ***- 1328.14 i
18.18 18.59 43.93 43.93~ 43.93 f DISTaleUTION REACTea C00LAsir 411.84 a
l 92.14 83.21 ~32.79 31.57 0.00 0.00 ACCasti.oToe 7.50 37.79 20.15 20.15 7.50 7.50 Coat *. Totes 225.41 225.41 -177.50 175. 4 155.15 PaIMany stETAL 242.32 162.64 151.34 151.34 131.78 128.06l .90.92 SECONDARY peET E 348.19 348.17 295.52 295.15 211.87 STEAM GDIEAAT0s 381.39 l' 8 4 .48 P*S.48 637.81 650.11 509.37 ~
TOTAL CONTENTS 132t.14 ii 414.46 573.49 680.00 974.91 EFFL'JDET SAEAst FLOW 0.00 414.4
$ 0.00 0.00 0.00 ,
i l
ECCS SPILL O.00 0.00 0.00
l 414.4 414. 4 573.49 680.00 474.97 TGTAL EFFLUOff _
0.00
~
1260.93 1260.93 1261.30 1330.11 1484.34
- 70TAL a4CouM77.st *** 1328.14 6.2-51 NOVEMSER, 1986 WAPWR-CS i 4322e:1d .
, . s -
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, 9
, 1 0 4 2 0 8 9 81 9 0 5 6 1 2 3 3 0 3 4 R 0 ,r 1 6 4 8 2 2 0 1 7 3 9 4 4 0 4 9 E t
7 7 9 5 3 6 0 5 5 47 3 5 7 0 1 2 B
- Q 0 6 5 4 2 2 7 M 9 7 7 4 5 4 9 4 1 3 9 9 2 E 9- 3 3 s - 9 2 2 1 1 2 V 9 1
_ O N
9 4 0 6 8 7 9 9 0 3 0 2 4 8 4 0 4 9 0 1 5 2 8 8 2 0 9 0 7 2 1 5 0 9 8
. t. .
2 9 8 9 4 3 5 0 5 7 79 3 9 1 0 1 2 5 7 8 1 0 0 9 s , E 2 7 8 5 -0 32 9 4 1 4 9 1 9 0 2 1
1 1 1 1 1 2
0 4 9 9 2 6 2 9 0 8 14 73 0 9 7 0 7 5 5 1 9 3 6 8 9 2 0 7 3 8 9 0 9 9 2 8 5 8 t 0 0 6 0 7 9 8 8 1 9 0 8 27 9 8 2 3 01 S 8 0 4 2 1 7 7 2 9 3 - 4 1 1 2 5 8 9 91 1 1 I
S _
6 4 6 6 0 0 6 9 4 0 8 0 0 2 9 0 8 7 X 4 1 0 4 4 0 2 2 0 5 7 2 0 8 7 0 7 9
__ A .
M 7 8 9 0 7 3 4 6 2 7 7 1 4 8 3 0 3 2 6 2 1 7 4 6 4 3 7 3 9 8 7 7 8
, E 1 3 - - 2 1 1 2 6 S 6 21 f
N 9 I
T O 0 4 3 91 0 1 2 9 9 5 9 4 9 8 6 0 6 3 L 5 1 0 4 2 9 5 7 1 4 3 9 4 4 0 4 9 L .
8 2 0 5 9 8 6 4 0 4 10 I 1 ) 8 0 01 7 77 8 06 1 8 2 2 5 4 4 1 6 U 3 UT 2 - - 2 2 1 3 8 4 4 2 G 3 9 9
S 1 E
0 N C N 2 2 O N O 8 5 1 4 9 8 e 0 6 3 5 e I A0 I 4 0 91 0 1 2 9 2 4 3 1 4 4 0 4 9 -
2 T L6 L 1 0 4 2 9 1 1
. . 2 C A L .
8 6 4 0 4 10 U D0 I 8 0 01 7 7 78 0 8 3 0 5 8 0
6 3 NI 2 9 1 9 2 2 6 4 14 1 4 29 6
- S Y 3 - - 2 2 3 8 4 E G 1 1 l P R Y b M E O A O N R 4 4 9 2 4 9 4 0 0 0 4 T, P E0 E 4 0 0 0 0 4 8 7 3 4 3 1 0 0 0 1 0 N 1 0 0 0 0 1 1 x 7 D E 8
O O O O 9 1 2 7 2 2 9 8 O O O 9 E 2 1 9 3 4 4 41 2 3 3 2 2 3 D 3 3 4 2 1 1 N 1 1 E
E L Y s R T A O N N D L R D E O N T
/
R
)
S G I T
O C
- N A L T A O S A EI A N T T T
N E
W D 5 C E L R E U E S D O R D T I W L L E P .NO C J T E O O E E E T O LI F L A C C N A s t 0 E C T R e V N N I
'ES I E O 0 L A O S E O L F B A. H R A S A R L T Y A C C F P E A
( S D F O ds S R DA N N L E S T C E Y L L T e I L N E R P A T A I C u E M O A CA A S A U
- e I t C A T A A C R I E T E C T O t
i N u E E O VT E C O R E T O R C O C T I P D H A R A C P S S T B E T C A
_- L L Y A G T A O N T R Y O G T O '
/ E N R I T
T E E T N U
- L E
- B N
- A
- I E
- R U
- I O T L T E I D S F D I F
- N D E I A Sd C1 R e W2 P2 A3 W4 i
O ~
~
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+ ;
TABLE 6.2-21 s
APWR/0.6 D0'JBLE ENDED PUMP SUCTION GUILLOTINE MIN SI
' ENERGY BALANCE TIME (SEC0'tDS) .00 35.50 35.50 179.31 609.40 1874.40 ENERGY (MILLION STU)
^
INITIAL ENERGY IN RCS,ACC,5 GEN 1328.14 1328.14 1328.14 1328.14 1328.14 1328.14 ADDED ENERGY PUMPED INJ ECTION -0.00 0.00 0.00 2.68 10.84 34.81 DECAT HEAT 0.00 11.04 11.04 30.07 74.10 173.72 HEAT FROM SECONDARY 0.00 -76.35 ~76.35 -76.35 -68.02 -58.82 TOTAL ADDED 0.00 -65.31 -65.31 -43.59 16.91 149.71 i
- TOTAL. AVAILKAE *** 1328.14 1262.83 1262.83 1284.55 1345.05 1477.85 DISTRIBUTION REACTOR COOLANT 411.84 18.94 18.98 43.77 43.77 43.77 ACCUMULATOR 92.14 81.85 81.81 31.57 0.00 0.00 CORE STORED 37.79 20.03 20.03 7.50 7.50 7.50
) PRIMARY METAL 242.32 224.82 224.82 178.41 175.85 155.20 SECONDARY METAL 162.64 152.74 152.74 . 133.40 128.72 90.96 STEAM GENERATOR 381.39 352.14 3'52.14 ' 299.63 296.67 211.95 TOTAL CONTENTS 1328.14 850.52 850.52 694.28 652.51 509.39 r
BREAK FLOW C.00 412.32 412.32 568.61 670.79 964.91 EFFLUENT ECCS SPILL 0.00 0.00 0.00 0.00 0.00 0.00 TOTAL EFFLUENT 0.00 ~412.32 412.32 568.61 670.79 %4.91
- TOTAL ACCOUNTABLE *** 1328.14 1262.84 1262.84 1262.89 1323.30 1474.29 NOVEMBER, 1986 WAPWR-CS 6.2-53 4322e:1d
l ~
O O O O O O i
4 I TABLE 6.2-22 1 APWR/ DOUBLE ENDE0 COLD LEG MIN SI I l
ENERGY BALANCE 1067.20 1702.20
.00 28.20 28.20 252.19 s
' TIME (SECONDS)
ENERGY (MILLION STU) 132E.14 1328.14 1328,14 1328.14 1328.14 1328.14 INITIAL ENERGY IN RCS,ACC,5 GEN f 0.00 0.00 4.24 19,68 31.72 PUMPED INJECTION O.00
! ADDED ENERGY 8.15 36.67 111.79 159.93 i DECAY HEAT 0.00 8.15
.l -76.72 -76.72 -76.72 -60.94 -59.20 NEAT FROM SECONDARY 0.00
-68.57 -35.82 70.53 132.45 TOTAL ADDED O.00 -68.57 f 1259.57 1259.57 1292.32 1398.67 1460.59
- TOTAL AVAILABLE *** 1328.14 11.97 42.46 42.46 42.46 REACTOR COOLANT 411.84 8.80 DISTRIBUTION 82.67 26.22 0.00 0.00 ACCUMULATOR 92.14 85.85 21.36 7.50 7.50 7.50 i
CORE STORED 37.79 21.36 i
226.46 177.08 167.93 155.00 l PRIMARY METAL 242.32 226.46 i
152.53 132.11 115.38 91.73 SECONDARY METAL 162.64 152.53 351.47 295.43 268.75 213.79 STEAM GENERATOR 381.39 351.47 i
846.46 480.00 602.03 510.49 1
' TOTAL CONTENTS 1328.1% 846.46 !
413.13 589.82 783.44 947.09 BREAK FLOW 0.00 413.13 EFFLUENT 0.00 0.00 0.00 0.00 ECCS SPILL 0.00 0.00 413.13 589.82 783.44 947.09 TOTAL EFFLUENT 0.00 413.13 1259.59 1270.61 1385.47 1457.58
- TOTAL ACCOUNTABLE
- 1328.14 1259.59 NOVEMBER, 1986 WAPWR-CS 6.2-54
'4322e:1d
TABLE 6.2-23 APWR/D0UBLE ENDED HOT LEG MIN SI O TIME (SECONDS)
ENERGf BALANCE
.00 50.00 50.00 ENEROf (MILLION STU) 1328.14 1328.14 1328.14 INITIAL ENERGY IN #C5.ACC.5 CEN O.00 0.00 0.00 ADDED ENERGf PUMPED INJECflON O.00 15.56 15.5R OECAV HEAT 0.00 -76.05 -76.05 HEAT FROM SECONDARY O.00 -89.29 ~6f.29 TOTAL ADDEO
- *** 1328.14 1266.55 1266.05 TOTAL AVAILABLE 411.84 53.06 56.23 0151RIBUTION REActon COOLANT ACCUMULATOR 82.14 67.19 84.02 37.79 11.63 18.63 CORE STORED PRIMARY METAL 242.32 218.85 281.85 162.64 145.99 145.99 SECONDARY METAL 381.39 334.57 334.57 STEAM GENERATOR 1328.14 824.28 824.28 TOTAL CONTENIS O.00 442.56 442.56 EFFLUENT 8REAK FLOW O.00 0.00 0.00 ECCS SPILL O.00 442.56 442.56 TOTAL EFFLUENT
- *** 1328.14 1266.84 1266.84 TOTAL ACCOUNTABLE 6.2-55 NOVEMBER, 1986 WAPWR-CS T322e:1d
1 l
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) TABLE 6.2-25 i .
l APWR/ DOUBLE ENDED PUMP SUCTION GUILLOTINE MIN SI
!l l INJECTION F1006ING EARRYOVER CORE DOWNCOMER FLOW TIME HEIGHT FRACTION TOTAL ACCUMULATOR SPILL ENTMALPT TEr RATE FRACTION HEIGHT FT FT (POUNDS MASS PER SECOND) 8TU/L8M SECONDS DEGREE F IN/SEC 0.00 .250 0.0 0.0 0.0 0.00 31.6 252.1 0.000 0.000 0.00 0.0 118.79 246.6 28.439 0.000 .65 1.51 .004 10894.1 10678.7 118.79 32.2 .000 1.03 1.57 .004 10831.5 10616.1 0.0 32.3 243.9 30.879 5.25 984 10523.8 10308.4 0.0 118.77 33.2 242.4 1.963 131 1.33 0.0 118.76
!' .213 1.40 6.95 437 10412.2 10196.8 118.75 33.6 243.0 3.332 9.08 .414 10277.4 10062.0 0.0 I
243.5 2.875 .315 1.50 118.74 34.1 2.685 443 1.63 12.97 402 10041.4 9826.0 0.0 118.68 35.1 244.9 2.00 27.69 .395 9235.3 9019.9 0.0 38.8 250.4 2.978 .649 .580 7411.9 7201.9 0.0 118.52 4
252.5 5.558 699 2.30 30.00 6994.9 0.0 118.49 41.1 722 2.50 30.00 .385 7204.9 i
42.7 254.1 4.899 .577 7175.8 6965.8 0.0 118.49 ,
i 43.1 254.5 5.249 724 2.55 30.00 6716.0 0.0 118.46 4.623 740 2.77 30.00 .362 6926.1 118.45 45.1 256.9 2.88 30.00 .576 6844.3 6634.1 0.0 46.1 258.1 4.956 747 6498.3 0.0 118.43 4.847 753 3.01 30.00 .573 6708.6 0.0 118.35
' 47.4 259.8 3.50 30.00 .566 6256.2 6045.5 52.7 267.1 4.526 766 5830.3 5619.3 0.0 118.27 4.254 776 4.01 30.00 .557 118.18 58.7 275.7 4.56 30.00 .548 5391.8 5180.3 0.0 i
66.1 286.1 3.984 788 4846.8 0.0 118.09 l
3.779 798 5.00 30.00 .540 5058.6 0.0 117.99 72.7 294.3 5.52 30.00 .531 4697.9 4485.6 i
81.1 293.6 3.597 801
.522 4395.8 4183.1 0.0 117.89 l
287.4 3.471 796 6.00 30.00 117.77 89.3 795 6.57 30.00 .513 4078.1 3865.0 0.0 1
99.1 284.7 3.324 .512 4018.1 3804.9 0.0 117.74 284.6 3.295 795 6.69 30.00 0.0 88.00
' 101.1 6.82 29.75 .646 209.1 0.0 i 103.1 284.4 5.012 760
.612 207.5 0.0 0.0 88.00 283.7 5.919 760 7.01 28.56 465.5 0.0 109.61 104.8 784 7.63 25.20 .588 676.7 111.2 283.9 3.714 24.56 .579 702.6 490.6 0.0 109.93 117.2 286.9 3.355 789 8.00 703.3 490.7 0.0 109.92 3.049 798 8.55 23.93 .573 0.0 109.80 127.2 293.5 23.62 .569 695.6 482.8
) 136.4 294.3 2.879 800 797 9.00 9.52 23.41 .567 683.0 469.9 0.0 109.61 147.2 291.7 2.751 .566 669.2 455.9 0.0 109.40 293.2 2.632 .800 10.00 23.30 437.6 0.0 109.11 J- 157.9 .802 10.57 23.26 .565 651.1 171.2 294.2 2.517 23.26 .565 643.3 429.8 0.0 108.99 i
176.9 293.0 2.484 .800 10.80 '
l l
1 j
1 6.2-57 NOVEMBER, 1986 i WAPWR-CS 4322e:1d ,
1 l
1 l l
i
)
l TABLE 6.2-26 SYSTEM PARAMETERS i
Design Plant model 4 loop, 12,792 ft core Core power 3899.5 MWt 1
Core inlet temperature 564.2*F l
i Steam pressure 1026 psi i
! Assumed initial containment 61.6 psia l I
back pressure O.
i l
l-l i
i O i.
1 O :
e i
lO r
l 6.2-58 NOVEMBER, 1986
! WAPWR-CS l 4322e:1d i
h
TABLE 6.2-27
. SPECTRUM OF SECONDARY SYSTEM PIPE RUPTURES O Caes 1 Full double-ended rupture at 102 percent power Case 2 Full double-ended rupture at 75 percent power
'O Case 3 Full double-ended rupture at 50 percent power Case 4 Full double-ended rupture at 25 percent power Case 5 Full double ended rupture at hot zero power
! Case 6 1.1 ft 2split at 102 percent power Case 7 1.1 ft 2split at 75 percent power Case 8 1.1 ft 2split at 50 percent power Case 9 1.1 ft 2split at 25 percent power i-2 Case 10 1.1 ft split at hot zero power l Case 11 Full double-ended rupture at hot' zero power MSIV failure Case 12 1.0 ft 2split at hot zero power MSIV failure l
i O
l O
WAPWR-CS 6.2-59 NOVEMBER, 1986 4322e:1d
.~. - . . + . . -
? -
i .
4 TABLE 6.2-28 1
SUMMARY
OF RESULTS FOR 9tSLB CONTAIMtENT ANALYSIS Time of Time of Time of Time of Time of Time of 71me of Time of Peak Peak Peak Peak H1-1 H1-2 Hi-3 Steam Time of Time of Containment Steam Temperature Temperature (5.75 (13.75 (24 Line Feedwater Fan Cooler Spray Generatoe Power Pressure Pressure (psig) (sec) (*F) (sec) psig) psig) psig) Isolation Isolation Initiation Initiation Dryout 5 Case Level Break 221.2 242 220. 2.58 -
102.0 8.0 8.0 75.58 172.2 226.0 1 102 DE 30.95 257.3 242 260. 3.52 -
118.0 7.5 8.0 75.52 188.2 268.0 2 75 DE 31.11 l
299.56 244 300. 2.47 -
126.0 7.5 8.0 75.47 196.2 318 3 50 DE 31.51 333.65 245 334, 2.42 -
136.0 7.5 8.0 75.42 206.2 338.
4 25 DE 32.1t 250 405. 2.39 148.0 7.5 8.0 75.39 218.2 410.
5 H7P DE ,
33.22 405.01 -
l 2 315 84. 10.43 29.32 71.7 36.32 17.5 83.43 141.9 240.
f G 102 1.1 ft s 28.81 229.06 I
- 259.97 312 83. 9.84 28.74 73.3 35.74 17.0 82.84 143.5 280.
7 75 1.9 ft s 29.18 i
9.44 74.8 35.39 16.5 82.44 145.0 308.0 8 50 1.1 ft#s 29.32 288.10 311 83. 28.39 1
1 I 82. 27.96 77.3 34.96 16.0 82.0 147.5 328 9 25 1.1 f t s 30.04 322.97 310 9.0 I
413.06 305 83. 9.5 30.3 98.0 37.3 16.5 82.5 16f.2 4f6.
10 H7P 1.0 ft a 30.60 '
\
2.37 -
121.2 7.5* 8.0 75.37 191.4 422.
l 11 HZP DE 32.34 413.48 245 415.
2 83. 9.45 30.3 92.3 37.3* 16.5 82.45 162.5 472.
12 HZP 1.0 ft s 29.56 464.42 305 l
NOVEIE8ER, 1986 6.2-60 yAPwe-CS j 4 322e:. td l
I TABLE 6.2-29 (SHEET 1 of 8)
CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6)
O 0.00
.50 1.00 0.000 11961.591 11518.946 0.000 14.253 13.736 1.50 11261.498 13.438 2.00 11022.528 13.160 2.50 10802.745 12.905 3.00 10600.657 12.669 O 3.50 4.00 4.50 10413.381 10239.330 10077.278 12.451 12.248 12.058 5.00 9926.370 11.881 5.50 9785.687 11.717 6.00 9656.537 11.565 6.50 9533.466 11.421 7.00 9417.830 11.285 7.50 9308.639 11.156
, 8.00 9204.744 11.034 8.50 2274.818 2.727 9.00 2265.259 2.716 9.50 2250.542 2.699 10.00 2235.632 2.681 10.50 2220.234 2.663 0 11.00 11.50 12.00 12.50 2204.218 2187.457 2169.869 2151.430 2.644 2.624 2.604 2.582 13.00 2132.168 2.559 13.50 2112.119 2.536 14.00 2091.379 2.511 14.50 2070.081 2.486 15.00 2048.356 2.460 15.50 2026.363 2.434 16.00 2004.180 2.408 16.50 1981.888 2.381 17.00 1959.535 2.355 17.50 1937.172 2.328 18.00 1914.858 2.302 18.50 1892.643 2.275 0 19.00 19.50 20.00 20.50 1870.581 1848.739 1827.165 1805.895 2.249 2.223 2.197 2.172 21.00 1785.062 2.147 21.50 1764.607 2.123 22.00 1744.599 2.099 O 22.50 23.00 23.50 1725.073 1706.051 1687.537 2.076 2.053 2.031 24.00 1669.566 2.009 24.50 1652.107 1.989 25.00 1635.155 1.968 25.50 1618.690 1.949 O 26.00 26.50 1602.688 1587.128 1.929 1.911 WAPWR-CS 6.2-61 NOVEMBER, 1986 1322e:1d
TABLE 6.2-29 (SHEET 2 Of 8)
O CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (lam /SEC) (BTU /SEC A 10E6) 27.00 1571.994 1.893
( 27.50 28.00 1557.192 1542.768 1.875 1.858 28.50 1528.705 1.841 29.00 1514.989 1.824 29.50 1501.742 1.808 30.00 1488.746 1.793 30.50 1476.054 1.778 l'
31.00 1463.594 1.763 31.50 1451.435 1.748 l
32.00 1439.556 1.734 32.50 1427.944 1.720 33.00 1416.604 1.706 33.50 1405.513 1.693 34.00 1394.678 1.680 34.50 1384.098 1.667 35.00 1373.753 1.655 35.50 1363.243 1.642 36.00 1353.407 1.630 i
' 36.50 1343.789 1.619 37.00 1334.388 1.607 37.50 1325.200 1.596 i
38.00 1316.223 1.585 38.50 1307.450 1.575 O 39.00 39.50 40.00 1298.875 1290.493 1282,299 1.564 1.554 1.544 i
40.50 1274.293 1.535 41.00 1266.464 1.525 41.50 1258.810 1.516 42.00 1251.328 1.507 42.50 1244.010 1.498 43.00 1236.952 1.490 43.50 1230.107 1.482 44.00 1223.441 1.474 44.50 1216.961 1.466 45.00 1210. 0t- 3 1.458 45.50 1204.485 1.451 46.00 1198.482 1.443
' 46.50 1192.605 1.436 47.00 1186.858 1.429 47.30 1181.223 1.423 l 48.00 1175.701 1.416 48.50 1170.279 1.409 49.00 1165.004 1.403 49.50 1159.796 1.397 50.00 1154.676 1.391
$0.50
.i i
O 51.00 51.50 52.00 1149.675 1144.738 1139.935 1135.171 1.385 1.379 1.373 1.367 l 52.50 1130.528 1.361 53.00 1125.919 1.356 53.50 1121.383 1.350 54.00 0 WAPWR-CS 54.50 1116.949 1112.561 6.2-62 1.345 1.340 NOVEMBER, 1996
, 4322e:1d
TABLE 6.2-29 (SHEET 3 of 8) t v
, CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (87U/SEC A 10E6)
O 55.00 55.50 56.00 1108.296 1104.051 1099.912 1.335 1.330 1.325 56.50 1095.799 1.320 57.00 1091.747 1.315 57.50 1087.762 1.310 58.00 1083.842 1.305 58.50 1079.988 1.300 59.00 1076.235 1.296 59.50 1072.538 1.291 60.00 1068.870 1.287 60.50 1065.260 1.283 1 61.00 1061.711 1.278 61.50 1058.219 1.274 62.00 1054.787 1.270 62.50 1051.408 1.266 i 63.00 1048.086 1.262 63.50 1044.815 1.258 64.00 1041.599 1.254 64.50 1038.430 1.250 65.00 1035.312 1.247 65.50 1032.239 1.243 66.00 1029.214 1.239 O 66.50 67.00 67.50 1026.277 1023.362 1020.445 1.236 1.232 1.229 68.00 1017.590 1.225 i
68.50 1014.774 1.222 69.00 1011.998 1.218 I
69.50 1009.263 1.215 70.00 10D6.563 1.212 70.50 1003.900 1.209 71.00 1001.273 1.205
- 71.50 998.680 1.202 i 72.00 996.123 1.199
[
72.50 993.597 1.196 73.00 991.104 1.193 73.50 988.647 1.190 74,00 986.217 1.187 O 74.[3 75.00 75.50 983.822 981.457 979.123 1.184 1.181 1.179 76.00 976.815 1.176 76.50 974.516 1.173 77.00 972.232 1.170
( 77.50 969.970 1.168 i 78.00 967.731 1.165 i 78.50 965.515 1.162 l 79.00 963.321 1.159 l 79.50 961.152 1.157
, 80.00 959.006 1.154 l 80.50 956.886 1.152 81.00 954.788 1.149 81.50 952.714 1.147 O. 82.00 82.50 950.661 948.633 1.144 1.142 WAPWR-CS 6.2-63 NOVEMBER, 1986 4322e:1d t
1 l
TABLE 6.2-29 (SHEET 4 Of 8)
CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) a 83.00 946.625 1.139 83.50 944.640 1.137 84.00 942.676 1.134 84.50 940.735 1.132 85.00 938.815 1.130 85.50 936.918 1.128 86.00 935.041 1.125 O 86.50 87.00 87.50 88.00 933.187 931.352 929.542 927.750 1.123 1.121 1.119 1.116 88.50 925.982 1.114 89.00 924.234 1.112 89.50 922.508 1.110
, 90.00 920.802 1.108 90.50 919.118 1.106 91.00 917.453 1.104 91.50 915.810 1.102 92.00 914.185 1.100 .
92.50 912.580 1.098 93.00 910.993 1.096
! 93.50 909.425 1.094 94.00 907.874 1.092 1 94.50 906.341 1.091 95.00 904.824 1.089
( .
95.50 903.323 1.087 i
96.00 901.838 1.085 96.50 900.369 1.083 97.00 898.914 1.082 i 97.50 897.473 1.080 98.00 896.042 1.078 98.50 894.627 1.076 99.00 893.226 1.075 99.50 891.838 1.073 100.00 890.465 1.071 101.00 888.422 1.069 102.00 885.795 1.066 103.00 883.266 1.063 104.00 880.743 1.060 105.00 878.262 1.057 106.00 875.826 1.054 107.00 873.438 1.051 108.00 871.092 1.048 109.00 868.785 1.045 110.00 866.520 1.042 111.00 864.336 1.040 112.00 862.204 1.037 0 113.00 114.00 115.00 860.118 858.071 856.053 1.035 1.032 1.030 116.00 854.062 1.027 117.00 852.098 1.025 118.00 850.159 1.023 119.00 848.240 1.020 O 120.00 121.00 846.346 844.477 1.018 1.016 WAPWR-CS 6.2-64 NOVEMBER, 1986 4322e:1d 1
TABLE 6.2-29 (SHEET 5 of 8)
O CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LSM/SEC) (BTU /SEC A 10E6)
O]
t 122.00 123.00 842.628 840.796 1.013 1.011 124.00 838.985 1.009 125.00 837.192 1.007 126.00 835.419 1.005 127.00 833.667 1.003 128.00 831.934 1.000 O 129.00 130.00 131.00 830.222 828.528 826.855
.998
.996
.994 132.00 825.200 .992 133.00 823.564 .990 134.00 821.947 .988 135.00 820.349 .986 136.00 818.770 .985 137.00 817.206 .983 3 , 138.00 815.661 .981 139.00 814.133 .979
- 140.00 812.621 .977 141.00 811.124 .975 i 142.00 809.640 .973 143.00 808.172 .972 144.00 806.719 .970 0 145.00 146.00 147.00 805.281 803.856 802.446
.968
.966
.965 148.00 801.049 .963 149.00 799.666 .961 150.00 798.296 .960 151.00 796.938 .958 152.00 795.592 .956 153.00 794.259 .955 154.00 792.935 .953 155.00 791.624 .952 156.00 790.321 .950 157.00 789.032 .949 158.00 787.753 .947 159.00 786.484 .945 160.00 785.224 .944 O 161.00 162.00 163.00 783.974 782.733 781.503
.942
.941
.939 164.00 780.284 .938 l
165.00 779.071 .936 166.00 777.870 .935 167.00 776.678 .934 i
168.00 775.493 .932 169.00 774.315 .931 170.00 773.147 929 171.00 771.986 .928 172.00 770.835 .926 173.00 769.687 .925 174.00 768.547 .924 175.00 767.417 .922
, \s 176.00 766.295 .921 177.00 765.177 .920 WAPWR-CS 6.2-65 NOVEMBER, 1986 4322e:1d
i l
TABLE 6.2-29 (SHEET 6 of 8)
CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW SREAK ENERGY (stc) (Lan/stc) (arv/ste x los6) 178.00 764.068 .918 179.00 762.965 .917 180.00 761.667 .916 181.00 760.775 .914 182.00 759.688 .913 183.00 758.609 .912 0 184.00 185.00 186.00 187.00 757.534 756.468 755.404 754.344
.910
.909
.908
.9 06 188.00 753.292 .905 189.00 752.242 .904 190.00 751.199 .903 191.00 750.158 .901 192.00 749.122 .900 193.00 748.095 .899 194.00 747.069 .598 195.00 746.050 .896 196.00 745.040 .895 197.00 744.030 .894 198.00 743.018 .893 199.00 742.000 .892
' 200.00 740.991 .890 201.00 739.726 .889 202.00 735.208 .883
, 203.00 733.700 .881 204.00 731.530 .879 205.00 729.732 .877 206.00 728.082 .875 207.00 726.574 .873
- 208.00 725.163 .871 i 209.00 723.839 .870 210.00 720.538 .865 211.00 706.047 .848 212.00 693.662 .833 213.00 677.512 .813
]
214.00 659.796 .792 215.00 639.514 .767 216.00 616.385 .739 217.00 590.552 .708 l
218.00 562.149 .673 219.00 531.454 .636 220.00 498.994 .597 221.00 465.215 .556 222.00 430.600 .514 223.00 395.834 472
, 224.00 362.158 431 225.00 330.258 .392 226.00 300.103 .356
- 227.00 271.848 .322 228.00 245.823 .291 229.00 222.105 .262 230.00 201.011 .237 l 231.00 183.186 .216 232.00 168.492 .198 I 233.00 155.123 .182 WAPWR-CS 6.2-66 NOVEMBER,1986 l 1322e
- 1d
. _ . , . - . . _ - . - . , . - . . - _ . ~ _ _ _ _ . _ .,. _ . -_ _.._ - .. . . . _ _ - __ -. . -
TABLE 6.2-29 (SHEET 7 of 8)
O CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIE BREAK FLOW SAEAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6)
O. 234.00 235.00 142.741 132.182
.167
.155 236.00 123.909 .145 237.00 115.738 .135 238.00 100.097 .126 239.00 101.289 .118 240.00 95.405 .111 O 241.00 242.00 243.00 90.398 86.134 82.431
.105
.300
.096 244.00 79.255 .092 245.00 76.822 .089 246.00 74.238 .086 247.00 72.175 .084 248.00 70.468 .082 249.00 69.033 .080 250.00 47.816 .079 251.00 66.783 .077 252.00 65.907 .076 253.00 65.170 .075 254.00 64.553 .075 255.00 64.042 .074 256.00 63.623 .074 l O 257.00 258.00 259.00 63.279 62.999 62.774
.073
.073
.073 260.00 62.597 .072
- 261.00 62.458 .072 262.00 62.351 .072 263.00 62.270 .072 264,00 62.208 .072 i
265.00 62.162 .072 266.00 62.129 .072 267.00 62.104 .072 268.00 62.087 .072 269.00 62.074 .072 270.00 62.066 .072 1 271.00 62.059 .072 272.00 62.055 .072 0 273.00 274.00 275.00 276.00 62.052 62.049 62.047 62.046
.072
.072
.072
.072 277.00 62.044 .072 278.00 62.043 .072 279.00 62.041 .072 0 280.00 281.00 282.00 283.00 62.040 62.039 62.037 62.036
.072
.072
.072
.072 284.00 62.035 .072 285.00 62.034 .072 286.00 62.032 .072 0 287.00 288.00 289.00 62.031 62.030 62.029
.072
.072
.072 WAPWR-CS 6.2-67 NOVEMBER, 1986 4322e:1d
i t
i TABLE 6.2-29 (SHEET 8 of 8)
I CASE 1: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY -
4 (SEC) (LBM/SEC) (BTU /SEC A 10E6) 290.00 62.027 .072 -
291.00 62.026 .072 292.00 62.025 .072 1
293.00 62.024 .072 j 294.00 62.023 .072 295.00 62.022 .072 I
296.00 62.021 .072 297.00 62.020 .072
! 298.00 62.019 .072 i 299.00 62.018 .072
- 300.00 62.017 .072 i
! r 180b.00 61.983 .072 l- 1802.00 62.058 .072 '
l 1804.00 62.339 .072 1806.00 $1.213 .059 1808.00 43.907 .051 O 1810.00 1812.00 1814.00 12.792
.394
.010
.015
.000
.000 1816.00 .000 .000 f
i 20$b.00 0. BOO 0.$b0 i
1 i
O O
O WAPWR-CS 6.2-68 NOVEMBER, 1986 4322e:1d
TABLE 6.2-30 (SHEET 1 of 9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER O TIME BREAK FLOW BREAK ENERG)
(SEC) (LBM/SEC) (BTU /SEC A 10E6) 0.00 0.000 0.000
.50 12533.863 14.915 1.00 11947.661 14.232 1.50 11599.021 13.829 0 2.00 2.50 3.00 11280.467 10988.042 10718.835 13.460 13.121 12.808 3.50 10470.764 12.519 4.00 10240.306 12.250 4.50 10025.823 11.999 11.765 O 5.00 5.50 6.00 9826.211 9642.451 9468.720 11.549 11.345 6.50 9306.331 11.154 7.00 9154.496 10.975 7.50 9011.963 10.808 8.00 2215.384 2.658
. 8.50 2184.651 2.621 i 9.00 2175.801 2.611 9.50 2159.295 2.591 10.00 2142.903 2.572 10.50 2126.334 2.552 11.00 2109.463 2.532 i 11.50 2092.253 2.512 12.00 2074.603 2.491 j
i 0 12.50 13.00 13.50 2056.547 2038.039 2019.087 2.470 2.448 2.425 14.00 1999.730 2.403 14.50 1980.070 2.379 15.00 1960.216 2.356 15.50 1940.220 2.332 16.00 1920.120 2.308 16.50 1899.943 2.284 17.00 1879.720 2.260 17.50 1859.487 2.236 18.00 1839.283 2.212 18.50 1819.146 2.188 2.164 19.00 1799.130 19.50 1779.270 2.140 O 20.00 20.50 21.00 1759.657 1740.194 1721.106 2.117 2.094 2.071 21.50 1702.342 2.049 i 22.00 1683.957 2.027 22.50 1665.982 2.005 l / 23.00 1648.435 1.984 23.50 1631.332 1.964 24.00 1614.673 1.944 24.50 1598.447 1.924 25.00 1582.642 1.905 25.50 1567.249 1.887 j
26.00 1552.249 1.869 i 26.50 1517.632 1.851 6.2-69 NOVEMBER, 1986 WAPWR-CS 1322e:1d
i TABLE 6.2-30 (SHEET 2 of 9)
- . CASE 2
- 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY O (SEC) (LBM/SEC) 1523.379 (BTU /SEC A 10E6) 1.834
- 27.00 27.50 1509.479 1.818 l
28.00 1495.915 1.801 28.50 1482.684 1.786 29.00 1469.724 1.770 29.50 1457.042 1.755 30.00 1444.669 1.740 30.50 1432.598 1.725 31.00 1420.799 1.711 2
l 31.50 1409.252 1.697 32.00 1397.976 1.684 i' 32.50 1386.963 1.670 33.00 1376.209 1.658
{
33.50 1365.280 1.644 1 34.00 1355.032 1.632 i 34.50 1345.001 1.620 t , 35.00 1335.202 1.608 i 35.50 1325.618 1.597 36.00 1316.247 1.585
! 36.50 1307.080 1.574 37.00 1298.118 1.564 37.50 1289.351 1.553 i 38.00 1280.778 1.543
! 38.50 1272.390 1.533
' 39.00 1264.187 1.523 0, 39.50 40.00 40.50 1256.162 1248.312 1240.630 1.513 1.504 1.494 j
41.00 1233.115 1.485
! 41.50 1225.763 1.476 ;
l 42.00 1218.565 1.468 I 42.50 1211.523 1.459 l 43.00 1204.626 1.451
! 43.50 1197.867 1.443 .
l 44.00 1191.242 1.435 44.50 1184.753 1.427
{
1 45.00 1178.391 1.419 4- 45.50 1172 157 1.412 i 46.00 1166.bt:6 1.404 l 46.50 1160.05' 1.397 O 47.00 47.50 48.00 1154.184 1148.425 1142.780 1.390 1.383 1.376 48.50 1137.244 1.370
- 49.00 1131.813 1.363 49.50 1126.486 1.357 i 50.00 1121.262 1.350 l 50.50 1116.137 1.344
! 51.00 1111.106 1.338 51.50 1106.172 1.332 l 52.00 1101.328 1.326 52.50 1096.576 1.321 r 53.00 1091.909 1.315
! 53.50 1067.329 1.309 I 54.00 1082.832 1.304 54.50 1078.416 1.299 l
! WAPWR-CS 6.2-70 NOVEMBER, 1986 1322e:1d ,
TABLE 6.2-30 (SHEET 3 of.9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FL0tt BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) 55.00 1074.081 1.293 55.50 1069.821 1.288
-56.00 1065.638 1.283 56.50 1061.529 1.278 57.00 1057.492 1.273 O 57.50 58.00 58.50 1053.525 1049.626 1045.796 1.269 1.264 1.259 1 59.00 1042.029 1.255 59.50 1038.317 1.250 60.00 1034.643 1.246 60.50 1031.016 1.241 O 61.00 61.50 62.00 1027.439 1023.911 1020.438 1.237 1.233 1.229 62.50 1017.014 1.224 63.00 1013.640 1.220 63.50 1010.315 1.216 64.00 1007.042 1.212 64.50 1003.817 1.208 65.00 1000.639 1.205 65.50 997.507 1.201 66.00 994.417 1.197 66.50 991.374 1.193 67.00 988.372 1.190
, 67.50 985.414 1.186 l 68.00 982.497 1.183 68.50 979.620 1.179 69.00 976.786 1.176 69.50 973.988 1.172 l 70.00 971.231 1.169 70.50 968.511 1.166 71.00 965.829 1.163 71.50 963.184 1.159 4
72.00 960.577 1.156 ;
72.50 958.006 1.153 i 73.00 955.472 1.150 i 73.50 952.972 1.147 i 74.00 950.510 1.144 i 74.50 948.081 1.141 4 75.00 945.687 1.138 75.50 943.327 1.135 l
1 76.00 940.999 1.132 I 76.50 938.705 1.130 l 77.00 936.441 1.127 1 77.50 934.210 1.124 78.00 932.009 1.122 78.50 929.838 1.119 l 79.00 927.696 1.116 i 79.50 925.581 1.114
! 80.00 923.494 1.111 80.50 921.433 1.109 81.00 919.400 1.106 l 81.50 917.392 1.104 l 82.00 915.407 1.102 1 82.50 913.448 1.099 NOVEMBER, 1986 l WAPWR-CS 6.2-71 1322e:1d
TABLE 6.2-30 (SHEET 4 of 9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY O (SEC) (LBM/SEC) 911.513 (BTU /SEC A 10E6) 1.097 83.00 83.50 909.600 1.094 84.00 907.710 1.092 84.50 905.842 1.090 0 85.00 85.50 86.00 903.997 902.174 900.373 1.088 1.085 1.083 86.50 898.591 1.081
-87.00 896.833 1.079 87.50 895.105 1.077 88.00 893.408 1.075 f 88.50 891.733 1.073
\
89.00 890.131 1.071 89.50 888.577 1.069 90.00 887.057 1.067 90.50 885.555 1.065 I 91.00 884.074 1.064 91.50 882.614 1.062 92.00 881.165 1.060 92.50 879.730 1.058 93.00 878.329 1.057 93.50 876.946 1.055 94.00 875.576 1.053 94.50 874.217 1.052 95.00 872.864 1.050 0' 95.50 96.00 96.50 871.518 870.181 868.870 1.048 1.047 1.045 97.00 867.560 1.044 97.50 866.261 1.042 98.00 864.977 1.040 98.50 863.703 1.039 99.00 862.449 1.037 99.50 861.199 1.036 100.00 859.957 1.034' t 101.00 858.111 1.032 l 102.00 855.755 1.029
! 103.00 853.410 1.026 l 104.00 851.088 1.024 105.00 848.792 1.021 0 106.00 107.00 108.00 846.600 844.359 842.160 1.018 1.016 1.013 1.010 109.00 839.999 110.00 837.871 1.008 111.00 835.773 1.005 112.00 833.705 1.003 O 113.00 114.00 115.00 831.664 829.654 827.671 1.000
.998
.995 116.00 825.719 .993 117.00 823.842 .991 118.00 821.963 .988 0 119.00 120.00 121.00 820.067 818.227 816.412
.986
.984
.982 6.2-72 NOVEMBER, 1986 WAPWR-CS 4322e:1d
TABLE 6.2-30 (SHEET 5 of 9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY N-s (SEC) (LBM/SEC) (BTU /SEC X 10E6) 122.00 814.624 .979 123.00 812.863 .977 124.00 811.130 .975 125.00 809.421 .973 126.00 807.739 .971 Os 127.00 806.080 .969 128.00 804.446 .967 129.00 802.835 .965 130.00 801.248 .963 131.00 799.683 .961 7- g 132.00 798.139 .960 133.00 796.617 .958 134.00 795.114 .956 135.00 793.630 .954 136.00 792.163 .952 137.00 790.715 .951 138.00 789.284 .949 139.00 787.872 .947 140.00 786.476 .945 141.00 785.099 .944 142.00 783.737 .942 I
143.00 782.390 .940 144.00 781.058 .939 145.00 779.742 .937 146.00 778.441 .936 O 147.00 148.00 149.00 777.155 775.882 774.621
.934
.933
.931 150.00 773.375 .930 151.00 772.142 .928 152.00 770.924 .927 153.00 769.717 .925 154.00 768.523 .924 155.00 767.340 .922 156.00 766.169 .921 157.00 765.007 .919 l
158.00 763.853 .918 159.00 762.709 .917 160.00 761.577 .915 161.00 760.457 .914 O 162.00 163.00 164.00 759.347 758.245 757.152
.913
.911
.910 165.00 756.065 .909
' 166.00 7 54.987 .907 167.00 753.917 .906
' 168.00 752.855 .905 169.00 751.799 .903 170.00 750.755 .902 l 171.00 749.725 .901 172.00 748.695 .900 173.00 747.666 .898 174.00 746.640 .897 O' 175.00 176.00 745.619 744.609 743.606
.896
.895
.893 177.00 6.2-73 NOVEMBER, 1986 WAPWR-CS 4322e:1d i
TABLE 6.2-30 (SHEET 6 of 9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY O (SEC) 178.00 (LBM/SEC) 742.610 (BTU /SEC K 10E6)
.892 179.00 741.620 .891 180.00 740.635 .890 181.00 739.652 .889 182.00 738.678 .888 O 183.00 184.00 737.708 736.741 735.778
.886
.885
.884 185.00 186.00 734.820 .883 187.00 733.868 .882 188.00 732.918 .881 0 189.00 190.00 191.00 731.971 731.027 730.086
.879
.878
.877 192.00 729.150 .876 193.00 728.217 .875 194.00 727.287 .874 195.00 726.359 .873 196.00 725.433 .871 197.00 724.513 .870 198.00 723.595 .869 199.00 722.681 .868 200.00 721.767 .867 201.00 720.676 .866 202.00 717.260 .862 203.00 715.668 .860 l
l 0 204.00 205.00 206.00 713.963 712.359 710.849
.858
.856
.854 207.00 709.439 .852 i
~208.00 708.115 .850 209.00 706.863 .849 210.00 705.663 .847 211.00 704.508 .846 212.00 703.382 .845 213.00 702.279 .843 1 l l 214.00 701.192 .842 215.00 700.114 .841
' 216.00 699.042 .839 217.00 697.966 .838 218.00 696.895 .837 O 219.00 220.00 221.00 695.827 694.762 693.703
.836
.834
.833 222.00 692.649 .832 223.00 691.601 .830 224.00 690.559 .829 225.00 689.524 .828 226.00 688.496 .827
.825 227.00 687.475 L .824 l 228.00 686.456 229.00 685.443 .823 230.00 684.435 .822 231.00 683.436 .821 4
0 232.00 233.00 682.443 681.459
.819
.818 WAPWR-CS 6.2-74 NOVEMBER, 1986 l 4322e:1d
TABLE 6.2-30 (SHEET 7 of 9)
CASE 2:
1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6)
{
234.00 680.467 .817 235.00 679.474 .816 236.00 678.487 .815 237.00 677.512 .813 238.00 676.539 .812 O 239.00 240.00 675.568 674.599
.811
.810 241.00 673.634 .809 242.00 672.669 .807 243.00 671.708 .806 244.00 670.188 .804 O, 245.00 246.00 659.702 649.173
.792
.779 247.00 638.573 .766 248.00 625.761 .751 249.00 612.103 .734 250.00 595.811 .714 251.00 578.408 .693 252.00 559.485 .670 253.00 538.962 .645 254.00 516.903 .618 255.00 493.643 .590 256.00 469.024 .560 257.00 443.416 .529 258.00 417.037 .497 259.00 390.441 465 260.00 364.227 .434 261.00 338.010 402 262.00 312.915 .372 263.00 288.550 .342 264.00 265.193 .314 265.00 243.069 .287 266.00 222.541 .263 267.00 203.821 .240 268.00 187.238 .221 269.00 173.259 .204 270.00 160.659 .189 271.00 148.563 .174
- 272.00 137.637 .161 273.00 129.074 .151 274.Or' 121.147 .142 275.00 113.540 .133 276.00 106.488 .124 277.00 100.208 .117 278.00 94.752 .110 279.00 90.070 .105 280.00 86.040 .100 281.00 82.510 .096 0s 282.00 283.00 79.459 77.077
.092
.089 284.00 74.613 .087 285.00 72.569 .084 286.00 70.872 .082 287.00 69.439 .080 0 288.00 289.00 68.216 67.169
.079
.078 NOVEMBER, 1986 WAPWR-CS 6.2-75 1322e:1d
TABLE 6.2-30 (SHEET 8 of 9)
CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6)
A 290.00 66.274 .077 291.00 65.513 .076 292.00 64.869 .075 293.00 64.323 .074 O 294.00 295.00 296.00 63.865 63.485 63.174
.074
.073
.073 l 297.00 62.922 .073 298.00 62.720 .073 299.00 62.559 .072 300.00 62.433 .072 0, 301.00 302.00 62.335 62.260
.072
.072 303.00 62.203 .072 304.00 62.159 .072 305.00 62.127 .072 306.00 62.103 .072 307.00 62.085 .072 308.00 62.072 .072 309.00 62.063 .072 310.00 62.056 .072 311.00 62.051 .072 312.00 62.047 .072
, 313.00 62.044 .072 l 314.00 62.042 .072 315.00 62.040 .072 316.00 62.038 .072 317.00 62.037 .072 318.00 62.035 .072 319.00 62.034 .072 320.00 62.032 .072 321.00 62.031 .072 322.00 62.030 .072
! 323.00 62.028 .072 324.00 62.027 .072 325.00 62.026 .072 326.00 62.025 .072 4
327.00 62.023 .072 328.00 62.022 .072 329.00 62.021 .072 O
330.00 62.020 .072 331.00 62.019 .072 332.00 62.018 .072 333.00 62.017 .072 334.00 62.016 .072 335.00 62.015 .072 336.00 62.014 .072 O 337.00 338.00 339.00 62.013 62.012 62.011
.072
.072
.072 340.00 62.010 .072 341.00 62.010 .072 342.00 62.009 .072 0 343.00 344.00 345.00 62.008 62.007 62.007
.072
.072
.072 NOVEMBER, 1986 WAPWR-CS 6.2-76 1322e:1d
TABLE 6.2-30 (SHEET 9 of 9) 4 CASE 2: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 75 PC POWER t
TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 346.00 62.006 .072 347.00 62.006 .072
- 348.00 62.005 .072
! 349.00 62.004 .072 350.00' 62.004 .072 f
. v 3r ir l 1800.00 61.980 .072 1802.00 62.055 .072 1804.00 62.335 .072 1806.00 51.214 .059 i 1808.00 43.915 .051 1810.00 17.983 .021 1812.00 .657 .001
! 1814.00 .019 .000 '
1816.00 .001 .000 1818.00 .000 .000
- s O si 2000.00 0. BOO 0.000 u
l l
1 O
!O l
!O WAPWR-CS 6.2-77 NOVEMBER, 1986 l 1322e:1d
4 TABLE 6.2-31 (SHEET 1 of 9)
CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 0.00 0.000 0.000 O .50 1.00 13094.755 12360.743 15.562 14.709 14.211 1.50 11928.037 2.00 11526.076 13.746 2.50 11161.800 13.324 3.00 10826.855 12.934 O 3.50 4.00 4.50 10519.008 10233.681 9968.368 12.576 12.243 11.932 5.00 9723.129 11.645 5.50 9493.629 11.375 6.00 9279.088 11.123 6.50 9079.304 10.887
! 7.00 8892.739 10.668 7.50 8718.045 10.461 8.00 2132.861 2.560 8.50 2095.780 2.516 9.00 2088.889 2.508 9.50 2071.737 2.488 10.00 2054.811 2.468 10.50 2037.944 2.448 11.00 2020.990 2.428 O 11.50 12.00 12.50 2003.992 1986.797 1969.473 2.408 2.387 2.367
! 13.00 1951.851 2.346 13.50 1934.055 2.325 14.00 1916.064 2.303 14.50 1897.936 2.282 1 15.00 1879.736 2.260 15.50 1861.492 2.238 16.00 1843.215 2.217 l 16.50 1824.911 2.195 17.00 1806.591 2.173 17.50 1788.266 2.151 18.00 1769.910 2.129 18.50 1751.535 2.107 l
O 19.00 19.50 20.00 1733.234 1714.909 1696.819 2.085 2.064 2.042 l 20.50 1678.892 2.021 i 21.00 1661.204 1.999 21.50 1643.808 1.979 l 22.00 1626.708 1.958 22.50 1609.998 1.938 i 23.00 1593.601 1.919 23.50 1577.630 1.899 24.00 1561.995 1.881 24.50 1546.724 1.862 25.00 1531.807 1,844 l (g 25.50 26.00 1517.198 1.827 1.810 g 26.50 1502.997 1489.112 1.793 l WAPWR-CS 6.2-78 NOVEMBER, 1986 4322e:1d f
- _ , - - - - - - ---..<,,,n_..._ .-,n.,,-,v.,,,,-, - - , , . _ , . . . .-n.,,..
_ _ = _ - . .
- l. -
f 1ABLE5.2-31(SHEET 2of9) f CASE 3: 1.4FT2DDUBLE-ENDEDRUPTUREAT50*CPodR T1hE BREAX FLOW BREAK ENERGY (S'dC) (LBM/SEC) (BTU /SEC K 10E6)
,27.00 1475.552 1.777 27.50 1462.247 1.761 O 28.00 28.50 29.00 1449.221 1436.578 1424.215 1.745 1.730 1.715 .
29.50 , 1412.132 1.701 >
1.687 e 30.00 1400.326
- 30.50 1388.004 1.673
> 31.00 1377.550 1.659 31.50 1366.133 1.645 32.00 3355.413 1.633 32.50 1344.935 1.620' 33.00 1334.678 1.608 33.50 1324.649 1.595 34.00 1314.S40 1.584 34.50 1305.243 1.572 35.00 1295.853 1.561 35.50 1286.665 1.550 36.00 1277.673 1.539 - ,
36.50 1268.872 1.528 37.00 1260.259 1.51E 37.50 1251.828 1.508 38.00 1243.575 1.49W i
38.50 1235.502 1.486 1.479 39.00 1227.591
' 39.50 1219.822 1.469 40.00 1212.201 1.460 40.50 1204.724 1.451 1.442 1 41.00 1197.386 41.50 1190.185 1.433 ,
42.00 1183.120 1.425 4 42.50 1176.188 1.417 43.00 1169.388 1.408 .
43.50 1162.714 1.400 '
44.00 1156.167 1.392 44.50 1149.743 1.385 '
45.00 1143.439 1.377
! 45.50 1137.254 1.370 46.00 1131.185 1.362 46.50 1125.229 1.355 O 47.00 47.50 48.00 1119.334' 1113.f49 1108.020 1.348 1.341 1.334' ,
48.50 1102.496 1.328 49.00 1097.075 1.321 49.50 1091.751 1.315
$0.00 10E6.526 1.308 -
i O\ 50.50 51.00 1081.399 1076.365 1.302 1.296 51.50 1071.425 1.290 s i 52.00 1066.574 1.284 52.50 1061.813 1.279
$3.00 1057.139 1.273 '
3 1.267 4
O $3.50 54.00 54.50 1052.550 1048.'045 1041 622 1.262 1.257 6.2-79 NOVEMBER, 1986 WAPWR-CS 4322e:1d
/'
TABLE 6.2-31 (SHEET 3 of 9)
F r .x CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER i ' TIME BREAK FLOW BREAK ENERGY i (SEC) (LBM/SEC) (BTU /SEC A 10E6)
.I
! dF $5,00 1039.278 1.251 s 55.50 1035.012 1.246 l: 1.241 i 56.00 1030.822 56.50 1026.706 1.236 57.00 1022.669 1.231 i 57.50 1018.713 1.226
! 58.00 1014.833 1.222
! i 58.50 1011.029 1.217 59.00 1007.299 1.213 i 59.50 1003.638 1.208 1
60.00 1000.044 1.204 c- ,
60.50 996.516 1.200 l 61.00 993.049 1.195 61.50 989.642 1.191
! 62.00 986.293 1.187 62.50 982.999 1.183 1 ,; - -
63.00 979.759 1.179
, . 63.50 976.571 1.175 1.172
'- 64.00 973.437 i
64.50 970.350 1.168 65.00 967.310 1.164 l
i 65.50 964.314 1.161
- 66.00 961.371 1.157
!' > 66.50 958.473 1.154 67.00 955.620 1.150 67.50 952.813 1.147
- 68.00 950.043 1.143 i
, 68.50 947.324 1.140 i
69.00 944.652 1.137 I 69.50 942.020 1.134 70.00 939.420 1.131 l '
70.50 936.847 1.127 1 71.00 934.317 1.124
' 71.50 931.832 1.121
' ,, 72.00 929.379 1.118 72.50 926.954 1.115 P 73.00 924.554 1.113 i 73.50 922.176 1.110
- l. 74.00 919.836 1.107 74.50 917.529 1.104 75.00 915.251 1.101 75.50 913.000 1.099 76.00 910.777 1.096
, 76.50 908.583 1.093
' 906.419 1.091 l 77.00 l 77.50 904.283 - 1.088 1.085
- 78.00 902.174 78.50 900.093 1.083
- 79.00 898.037 1.080 79.50 896.002 1.078
' ~ 80.00 893.993 1.076
, 80.50 892.008 1.073 61.00 890.048 1.071 81.50 888.112 1.068 82.00 886.203 1.066 82.50 884.318 1.064 WAPWR-CS 6.2-80 NOVEMBER,1986 T322e:1d
/
..m. .-..-___.-._,_.,,, _%,m,,_ _ _.--.- -,_..,m_, , _ _ . , . . . , , , - . _ _ _ _ _ - ._- - - .._ _ ,____
i TABLE 6.2-31 (SHEET 4 of 9)
CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY t s (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 882.448 1.062 O E3.50 84.00 84.50 880.610 878.806 877.026 1.059 1.057 1.055 1 85.00 875.262 1.053 85.50 873.514 1.051 86.00 871.777 1.049 86.50 870.052 1.047 0 87.00 87.50 88.00 868.340 866.645 864.969 1.045 1.042 1.040 88.50 863.314 1.038 89.00 861.682 1.036 89.50 860.071 1.035 90.00 858.481 1.033 90.50 856.913 1.031 91.00 855.364 1.029 91.50 853.834 1.027 92.00 852.322 1.025 92.50 850.827 1.023 93.00 849.351 1.022 93.50 847.891 1.020 l 94.00 846.447 1.018 i 94.50 845.019 1.016 l 95.00 843.607 1.015 95'.50 842.212 1.013
[
96.00 840.831 1.011 96.50 839.466 1.010 97.00 838.117 1.008 97.50 836.781 1.006 98.00 835.459 1.005 98.50 834.151 1.003 99.00 832.857 1.002 99.50 831.577 1.000
! 100.00 830.310 .998 101.00 828.426 .996 102.00 826.032 .993 103.00 823.684 .900 104.00 821.369 .988 O
j 1 105.00 819.098 .985 l 106.00 816.874 .982 l 107.00 814.697 .950 108.00 812.564 .977 I i 109.00 810.471 .974 110.00 808.413 .972 111.00 806.393 .970 l
l 0 112.00 113.00 114.00 804.408 S02.454 800.531
.967
.965
.962 115.00 798.641 .960 116.00 796.783 .958 117.00 794.959 .956 O 118.00 119.00 120.00 793.167 791.403 789.669
.954
.951
.949 121.00 787.965 .947 WAFWR-CS 6.2-81 NOVEMBER, 1986 T322e:1d
TABLE 6.2-31 (SHEET 5 of 9)
O CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O 122.00 123.00 224.00 786.290 784.644 783.028
.945
.943
.941 125.00 781.439 .939 126.00 779.877 .937 127.00 778.341 .936 128.00 776.829 .934 O 129.00 130.00 131.00 775.341 773.879 772.438
.932
.930
.928 132.00 771.020 .927 133.00 769.623 .925 134.00 768.248 .923 135.00 766.894 .922
-136.00 765.559 .920 137.00 764.241 .918 138.00 762.944 .917 139.00 761.665 .915 140.00 760.403 .914 141.00 759.158 .912 142.00 757.928 .911 143.00 756.715 .909 t
O' 144.00 145.00 146.00 147.00 755.517 754.335 753.166 752.013
.908
.906
.905
.904 148.00 750.872 .902 149.00 749.744 .901 150.00 748.627 .900 151.00 747.523 .898 152.00 746.431 .897 153,00 745.350 .896 154.00 744.280 .894 155.00 743.222 .893 156.00 742.175 .892 157.00 741.137 .890 l 158.00 740.108 .889 l 159.00 739.087 .888 O 160.00 161.00 162.00 738.074 737.071 736.077
.887
.886
.884 163.00 735.091 .883 164.00 734.112 .882 165.00 733.141 .881 166.00 732.178 .880 0 167.00 168.00 169.00 731.222 730.272 729.328
.878
.877
.876 170.00 728.390 .875 171.00 727.457 .874 172.00 726.529 .873 173.00 l
! O 174.00 175.00 176.00 725.606 724.690 723.779 722.873
.872
.871
.869
.868 177.00 721.970 .867 WAPWR-CS 6.2-82 NOVEMBER, 1986 T322e:1d
TABLE 6.2-31 (SHEET 6 of 9)
CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) 178.00 721.071 .866 179.00 720.177 .865 180.00 719.287 .864 O 181.00 182.00 718.403 717.522
.863
.862 183.00 716.646 .861 184.00 715.772 .860 185.00 714.902 .859 186.00 714.034 .858
'T 187.00 713.171 .857 188.00 712.310 .856 189.00 711.450 .855 190.00 710.593 .853 191.00 709.739 .852 192.00 708.889 .851 193.00 708.041 .850 194.00 707.195 .849 195.00 706.351 .848 196.00 705.509 .847 197.00 704.669 .846 198.00 703.831 .845 199.00 702.996 .844 200.00 702.163 .843 201.00 701.196 .842 202.00 698.498 .839 0 203.00 204.00 205.00 696.954 695.463 694.029
.837
.835
.833 206.00 692.670 .832 207.00 691.389 .830 208.00 690.177 .829 209.00 689.024 .827 210.00 687.920 .826 211.00 686.849 .825 212.00 685.807 .823 213.00 684.786 .822 214.00 683.779 .821 215.00 682.783 .820 216.00 681.793 .819 217.00 680.809 .817 218.00 679.830 .816 O. 219.00 220.00 678.854 677.883
.815
.814 221.00 676.912 .813 222.00 675.949 .811 223.00 674.997 .810 224.00 674.061 .809 l
1 O 225.00 226.00 227.00 673.108 672.146 671.194
.808
.807
.806 l 228.00 670.253 .805 l 229.00 669.319 .803 230.00 668.393 .802 231.00 667.470 .801 0 WAPWR-CS 232.00 233.00 666.552 665.636 6.2-83
.800
.799 NOVEMBER, 1986 4322e:1d
l TABLE 6.2-31 (SHEET 7 of 9)
CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) 234.00 664.723 .798
/'"' 235.00 236.00 663.815 662.911
.797
.796
\
237.00 662.008 .795 238.00 661.108 .793 239.00 660.207 .792 240.00 659.309 .791 241.00 658.419 .790 0 242.00 243.00 244.00 657.525 656.635 655.745
.789
.788
.787
.786 245.00 654.958 246.00 654.059 .785 247.00 653.174 .784 248.00 652.292 .783 249.00 651.411 .782 250.00 650.534 .781 251.00 649.657 .780 252.00 648.780 .779 253.00 647.906 .777 254.00 647.033 .776 255.00 646.160 .775 256.00 645.291 .774 l 257.00 644.424 .773 1 258.00 643.559 .772 259.00 642.695 .771 260.00 641.830 .770 261.00 640.965 .769 262.00 640.102 .768 263.00 639.241 .767 264.00 638.381 .766 265.00 637.523 .765 266.00 636.667 .764 267.00 635.809 .763 268.00 634.743 .761 269.00 629.815 .755 270.00 619.209 .743 271.00 608.937 .730 272.00 595.702 .714 0 273.00 274.00 275.00 581.169 564.301 546.061
.696
.676
.654 276.00 535.112 .641 277.00 528.368 .633 278.00 526.291 .630 279.00 526.761 .631 0 280.00 281.00 282.00 527.289 527.752 527.067
.631
.632
.631 283.00 525.252 .629 284.00 522.987 .626 285.00 $19.675 .622 286.00 515.253 .617
,J 287.00 508.991 .609 288.00 502.954 .602 289.00 496.115 .593 i WAPWR-CS 6.2-84 NOVEMBER, 1986 l T322e:1d l
TABLE 6.2-31 (SHEET 8 of 9)
CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) av0.00 489.287 .585 O 291.00 292.00 293.00 481.716 473.839 466.389
.576
.566
.557 294.00 459.194 .549 295.00 450.594 .538 296.00 441.193 .527 297.00 430.343 .514 O 298.00 299.00 300.00 420.544 409.490 398.084
.502
.488
.475 301.00 384.762 458 302.00 370.413 .441 303.00 355.990 .424 304.00 343.564 .409 305.00 329.366 .392 306.00 313.299 .372 307.00 296.796 .352 308.00 280.342 .332 309.00 264.352 .313 310.00 250.553 .297 311.00 237.044 .280 312.00 221.953 .262 O 313.00 314.00 315.00 207.105 193.071 180.925
.244
.228
.213 316.00 169.745 .200 317.00 158.957 .187 318.00 148.466 .174 319.00 138.887 .163 320.00 130.927 .153 321.00 123.962 .145 322.00 117.066 .137 323.00 110.446 .129 324.00 104.347 .122 325.00 98.886 .115 326.00 94.081 .110 327.00 89.892 .105 328.00 86.223 .100 O 329.00 330.00 331.00 82.964 80.105 77.757
.096
.093
.090 332.00 75.566 .088 333.00 73.525 .085 334.00 71.826 .083 335.00 70.381 .082 0 336.00 337.00 338.00 69.138 68.061 67.126
.080
.079
.078 339.00 66.311 .077 340.00 65.604 .076 341.00 64.994 .075 342.00 64.472 O 343.00 344.00 64.030 63.657
.075
.074
.074 345.00 63.346 .073 NOVEMBER, 1986 WAPWR-CS 6.2-85 4322e:1d 1 - _ _ - - - . _ - _ - _ _ _ _ - . , _ --
TABLE 6.2-31 (SHEET 9 of 9)
[ CASE 3: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) 346.00 63.088 '.073 347.00 62.876 .073
.073 0 348.00 349.00 350.00 62.703 62.562 62.449 62.359
.072
.072
.072 351.00 352.00 62.287 .072 353.00 62.230 .072 354.00 62.185 .072 0 355.00 356.00 357.00 62.349 62.122 62.100
.072
.072
.072
.072 358.00 62.083 359.00 62.070 .072 360.00 62.060 .072 361.00 62.051 .072 362.00 62.045 .072 363.00 62.040 .072 364.00 62.036 .072 365.00 62.032 .072 366.00 62.029 .072 367.00 62.027 .072 368.00 62.025 .072 369.00 62.023 .072
.072 O 370.00 371.00 372.00 62.021 62.019 62.018
.072
.072
.072 373.00 62.017 374.00 i'. 015 .072 375.00 o2.014 .072 376.00 62.013 .072 377.00 62.012 .072 378.00 62.011 .072 379.00 62.010 .072 380.00 62.009 .072
- %f v nr O 1800.00 1802.00 1804.00 61.975 61.975 62.341
.072
.072
.072 1806.00 51.221 .059 1808.00 43.935 .051 l
1810.00 24.662 .028 1812.00 1.158 .001 1814.00 .045 .000
\
1816.00 .002 .000 1818.00 .000 .000 0 20db.00 0.' BOO 0.0'b0 NOVEMBER,1986 WAPWR-CS 6.2-86 4322e:1d
J-TABLE 6.2-32 (SHEET 1 of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLO6i BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O.00 0.000 0.000
.50 13665.465 16.219 1.00 12758.264 15.167 1.50 12221.035 14.550
' 2.00 11725.350 13.978 2.50 11277.161 13.459 3.00 10866.238 12.981 3.50 10489.311 12.542 4.00 10140.473 12.134 4.50 9816.406 11.755 5.00 9517.228 11.404 5.50 9236.631 11.073 6.00 8976.007 10.766 .
6.50 8733.335 10.480 -
7.00 8506.869 10.212 7.50 8295.411 9.962 8.00 2017.189 2.423 8.50 1973.076 2.371 9.00 1970.994 2.368 9.50 1954.755 2.349 10.00 1938.902 2.330 0 10.50 11.00 11.50 12.00 1923.176 1907.579 1892.068 1876.596 2.312 2.293 2.275 2.256 12.50 1861.117 2.238 13.00 1845.587 2.219 13.50 1829.974 2.201 14.00 1814.244 2.182 14.50 1798.374 2.163 15.00 1782.477 2.144 15.50 1766.399 2.125 16.00 1750.321 2.106 16.50 1734.113 2.087 17.00 1717.938 2.067 17.50 1701.650 2.048 18.00 1685.435 2.028 18.50 1669.195 2.009 1
l O 19.00 19.50 20.00 1652.978 1636.823 1620.768 1.990 1.970 1.951 20.50 1604.837 1.932 21.00 1588.988 1.913 21.50 1573.297 1.894 22.00 1557.807 1.876 O 22.50 23.00 23.50 1542.546 1527.530 1512.772 1.857 1.839 1.822 24.00 1498.279 1.804 24.50 1484.060 1.787 25.00 1470.091 1.770 25.50 1456.373 1.754 0 26.00 26.50 1442.953 1429.794 1.738 1.722 WAPWR-CS 6.2-87 NOVEMBER, 1986 4322e:1d
TABLE 6.2-32 (SHEET 2 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAT. FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O- 27.00 27.50 1416.971 1404.406 1.707 1.691 28.00 1392.131 1.677 28.50 1380.138 1.662 29.00 1367.999 1.648 29.50 1356.530 1.634 O 30.00 30.50 31.00 1345.368 1334.441 1323.754 1.620 1.607 1.594 31.50 1313.307 1.582 32.00 1303.103 1.570 32.50 1293.129 1.558 33.00 1283.381 1.546 33.50 1273.853 1.534 -
34.00 1264.536 1.523 34.50 1255.425 1.512 35.00 1246.513 1.501 35.50 1237.792 1.491 36.00 1229.262 1.481 36.50 1220.911 1.471 37.00 1212.732 1.461 37.50 1204.719 1.451 O. 38.00 38.50 39.00 1196.863 1189.154 1181.601 1174.195 1.442 1.432 1.423 1.414 39.50 40.00 If66.934 1.405 40.50 1159.813 1.397 41.00 1152.830 1.388 41.50 1145.982 1.380 42.00 1139.262 1.372 42.50 1132.676 1.364 43.00 1126.216 1.356 43.50 1119.888 1.349 44.00 1113.686 1.341 44.50 1107.605 1.334 45.00 1101.643 1.327 45.50 1095.797 1.320 O .
46.00 46.50 47.00 1090.067 1084.449 1078.941 1073.542 1.313 1.306 1.299 1.293 47.50 48.00 1068.247 1.286 48.50 1063.054 1.280 49.00 1057.957 1.274 1.268 O 49.50 50.00 50.50 1052.956 1048.051 1043.235 1.262 1.256 1.250 51.00 1038.505 51.50 1033.864 1.245 52.00 1029.307 1.239 52.50 1024.831 1.234 O 53.00 53.50 54.00 54.50 1020.435 1016.116 1011.873 1007.704 1.229 1.223 1.218 1.213 WAPWR-CS 6.2-88 NOVEMBER, 1986 4322e:1d
m TABLE 6.2-32 (SHEET 3 of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) 04 55.00 55.50 1003.606 999.578 1.208 1.203 56.00 995.619 1.199 56.50 991.726 1.194 57.00 987.898 1.189 57.50 984,133 1.185 O 58.00 58.50 59.00 980.429 976.785 973.201 1.180 1.176 1.171 59.50 969.675 1.167 60.00 966.206 1.163 60.50 962.793 1.159 61.00 959.435 1.155 61.50 956.131 1.151 -
62.00 952.878 1.147 62.50 949.679 1.143 63.00 946.529 1.139 63.50 943.428 1.135 64.00 940.376 1.132 64.50 937.369 1.128 65.00 934.405 1.124 65.50 931.483 1.121 O 66.00 66.50 67.00 928.602 925.760 922.957 1.117 1.114 1.111 67.50 920.195 1.107 68.00 917.469 1.104 68.50 914.781 1.101 69.00 912.128 1.098 69.50 909.511 1.094 70.00 906.928 1.091 70.50 904.380 1.088 '
71.00 901.863 1.085 71.50 899.379 1.082 72.00 896.922 1.079 72.50 894.494 1.076 73.00 892.100 1.073 73.50 889.737 1.070 1.068 0 74.00 74.50 75.00 75.50 887.405 885.105 882.835 880.596 1.065 1.062 1.059 76.00 878.388 1.057 76.50 876.209 1.054 77.00 874.060 1.051 77.50 871.940 1.049 O 78.00 78.50 79.00 869.849 867.786 865.751 1.046 1.044 1.041 79.50 863.744 1.039 80.00 861.765 1.037 80.50 859.812 1.034 81.00 857.864 1.032 O 81.50 82.00 82.50 855.982 854.105 852.252 1.030 1.027 1.025 6.2-89 NOVEMBER, 1986 WAPWR-CS T322e:1d
l TABLE 6.2-32 (SHEET 4 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENER0Y (SEC) (LEM/SEC) (BTU /SEC K 10E6) 83.00 850.422 1.023 83.50 848.617 1.021 84.00 846.835 1.019 84.50 845.075 1.016 85.00 843.338 1.014 85.50 841.622 1.012 g 86.00 839.929 1.010 86.50 838.256 1.008 87.00 836.604 1.006 87.50 834.971 1.004 88.00 833.360 1.002 88.50 831.768 1.000 89.00 830.196 .998 89.50 828.643 .996 -
90.00 827.109 .995 90.50 825.594 .993 91.00 824.097 .991 91.50 822.618 .989 92.00 821.156 .987 92.50 819.713 .986 j 93.00 818.286 .984 93.50 816.875 .982 94.00 815.484 .981 C 94.50 814.109 .979 95.00 812.749 .977 95.50 811.405 .976 96.00 810.078 .974 96.50 808.767 .972 97.00 807.470 .971 97.50 806.189 .969 98.00 804.923 .968 98.50 803.671 .966 -
99.00 802.434 .965 99.50 801.211 .963 100.00 800.001 .962 101.00 798.206 .960 102.00 795.911 .957 103.00 793.669 .954 O 104.00 105.00 106.00 791.465 789.305 787.191
.951
.949
.946 107.00 785.123 .944
( 108.00 783.097 .941 109.00 781.113 .939 110.00 779.166 .937 O 111.00 112.00 113.00 777.255 775.379 773.536
.934
.932
.930 114.00 771.727 .928 115.00 769.951 .925 116.00 768.208 .923 117.00 766.498 .921 0 118.00 119.00 120.00 121.00 764.820 763.173 761.556 759.969
.919
.917
.915
.913 i
6.2-90 NOVEMBER,1986 WAPWR-CS 1322e:1d ,
l
--_w. - . --
e TABLE 6.2-32 (SHEET 5 of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY s (SEC) (LBM/SEC) (BTU /SEC K 10E6)
\ 122.00 758.411 .911 123.00 756.883 .910 124.00 755.382 .908 125.00 753.909 .9 06 126.00 752.462 .904 127.00 751.040 .902 0 v 128.00 129.00 130.00 749.642 748.269 746.919
.901
.899
.897 131.00 745.592 .896 132.00 744.286 .894 133.00 743.002 .893 134.00 741.737 .891 135.00 740.491 .890 -
136.00 739.265 .888 137.00 738.058 .887 138.00 736.869 .885 139.00 735.696 .884 140.00 734.539 .882 141.00 733.399 .881 142.00 732.274 .880 143.00 731.164 .878 l
l 0 144.00 145.00 146.00 730.070 728.990 727.925
.877
.876
.874 147.00 726.871 .873 148.00 725.829 .872 149.00 724.799 .871 150.00 723.781 .869 151.00 722.775 .868 152.00 721.779 .867 153.00 720.794 .866 154.00 719.820 .865 155.00 718.859 .863 156.00 717.907 .862 157.00 716.961 .861 158.00 716.025 .860 159.00 715.097 .859 .
O 160.00 161.00 162.00 714.177 713.265 712.361 711.465
.858
.857
.856
.855 163.00 164.00 710.576 .853 165.00 709.693 .852 166.00 708.818 .851 0 167.00 168.00 169.00 170.00 707.949 707.086 706.229 705.377
.850
.849
.848
.847 171.00 704.532 .846 172.00 703.691 .845 173.00 702.857 .844 O 174.00 175.00 176.00 177.00 702.026 701.201 700.378 699.562
.843
.642
.841
.840 WAPWR-CS 6.2-91 NOVEMBER,1986 4322e:1d
TABLE 6.2-32 (SHEET 6 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (L8M/SEC) (BTU /SEC K 10E6) 178.00 698.747 .839 179.00 697.931 .838 180.00 697.119 .837 181.00 696.311 .836 182.00 695.507 .835 183.00 694.707 .834 3 ' 184.00 693.909 .833 185.00 693.114 .832 186.00 692.322 .831 187.00 691.533 .830 188.00 690.746 .829 189.00 689.964 .828 190.00 689.183 .828 191.00 688.403 .827 -
192.00 687.628 .826 193.00 686.853 .825 194.00 686.080 .824 195.00 685.309 .823 196.00 684.541 .822 197.00 683.774 .821 198.00 683.008 .820 199.00 682.245 .819 0 200.00 201.00 202.00 681.483 680.723 678.793
.818
.817
.815
.813 203.00 677.546 204.00 676.342 .812 .
205.00 675.175 .811 206.00 674.049 .809 207.00 672.966 .808 208.00 671.921 .807 209.00 670.911 .805
[ .804 210.00 669.930 211.00 668.974 .803 212.00 668.038 .802 213.00 667.118 .801 214.00 666.207 .800 215.00 665.310 799 I
0 216.00 217.00 218.00 219.00 664.420 663.536 662.656 661.780
.797
.796 795 794 220.00 660.909 793 221.00 660.043 .792 222.00 659.180 .791
.790 0 223.00 224.00 225.00 226.00 658.320 657.462 656.610 655.761
.789 788
.787 227.00 655.019 .786 228.00 654.166 .785 229.00 653.326 .784 l
230.00 652.487 .783
' 231.00 651.653 782 232.00 650.822 .781 233.00 649.993 780 6.2-92 NOVEMBER, 1986 l WAPWR-CS l 1322e:1d l
TABLE 6.2-32 (SHEET 7 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) 234.00 649.168 .779 235.00 648.346 .778 236.00 647.527 .777 237.00 646.708 .776 238.00 645.894 .775 239.00 645.080 .774 240.00 644.270 .773 06 241.00 643.461 642.653
.772
.771 242.00 243.00 641.849 .770 244.00 641.044 .769 245.00 640.243 .768 246.00 639.441 .767 247.00 638.643 .766 ~
248.00 637.845 .765 249.00 637.048 .764 250.00 636.253 .763 251.00 635.459 .762 252.00 634.667 .761 253.00 633.876 .760 254.00 633.085 .760 255.00 632.296 .759
/] 256.00 631.508 .758
\.Q 257.00 630.722 .757 258.00 629.935 .756 259.00 629.150 .755 260.00 628.366 .754 261.00 627.385 .753 262.00 626.803 .752 263.00 626.022 .751 264.00 625.241 .750 265.00 624.462 .749 266.00 623.686 748 267.00 622.908 .747 268.00 622.132 .746 269.00 621.356 .745 270.00 620.582 .744 271.00 619.809 .743 O 272.00 273.00 274.00 619.036 618.263 617.492
.742
.742
.741 275.00 616.722 .740 276.00 615.953 .739 277.00 615.184 .738
! 278.00 614.415 .737 279.00 613.649 .736 280.00 612.881 .735 281.00 612.117 .734 282.00 611.351 .733 283.00 610.589 .732 284.00 609.825 .731 285.00 609.064 .730 i
l 0 286.00 287.00 288.00 289.00 608.301 607.542 606.781 606.022
.729
.729
.728
.727 WAPWR-CS 6.2-93 NOVEMBER, 1986 4322e:Id
TABLE 6.2-32 (SHEET 8 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY s (SEC) (LBM/SEC) (BTU /SEC K 10E6) 290.00 605.263 .726 291.00 604.508 .725 292.00 603.750 .724 293.00 602.995 .723 294.00 602.238 .722 295.00 601.485 .721 4
0 296.00 297.00 298.00 600.731 599.979 599.225
.720
.719
.718 299.00 598.475 .718 300.00 597.724 .717 301.00 596.975 .716 302.00 596.224 .715 303.00 595.477 .714 .
304.00 594.729 .713 305.00 593.983 .712 306.00 593.235 .711 307.00 592.491 .710 308.00 591.746 .709 309.00 591.002 .708 310.00 590.258 .708 311.00 589.516 .707 O. 312.00 313.00 314.00 588.775 588.034 587.293
.706
.705
.704 315.00 586.553 .703 316.00 585.815 .702 317.00 585.078 .701 318.00 584.339 .700 319.00 583.626 .700 320.00 582.918 .699 321.00 582.223 .698 322.00 580.944 .696 323.00 571.710 .685 324.00 563.995 .676 325.00 553.982 .664 326.00 543.439 .651
- 327.00 530.261 .635 l
- 0. 328.00 329.00 330.00 515.807 499.482 480.988
.617
.597
.575 j 331.00 460.394 .550 332.00 437.526 .522 l' 333.00 412.432 492 334.00 385.331 459 335.00 356.753 424 O\ 336.00 337.00 327.184 297.273
.389
.353 338.00 267.463 .317 339.00 238.590 .282 340.00 211.584 .250 341.00 189.309 .223 0 342.00 343.00 344.00 345.00 172.440 194.453 307.830 322.460
.203
.230
.366
.383 WAPWR-CS 6.2-94 NOVEMBER, 1986 4322e:1d
, , . - , c . , - - . .,,,..r_ -
,_ . - _ - - . -m ., - . _ - -- - - _ . - , .
TABLE 6.2-32 (SHEET 9 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 1 O 346.00 347.00 325.741 320.728
.387
.381 348.00 309.712 .368 349.00 293.402 .348 350.00 273.059 .324 351.00 250.111 .296 O 352.00 353.00 354.00 226.094 202.395 187.300
.267
.239
.221 355.00 207.541 .245 356.00 245.750 .291 357.00 270.833 .321 358.00 270.553 .321 359.00 259.857 .308
- l
-360.00 244.700 .289 361.00 226.418 .267 '
362.00 206.581 .244 '
i 363.00 190.901 .225 364.00 205.127 .242 365.00 234.324 .277 366.00 256.502 .304 367.00 260.356 .308 O 368.00 369.00 370.00 249.069 233.579 215.189
.295
.276
.254 371.00 197.902 .233 372.00 197.396 .233 373.00 214.117 .253 374.00 235.450 .279 375.00 245.734 .291 376.00 234.586 .277 377.00 219.920 .260 378.00 202.579 .239 379.00 187.839 .221
- 380.00 194.631 .230 381.00 212.568 .251 382.00 230.106 .272 383.00 235.946 .279 O
384.00 224.487 .265 385.00 209.583 .247 386.00 193.300 .228 387.00 187.316 .221
.388.00 193.225 .228 389.00 205.374 .242 l 390.00 215.253 .254 391.00 216.357 .255 392.00 204.148 .241 393.00 189.872 .224 394.00 180.752 .213 395.00 181.507 .214 396.00 187.776 .221 397.00 194.090 .229 0 398.00 399.00 400.00 401.00 196.768 193.376 181.660 171.168
.232
.228
.214
.201 WAPWR-CS 6.2-95 NOVEMBER, 1986 4322e:1d i
TABLE 6.2-32 (SHEET 10 of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY
's (SEC) (LBM/SEC) (BTU /SEC X 10E6)
~
402.00 167.391 .197 403.00 168.063 .198 404.00 170.815 .201 405.00 171.141 .201 406.00 168.536 .198 e 407.00 162.561 .191 408.00 155.071 .182 409.00 149.704 .176 410.00 145.339 .171 411.00 142.252 .167 412.00 139.413 .163 413.00 137.362 .161 414.00 133.810 .157 415.00 130.664 .153 ,
416.00 127.131 .149 417.00 122.898 .144 418.00 118.816 .139 419.00 114.940 .134 420.00 111.173 .130 421.00 107.439 .125 422.00 103.786 .121 423.00 100.300 .117 O 424.00 425.00 426.00 97.030 93.988 91.167
.113
.109
.106 427.00 88.565 .103 428.00 86.134 .100 429.00 83.873 .097 430.00 81.790 .095 431.00 79.892 .093 432.00 78.236 .091 433.00 76.863 .089 434.00 75.238 .087 435.00 73.825 .086 436.00 72.583 .084 437.00 71.479 .083 438.00 70.488 .082 439.00 69.593 .081 O 440.00 441.00 442.00 68.782 68.047 67.380
.080
.079
.078 443.00 66.777 .077 444.00 66.231 .077 445.00 65.739 .076 446.00 65.297 .076 O 447.00 448.00 449.00 64.900 64.546 64.231
.075
.075
.074 450.00 63.950 .074 451.00 63.702 .074 452.00 63.484 .073 453.00 63.291 .073 O 454.00 455.00 456.00 63.121 62.973 62.843
.073
.073
.073 457.00 62.730 .073 6.2-96 NOVEMBER, 1986 WAPWR-CS 4322e:1d I
1
l TABLE 6.2-32 (SHEET 11 Of 11)
CASE 4: 1.4 FT2 DOUBLE-ENDED RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC E 10E6) 458.00 62.631 .072 459.00 62.545 .072 460.00 62.470 .072 461.00 62.405 .072 462.00 62.349 .072 463.00 62.300 .072 O 464.00 465.00 466.00 62.258 62.221 62.189
.072
.072
.072 467.00 62.162 .072 468.00 62.138 .072 469.00 62.118 .072 470.00 62.100 .072 471.00 62.085 .072 .
472.00 62.071 .072 473.00 62.060 .072 474.00 62.050 .072 475.00 62.041 .072 476.00 62.033 .072 477.00 62.027 .072 478.00 62.021 .072 62.017 .072 O 479.00 480.00 62.012 .072 sr v v 1800.00 61.970 .072 1802.00 61.970 .072 1804.00 62.334 .072 1806.00 51.220 .059 1808.00 43.975 .051 1810.00 35.475 .041 1812.00 7.140 .008 1814.00 .590 .001 1816.00 .046 .000 1818.00 .004 .000 0 1820.00 .000 .000 se se s<
2000.00 0.000 0. 0 )0 l
0 WAPWR-CS 6.2-97 NOVEMBER, 1986 1322e:1d I- . _ , . - _ _ . - . __ - .
4 w
TABLE 6.2-33 (SHEET 1 Of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 0.00 0.000 0.000
.50 14317.938 16.967 1.00 13228.440 15.708 1.50 12569.433 14.952 2.00 11975.331 14.268 2.50 11432.083 13.640
' O 3.00 3.50 4.00 10939.465 10488.537 10072.122 13.068 12.542 12.055 4.50 9687.908 11.605 5.00 9328.642 11.182 5.50 8995.555 10.790 6.00 8686.239 10.425 6.50 8398.463 10.085 -
7.00 8130.582 9.767 7.50 7880.772 9.471 8.00 1903.427 2.288 8.50 1851.973 2.227 9.00 1855.176 2.231 9.50 1840.077 2.213 10.00 1825.400 2.195 10.50 1810.933 2.178 O 11.00 11.50 12.00 1796.704 1782.692 1768.851 2.161 2.144 2.128 12.50 1755.128 2.112 13.00 1741.476 2.095 13.50 1727.845 2.079 14.00 1714.213 2.063 14.50 1700.514 2.046 15.00 1686.535 2.030 15.50 1672.398 2.013 16.00 1658.119 1.996 16.50 1643.721 1.979 17.00 1629.220 1.961 17.50 1614.633 1.944 18.00 1599.981 1.926 18.50 1585.289 1.909 O 19.00 19.50 20.00 20.50 1570.600 1555.991 1541.445 1526.958 1.891 1.873 1.856 1.839 1
21.00 1512.666 1.822 21.50 1498.455 1.804 22.00 1484.456 1.788 22.50 1470.552 1.771 O- 23.00 23.50 1456.847 1443.357 1.754 1.738 24.00 1430.071 1.722 24.50 1417.050 1.707 25.00 1404.233 1.691 25.50 1391.714 1.676 26.00 1379.439 1.661 26.50 1367.010 1.646 WAPWR-CS 6.2-98 NOVEMBER, 1986 4328e:1d
m TABLE 6.2-33 (SHEET 2 Of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O 27.00 27.50 1355.283 1343.806 1.632 1.619 28.00 1332.582 1.605 28.50 1321.576 1.592 29.00 1310.854 1.579 29.50 1300.361 1.566 O 30.00 30.50 31.00 1290.101 1280.065 1270.245 1.554 1.542 1.530 31.50 1260.636 1.518 32.00 1251.235 1.507 32.50 1242.029 1.496 33.00 1233.013 1.485 33.50 1224.184 1.474 ,
34.00 1215.531 1.464 34.50 1207.050 1.454 35.00 1198.728 1.444 35.50 1190.559 1.434 36.00 1182.542 1.424 36.50 1174.669 1.415 37.00 1166.939 1.405 37.50 1159.352 1.396 O 38.00 38.50 39.00 1151.904 1144.591 1137.411 1.387 1.378 1.370 39.50 1130.364 1.361 40.00 1123.448 1.353 40.50 1116.658 1.345 41.00 1109.996 1.337 41.50 1103.454 1.329 42.00 1097.033 1.321 42.50 1090.735 1.313 43.00- 1084.554 1.306 43.50 1078.487 1.299 44.00 1072.533 1.291 44.50 1066.690 1.284 45.00 1060.956 1.277 45.50 1055.328 1.271 46.00 1049.805 1.264 O 46.50 47.00 47.50 1044.384 1039.059 1033.836 1.257 1.251 1.245 48.00 1028.709 1.239 48.50 1023.674 1.232 49.00 1018.730 1.226 49.50 1013.876 1.221 O 50.00 50.50 51.00 1009.108 2004.426 999.827 1.215 1.209 1.204 51.50 995.309 1.198 52.00 990.871 1.193 52.50 986.510 1.188 53.00 982.221 1.182 O 53.50 54.00 54.50 978.012 973.876 969.811 1.177 1.172 1.167 l WAPWR-CS 6.2-99 NOVEMBER,1986 l
1328c:1d I
( TABLE 6.2-33 (SHEET 3 of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER 7IME BREAK FLOW BREAK ENERGY s (SEC) (LBM/SEC) (BTU /SEC A 10E6) 55.00 965.815 1.162 55.50 961.888 1.158 56.00 958.028 1.153 56.50 954.233 1.148 57.00 950.502 1.144 57.50 946.833 1.140 0- 58.00 58.50 59.00 943.226 939.680 936.192 1.135 1.131 1.127 59.50 932.761 1.122 60.00 929.388 1.118 60.50 926.069 1.114 61.00 922.805 1.110 61.50 919.590 1.107 62.00 916.432 1.103 -
62.50 913.323 1.099 63.00 910.265 1.095 63.50 907.255 1.092 64.00 904.294 1.088 64.50 901.378 1.085
. 65.00 898.504 1.081 65.50 895.665 1.078 66.00 892.867 1.074 O'
- 66.50 67.00 890.111 887.396 1.071 1.068 67.50 884.721 1.064 68.00 882.064 1.061 68.50 879.486 1.058 69.00 876.926 1.055 69.50 874.401 1.052 70.00 871.912 1.049 70.50 869.458 1.046 71.00 867.038 1.043 71.50 864.651 1.040 72.00 862.296 1.037 72.50 859.973 1.034 73.00 857.682 1.032 73.50 855.423 1.029 74.00 853.195 1.026 l
O 74.50 75.00 75.50 850.997 848.829 846.692 1.024 1.021 1.018 76.00 844.584 1.016 76.50 842.505 1.013 77.00 840.455 1.011 77.50 838.433 1.008
/ 78.00 836.440 1.006
\d) 78.50 79.00 834.473 832.533 1.004 1.001 79.50 830.620 .999 80.00 828.733 .997 80.50 826.872 .994 81.00 825.036 .992
, 81.50 823.224 .990
! s 82.00 821.437 .988 82.50 819.674 .986 WAPWR-CS 6.2-100 NOVEMBER, 1986 l 1328e:1d
TABLE 6.2-33 (SHEET 4 of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O- 83.00 83.50 817.934 816.216
.984
.981 84.00 814.522 .979 84.50 812.849 .977 85.00 811.198 .975
- 85.50 809.568 .973 86.00 807.959 .971 86.50 806.370 .970 87.00 804.801 .968 87.50 803.252 .966 88.00 801.722 .964 88.50 800.211 .962 89.00 798.719 .960 89.50 797.245 .958 -
90.00 795.789 .957 90.50 794.352 .955 91.00 792.931 .953 91.50 791.528 .952 92.00 790.140 .950 92.50 788.769 .948 93.00 787.414 .947 93.50 786.076 .945 O
\
94.00 94.50 95.00 784.753 783.446 782.154 780.878
.943
.942
.940
.939 95.50 96.00 779.616 .937 96.50 778.369 .936 97.00 777.137 .934 97.50 775.918 .933 98.00 774.714 .931 98.50 773.524 .930 99.00 772.347 .928 99.50 771.184 .927 100.00 770.034 .925 101.00 768.326 .923 102.00 766.136 .921 103s00 763.998 .918
, 104.00 761.902 .916 105.00 759.851 .913 106.00 757.845 .911 107.00 755.884 .908 108.00 753.966 .906 109.00 752.088 .904 110.00 750.248 .902 111.00 748.444 .899 746.675 .897 0- 112.00 113.00 114.00 744.938 743.235
.895
.893 115.00 741.563 .891 116.00 739.923 .889 117.00 738.314 .887 118.00 736.736 .885 O 119.00 120.00 121.00 735.187 733.667 732.177
.883
.881
.880 6.2-101 NOVEMBER,1986 WAPWR-CS T328e:1d
t i
TABLE 6.2-33 (SHEET 5 Of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW 8REAK ENERGY (SEC) (LBM/SEC) (BTU /SEC 110E6)
[
122.00 730.715 .878 123.00 729.279 .876 124.00 727.872 .874
, 125.00 726.490 .873 126.00 725.131 .871 127.00 723.798 .869 .
0 128.00 129.00 130.00 722.487 721.199 719.934
.868
.866
.865 131.00 718.691 .863 132.00 717.469 .862 133.00 716.267 .860 134.00 715.086 .859 135.00 713.924 .857 -
136.00 712.781 .856 137.00 711.656 .855 138.00 710.549 .853 139.00 709.457 .852 140.00 708.383 .851 141.00 707.325 .850 142.00 706.281 .848 143.00 705.253 .847 O 144.00 145.00 146.00 704.238 703.237 702.249
.846
.845
.843 147.00 701.274 .842 148.00 700.311 .841 l 149.00 699.360 .840 150.00 698.416 .839 151.00 697.480 .838 152.00 696.555 .836 153.00 695.641 .835.
154.00 694.737 .834 155.00 693.842 .833 156.00 692.956 .832 157.00 692.080 .831 158.00 691.221 .830 159.00 690.373 .829 160.00 689.528 .828 l O 161.00 162.00 163.00 688.684 687.843 687.017
.827
.826
.825 164.00 686.200 .824 165.00 685.394 .823 166.00 684.592 .822 167.00 683.796 .821 0 168.00 169.00 170.00 683.001 682.211 681.433
.820
.819
.818 171.00 680.655 .817 172.00 679.869 .816 173.00 679.088 .815 174.00 678.322 .814 O 175.00 176.00 177.00 677.571 676.816 676.059
.813
.813
.812 6.2-102 NOVEMBER, 1986 WAPWR-CS 4328e:1d i
TABLE 6.2-33 (SHEET 6 Of 11) t CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 178.00 675.308 .811 179.00 674.557 .810 180.00 673.799 .809 181.00 673.047 .808 182.00 672.310 .807 N 183.00 671.578 .806 7
i 184.00 670.839 .805 185.00 670.103 .804 186.00 669.380 .804 187.00 668.670 .803 188.00 667.954 .802 189.00 667.234 .801 190.00 666.519 .800 191.00 665.802 .799 -
192.00 665.077 .798 193.00 664.356 .797 194.00 663.649 .797 195.00 662.955 .796 196.00 662.256 .795 197.00 661.552 .794 198.00 660.852 .793 199.00 660.150 .792 O 200.00 201.00 202.00 659.439 658.733 657.553
.791
.791
.789 203.00 656.634 .788 204.00 655.725 .787 205.00 654.934 .786 206.00 654.064 .785 207.00 653.225 .784 208.00 652.394 .783 209.00 651.572 .782 210.00 650.767 .781 211.00 649.969 .780 212.00 649.170 779 f
! 213.00 648.382 778 214.00 647.615 .777 215.00 646.866 .776 646.114 .775 l O 216.00 217.00 218.00 219.00 645.358 644.609 643.858
.774
.773
.773 220.00 643.098 .772 221.00 642.344 .771 222.00 641.606 .770 223.00 640.873 .769 0 224.00 225.00 226.00 640.130 639.389 638.662
.768
.767
.766 227.00 637.950 .765 228.00 637.231 .765 229.00 636.505 .764 230.00 635.783 .763 O 231.00 232.00 233.00 635.060 634.326 633.596
.762
.761
.760 WAPWR-CS 6.2-103 NOVEMBER, 1986 T328e:1d
TABLE 6.2-33 (SHEET 7 of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY
'~'s (SEC) (LBM/SEC) (BTU /SEC K 10E6) 234.00 632.882 .759 235.00 632.184 .758 236.00 631.479 .758 237.00 630.766 .757 238.00 630.058 .756 w 239.00 629.346 .755 l 240.00 628.625 .754 )
241.00 627.907 .753 242.00 627.206 .752 243.00 626.507 .752 244.00 625.798 .751 245.00 625.090 .750 246.00 624.394 .749 247.00 623.713 .748 248.00 623.023 .747 -
249.00 622.325 .746 250.00 621.630 746 251.00 620.932 .745 252.00 620.223 .744 253.00 619.517 .743 254.00 618.827 .742 255.00 618.140 .741 0 256.00 257.00 258.00 259.00 617.442 616.744 616.060 615.390
.741
.740
.739
.738 260.00 614.710 .737 261.00 614.022 .736 262.00 613.337 .736 263.00 612.649 .735 264.00 611.948 .734 265.00 611.250 .733 266.00 610.569 .732
- 267.00 609.903 .731
- 268.00 609.228 .731 l 269.00 608.544 .730
' 270.00 607.864 .729 271.00 607.181 .728 272.00 606.485 .727 O 273.00 274.00 275.00 605.792 605.117 604.445
.726
.726
.725 276.00 603.759 .724 277.00 603.074 .723 278.00 602.403 .722 l
279.00 601.748 .722 l 280.00 601.081 .721 281.00 600.404 .720 282.00 599.732 .719 283.00 599.054 .718 284.00 598.364 .717 285.00 597.677 .717 286.00 597.009 .716 287.00 596.343 .715 288.00 595.663 .714 289.00 594.984 .713 6.2-104 NOVEMBER, 1986 WAPWR-CS j '4328e:1d
OV TABLE 6.2-33 (SHEET 8 Of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6)
O- 290.00 291.00 594.320 593.672
.713
.712 i
292.00 593.012 .711 293.00 592.341 .710 294.00 591.675 .709 295.00 591.004 .708 fr-~g 296.00 590.319 .708 297.00 589.638 .707 298.00 598.976 .706 299.00 588.317 .705 300.00 587.643 .704 301.00 586.969 .704 302.00 586.312 703 303.00 585.670 .702 304.00 585.017 .701 -
305.00 584.352 .700 306.00 583.691 .700 307.00 583.026 .699 308.00 582.346 .698 309.00 581.670 .697 310.00 581.015 .696 311.00 580.361 .696 312.00 579.693 .695 0- 313.00 314.00 579.025 578.374
.694
.693 315.00 577.739 .692 316.00 577.092 .692 317.00 576.432 .691 318.00 575.777 .690 319.00 575.117 .689 320.00 574.442 .688 321.00 573.771 .688 322.00 573.122 .687 323.00 572.475 .686 324.00 571.812 .685 325.00 571.149 .684 326.00 570.505 .684 327.00 569.878 .683 328.00 569.236 .682 0 329.00 330.00 331.00 568.581 567.932 567.278
.681
.681
.630 332.00 566.607 .679 333.00 565.942 .678 334.00 565.299 .677 l
335.00 564.658 .677 336.00 564.000 .676 337.00 563.343 .675 338.00 562.705 .674 339.00 562.085 .673 340.00 561.449 .673 341.00 560.786 .672 342.00 560.124 .671 343.00 559.465 .670
) 558.805 .669 j 344.00 345.00 558.159 .669 WAPWR-CS 6.2-105 NOVEMBER, 1986 4328e:1d l
TABLE 6.2-33 (SHEET 9 Of 11)
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY
, (SEC) (LBM/SEC) (BTU /SEC 1 10E6) 346.00 557.541 .668 347.00 556.915 .667 .
348.00 556.264 .666 349.00 555.613 .666 350.00 554.986 .665 351.00 554.354 .664 l \ 352.00 553.701 .663 353.00 553.050 .662 354.00 552.404 .662 355.00 551.769 .661 356.00 551.153 .660 357.00 550.543 .659 358.00 549.910 .659 359.00 549.266 .658 360.00 548.611 .657 361.00 547.945 .656 362.00 547.295 .656 363.00 546.676 .655 364.00 546.052 .654 365.00 545.426 .653 366.00 544.809 .652 367.00 544.194 .652 368.00 543.560 .651 O- 3o9.00 370.00 371.00 542.918 542.268 541.605
.650
.649
.649 372.00 540.961 .648 373.00 540.349 .647 374.00 539.731 .646 375.00 539.110 .646 376.00 538.476 .645 377.00 537.845 .644 378.00 537.234 .643 379.00 536.631 .643 380.00 536.005 .642 381.00 535.369 .641 382.00 534.722 .640 383.00 534.062 .639 384.00 533.423 .639 i
O 385.00 386.00 387.00 532.819 532.207 531.590
.638
.637
.636
( 388.00 530.958 .636 l 389.00 530.331 .635 390.00 529.725 .634 391.00 529.129 .633
(
392.00 528.322 .632 393.00 524.305 .628 394.00 517.585 .619 395.00 $11.140 .612 396.00 503.342 .602 397.00 494.321 .591 398.00 483.592 .578 O 399.00 472.482 .565 400.00 459.199 .549 401.00 445.078 .532 6.2-106 NOVEMBER, 1985 WAPWR-CS T328e:1d
- d. %
ei .
~ ,
a m
t 1
TABLE 6.2-33 (SHEIT 10 of 11) ,
CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZER0' POWER TIME BREAK FD/J BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6)
ON ~402.00 428.491 .511 490 403.00, 410.413 '
4G4.00 390.673' 466 !
~'
405.00 369.376 .440 s '
406.00 346.548 .412 - s '
407.00 322.537 .383 O 408.00 409.00 410.00 297.650 272.122 246.653
.353
.322
.292 411.00 221.887 .262 .
412.00 198.236 .234 413.00 177.372 .209 414.00 160.057 .188 415.00 144.766 .170 416.00 132.228 .155 417.00 122.551 .143 418.00 112.985 .132 .
419.00 104.209 .122 420.00 96.521 .112 421.00 89.924 .105 422.00 84507 . D98 ,
! 423.00 79.222 .092 '
424.00 74.624 .087 425.00 70.347 .082 426.00 66.495. .077 427.00 62.71$ .073 . >
l 428.00 59.675 .067 .
/
429.00 61.082 .071 430.00 61.131 !071 431.00 61.221 .071 432.00 61.328 .071 433.00 61.446 .071 434.00 -
61.567 .071 '
435.00 61.685 .071 ,
436.00 61.793 .071 437.00 61.888 .072 438.00 61.969 .072 439.00 62.034 .072 440.00 - 62.084 .072 441.00 62.120 .072 442.00 62.143 .072
. 443.00 62.156 .072 444.00 62.161 .072 l .072
~
l 445.00 62.160 l 446.00 62.154 .072
! 447.00 62.145 .072 448.00 62.135 .072 .
' 449.00 62.125 .072 450.00 62.114 .072 _
451.00 62.103 .072 452.00 62.094 .072 453.00 62.085 .072 454.00 62.077 .072 455.00 62.070- .072 456.00 62.063 .072 457.00 62.058 ' .072 6.2-107 NOVEMBER,198I6 WAPWR-CS 4328e:1d <
i a l
r, ,
1, /
i s %
< 'S TABLE 6.2-33 (SHEET 11 Of 11)
'i y 1 CASE 5: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER TIMI BREAK FLOW BREAK ENERGY (BTU /SEC K 10E6)
O (SEC) (LBM/SEC) 458.00 62.052 .072 4 , 459.00 62.048 .072
- 460.00 62.044 .072
\
461.00 62.040 .072 i , 462.00 62.037 .072 j' < 463.00 62.034 .072 464.00 62.032 .072 465.00 62.029 .072 466.00 62.027 .072
.072 467.00 62.025 468.00 62.024 .072 469.00 62.022 .072 470.00 62.021 .072 471.00 62.019 .072 ,
472.00 62.018 .072 473.00 62.016 .072 474.00 62.015 .072 475.00 62.013 .072 476.00 62.012 .072 477.00. 62.011 .072 478.00 62.009 .072 479.00 62.008 .072 O 480.00 62.007 .072 l ir 3r 3r 1800.00 61.962 .072 l 1802.00 61.962 .072
! 1804.00 62.327 .072 1806.00 51.217 .059 1808.00 43.795 .050 1810.00 35.293 .041
< 1812.00 25.536 .029
- ; i 1814.00 0.000 0.000 t i i
I
,, se ,,
2000.0 0.000 0.030
(
t
'O _
[
l 'y '
t-WAPWR-CS 6.2-108 NOVEMBER, 1986
, 4328e:1d
. . _ - , _ . . . . _ _ _ . _ _ _ _ - ~ . - - . . _ - __ ._,-..__.-_ _ ._._ _ _____-._. _ _ _ _ _ . _ _ . _ _
TABLE 6.2-34 (SHEET 1 Of 7)
O.. CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER TIME hiEAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 0.00 0.000 0.000
.50 4 . 2247.129 2.676 1.00 '2247.129 2.676 1.50 1122.041 2.647 f 2.00 2206.269 2.629 2.50 2191.055 2.611 1 3.00 2177.616 2.596
' 2162.299 2.578 .I 3.50 4.00 2149.569 2.563 4.50 2136.431 2.548 5.00 2123.520 2.533 5.50 2110.985 2.518
/ 6.00 2098.885 2.504 6.50 2087.154 2.491 ~
7.00 2075.769 2.478 7.50 2064.736 2.465 8.00 2054.047 2.452 g 2.440 8.50 2043.667
< 9.00 2033.601 2.428 g 2025.143 2.419 9.50
%. 2.406 t 10.00 2014.635 2.397 l 10.50 2006.476 ,
11.00 1997.842 2.387
(
t 11.50 1989.230 2.377 12.00 1980.816 2.367 12.50 2065.173 2.467 13.00 2103.081 2.512 13.50 2103.061 2.511 14.00 2123.374 2.534 14.50 2143.778 2.558 15.00 2163.541 2.581 15.50 2182.840 2.603 16.00 2201.721 2.625 16.50 2220.212 2.647 17.00 2238.319 2.668 17.50 2255.967 2.6B?
18.00 2289.337 2. fit 1 18.50 2289.546 ?. 27 19.00 2332.907 . J71 O 19.50 20.00 20.50 2350.998 2368.179 2383.790
- 2. t v.
2.818 2.836 21.00 2398.051 2.852 21.50 2410.536 2.867 22.00 2421.298 2.879 22.50 2430.528 2.890 l
O 23.00 23.50 24.00 2437.782 2443.615 2447.743 2.898 2.905 2.910 24.50 2450.446 2.913 25.00 2452.125 2.915 25.50 2452.381 2.915 26.00 2452.046 2.915 O 26.50 2452.046 2.915 WAPWR-CS 16.2-109 NOVEMBER, 1986 4328e:1d e - . - . - -
1 m
TABLE 6.2-34 (SHEET 2 Of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY 4 (SEC) (LBM/SEC) (BTU /SEC X 10E6)
\('~'Y
'"' 2.909 27.00 2447.292 27.50 2447.292 2.909 28.00 2443.264 2.905 28.50 2438.785 2.900 29.00 2433.688 2.894 29.50 2427.850 2.887
/N 30.00 2421.815 2.880
('-) 30.50 2415.558 2.873 2.866 31.00 2409.130 31.50 2402.616 2.858 32.00 2395.878 2.851 32.50 2389.327 2.843 33.00 2382.820 2.836 33.50 2376.361 2.828 34.00 2369.967 2.821 .
34.50 2363.633 2.814 35.00 2357.367 2.806 35.50 2351.163 2.799 36.00 2345.018 2.792 36.50 2338.918 2.785 37.00 2332.648 2.780 l (
(-- j) 37.50 38.00 2259.002 2211.607 2.694 2.639
' 38.50 2166.576 2.587 39.00 2123.891 2.537 39.50 2083.452 2.490 40.00 2044.886 2.445 40.50 2008.009 2.402 41.00 1972.603 2.361 41.50 1938.824 2.321 42.00 1906.889 2.2E4 42.50 1875.828 2.247 43.00 1846.115 2.212 43.50 1817.711 2.179 44.00 1790.560 2.147 44.50 1764.580 2.116 45.00 1739.709 2.087 45.50 1715.877 2.059 46.00 1693.018 2.032
/ ) 46.50 1671.088 2.006 (s_,/ 47.00 1650.038 1.981 i
) 47.50 1629.813 1.957 48.00 1610.363 1.934 48.50 1591.638 1.912 49.00 1573.595 1.891 49.50 1556.188 1.870
/) 50.00 1539.376 1.850 t _f 50.50 1523.127 1.831 51.00 1507.324 1.812 51.50 1492.051 1.794 52.00 1477.331 1.776 52.50 1463.012 1.759 53.00 1449.106 1.743 l
53.50 1435.543 1.726
54.00 1422.429 1.711 54.50 1409.645 1.696 6.2-110 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-34 (SHEET 3 of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
' - ' 55.00 1397.192 1.681 55.50 1384.994 1.666 56.00 1373.094 1.652 56.50 1361.580 1.638 57.00 1350.313 1.625 57.50 1339.258 1.612 O 58.00 58.50 59.00 1328.458 1317.909 1307.714 1.599 1.586 1.574 59.50 1297.714 1.562 ,
60.00 1287.943 1.550 60.50 1278.391 1.539 l 61.00 1269.059 1.528 61.50 1259.945 1.517 )
62.00 1251.024 1.506 -
62.50 1242.305 1.496 63.00 1233.782 1.485 63.50 1225.449 1.475 64.00 1217.300 1.466 64.50 1209.339 1.456 65.00 1201.549 1.447 65.50 1193.929 1.438 l
66.00 1186.476 1.429 i ss ,s/ 66.50 1179.182 1.420 t . 67.00 1172.044 1.411 67.50 1165.061 1.403 68.00 1158.219 1.395 68.50 1151.500 1.387 69.00 1144.928 1.379 l
69.50 1138.501 1.371 70.00 1132.215 1.364 70.50 1126.062 1.356 71.00 1120.045 1.349 71.50 1114.153 1.342 72.00 1108.382 1.335 72.50 1102.733 1.328 73.00 1097.208 1.321 73.50 1091.797 1.315 74.00 1086.504 1.309 i
O 74.50 75.00 75.50 1081.319 1075.913 1070.959 1.302 1.296 1.290 76.00 1066.101 1.284 76.50 1061.343 1.278 I 77.00 1056.676 1.273 77.50 1052.107 1.267 0 78.00 78.50 79.00 1047.625 1043.232 1038.922 1.262 1.257 1.251 79.50 1034.698 1.246 80.00 1030.550 1.241 80.50 1026.484 1.236
! 81.00 1022.492 1.232 l 81.50 1018.575 1.227 l 82.00 1014.729 1.222 82.50 1010.953 1.218 6.2-111 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-34 (SHEET 4 Of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER
- TIME BREAK FLOW 8REAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 1007.248 1.213 83.50 1003.605 1.209 84.00 1000.031 1.205 84.50 996.516 1.200 85.00 993.065 1.196 85.50 989.672 1.192 O 86.00 86.50 87.00 986.338 983.062 979.838 1.188 1.184 1.180 87.50 976.670 1.176 88.00 973.683 1.173 88.50 970.732 1.169 89.00 967.838 1.166 89.50 964.988 1.162 90.00 962.201 1.159 .
90.50 959.465 1.156 91.00 956.770 1.152 91.50 954.116 1.149 92.00 951.501 1.146 92.50 948.920 1.143 93.00 946.373 1.140
' 93.50 943.858 1.137 94.00 941.405 1.134 94.50 938.958 1.131 95.00 936.538 1.128 95.50 934.145 1.125 96.00 931.780 1.122 96.50 929.471 1.119 97.00 927.168 1.117 97.50 924.891 1.114 98.00 922.641 1.111 98.50 920.456 1.109 99.00 918.266 1.106 99.50 916.095 1.103 100.00 913.984 1.101 101.00 910.805 1.097 102.00 906.830 1.092 103.00 902.824 1.087 1.083 O 104.00 105.00 106.00 107.00 898.944 895.144 891.446 887.835 1.078 1.074 1.069 108.00 884.313 1.065 109.00 880.876 1.061 I 110.00 877.511 1.057 111.00 874.218 1.053 i
O 112.00 113.00 114.00 870.995 867.836 864.741 1.049 1.045 1.041 l
l 115.00 861.710 1.038 116.00 858.738 1.034 117.00 855.828 1.031 118.00 852.976 1.027 0 119.00 120.00 121.00 850.182 847.444 844.760 1.024 1.020 1.017 6.2-112 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-34 (SHEET 5 of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 122.00 842.129 1.014 123.00 839.488 1.011 124.00 836.861 1.008 125.00 834.274 1.005 126.00 831.731 1.001 127.00 829.221 .998 0 128.00 129.00 130.00 826.758 824.330 821.944
.995
.993
.990 131.00 819.601 .987 132.00 817.294 .984 133.00 815.034 .981 134.00 812.807 .979 135.00 810.630 .976 136.00 808.488 .973 -
137.00 806.390 .971 138.00 804.321 .968 139.00 802.298 .966 140.00 800.304 .963 141.00 798.347 .961 142.00 796.418 .959 143.00 794.522 .957 O 144.00 145.00 146.00 792.649 790.809 788.985 954
.952
.950 147.00 787.189 .948 148.00 785.417 .946 149.00 783.670 .943 150.00 781.942 .941 151.00 780.238 .939 152.00 778.556 .937 153.00 776.898 .935 154.00 775.254 .933 155.00 773.632 .931 156.00 772.031 .929 157.00 770.449 .927 158.00 768.881 .926 159.00 767.332 .924 160.*00 765.799 .922 O 161.00 162.00 163.00 764.284 762.787 761.301
.920
.918
.916 164.00 759.830 .915 165.00 758.373 .913 166.00 756.934 .911 167.00 755.508 .909 0 168.00 169.00 170.00 754.094 752.691 751.302
.908
.906
.904 171.00 749.926 .903 172.00 748.567 .901 173.00 747.211 .899 174.00 745.870 .898 O 175.00 176.00 177.00 744.541 743.222 741.915
.896
.894
.893 6.2-113 NOVEMBER, 1986 WAPWR-CS 4328e:1d
f TABLE 6.2-34 (SHEET 6 Of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER 7IME BREAK FLOW BREAK ENERGY O (SEC) 178.00 (LBM/SEC) 740.619 739.332 (BTU /SEC K 10E6)
.891
.890 179.00 180.00 738.055 .888 181.00 736.787 .887 182.00 735.528 .885 183.00 734.284 .884
\ 184.00 733.049 .882 185.00 731.854 .881 186.00 730.676 .879 187.00 729.516 .878 188.00 728.368 .877 189.00 727.225 .875 190.00 726.087 .874 191.00 724.956 .872 -
192.00 723.826 .871 193.00 722.700 .870 194.00 721.577 .868 195.00 720.459 .867 196.00 719.345 .866 197.00 718.234 .864 198.00 717.129 .863 199.00 716.025 .862 O 200.00 202.00 204.00 714.923 712.845 705.291
.860
.858
.849 206.00 704.448 .848 208.00 699.304 .841 210.00 698.117 .840 212.00 694.226 .835 214.00 692.797 .833 216.00 689.235 .829 218.00 677.255 .814 220.00 640.269 .770 222.00 614.500 .738 224.00 577.046 .693 226.00 531.949 .638 228.00 482.243 .578 230.00 430.562 .515 232.00 378.624 452 234.00 328.986 .392 236.00 283.359 .337 238.00 244.534 .290 240.00 211.397 .250 242.00 183.124 .216 244.00 159.538 .188 246.00 141.125 .166 O* 248.00 250.00 127.357 114.013
.150
.134 252.00 103.354 .121 254.00 95.832 .112 256.00 88.999 .104 258.00 83.047 .097 78.291 .091 O
l 260.00
' 262.00 74.650 .087 264.00 71.849 .084 l 266.00 69.669 .081 6.2-114 NOVEMBER, 1986 WAPWR-CS 4328e:1d
O U
TABLE 6.2-34 (SHEET 7 Of 7)
CASE 6: 1.1 FT2 SPLIT RUPTURE AT 102 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 67.947 .079 270.00 66.608 .077 272.00 65.581 .076 274.00 64.786 .075 276.00 64.166 .075 278.00 63.686 .074
( 280.00 63.314 .074 282.00 63.027 .073 284.00 62.804 .073 286.00 62.630 .073 288.00 62.495 .073 290.00 62.390 .072 292.00 62.308 .072 294.00 62.243 .072 -
296.00 62.193 .072 298.00 62.154 .072 300.00 62.123 .072 302.00 62.099 .072 304.00 62.080 .072 306.00 62.065 .072 308.00 62.053 .072 310.00 62.044 .072 l
O 312.00 314.00 316.00 62.036 62.030 62.025
.072
.072
.072 318.00 62.021 .072 320.00 62.017 .072 322.00 62.014 .072 324.00 62.011 .072 326.00 62.009 .072 328.00 62.006 .072 330.00 62.004 .072 u 3r v 1800.00 61.983 .072 0 1804.00 1808.00 1812.00 1816.00 62.117 62.757 15.824
.651
.072
.073
.018
.001 1820.00 .021 .000 1824.00 .001 .000 1828.00 .000~
.000 0
20db.00 0.dOO 0.03 0 0
WAPWR-CS 6.2-115 NOVEMBER, 1986 1328a:1d l
i TABLE 6.2-35 (SHEET 1 Of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) 0.00 0.000 0.000
.50 2401.244 2.855 1.00 2400.166 2.854 1.50 2373.340 2.823 2.00 2356.198 2.803 2.50 2339.695 2.784 O 3.00 3.50 4.00 2323.728 2307.543 2292.623 2.766 2.747 2.730 4.50 2278.969 2.714 5.00 2265.020 2.698 5.50 2251.388 2.682 6.00 2238.159 2.667 6.50 2225.338 2.652 -
7.00 2212.902 2.638 7.50 2200.844 2.624 8.00 2189.138 2.610 8.50 2177.779 2.597 9.00 2166.767 2.584 9.50 2156.082 2.572 10.00 2145.701 2.560 10.50 2136.459 2.549 0 11.00 11.50 12.00 2125.936 2117.126 2157.213 2.537 2.527 2.574 2.601 12.50 2179.837 13.00 2179.837 2.600 13.50 2190.366 2.613 14.00 2200.937 2.625 14.50 2211.165 2.637 15.00 2221.139 2.648 15.50 2230.897 2.660 16.00 2240.477 2.671 16.50 2249.871 2.681 17.00 2259.050 2.692 17.50 2276.426 2.712 18.00 2276.887 2.712 18.50 2293.030 2.731 2305.988 2.746 0 19.00 19.50 20.00 20.50 2318.829 2340.457 2349.307 2.761 2.786 2.796 21.00 2357.265 2.806 21.50 2363.753 2.813 22.00 2369.161 2.819 22.50 2373.073 2.824 O 23.00 23.50 24.00 2375.704 2377.453 2377.453 2.827 2.829 2.829 24.50 2377.820 2.829 25.00 2377.820 2.830 25.50 2376.570 2.828 26.00 2374.224 2.826 O 2(.50 2371.189 2.822 WAPWR-CS 6.2-116 NOVEMBER, 1986 4328e:1d
TABLE 6.2-35 (SHEET 2 Of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY
, (SEC) (LBM/SEC) (BTU /SEC X 10E6) 1 27.00 2367.225 2.818 27.50 2362.841 2.813 28.00 2357.989 2.807 28.50 2352.730 2.801 29.00 2346.957 2.794 29.50 2341.127 2.788
', 30.00 2335.148 2.781 30.50 2329.045 2.774 31.00 2322.872 2.767 31.50 2315.730 2.758 32.00 23D9.498 2.751 32.50 2303.289 2.744 33.00 2297.093 2.737 33.50 2290.933 2.730 34.00 2284.802 2.723 -
34.50 2278.715 2.716 35.00 2272.666 2.709 35.50 2266.653 2.702 36.00 2260.673 2.695 36.50 2254.640 2.689 37.00 2188.421 2.612 37.50 2144.845 2.561 38.00 2103.400 2.513 0s -
38.50 39.00 2064.077 2026.493 2.467 2.424 39.50 1990.403 2.381 40.00 1955.795 2.341 40.50 1922.669 2.302 41.00 1891.362 2.265 41.50 1860.895 2.230 42.00 1831.673 2.195 42.50 1803.705 2.162 43.00 1776.905 2.131 43.50 1751.210 2.101 44.00 1726.558 2.071 44.50 1702.897 2.044 45.00 1680.175 2.017 45.50 1658.356 1.991 46.00 1637.386 1.966 O 46.50 47.00 47.50 1617.218 1597.806 1579.035 1.942 1.919 1.897 48.00 1560.963 1.876 48.50 1543.488 1.855 49.00 1526.644 1.835 49.50 1510.420 1.816 O 50.00 50.50 51.00 1494.682 1479.405 1464.644 1.797 1.779 1.761 51.50 1450.298 1.744 52.00 1436.364 1.727 52.50 1422.823 1.711 53.00 1409.616 1.696 53.50 1396.816 1.680 54.00 1384.317 1.665 54.50 1372.085 1.651 WAPWR-CS 6.2-117 NOVEMBER, 1986 4328e:1d
TABLE 6.2-35 (SHEET 3 of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
' 55.00 1360.151 1.637 55.50 1348.583 1.623 56.00 1337.267 1.609 56.50 1326.217 1.596 57.00 1315.418 1.583 57.50 1304.822 1.570 58.00 1294.536 1.558
\
58.50 1284.463 1.546 59.00 1274.615 1.534 59.50 1264.985 1.523 60.00 1255.570 1.512 60.50 1246.360 1.501 61.00 1237.352 1.490 61.50 1228.537 1.479 62.00 1219.918 1.469 -
62.50 1211.487 1.459 63.00 1203.241 1.449 63.50 1195.165 1.439 64.00 1187.263 1.430 64.50 1179.529 1.420 65.00 1171.961 1.411 65.50 1164.552 1.402
('"' 66.00 1157.296 1.394 66.50 1150.171 1.385 67.00 1143.199 1.377 67.50 1136.376 1.369 68.00 1129.702 1.361 68.50 1123.168 1.353 69.00 1116.774 1.345 69.50 1110.510 1.337 70.00 1104.375 1.330 70.50 1098.373 1.323 71.00 1092.498 1.316 71.50 1086.748 1.309 72.00 1081.118 1.302 72.50 1075.275 1.295 73.00 1069.895 1.289 73.50 1064.617 1.282 1.276 O 74.00 74.50 75.00 75.50 1059.449 1054.382 1049.419 1044.552 1.270 1.264 1.258 76.00 1039.782 1.252 76.50 1035.105 1.247 77.00 1030.515 1.241 77.50 1026.018 1.236 O 78.00 78.50 79.00 1021.602 1017.273 1013.021 1.230 1.225 1.220 79.50 1008.851 1.215 80.00 1004.756 1.210 80.50 1000.737 1.205 81.00 996.790 1.201 O 81.50 82.00 82.50 992.914 989.108 985.368 1.196 1.191 1.187 WAPWR-CS 6.2-118 NOVEMBER, 1986 4328e:1d
-_ - - . - - _ - - ~_ _- --. . , -_
l
, TABLE 6.2-35 (SHEET 4 of 8)
) CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 981.695 1.182 83.50 978.085 1.178 84.00 974.537 1.174 84.50 971.052 1.170 85.00 967.624 1.165 85.50 964.255 1.161 86.00 960.942 1.157 86.50 957.685 1.153 87.00 954.481 1.150 4 87.50 951.329 1.146 88.00 948.230 1.142 88.50 945.176 1.138 89.00 942.171 1.135 89.50 939.212 1.131 90.00 936.298 1.128 -
90.50 933.430 1.124 91.00 930.605 1.121
. 91.50 927.822 1.117 92.00 925.084 1.114 92.50 922.386 1.111 93.00 919.728 1.108 93.50 917.109 1.105
' 94.00 914.531 1.101 94.50 911.988 1.098 l 1.095 95.00 909.484 l 95.50 907.017 1.092 96.00 904.584 1.089 i 96.50 902.187 1.087 97.00 899.825 1.084 97.50 897.495 1.081 98.00 895.199 1.078 98.50 892.935 1.075 99.00 890.702 1.073 99.50 888.501 1.070 100.00 886.330 1.067 101.00 883.111 1.064 102.00 879.043 1.059 l 103.00 875.065 1.054 104.00 871.115 1.049 105.00 867.206 1.044 106.00 863.378 1.040 107.00 859.639 1.035 108.00 855.980 1.031 109.00 852.407 1.026
! 110.00 848,904 1.022 111.00 845.475 1.018 l 112.00 842.110 1.014 113.00 838.820 1.010 114.00 835.595 1.006 115.00 832.445 1.002 116.00 829.364 .999
- 117.00 826.355 .995 118.00 823.412 .991 O 119.00 120.00 121.00 820.542 817.731 814.990
.988
.985
.981 WAPWR-CS 6.2-119 NOVEMBER, 1986 4328e:1d 4
~w..--.-r,-.-,_,,,,,--..,,,,,,,,_,,,m _- _ ,,._ ,_-m- , .-.. _ . _ - -.,---
I TABLE 6.2-35 (SHEET 5 of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 122.00 812.303 .978 123.00 809.677 .975 124.00 807.098 .972 125.00 804.576 .969 126.00 802.102 .966 127.00 799.680 .963 O 128.00 129.00 130.00 797.295 794.962 792.669
.960
.957
.954 131.00 790.421 .952 132.00 788.209 .949 133.00 786.037 .946 134.00 783.909 .944 135.00 781.811 .941 136.00 779.752 .939 137.00 777.722 .936 138.00 775.730 .934 139.00 773.770 .931 140.00 771.841 .929 141.00 769.946 .927 142.00 768.075 .925 143.00 766.235 .922 O 144.00 145.00 146.00 764.421 762.634 760.874
.920
.918
.916 147.00 759.140 .914 148.00 757.430 .912 149.00 755.744 .910 150.00 754.080 .908 151.00 752.441 .906 152.00 75u.822 .904 153.00 749.225 .902 l 154.00 747.649 .900 155.00 746.094 .898 156.00 744.558 .896 157.00 743.071 .894 158.00 741.619 .893 159.00 740.198 .891 0 160.00 161.00 162.00 163.00 738.801 737.423 736.060 734.711
.389
.887
.886
.884 164.00 733.376 .883 165.00 732.053 .881 166.00 730.740 .879 167.00 729.436 .878 O 168.00 169.00 170.00 728.141 726.858 725.584
.876
.875
.873 171.00 724.321 .872 172.00 723.068 .870 173.00 721.825 .869 174.00 720.591 .867 O 175.00 176.00 177.00 719.368 718.155 716.956
.866
.864
.863 6.2-120 NOVEMBER, 1986 WAPWR-CS T328e:1d
~ _ _ . . _ . _ . . ._
l
+
l l
TABLE 6.2-35 (SHEET 6 of 8) f CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME 8REAK FLOW 8REAK ENERGY (SEC) (L8M/SEC) (BTU /SEC K 10E6) l 178.00 715.766 .861 179.00 714.588 .860 180.00 713.420 .858 181.00 712.261 .857 l 182.00 711.110 .856 183.00 709.972 .854 184.00 708.846 .853 O- 185.00 186.00 707.727 706.617
.852
.850 187.00 705.516 .849 ;
188.00 704.420 .848 l 189.00 703.335 .846 I 190.00 702.259 .845 ,
191.00 701.191 .844 l 192.00 700.153 .842 .
193.00 699.217 .841 194.00 698.260 .840 195.00 697.294 .839 196.00 696.328 .838 197.00 695.362 .837 i 198.00 694.396 .835 l 199.00 693.430 .834 200.00 692.464 .833 O 202.00 204.00 206.00 690.681 684.506 683.294
.831
.823
.822 ;
208.00 679.531 .817 1 210.00 677.422 .815 212.00 -675.340 .812 214.00 672.689 .809 216.00 670.671 .807 218.00 668.357 .804 220.00 666.228 .801 '
222.00 664.062 .799 224.00 661.969 .796 226.00 659.890 .794 l 228.00 657.847 .791 230.00 655.826 .789 232.00 653.833 .786
< O 234.00 236.00 238.00 651.869 649.922 647.990
.784
.782
.779 240.00 646.082 .777 242.00 640.507 .770 244.00 610.947 .734 246.00 596.235 .716
.702 O 248.00 250.00 252.00 254.00 584.688 564.817 541.599 523.757
.678
.650
.629 256.00 500.137 .600 258.00 463.898 .556 260.00 427.485 .512 0 262.00 264.00 266.00 396.141 361.281 321.925 474 431
.384 6.2-121 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-35 (SHEET 7 of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER TIME BREAK FLOW BREAK ENERGY
/ (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 284.829 .339 270.00 253.668 .301 272.00 224.857 .267 274.00 197.192 .233 276.00 173.346 .205 278.00 153.828 .181 O 280.00 282.00 284.00 138.615 125.419 112.967
.163
.147
.132 286.00 103.241 .121 288.00 96.079 .112 290.00 89.616 .105 292.00 83.865 .098 294.00 79.145 .092 296.00 75.461 .088 -
298.00 72.593 .085 300.00 70.338 .082 302.00 68.544 .080 304.00 67.116 .078 306.00 65.997 .077 308.00 65.133 .076 310.00 64.462 .075 O 312.00 314.00 316.00 63.936 63.523 63.198
.074
.074
.073 318.00 62.944 .073 320.00 62.745 .073 322.00 62.588 .073 324.00 62.465 .073 326.00 62.368 .072 328.00 62.291 .072 330.00 62.231 .072 332.00 62.184 .072 334.00 62.146 .072 l 336.00 62.117 .072 1 338.00 62.093 .072 340.00 62.075 .072 342.00 62.060 .072 O 344.00 346.00 348.00 350.00 62.048 62.038 62.031 62.025
.072
.072
.072
.072 352.00 62.020 .072
' 354.00 62.015 .072 356.00 62.012 .072 .
358.00 62.009 .072 360.00 62.007 .072 180b.00 61.579 . 05 2 0 1804.00 1808.00 1812.00 62.113 62.753 18.563
.072
.073
.021 WAPWR-CS 6.2-122 NOVEMBER, 1986 4323e:1d
TABLE 6.2-35 (SHEET 8 of 8)
CASE 7: 1.1 FT2 SPLIT RUPTURE AT 75 PC POWER i
5 TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) l 1816.00 .922 .001 i 1820.00 .037 .000
- 1824.00 .002 .000 i 1828.00 .000 .000 1 l
l
)
v i
- 2000.00 0.0b0 0.000 i
t I !
O. ,
l i
i O
6.2-123 NOVEMBER, 1986 WAPWR-CS T328e:Id
TABLE 6.2-36 (SHEET 1 Of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK TLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) 0.00 0.000 0.000
.50 2538.891 3.014 1.00 2537.406 3.013 1.50 2508.579 2.979 2.00 2489.684 2.958 2.50 2471.521 2.937 O(,_,/ 3.00 2453.949 2.917 3.50 2436.933 2.897 4.00 2420.436 2.878 4.50 2404.431 2.860 5.00 2388.906 2.842 5.50 2373.849 2.824 6.00 2359.785 2.808 6.50 2345.654 2.792 -
7.00 2331.899 2.776 7.50 2318.547 2.761 8.00 2304.860 2.745 8.50 2292.309 2.730 9.00 2280.117 2.716 9.50 2268.266 2.703 10.00 2256.754 2.689 10.50 2245.558 2.676 O 11.00 11.50 12.00 2234.671 2244.725 2245.780 2.664 2.676 2.677 12.50 2253.944 2.687 13.00 2256.058 2.689 13.50 2258.050 2.691 14.00 2259.823 2.693 14.50, 2261.811 2.696 15.00 2263.509 2.698 15.50 2265.444 2.700 16.00 2267.117 2.702 16.50 2269.044 2.704 17.00 2272.388 2.708 17.50 2272.944 2.708 18.00 2282.987 2.720 18.50 2290.005 2.728 O 19.00 19.50 20.00 2296.625 2302.585 2308.106 2.736 2.742 2.749 20.50 2312.749 2.754 21.00 2316.783 2.759 21.50 2320.552 2.763 22.00 2324.108 2.768 O 22.50 23.00 23.50 2324.108 2324.344 2324.344 2.768 2.768 2.768 24.00 2323.234 2.767 24.50 2321.219 2.764 25.00 2318.617 2.762 25.50 2314.427 2.757 0 26.00 26.50 2310.592 2306.295 2.752 2.747 6.2-124 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-36 (SHEET 2 of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER
' TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) ' (BTU /SEC K 10E6) 27.00 2301.576 2.742 27.50 2296.512 2.736 28.00 2290.963 2.730 28.50 2285.356 2.723 l 29.00 2279.585 2.717 29.50 2273.670 2.710 30.00 2267.660 2.703 30.50 2261.582 2.696 31.00 2255.465 2.689 31.50 2249.150 2.682 32.00 2242.993 2.674 32.50 2236.853 2.667 33.00 2230.729 2.660 33.50 2224.614 2.653 ,
- 34.00 2218.524 2.646 34.50 2212.464 2.639 i'
35.00 2206.467 2.632 35.50 2200.491 2.625 36.00 2194.536 2.620 36.50 2133.739 2.549 37.00 2093.388 2.502 37.50 2054.892 2.457 i
38.00 2018.102 2.414 38.50 1982.741 2.372 39.00 1948.791 2.333 39.50 1916.244 2.295 40.00 1885.447 2.258 40.50 1855.410 2.223 l 41.00 1826.559 2.189 I 41.50 1798.896 2.157 42.00 1772.338 2.125 42.50 1746.829 2.095.
43.00 1722.318 2.066 43.50 1698.738 2.039 44.00 1676.069 2.012 44.50 1654.271 1.986 45.00 1633.294 1.961 45.50 1613.098 1.937 46.00 1593.638 1.914 O. 46.50 47.00 1574.820 1556.637 1.892 1.870
- 47.50 1539.061 1.850 48.00 1522.060 1.829 48.50 1505.608 1.810 49.00 1489.672 1.791 49,50 1474.283 1.773 O 50.00
$0.50 51.00 1459.386 1444.917 1430.927 1.755 1.738 1.721 51.50 1417.301 1.705 52.00 1404.044 1.689 52.50 1391.126 1.674 53.00 1378.535 1.659 l
1 O 53.50 54.00 54.50 1366.254 1354.275 1342.580 1.644 1.630 1.616 6.2-125 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-36 (SHEET 3 Of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER
' TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 55.00 1331.164 1.602 55.50 1320.011 1.589 56.00 1309.116 1.576 56.50 1298.464 1.563 57.00 1288.052 1.550 57.50 1277.867 1.538 0 58.00 58.50 59.00 1267.908 1258.162 1248.629 1.526 1.515 1.503 59.50 1239.297 1.492 60.00 1230.173 1.481 60.50 1221.232 1.470
- 61.00 1212.486 1.460 61.50 1203.917 1.450 -
62.00 1195.528 1.440 62.50 1187.314 1.430 63.00 1179.278 1.420 63.50 1171.401 1.411 64.00 1163.686 1.401 j 64.50 1156.115 1.392 65.00 1148.692 1.383 65.50 1141.422 1.375 O 66.00 66.50 67.00 1134.306 1127.340 1120.522 1.366 1.358 1.350 67.50 1113.846 1.341 68.00 1107.308 1.334 1 68.50 1100.902 1.326 69.00 1094.638 1.318 69.50 1088.498 1.311 70.00 1082.493 1.304 70.50 1076.281 1.296
' 71.00 1070.534 1.289 l 71.50 1064.901 1.283 l 72.00 1059.380 1.276 72.50 1053.969 1.269 73.00 1048.666 1.263 73.50 1043.466 1.257 74.00 1038.368 1.251 O 74.50 75.00 75.50 1033.368 1028.465 1023.654 1.245 1.239 1.233 76.00 1018.935 1.227 76.50 1014.306 1.222 77.00 1009.762 1.216 77.50 1005.302 1.211 O 78.00 78.50 79.00 1000.926 996.626 992.407 1.206 1.200 1.195 79.50 988.262 1.190 80.00 984.192 1.185 80.50 980.194 1.181 81.00 976.266 1.176 O 81.50 82.00 82.50 972.407 968.614 964.887 1.171 1.167 1.162 15.2-126 NOVEMBER, 1986 WAPWR-CS 4328e:1d
r TABLE 6.2-36 (SHEET 4 Of 8)
, CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERCY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 961.225 1.158 83.50 957.622 1.153 84.00 954.082 1.149 84.50 950.600 1.145 85.00 947.174 1.141 85.50 O 86.00 86.50 87.00 943.800 940.458 937.152 933.892 1.137 1.133 1.129 1.125 87.50 930.675 1.121 88.00 927.504 1.117
! 88.50 924.374 1.113 89.00 921.291 1.110 l 89.50 918.249 1.106 ~
i 90.00 915.254 1.102 90.50 912.296 1.099 l 91.00 909.383 1.095 91.50 906.512 1. 09 2 92.00 903.680 1.088 92.50 900.890 1.085 93.00 898.135 1.082 93.50 895.421 1.078 O 94.00 94.50 95.00 892.746 890.106 887.506 1.075 1.072 1.069 95.50 . 884.940 1.066 96.00 882.412 1.063 96.50 879.919 1.060 97.00 877.460 1.057 97.50 875.038 1.054 98.00 872.649 1.051 98.50 870.295 1.048 99.00 867.975 1.045 99.50 865.687 1.042 100.00 863.435 1.040 l 101.00 860.097 1.036 j 102.00 855.865 1.031 .
! 103.00 851.741 1.026 104.00 847.710 1.021
\g,,, 105.00 843.781 1.016 106.00 839.952 1.011 107.00 836.227 1.007 108.00 832.591 1.003 109.00 829.044 .998 110.00 825.573 .994 111.00 822.183 .990 O 112.00 113.00 114.00 818.860 815.612 812.431
.986
.982
.978 115.00 809.320 .974 116.00 806.273 .971 117.00 803.293 .967 118.00 800.379 .964 O 119.00 120.00 121.00 797.526 794.733 792.002
.960
.957
.953 l
1 6.2-127 NOVEMBER, 1986
~
WAPWR-CS {
4328e:1d
1 O
G TABLE 6.2-36 (SHEET 5 of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O 122.00 123.00 789.329 786.711
.950
.947 124.00 784.145 .944 125.00 781.636 .941 126.00 779.173 .938 127.00 776.760 .935 O 128.00 129.00 130.00 774.394 772.074 769.800
.932
.929
.927 131.00 767.588 .924 132.00 765.450 .921 133.00 763.369 .919 134.00 761.340 .916 135.00 759.355 .914 136.00 757.408 .912 .
137.00 755.495 .909 138.00 753.616 .907 139.00 751.768 .905 140.00 749.946 .903 141.00 748.154 .900
' 142.00 746.389 .898 143.00 744.649 .896 f 144.00 742.933 .894 l
145.00 741.238 .892 146.00 739.568 .890 147.00 737.921 .888 148.00 736.298 .886 149.00 734.696 .884 150.00 733.119 .882 151.00 731.564 .880 152.00 730.030 .879 153.00 728.517 .877 154.00 727.027 .875 155.00 725.561 .873 156.00 724.115 .871 157.00 722.687 .870 158.00 721.278 .868 159.00 719.889 .866 160.00 718.519 .865
- 161.00 717.168 .863 162.00 715.834 .861 163.00 714.518 .860 l
! 164.00 713.219 .858 165.00 711.936 .857 166.00 710.669 .855 167.00 709.416 .854 O 168.00 169.00 170.00 708.181 706.961 705.755
.852
.851
.849 171.00 704.559 .848 172.00 703.377 .846 173.00 702.210 .845 174.00 701.055 .843 1
0 175.00 176.00 177.00 699.915 698.787 697.674
.842
.841
.839 6.2-128 NOVEMBER, 1986 WAPWR-CS l 1328e:1d
. - - - - - - - . - . - . ~ , . . - - - . - . - - - - . - . - . - - - - - - . - - . - . - - _ - . - - - - - - - - - - . . . - - - - - -
TABLE 6.2-36 (SHEET 6 of 8) -
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY
/N (SEC) (LBM/SEC) (BTU /SEC A 10E6) 178.00 696.572 .838 179.00 695.481 .837 180.00 694.400 .835 181.00 693.329 .834 182.00 692.271 .833 i 183.00 691.223 .832 l 184.00 690.185 .830 185.00 689.156 .829 186.00 688.138 .828 187.00 687.129 .827 188.00 686.130 .825 189.00 685.139 .824 190.00 684.155 .823 191.00 683.181 .822 192.00 682.218 .821 -
193.00 681.261 .819 194.00 680.308 .818 195.00 679.356 .817 196.00 678.412 .816 197.00 677.479 .815 198.00 676.554 .814 199.00 675.635 .813 O '
200.00 202.00 204.00 674.722 673.123 668.244
.812
.810
.804 206.00 666.346 .801 208.00 663.448 .798 210.00 661.190 .795 212.00 659.043 .793 214.00 656.955 .790 216.00 654.905 .788 218.00 652.885 .785 220.00 650.886 .783 222.00 648.911 .780 224.00 646.965 .778 226.00 645.042 .776 228.00 643.145 .773 230.00 641.271 .771 232.00 639.424 .769 0 234.00 236.00 238.00 637.591 635.769 633.971
.767
.764
.762 240.00 632.187 .760 l
242.00 630.420 .758 244.00 628.659 .756 246.00 626.917 .754 f'-'g 248.00 625.176 .752 250.00 623.446 .749 252.00 621.719 .747 254.00 620.003 .745 256.00 618.300 743 258.00 616.595 .741 260.00 614.906 .739 l
1 0 262.00 264.00 266.00 613.214 611.537 605.008
.737
.735
.727 WAPWR-CS 6.2-129 NOVEMBER, 1986 l T328e:1d
- - - _ . -- - - - - . _ - _ _ _ _ _ - - - . - _ . - - - - _ - . ~ - - - - . _ . . - . - - . - -
TABLE 6.2-36 (SHEET 7 of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 574.923 .691 270.00 555.481 .667 272.00 519.026 .623 274.00 477.107 .572 276.00 424.769 .508 278.00 370.880 443 O 280.00 282.00 284.00 358.126 448.689 474.291 429
.538
.568 286.00 446.406 .535 288.00 403.922 483 290.00 358.654 429 292.00 355.932 426 294.00 402.295 .482 296.00 415.443 497 298.00 386.217 461 300.00 334.721 .399 302.00 290.235 .346 304.00 319.848 .382 306.00 339.590 .405 308.00 317.280 .378 310.00 263.512 .313 O 312.00 314.00 316.00 226.258 232.507 234.884
.269
.276
.279 318.00 212.932 .252 320.00 173.255 .205 322.00 156.658 .185 324.00 157.734 .186 326.00 142.016 .167 328.00 121.981 .143 330.00 112.796 .132 332.00 107.158 .126 334.00 100.191 .117 336.00 92.613 .108 338.00 86.878 .101 340.00 82.423 .096 342.00 78.525 .092 344.00 75.171 .088 O\ 346.00 348.00 72.498 70.413
.084
.082 350.00 68.745 .080 352.00 67.387 .078 354.00 66.294 .077 356.00 65.429 .076 358.00 64.744 .075 O 360.00 362.00 364.00 64.198 63.759 63.407
.075
.074
.074 366.00 63.126 .073 368.00 62.902 .073 370.00 62.722 .073 372.00 62.576 .073 0 374.00 376.00 378.00 62.463 62.371 62.297
.073
.072
.072 6.2-130 NOVEMBER, 1986 WAPWR-CS 4328e:1d
. . _ ~..
TABLE 6.2-36 (SHEET 8 of 8)
CASE 8: 1.1 FT2 SPLIT RUPTURE AT 50 PC POWER TIME BREAK FLOW BREAK ENERGY O (SEC) 380.00 (LBM/SEC) 62.237 (BTU /SEC A 10E6)
.072 382.00 62.189 .072 384.00 62.151 .072 386.00 62.120 .072 388.00 62.095 .072 l
390.00 62.075 .072 I
392.00 62.059 .072 l 394.00 62.046 .072 1
396.00 62.035 .072 l
' 398.00 62.027 .072 400.00 62.020 .072 4
180h.00 61.974 .$72 1804.00 62.109 .072 1808.00 62.747 .073 1812.00 22.048 .026 1816.00 1.456 .002
.081 .000 O 1820.00 1824.00 1828.00
.004
.000
.000
.000 200b.00 0.'dOO 0.$00 O
O O
6.2-131 NOVEMBER,1986 WAPWR-CS 4328e:1d ,
-- -,- --- m .,-,, . ---,-ew_-,-~~,,__
O Q TABLE 6.2-37 (SHEET 1 Of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERCT
[ (SEC) (LBM/SEC) (BTU /SEC K 10E6) 0.00 0.000 0.000
.50 2671.998 3.166 1.00 2663.466 3.157 1.50 2637.905 3.128 2.00 2617.019 3.104 2.50 2596.821 3.081 Os 3.00 3.50 2577.223 2558.239 3.058 3.037 4.00 2539.823 3.016 4.50 2522.243 2.996 5.00 2504.880 2.976 5.50 2488.015 2.956 i 6.00 2471.657 2.938 1 6.50 2455.784 2.919 .
7.00 2440.381 2.902 7.50 2425.735 2.885 8.00 2411.208 2.868 8.50 2397.077 2.852 9.00 2383.344 2.836 9.50 2369.987 2.821 10.00 2156.992 2.806 l
10.50 2344.341 2.791 11.00 2332.022 2.777
' 11.50 2320.009 2.763 12.00 2320.237 2.763 12.50 2316.736 2.759 13.00 2310.834 2.753 13.50 2304.986 2.746 14.00 2299.224 2.739 14.50 2293.549 2.733 15.00 2287.956 2.726 15.50 2282.447 2.720 16.00 2277.002 2.714 16.50 2266.279 2.701 17.00
- 2266.279 2.701 17.50 2269.705 2.705 18.00 2270.261 2.706 18.50 2270.505 2.706 O 19.00 19.50 20.00 2270.505 2270.505 2270.505 2.7 06 2.706 2.706 2.705 20.50 2269.639 21.00 2268.192 2.703 21.50 2266.665 2.701 22.00 2264.325 2.699 4
22.50 2261.532 2.696 23.00 2258.480 2.692 23.50 2255.038 2.688 1 24.00 2251.217 2.684 24.50 2247.047 2.679 25.00 2242.564 2.674 i
25.50 2237.796 2.668 26.00 2232.594 2.662 O 26.50 2227.344 2.656 WAPWR-CS 6.2-132 NOVEMBER, 1986 1328e:1d
TABLE 6.2-37 (SHEET 2 of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O' 27.00 27.50 2221.924 2216.347 2.650 2.644 28.00 2210.646 2.637 28.50 2204.841 2.630 29.00 2198.959 2.623 29.50 2193.018 2.617 O 30.00 30.50 31.00 2187.022 2181.015 2174.813 2.610 2.603 2.595 31.50 2168.776 2.588 32.00 2162.740 2.581 32.50 2156.717 2.575 33.00 2150.706 2.568 33.50 2144.714 2.561 34.00 2138.743 2.554 -
34.50 2132.788 2.547 35.00 2126.861 2.540 35.50 2121.069 2.534 36.00 2066.678 2.470 36.50 2029.911 2.428 37.00 1994.534 2.386 37.50 1960.552 2.346 O 38.00 2.308 1927.995 38.50 1897.162 2.272 39.00 1867.046 2.237 39.50 1838.040 2.203 40.00 1810.167 2.170 40.50 1783.358 2.138 41.00 1757.555 2.108 41.50 1732.712 2.079 42.00 1708.787 2.050 42.50 1685.728 2.023 43.00 1663.522 1.997
. 43.50 1642.121 1.972
! 44.00 1621.489 1.947 44.50 1601.588 1.924 45.00 1582.384 1.901 45.50 1563.833 1.879 46.00 1545.917 1.858 O 46.50 47.00 47.50 1528.573 1511.808 1495.551 1.837 1.817 1.798 48.00 1479.816 1.779 48.50 1464.551 1.761 49.00 1449.732 1.743 49.50 1435.338 1.726
/
50.00 1421.345 1.710 50.50 1407.735 1.693 51.00 1394.480 1.678
$1.50 1381.559 1.662
! $2.00 1368.955 1.647 52.50 1356.658 1.632 53.00 1344.652 1.618 O 53.50 54.00 54.50 1332.929 1321.473 1310.279 1.604 1.590 1.577 6.2-133 NOVEMBER, 1986 WAPWR-CS 4328e:1d
k D
V TABLE 6.2-37 (SHEET 3 Of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 1CE6) 55.00 1299.331 1.564 55.50 1288.628 1.551 56.00 1278.154 1.539 56.50 1267.910 1.526 c
57.00 1257.881 1.514
- l. 57.50 1248.072 1.503 58.00 1238.461 1.491 58.50 1229.053 1.480 59.00 1219.839 1.469
$9.50 1210.823 1.458 60.00 1201.984 1.447 60.50 1193.328 1.437 61.00 1184.847 1.427 61.50 1176.540 1.417 62.00 1168.400 1.407 -
.! 62.50 1160.430 1.397 63.00 1152.582 1.388 63.50 1144.893 1.379 64.00 1137.365 1.370 64.50 1130.000 1.361 65.00 1122.781 1.352 65.50 1115.709 1.344 O 66.00 66.50 67.00 1108.773 1101.982 1095.333 1.335 1.327 1.319 67.50 1088.821 1.311 68.00 1082.415 1.304 68.50 1075.796 1.296 69.00 1069.640 1.288 i 69.50 1063.595 1.281 70.00 1057.665 1.274 l 70.50 1051.846 1.267 71.00 1046.140 1.260 71.50 1040.539 1.253 72.00 1035.040 1.247 72.50 1029.640 1.240 73.00 1024.339 1.234 73.50 1019.133 1.228 74.00 1014.020 1.221 O 74.50 75.00 75.50 1009.001 1004.070 999.228 1.215 1.209 1.204 76.00 994.470 1.198 76.50 989.795 1.192 77.00 985.204 1.187 77.50 980.691 1.181 78.00 976.259 1.176 ,
78.50 971.901 1.171 79.00 967.620 1.165 79.50 963.413 1.160 80.00 959.277 1.155 80.50 955.214 1.150 81.00 951.216 1.146 n/
\~ -
81.50 82.00 82.50 947.288 943.422 939.618 1.141 1.136 1.132 6.2-134 NOVEMBER, 1986 WAPWR-CS 4328e:1d
y ._ _ . . - _
t ,
u TABLE 6.2-37 (SHEET 4 Of 1) ,
,_ _ 7
~ '
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLOW ' frMAK ENERGY (SEC) (LBM/SEC) (PTU/IEC K 10E6) 83.00 935.876 ; 1.127 3 83.50 932.193 1.123 .
84.00 928.572 1.118 -
84.50 ,925.008 1.114 <
25.00 321.499 1.110 . -
85.50 918.047 1.106 O 86.00 86.50 87.00 014.650 911.306 908.015 1.102 1.098 1.094 87.50 904.773 1.090 '
l 88.00 901.583 1.086 88.50 898.439 1.082 s.
89.00 895.345 1.078 .
89.50 892.296 1.075 .
90.00 889.294 1.071 '
90.50 886.336 l'.067 91.00 833.421 1.064 91.50 880.551 1.06 0 ,
92.00 877.722 L.057 92.50 874.935 -1.054 5 93.00 ~872.188 1'150 93.50
( 94.00 869.481 866.814 1.047 1.044, -
l 94.50 864.183 2.041 95.00 861.59.T 1.038 95.50 859.037
~
1.034 96.00 856.518 1.031 96.50 B54.036 1.028 97.00 551.586 1.025 97.50 849.173 1.023 i 98.00 846.792 1.020 98.50 844.445 1.017 99.00 842.130 1.014 99.50 839.846 1.011 100.00 837.594 1.009 101.00 834.256 1.005 102.00 830.005 .999 103.00 825.857 .994 i 104.00 821.805 .989 .
l 105.00 817.853 .985 106.00 814.000 .980 ,
107.00 810.289 .976 108.00 806.704 .971 109.00 803.232 .967 '
110.00 799.8,4 .963
!!1.00 796.573 .959 112.00 '793.364 .955 113.00 790.228 . .951 214.00 787.162 , .948 / 1 115.30 784.163 .944 J 116.00 781.230 .940 ,
117.00 778.357 .937 118.00 775.546 .934
-O 119.00 120.00 121.00 772.792 770.096 767.454
.930
.927
.924 i
l NOVEh9ER, 1985 l WAPWR-CS 6.2-135 4328e:1d
-.A
-- , g . . -. . - - - .
~. . .
A g
~ ' ~
~
'>lh 7 >L ;.
p( TABLE 6.2-37 (SHEET 5 of 9)
- w '1 >
'E -
s CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER i
- TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) i 122.00 764.868 .921 4
123.00 762.334 .918
- 124.00 759.852 .915 125.00 757.422 912 (i :.
?
126.00 127.00 755.043 752.712
.909
.906 i.O i
\ 128.00 129.00 130.00 750.428 748.193 746.004
.903
.900 898 i
131.00 743.862 .895
^
132.00 741.762 .893 r 133.00 739.703 .890 l
134.00 737.685 .888 L. _ 135.00 735.706 .885
- 136.00 733.766 .883 137.00 731.864 .881 138.00 729.998 .878 139.00 728.167 .876 I 140.00 726.372 .874 141.00 724.609 .872 142.00 722.878 .870 143.00 721.180 .868 144.00 719.513 .866 145.00 717.876 .864 146.00 716.269 .862 147.00 714.690 .860
( -
m 148.00 713.138 .858 i i 149.00 711.612 .856 150.00 710.113 .854 l
151.00 708.639 .853 9 707.190 .851 152.00 153.00 705.765 .849
! 154.00 704.358 .847 i 155,00 702.975 .846
/ 156.00 701.615 .844 157.00 700.275 .843 158.00 698.955 .841 l .,,
159.00 697.655 .839 160.00 696.375 .838 O 161.00 162.00 163.00 695.115 693.874 692.649
.836
.835
.833 164.00 691.442 .832 165.00 690.252 .830
' 166.00 689.078 .829 i > 167.00 687.919 .828
' 168.00 686.774 .826 169.00 685.645 .825 170.00 684.530 .823
. i 171.00 683.430 .822 l 172,00 682.343 .821
., 173.00 681.268 .820
' 680.206 .818
- 174.00
) 175.00 679.155 .817 176.00 678.117 .816 177.00 677.091 .814 s
ss 6.2-136 NOVEMBER, 1986 I' WAPWR-CS
%: 4328e:1d .
4.
--..-.-,.-._-,-g,_,,.,.,,..,--,.,~_,,,,-_...,.. , . . - - - . - - - - - - - - - . - - - - . . . - - . - . . - . . . -
, TABLE'6.2-37 (SHEET 6 of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME 8REAK FLOW 8REAK ENERGY
/'~'N ,
, (SEC) (L8M/SEC) (BTU /SEC K 10L6)
'f 178.00 676.074 .813 179.00 675.067 .812 180.00 674.071 .811 181.00 673.084 .810 182.00 672.106 .808 l 's 183.00 671.137 .807 l 18A.00 670.177 .806
, 185.00 669.225 .805 186.00 668.281 .804 ,
187.00 667.346 .803 !
188.00 666.419 .802 189.00. 665.498 .800 190.00 664.584 .799 7 191.00 663.678 .798 1 192.00 662.777 .797 )
193.00 661.883 .796 194.00 661.000 .795 195.00 660.117 .794 196.00 659.240 .793
/ 197.00 658.367 .792 198.00 657.498 .791 199.00 656.636 .790 0 200.00 202.00 204.00 206.00 655.782 654.376 650.817 648.760
.789
.783
.780 787 l
208.00 646.563 .777 210.00 644.495 .775 r 212.00 642.535 .773
, 214.00 640.628 .770 216.00 638.756 .768 218.00 636.902 .766 220.00 635.067 .764 222.00 633.255 .761 224.00 631.462 .759 l
l 226.00 629.690 .757 228.00 627.938 .755 3 230.00 626.205 .753 l 232.00 624.483 751 234.00 622.772 .749 l
236.00 621.076 .747 238.00 619.392 .745 240.00 617.727 .743 242.00 616.066 .741 244.00 614.412 .739 246.00 612.768 .737 O 248.00 250.00 252.00 611.130 609.507 607.885
.735
.733
.731 254.00 606.279 .729 256.00 604.671 .727 258.00 603.076 .725 260.00 601.481 .723 l
l l
O /
262.00 264.00 266.00 599.894 598.316 596.740
.721
.719
.717 l
l WAPWR-CS 6.2-137 NOVEMBER, 1986
, 4328e:1d l
1
TABLE 6.2-37 (SHEET 7 Of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 595.164 .715 270.00 593.597 .713 272.00 592.031 .711 274.00 590.470 .710 276.00 588.920 .708
, 278.00 587.368 .706 280.00 585.825 .704 282.00 584.282 .702 284.00 582.746 .700 286.00 581.213 .698 288.00 579.681 .696 290.00 578.158 .695 292.00 576.638 .693 294.00 575.122 .691 296.00 573.606 .689 298.00 572.099 .687 300.00 570.593 .685 302.00 569.091 .684 304.00 567.595 .682 306.00 566.104 .680 308.00 564.623 .678 1 310.00 563.027 .676 312.00 556.993 .669 314.00 532.862 .640 316.00 517.367 .621 318.00 488.120 .585 320.00 455.089 .545 322.00 413.365 494 324.00 365.793 .437 326.00 311.975 .371 l
328.00 257.742 .306 330.00 212.158 .251 332.00 176.354 .208 334.00 146.726 .173 336.00 127.596 .150 338.00 114.077 .134 340.00 252.112 .303 342.00 555.913 .666 O 344.00 416.032 498 346.00 438.145 .525 348.00 395.404 473 350.00 343.432 410 352.00 283.706 .337 354.00 232.082 .275 356.00 192.806 .228 i
358.00 160.148 .189 360.00 134.199 .158 362.00 117.546 .138 364.00 141.033 .169 366.00 419.695 .501 368.00 332.236 .396 370.00 288.388 .343 372.00 236.545 .281 0 374.00 376.00 378.00 195.318 162.194 134.923
.231
.191
.159 WAPWR-CS 6.2-138 NOVEMBER, 1986 4328e:1d r_ m.
TABLE 6.2-37 (SHEET 8 Of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME BREAK FLO6i BREAK ENERGY s (SEC) (LBM/SEC) (BTU /SEC K 10E6)
- s. 380.00 116.710 137 382.00 103.119 .121 384.00 157.668 .188 386.00 389.240 462 388.00 224.270 .266 390.00 183.735 .217 O 392.00 394.00 396.00 151.960 127.740 109.378
.179
.150
.128 398.00 100.432 .118 400.00 111.424 .131 404.00 126.082 .148 408.00 97.424 .114 412.00 69.562 .081 416.00 58.880 .068 -
420.00 84.760 .100 424.00 193.406 .226 428.00 74.695 .087 432.00 65.419 .076 436.00 53.751 .062 440.00 44.236 .051 444.00 33.599 .039 448.00 19.229 .022 O. 452.00 456.00 57.109 158.354
.067
.184 460.00 57.770 .067 464.00 53.324 .062 468.00 43.361 .050 472.00 32.488 .037 476.00 50.248 .059 480.00 109.868 .128 484.00 58.237 . 067 488.00 49.082 .057 492.00 39.101 .045 496.00 50.968 .060 500.00 99.609 .116 504.00 61.033 .071 508.00 54.247 .063 512.00 64.031 .074 O 516.00 520.00 524.00 64.264 61.238 61.318
.075
.071
.071 528.00 62.188 .072 532.00 62.265 .072 536.00 61.890 .072 540.00 61.836 .072 O 544.00 548.00 552.00 61.996 62.033 61.968
.072
.072
.072 556.00 61.947 .072 560.00 61.973 .072 564.00 61.983 .072 568.00 61.973 .072 572.00 61.967 .072
_s 576.00 61.970 .072 WAPWR-CS 6.2-139 NOVEMBER,1986 4328e:1d
( .__ _. .-_
E TABLE 6.2-37 (SHEET 9 Of 9)
CASE 9: 1.1 FT2 SPLIT RUPTURE AT 25 PC POWER TIME CREAK FLOW BREAK ENERGY O (SEC) 580.00 (LBM/SEC) 61.973 (8TU/SEC A 10E6)
. 072 180'b.00 61.967 . h72 1804.00 62.102 . 072 ,
1808.00 62.739 . 073 1812.00 20.886 . 024 1816.00 0.000 0.000 20b0.00 0.' BOO 0.bb0 1
i I
O i
lO '
O 6.2-140 NOVEMBER, 1986 WAPWR-CS y T328e:1d 9---N3- 9%w--,,-m.-%,y.yw., nw-.-w.- py
TABLE 6.2-38 (SHEET 1 Of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER j TIME BREAK FLOW BREAK ENERGY
/ (SEC) (LBM/SEC) (BTU /SEC A 10E6) 0.00 0.000 0.000
.50 2560.140 3.027 1.00 2539.755 3.004 1.50 2519.395 2.981 2.00 2499.807 2.959 2.50 2481.054 2.938 O 5.00 3.50 4.00 2463.028 2445.571 2428.582 2.917 2.898 2.878 4.50 2412.028 2.859 5.00 2395.890 2.841 5,50 2380.166 2.823 6.00 2364.848 2.806 6.50 2349.896 2.789 ,
7.00 2335.341 2.772 7.50 2321.181 2.756 8.00 2307.403 2.740 8.50 2293.990 2.725 9.00 2280.924 2.710 9.50 2268.192 2.695 10.00 2255.775 2.681 10.50 2243,660 2.667 0 '
11.00 11.50 12.00 2231.829 2220.263 2209.216 2.653 2.640 2.627 12.50 2198.288 2.615 13.00 2187.584 2.603 2 13.50 2177.071 2.591 14.00 2166.769 2.579 14.50 2156.621 2.567 15.00 2146.639 2.556 15.50 2136.801 2.544 16.00 2127.100 2.533 16.50 2117.532 2.522 17.00 2099.203 2.500 17.50 2099.780 2.501 18.00 2098.487 2.500 18.50 2094.113 2.495
/'~ 19.00 2089.713 2.490 19.50 2085.275 2.485 20.00 2080.777 2.479 20.50 2076.224 2.474 21.00 2071.641 2.469 21.50 2067.005 2.464 22.00 2062.319 2.458 22.50 2057.578 2.453 O 23.00 23.50 24.00 2052.783 2047.937 2043.039 2.447 2.442 2.436 24.50 2038.095 2.430 25.00 2033.102 2.424 25.50 2028.068 2.419 26.00 2022.995 2.413 O 26.50 2017.887 2.407 WAPWR-CS 6.2-141 NOVEMBER, 1986 4328e:1d
)
TABLE 6.2-38 (SHEET 2 Of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6)
O 27.00 27.50 2012.745 2007.573 2.401 2.395 28.00 2002.369 2.389 28.50 1997.158 2.383 29.00 1991.920 2.377 s 29.50 1986.680 2.371 30.00 1981.426 2.365 30.50 1976.161 2.358 31.00 1970.905 2.352 31.50 1965.517 2.346 32.00 1960.264 2.340 32.50 1955.019 2.334 33.00 1949.778 2.328 33.50 1944.553 2.322 34.00 1939.339 2.316 -
34.50 1934.138 2.310 35.00 1928.957 2.304 35.50 1923.788 2.298 36.00 1918.651 2.292 36.50 1913.546 2.286 37.00 1908.462 2.280 37.50 1903.391 2.274 O 38.00 38.50 39.00 1897.702 1856.455 1827.933 1800.353 2.268 2.220 2.186 2.154 39.50 40.00 1773.878 2.123 40.50 1748.372 2.093 41.00 1724.140 2.065 41.50 1700.311 2.037 42.00 1677.245 2.010 42.50 1654.959 1.984 ^
43.00 1633.429 1.958 43.50 1612.618 1.934 44.00 1592.489 1.910 44.50 1573.021 1.887 45.00 1554.179 1.865
! 45.50 1535.939 1.843 I 46.00 1518.286 1.823 l 46.50 1501.195 1.802 1 N- 47.00 1484.643 1.783 47.50 1468.607 1.764 48.00 1453.058 1.745 48.50 1437.980 1.727 49.00 1423.337 1.710 49.50 1409.128 1.693 0 50.00 50.50 51.00 51.50 1395.304 1381.837 1368.720 1355.955 1.677 1.661 1.645 1.630 52.00 1343.545 1.615 52.50 1331.445 1.601 53.00 1319.674 1.587 l 53.50 1308.134 1.573 54.00 1296.855 1.560 54.50 1285.865 1.547 6.2-142 NOVEMBER,1986 WAPWR-CS l T328e:1d l
TABLE 6.2-38 (SHEET 3 Of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY
/N (SEC) (LBM/SEC) (BTU /SEC K 10E6) 55.00 1275.176 1.534 55.50 1264.687 1.521 56.00 1254.400 1.509 56.50 1244.310 1.497 57.00 1234.418 1.485 l 57.50 1224.719 1.474 58.00 1215.209 1.462 58.50 1205.882 1.451 59.00 1196.733 1.440 59.50 1187.754 1.430 60.00 1178.948 1.419 60.50 1170.301 1.409 61.00 1161.814 1.399 61.50 1153.481 1.389 -
62.00 1145.275 1.379 62.50 1137.255 1.369 63.00 1129.368 1.360 63.50 1121.625 1.350 64.00 1114.019 1.341 64.50 1106.551 1.332 65.00 1099.212 1.324 65.50 1092.007 1.315 O 66.00 66.50 67.00 1084.929 1077.974 1071.143 1.3 06 1.298 1.290 l 67.50 1064.433 1.282 68.00 1.274 1057.841 68.50 1051.352 1.266 69.00 1044.963 1.258 69.50 1038.693 1.251 70.00 1032.536 1.244 70.50 1026.493 1.236 71.00 1020.560 1.229 71.50 1014.733 1.222 72.00 1009.007 1.215 72.50 100J.384 1.208 73.00 997.867 1.202 73.50 992.452 1.195 74.00 987.136 1.189 74.50 981.914 1.183 75.00 976.486 1.176 75.50 971.463 1.170 76.00 966.523 1.164 76.50 961.666 1.158 77.00 956.898 1.153 77.50 952.210 1.147 O 78.00 78.50 79.00 947.599 943.064 938.604 1.141 1.136 1.131 79.50 934.215 1.125 80.00 929.898 1.120 80.50 925.649 1.115 81.00 921.467 1.110 O 81.50 82.00 82.50 917.351 913.298 909.308 1.105 1.100 1.095 WAPWR-CS 16.2-143 NOVEMBER, 1986 T328e:1d
TABLE 6.2-38 (SHEET 4 of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT 2ERO POWER TIME 8REAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 905.380 1.091 83.50 901.513 1.086 84.00 897.704 1.081 84.50 893.955 1.077 85.00 890.261 1.072 85.50 886.624 1.068 O' 86.00 86.50 87.00 883.042 879.513 876.037 1.064 1.059 1.055 87.50 872.612 1.051 88.00 869.238 1.047 88.50 865.914 1.043 89.00 862.638 1.039 89.50 859.407 1.035 90.00 856.220 1.031 -
90.50 853.078 1.027 91.00 849.989 1.024
- 91.50 846.953 1.020 92.00 843.967 1.016
' 92.50 841.030 1.013 93.00 838.140 1.009 93.50 835.298 1.006 O 94.00 94.50 95.00 832.498 829.745 827.034 1.003-
.999
.996 95.50 824.363 .993
) 96.00 821.732 .990 96.50 819.136 .987 97.00 816.578 .983 97.50 814.056 .980 98.00 811.569 .977 98.50 809.116 .974 99.00 8D6.697 .972 99.50 804.311 .969 100.00 801.953 .966 l
101.00 798.468 .962 102.00 794.023 .956 103.00 789.706 .951 785.475 .946 0 104.00 105.00 106.00 107.00 781.333 777.296 773.370
.941
.936
.931 108.00 769.554 .927 109.00 765.839 .922 110.00 762.216 .918 111.00 758.684 .914 O 112.00 113.00 114.00 755.239 751.878 748.599
.909
.905
.901 115.00 745.401 .897 116.00 742.281 .894 117.00 739.238 .890 118.00 736.268 .886 0 119.00 120.00 121.00 733.372 730.546 727.788
.883
.880
.876 6.2-144 NOVEMBER, 1986 WAPWR-CS T328e:1d
TABLE 6.2-38 (SHIET 5 of 8)
CASE 10: 1.0 FT2 SPLIT RUPTlRE AT HOT ZERO POWER 7IME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 122.00 725.096 .873 123.00 722.469 .870 124.00 719.905 .867 125.00 717.401 .864 126.00 714.956 .861 127.00 712.568 .858 0 128.00 129.00 130.00 710.236 707.956 705.727
.855
.852
.850 131.00 703.549 .847 132.00 701.420 .844 133.00 699.339 .842 134.00 697.303 .839 135.00 695.311 .837 136.00 693.362 .835 ,
137.00 691.453 .832 138.00 689.585 .830 139.00 687.756 .828 140.00 685.965 .826 141.00 684.211 .824 142.00 682.493 .821 143.00 680.809 .819 0 144.00 145.00 146.00 679.157 677.538 675.950 674.392
.817
.815
.814
.812 147.00 148.00 672.863 .810 j
149.00 671.364 .808 150.00 669.891 .806 151.00 668.444 .804 152.00 667.025 .803 153.00 665.630 .801 154.00 664.258 .799 155.00 662.910 .798 156.00 661.585 796
' 157.00 660.281 .795 158.00 659.000 .793 159.00 657.739 .791 656.498 .790 0 160.00 161.00 162.00 163.00 655.276 654.072 652.887
.789
.787
.786 -
164.00 651.720 .784 165.00 650.569 .783 166.00 649.434 .781 l .780 l 167.00 648.315 168.00 647.211 .779 169.00 646.123 .777 l
170.00 645.048 776 l
171.00 643.988 .775 172.00 642.940 .774 173.00 641.906 .772 174.00 640.882 .771 i
0 175.00 176.00 177.00 639.870 638.870 637.882
.770
.769
.767 WAPWR-CS 6.2-145 NOVEMBER, 1986 4328e:1d
TABLE 6.2-38 (SHEET 6 Of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT 2ERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 178.00 636.903 .766 179.00 635.936 .765 180.00 634.980 .764 181.00 634.034 .763 182.00 633.098 762 183.00 632.170 .761 0 184.00 185.00 186.00 631.251 630.341 629.439
.759
.758
.757 187.00 628.546 .756 188.00 627.661 755 189.00 626.785 .754 190.00 625.915 .753 191.00 625.051 .752 -
192.00 624.194 .751 193.00 623.344 .750 194.00 622.501 .749
- 195.00 621,663 .748 196.00 620.832 .747 197.00 620.007 .746 198.00 619.188 .745 199.00 618.373 744 O 200.00 202.00 204.00 617.562 616.353 613.990
.743
.741
.739 206.00 612.227 .736 208.00 610.443 734 210.00 608.709 .732 212.00 607.021 730 214.00 605.360 .728
.726 216.00 603.716 218.00 602.090 .724 220.00 600.475 .722 222.00 598.876 .720 224.00 597.293 .718 226.00 595.724 .716 228.00 594.168 .715 230.00 592.623 .713 591.0b8 .711 O 232.00 234.00 236.00 238.00 589.568 588.058 586.559
.7 09
.707
.705 240.00 585.068 .704 242.00 583.585 .702 244.00 582.108 700 246.00 5BC.639 .698 0 248.00 250.00 252.00 579.179 577.723 576.273
.696
.695
.693 254.00 574.829 .691 256.00 573.386 .689 258.00 571.949 .688 260.00 570.517 .686 262.00 569.093 .684 264.00 557.674 .682 266.00 566.255 .681 6.2-146 NOVEMBER, 1985 WAPWR-CS 4328e:1d
TABLE 6.2-38 (SHEET 7 of 8) hm CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 564.838 . 6 .;
270.00 563.426 .671 272.00 562.014 .676 274.00 560.607 .674 276.00 559.204 .672
's 278.00 557.812 .670 280.00 556.419 .669 282.00 555.024 .667 284.00 553.635 .665 286.00 552.248 .664 288.00 550.867 .662 290.00 549.487 .660 292.00 548.111 .659 294.00 546.739 .657 -
296.00 545.369 .655 298.00 544.005 .654 300.00 542.643 .652 302.00 541.283 .650 304.00 539.927 .649 306.00 538.574 .647 308.00 537.222 .646 310.00 535.877 .644 O
- 312.00 314.00 316.00 534.531 533.192 531.854
.642
.641
.639 318.00 530.519 .637 320.00 529.187 .636 322.00 527.856 .634 324.00 526.532 .633 326.00 525.209 .631 328.00 523.893 .629 330.00 522.573 .628 332.00 521.260 .626 334.00 519.949 .625 336.00 518.644 .625 338.00 517.339 .621 340.00 516.037 .620 342.00 514.739 .618 344.00 513.445 .617 O 346.00 348.00 350.00 512.155 510.864 509.581
.615
.614
.612 352.00 508.298 .611 j
, 354.00 507.020 .609
' 356.00 505.743 .607 358.00 504.470 .606 360.00 503.200 .604 i 362.00 501.935 .603 f 364.00 500.670 .601 l 366.00 499.409 .600 368.00 498.143 .598 370.00 496.879 .597 372.00 495.823 .595 O 374.00 376.00 378.00 494.540 493.134 491.816
.594
.592
.591 6.2-147 NOVEMBER,1986 WAPWR-CS 4328e:1d
i i
TABLE 6.2-38 (SHEET 8 of 8)
CASE 10: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER TIME BREAK FLOW BREAK ENERGY O (SEC) 380.00 (LBM/SEC) 490.558 (BTU /SEC K 10E6)
.589 382.00 489.531 .588 384.00 488.265 .586 386.00 487.061 .585 388.00 485.731 .583 O 390.00 392.00 394.00 484.543 483.231 482.078
.582
.580
.579
.577 396.00 480.771 398.00 478.675 .575 400.00 469.379 .563 404.00 452.537 .543 408.00 426.171 .510 412.00 363.880 .435 ,
416.00 299.240 .356 420.00 213.587 .253 424.00 147.466 .174 428.00 105.248 .123 432.00 83.503 .097 436.00 66.576 .077 440.00 59.774 .070 444.00 86.831 .101 448.00 64.631 .075 l 452.00 58.796 .068 456.00 63.648 .074 460.00 63.771 .074 464.00 61.952 .072 468.00 61.821 .072 472.00 62.262 .072 476.00 62.254 .072 4S0.00 62.016 .072 484.00 61.962 .072 488.00 62.024 .072 492.00 62.032 .072 496.00 61.997 .072 500.00 61.983 .072 0 18db.00 61.956 .072 1804.00 62.096 .072 1808.00 62.805 .073 1812.00 36.287 .042 O 1816.00 1820.00
.025
.000
.000
.003 sr 3, 0.000 O 2000.00 0.000 6.2-148 NOVEMBER, 1986 WAPWR-CS 4328e:1d
O Q TABLE 6.2-39 (SHEET 1 Of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY O (SEC) 0.00 (LBM/SEC) 0.000 (BTU /SEC K 10E6) 0.000
.50 14317.938 16.967 1.00 13228.440 15.708 1.50 12569.433 14.952 2.00 11975.331 14.268 0 2.50 3.00 3.50 11432.083 10939.465 10488.537 13.640 13.068 12.542 4.00 10072.122 12.055 4.50 9687.908 11.605 5.00 9328.642 11.182 5.50 8995.555 10.790 6.00 8686.239 10.425 6.50 8398.463 10.085 -
7.00 8130.582 9.767 7.50 7880.772 9.471 8.00 7647.415 9.194 8.50 7445.396 8.952 9.00 7463.676 8.974 9.50 7407.977 8.908 10.00 7353.388 8.843 10.50 1299.678 8.779 O- 11.00 11.50 7246.811 7194.653 8.716 8.654 12.00 1768.313 2.127 12.50 1754.420 2.111 13.00 1740.598 2.094 13.50 1726.882 2.078 14.00 1713.084 2.061 14.50 1699.100 2.045 l 15.00 1684.959 2.028 15.50 1670.821 2.011-16.00 1656.522 1.994 16.50 1642.107 1.977 17.00 1627.573 1.959 17.50 1612.940 1.942 18.00 1598.239 1.924
'N 18.50 1583.506 1.906 19.00 1568.832 1.889 i 19.50 1554.284 1.871 20.00 1539.726 1.854 20.50 1525.241 1.837 21.00 1510.837 1.819 21.50 1496.527 1.802 22.00 1482.366 1.785 0 22.50 23.00 23.50 1468.274 1454.298 1440.500 1.768 1.751 1.735 24.00 1426.895 1.718 24.50 1413.489 1.702 25.00 1400.302 1.687 25.50 1387.336 1.671 26.00 1374.646 1.656 s,,s/ 26.50 1361.769 1.640 WAPWR-CS 6.2-149 NOVEMBER,1986 l
4328e:1d
TABLE 6.2-39 (SHEET 2 of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY (LBM/SEC) (BTU /SEC K 10E6)
Q( ,/ (SEC) 27.00 1349.618 1.626 27.50 1337.704 1.611 28.00 1326.044 1.597 28.50 1314.636 1.583 29.00 1303.454 1.570 O 29.50 30.00 30.50 1292.551 1281.879 1271.442 1.557 1.544 1.531 31.00 1261.233 1.519 31.50 1251.248 1.507 32.00 1241.479 1.495 32.50 1231.916 1.484 33.00 1222.556 1.473 33.50 1213.395 1.461 34.00 1204.423 1.451 34.50 1195.623 1.440 35.00 1186.993 1.430 35.50 1178.530 1.419 36.00 1170.230 1.409 36.50 1162.091 1.400 37.00 1154.107 1.390 0 37.50 38.00 38.50 39.00 1146.276 1138.595 1131.059 1123.665 1.381 1.371 1.362 1.353 I
39.50 1116.415 1.344 40.00 1109.301 1.336 40.50 1102.322 1.327 41.00 1095.475 1.319 41.50 1088.760 1.311 42.00 1082.173 1.303 42.50 1075.711 1.295
! 1.288 43.00 1069.371 43.50 1D63.151 1.280 44.00 1057.050 1.273 44.50 1051.064 1.266 l
l 45.00 1045.192 1.258 45.t0 1039.431 1.251 1
O 46.00 46.50 47.00 1033.779 1028.232 1022.789 1.245 1.238 1.231 47.50 1017.451 1.225 48.00 1012.210 1.219 48.50 1007.064 1.212 49.00 1002.016 1.206 l
O 49.50 50.00 50.50 997.061 992.200 987.427 1.200 1.194 1.189 51.00 982.741 1.183 i
51.50 978.140 1.177 52.00 973.624 1.172 52.50 969.189 1.167 O 53.00 53.50 54.00 964.833 960.554 956.352 952.223 1.161 1.156 1.151 1.146 54.50 6.2-150 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-39 (SHEET 3 of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK TLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 55.00 948.165 1.141 55.50 944.180 1.136 56.00 940.264 1.132 56.50 936.413 1.127 57.00 932.633 1.122 57.50 928.919 1.118
/' 58.00 925.268 1.113
\ 58.50 921.679 1.109 59.00 918.152 1.105 59.50 914.686 1.101 60.00 911.278 1.097 60.50 907.924 1.092 61.00 904.631 1.088 61.50 901.393 1.085 -
62.00 898.209 1.081 62.50 895.069 1.077 63.00 891.983 1.073 63.50 888.950 1.069 64.00 885.969 1.066 64.50 883.035 1.062 65.00 880.149 1.059 65.50 877.307 1.055 O 66.00 66.50 67.00 874.508 871.753 869.041 1.052 1.049 1.045 67.50 866.369 1.042 68.00 863.737 1.039 68.50 861.145 1.036 69.00 858.592 1.033 69.50 856.077 1.030 70.00 853.598 1.027 70.50 851.155 1.024 71.00 848.748 1.021 71.50 846.374 1.018 72.00 844.035 1.015 72.50 841.728 1.012 73.00 839.454 1.010 73.30 837.212 1.007 1.004 O 74.00 74.50 75.00 75.50 835.002 832.823 830.675 828.558 1.002
.999
.996 76.00 826.471 .994 76.50 824.413 .991 77.00 822.385 .989 77.50 820.386 .986 O 78.00 78.50 79.00 818.415 816.471 814.555
.984
.982
.979 79.50 812.667 .977 80.00 810.804 .975 80.50 808.967 .973 81.00 807.156 .970 0 81.50 82.00 82.50 805.370 803.608 801.869
.968
.966
.964 6.2-151 NOVEMBER, 1986 WAPWR-CS 1328e:1d
TABLE 6.2-39 (SHEET 4 Of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE 7IME 3REAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 83.00 800.155 .962 83.50 798.463 .960 84.00 796.793 .958 84.50 795.145 .956 85.00 793.517 .954 N 85.50 791.910 .952 86.00 790.323 .950 86.50 788.755 .948 87.00 787.207 .946 87.50 785.678 .944 88.00 784.167 .943 88.50 782.675 .941 89.00 781.202 .939 89.50 779.746 .937 90.00 778.308 .936 .
90.50 776.888 .934 91.00 775.485 .932 91.50 774.100 .930 92.00 772.732 .929 92.50 771.380 .927 93.00 770.044 .926 93.50 768.724 .924 O 94.00 94.50 95.00 767'.421 766.133 764.860
.922
.921
.919 95.50 763.604 .918 96.00 762.362 .916 96.50 761.135 .915 97.00 759.923 .913 .
97.50 758.725 .912
- 98.00 757.542 .910 98.50 756.373 .909 99.00 755.217 .908 99.50 754.075 .906 i
l 100.00 752.946 .905 101.00 751.270 .903 l 102.00 749.120 .900 103.00 747.023 .898 l 744.970 .895 104.00 l 742.961 .893 l
105.03
' 106.00 740.996 .890 107.00 739.077 .888 108.00 737.199 .886 109.00 735.362 .883 110.00 733.562 .881
, 111.00 731.798 .879 5 112.00 730.068 .877 113.00 728.372 .875 114.00 726.708 .873 115.00 725.075 .871 116.00 723.474 .869 117.00 721.904 .867 118.00 720.364 .865
S 119.00 718.855 .863 120.00 717.375 .862 121.00 715.925 .860 WAPWR-CS 6.2-152 NOVEMBER, 1986 4328e:1d
TABLE 6.2-39 (SHEET 5 of 12)
CASE 11: 1.4-FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE i 7IME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC X 10E6) 122.00 714.503 .858 123.00 713.109 .857
, 124.00 711.743 .855 l
l 125.00 710.404 .853 126.00 709.089 .852 127.00 707.799 .850 0 128.00 129.00 130.00 706.533 705.290 704.070
.849
.847
.846 131.00 702.871 .844 132.00 701.694 .843 133.00 700.537 .841 134.00 699.400 .840 135.00 698.276 .839.
136.00 697.168 .837 -
137.00 696.077 .836 138.00 695.014 .835
. 139.00 693.972 .833 140.00 692.939 .832 141.00 691.924 .831 142.00 690.922 .830 143.00 689.936 .828 l
( 0
- 144.00 145.00 146.00 688.959 687.987 687.030
.827
.826
.825 147.00 686.097 .824 148.00 685.185 .823
, 149.00 684.276 .822 l 150.00 683.368 .820 151.00 682.473 .819 152.00 681.585 .818 153.00 680.696 .817 154.00 679.819 .816 155.00 678.962 .815 156.00 678.126 .814
, 157.00 677.291 .813 158.00 676.459 .812 l
i 159.00 675.636 .811 160.00 674.827 .810 161.00 674.018 .809
! 162.00 673.212 .808 163.00 672.418 .807 164.00 671.627 .806 165.00 670.834 .805 166.00 670.049 .804 167.00 669.281 .803 O 168.00 169.00 170.00 668.530 667.778 667.024
.802
.802
.801 171.00 666.279 .800 172.00 665.534 .799 173.00 664.785 .798 174.00 664.043 .797 O 175.00 176.00 177.00 663.315 662.603 661.888
.796
.795
.794 l WAPWR-CS 6.2-153 NOVEMBER, 1986 4328e:1d
l 4
TABLE 6.2-39 (SHEET 6 Of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK F1.0W BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 178.00 661.171 .794 179.00 660.459 .793 180.00 659.757 .792 181.00 659.051 .791 182.00 658.344 .790 l 183.00 657.645 .789 184.00 656.946 .788 185.00 656.241 .788 186.00 655.541 .787 187.00 654.957 .786 188.00 654.279 .785 189.00 653.599 .784 190.00 652.916 .784 191.00 652.238 .783 '
192.00 651.559 .782 193.00 650.873 .781 194.00 650.190 .780 195.00 649.521 .779 l 196.00 648.865 .779 197.00 648.204 778 198.00 647.538 .777 199.00 646.876 .776 O 200.00 201.00 202.00 646.213 645.541 644.401
.775
.775
.773 203.00 643.521 .772 204.00 642.672 .771 205.00 641.833 .770
! 206.00 641.004 .769 207.00 640.194 768 208.00 639.396 767 209.00 638.604 .766 210.00 637.827 .765 211.00 637.073 .764 212.00 636.341 .763 213.00 635.609 .763 214.00 634.877 .762 215.00 634.154 .761 t
l l
0 216.00 217.00 218.00 219.00 633.432 632.703 631.979 631.271
.760
.759
.758
.757 220.00 630.578 .756 221.00 629.879 756 222.00 629.175 .755 O 223.00 224.00 225.00 226.00 628.477 627.776 627.067 626.362
.754
.753
.752
.751 l
227.00 625.672 .751 228.00 624.997 .750 229.00 624.316 .749 230.00 623.628 .748 l 231.00 622.946 .747 l 232.00 622.261 .746 233.0L 621.567 .746 WAPWR-CS 6.2-154 NOVEMBER, 1986 4328e:1d
TABLE 6.2-39 (SHEET 7 Of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME SREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 234.00 620.877 .745 235.00 620.202 .744 236.00 619.530 .743 237.00 618.849 .742 238.00 618.168 .741 239.00 617.500 .741 0 240.00 241.00 242.00 616.846 616.183 615.513
.740
.739
.738 243.00 614.847 .737 244.00 614.178 .737 245.00 613.498 .736 246.00 612.822 735 247.00 612.159 .734 248.00 611.512 .733 -
249.00 610.856 .733 250.00 610.193 .732 251.00 609.533 .731 252.00 608.871 .730 253.00 608.197 .729 254.00 607.527 .729 255.00 606.872 .728
, O 256.00 257.00 258.00 606.220 605.556 604.893
.727
.726
.725 259.00 604.242 .725 260.00 603.605 .724 602.958 .723 261.00 262.00 602.303 .722 263.00 601.652 .721 264.00 600.997 .721 265.00 600.330 .720 266.00 599.665 .719 267.00 599.016 .718
, 268.00 598.382 .717 269.00 597.738 .717 270.00 597.087 .716 271.00 596.439 .715 272.00 595.787 .714 273.00 595.124 .713 274.00 594.464 .713 275.00 593.820 .712 276.00 593.178 .711 277.00 592.524 .710 278.00 591.870 .710
, 279.00 591.229 .709 280.00 590.602 .708 281.00 589.965 .707 282.00 589.319 .706 283.00 588.676 .706 284.00 588.029 .705 285.00 587.370 .704 i
286.00 586.714 .703 287.00 586.074 .703
'N- 288.00 585.437 .702 289.00 584.787 .701 WAPWR-CS 6.2-155 NOVEMBER,1986 t 4328e:1d i
l
.- - _ _ - - _ _ . . - - _ . _ - - - - - _ _ _ _ _ _ - _ _ _ _ , _ . - - - . _ - - _ . _ _ _ _ - _ = . _ _ , _ _ , ,_- .--. -___-_ - -. --_--.
TABLE 6.2-39 (SHEET 8 Of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER NSIV FAILURE TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 290.00 584.138 .700 291.00 583.502 .699 292.00 582.881 .699 293.00 582.249 .698 294.00 581.607 .697
' 295.00 580.969 .696 296.00 580.326 .696 297.00 579.671 .695 298.00 579.019 .694 299.00 578.384 .693 300.00 577.752 .692 301.00 577.106 .692 302.00 576.462 .691 303.00 575.833 .690 304.00 575.216 .689 305.00 574.587 .689 306.00 573.950 .688
'
- 307.00 573.318 .687 308.00 572.679 .686 309.00 572.026 .685 310.00 571.378 .685 311.00 570.750 .684 O 312.00 313.00 314.00 570.134 569.508 558.873
.683
.682
.682 315.00 568.230 .681 316.00 567.590 .680 317.00 566.951 .679 318.00 566.319 .679 319.00 565.685 .678 320.00 565.056 .677
' 321.00 564.425 .676 322.00 563.796 .676 323.00 563.165 .675 324.00 562.538 .674 325.00 561.923 .673 326.00 561.315 .672 327.03 560.690 .672 328.00 560.058 .671 O 329.00 330.00 331.00 559.417 558.766 558.126
.670
.669
.669 332.00 557.510 .668 333.00 556.893 .667 334.00 556.275 .666
' 335.00 555.663 .666
( 555.054 .665 336.00 337.00 554.431 .664 338.00 553.801 .663 339.00 553.164 .663 340.00 552.532 .662 341.00 551.901 .661 342.00 551.261 .660 O 343.00 344.00 345.00 550.632 550.025 549.415
.660
.659
.658 WAPWR-CS 6.2-156 NOVEMBER, 1986 4328e:1d
l f
() TABLE 6.2-39 (SHEET 9 Of 12) ]
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE
! TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC 1 10E6) 346.00 548.803 .657 347.00 548.197 .657 348.00 547.594 .656 349.00 546.975 .655 350.00 546.349 .654 351.00 545.714 .654 Gi 352.00 353.00 545.086 544.459
.653
.652
.651 l 354.00 543.823 355.00 543.198 .651 356.00 542.598 .650
'57.00 541.993 .649 358.00 541.385 .648 f
' 359.00 540.785 .648 -
! 360.00 540.188 .647 i 361.00 539.573 .646 l 362.00 538.951 .645 363.00 538.320 .645 364.00 537.697 .644 365.00 537.074 .643 366.00 536.460 .642 367.00 535.844 .642 368.00 535.216 .641 O~ 369.00 534.598 .640 370.00 534.006 .639 371.00 533.409 .639 372.00 532.807 .638 373.00 532.214 .637 374.00 $31.621 .637 375.00 531.007 .636 376.00 530.387 .635 377.00 529.757 .634 378.00 529.136 .633 379.00 528.517 .633 380.00 527.008 .632 381.00 527.296 .631 382.00 526.692 .631 383 00 526.083 .630 384.00 525.481 .629 0- 385.00 386.00 524.874 524.273
.628
.628
.627 387.00 523.668 388.00 523.067 .626 389.00 522.462 .625 ,
390.00 521.862 .625 l J
391.00 521.257' .624 l 392.00 520.657 .623 393.00 520.053 .622 394.00 519.454 .622 395.00 518.850 .621 396.00 $18.253 .620 397.00 517.650 .620 398.00 517.054 .619 0 399.00 400.00 401.00
$16.453 515.858 515.258
.616
.617
.617 6.2-157 NOVEMBER, 1986 WAPWR-CS 4328e:1d
I i TABLE 6.2-39 (SHEET 10 of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) 402.00 514.664 .616 403.00 513.348 .614 404.00 506.526 .606 i
405.00 500.949 .599 406.00 494.061 .591 407.00 486.192 .581
.570 O* 408.00 409.00 477.165 466.965 .558 410.00 455.121 .544 411.00 442.685 .529
, 412.00 427.949 .511 413.00 412.052 492 414.00 394.517 470 415.00 375.470 447 416.00 354.891 422 -
417.00 332.979 .396 418.00 309.918 .368 419.00 285.981 .339 I 420.00 261.623 .310 421.00 237.435 .281 422.00 213.923 .252
! 423.00 191.343 .225 424.00 172.111 .202 425.00 155.564 .183 I 426.00 140.945 .165 427.00 129.623 .152 428.00 119.802 .140 l 429.00 110.411 .129 l
430.00 101.929 .119 431.00 94.557 .110 432.00 88.248 .103 433.00 82.715 .096 434.00 77.913 .090 l
l 435.00 73.344 .085
! 436.00 69.239 .080 437.00 65.439 .076 l 61.758 .071 438.00 439.00 59.643 .069 O 440.00 61.105 .071 441.00 61.296 .071 442.00 61.467 .071 443.00 61.619 .071 444.00 61.757 .071 445.00 61.878 .072 446.00 61.980 .072 447.00 62.064 .072 448.00 62.129 .072 4Os 449.00 62.177 .072 450.00 62.209 .072 451.00 62.227 .072 452.00 62.233 .072 453.00 62.230 .072 l 454.00 62.220 .072 455.00 62.206 .072 456.00 62.188 .072 457.00 62.170 .072 6.2-158 NOVEMBER, 1986 WAPWR-CS 4328e:1d
1 TABLE 6.2-39 (SHEET 11 of 12)
CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 458.00 62.151 .072 459.00 62.134 .072 460.00 62.118 .072 461.00 62.104 .072 462.00 62.092 .072 l \ 463.00 62.082 .072 1 464.00 62.073 .072 465.00 62.065 .072 466.00 62.059 .072 467.00 62.054 .072 468.00 62.049 .072 469.00 62.046 .072 470.00 62.042 .072 471.00 62.039 .072 -
472.00 62.037 .072 473.00 62.034 .072 474.00 62.032 .072 475.00 62.030 .072 l 476.00 62.028 .072 477.00 62.027 .072 478.00 62.025 .072 479.00 62.024 .072 O '
480.00 481.00 482.00 62.022 62.021 62.019
.072
.072
.072 483.00 62.018 .072 484.00 62.016 .072 485.00 62.015 .072 486.00 62.014 .072 487.00 62.012 .072 468.00 62.011 .072 489.00 62.009 .072 490.00 62.008 .072 491.00 62.006 .072 492.00 62.005 .072 493.00 62.004 .072 '
494.00 62.003 .072 495.00 62.002 .072 .
l 496.00 62.000 .072 497.00 61.999 .072
.072 498.00 61.998 l
499.00 61.997 .072 500.00 61.996 .072 0 '
1800.00 61.960 .072 1802.00 61.961 .072 1804.00 62.327 .072 1806.00 51.218 .059 1808.00 43.797 .050 1810.00 35.383 .041 1812.00 25.791 .030 WAPWR-CS 6.2-159 NOVEMBER, 1986
'4328e:1d
.. . . .. - ___-. ......_.-.-. . - .~.-.--._.--- -.-- .. - - - . _ -
t i
TABLE 6.2-39 (SHEET 12 of 12)
T CASE 11: 1.4 FT2 DOUBLE-ENDED RUPTURE AT HOT ZERO POWER MSIV FAILURE f
i TIME BREAK FLOW SREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC A 10E6) i 1814.00 0.000 0.000 lO' u '
1 2000.00 0.'dOO 0. BOO i
1 i
i i-O l
O ,
i O ,
O f 6.2-160 NOVEMBER, 1986 WAPWR-CS
'4328e:1d
i l TABLE 6.2-40 (SHEET 1 of 9)
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE l
l TIME BREAK FLOW ' BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 0.00 0.000 0.000
.50 2560.140 3.027 1.00 2539.790 3.004 1.50 2519.865 2.982 2.00 2500.507 2.560 0 2.50 3.00 3.50 4.00 2482.074 2464.315 2447.124 2430.394 2.939 2.919 2.899 2.880 4.50 2414.081 2.862
- 5.00 2398.182 2.844
! 5.50 2382.677 2.826 6.00 2367.570 2.809 6.50 2352.821 2.792 .
7.00 2338.460 2.775 7.50 2324.464 2.759 8.00 2310.850 2.744 8.50 2297.609 2.729
. 9.00 2284.669 2.714 i 9.50 2272.073 2.700 10.00 2259.783 2.685 10.50 2247.789 2.672 l 11.00 2236.062 2.658 11.50 2224.599 2.645 12.00 2213.665 2.633 12.50 2202.852 2.620 13.00 2192.237 2.608 13.50 2181.817 2.596 14.00 2171.578 2.584 14.50 2161.507 2.573 15.00 2151.590 2.561 15.50 2141.819 2.550 16.00 2132.169 2.539 16.50 2122.635 2.528 17.00 2104.565 2.507 17.50 2105.279 2.508 18.00 2103.719 2.506 18.50 2099.439 2.501 O 19.00 19.50 20.00 2095.039 2090.586 2086.085 2.496 2.491 2.486 20.50 2081.541 2.480 21.00 2076.951 2.475 21.50 2072.318 2.470 22.00 2067.634 2.464 O, 22.50 23.00 2062.903 2058.112 2053.285 2.459 2.453 2.448 23.50 24.00 2048.406 2.442 24.50 2043.483 2.436 25.00 2038.514 2.431 25.50 2033.506 2.425 0 26.00 26.50 2028.459 2023.379 2.419 2.413 6.2-161 NOVEMBER, 1986 WAPWR-CS 1328e:1d
TABLE 6.2-40 (SHEET 2 of 9)
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY O (SEC) 27.00 (LBM/SEC) 2018.266 (BTU /SEC K 10E6) 2.407 27.50 2013.003 2.401 28.00 2007.834 2.395 28.50 2002.653 2.389 29.00 1997.453 2.383 2.377 O 29.50 30.00 30.50 1992.241 1987.013 1981.792 1976.561 2.371 2.365 2.359 31.00 31.50 1971.339 2.353 32.00 1966.118 2.347 32.50 1960.897 2.341 33.00 1955.694 2.335 33.50 1950.495 2.329
- 34.00 1945.316 2.323 34.50 1940.149 2.317 35.00 1934.997 2.311 35.50 1929.854 2.305 36.00 1924.738 2.299 36.50 1919.635 2.293 37.00 1914.565 2.287 37.50 1909.506 2.281 O. 38.00 38.50 1904.539 1866.060 2.276 2.231 1 39.00 1839.196 2.200 39.50 1813.163 2.169 40.00 1788.094 2.140 40.50 1763.881 2.112 41.00 1740.439 2.084 41.50 1718.130 2.058 42.00 1696.089 2.032 42.50 1674.709 2.007 43.00 1654.005 1.983 43.50 1633.955 1.959 44.00 1614.525 1.936 44.50 1595.692 1.914 45.00 1577.430 1.892 ,
45.50 15!9.720 1.871 O 46.00 46.50 47.00 1542.532 1525.854 1509.675 1.851 1.831 1.812 1.794 47.50 1493.966 48.00 1478.708 1.776 48.50 1463.880 1.758 49.00 1449.465 1.741 1.724 O 49.50 50.00 50.50 1435.416 1421.728 1408.402 1395.436 1.708 1.692 1.677 51.00 51.50 1382.826 1.662 52.00 1370.508 1.647 52.50 1358.485 1.633 1346.744 1.619 O 53.00 53.50
$4.00 54.50 1335.272 1324.058 1313.092 1.605 1.592 1.579 l
6.2-162 NOVEMBER, 1986 WAPWR-CS 4328e:1d l
t _
3 x
e m
TABLE 6.2-40 (SHEET 3 of 9)
CASE 12: 1.0 Fi2 SFI.IT RUPTURE AT HOT ZERO POWER 4fSIV FAILURE TIME BREAK FLOW BREAK EhT.RGY
[N (SEC) (LBM/SEC) ' (BTU /SEC K 10E6) p 55.00 1302.366 1.565 55.50 1291.868 1.554 56.00 1281.593 1.542 ,
56.50 1271.527 1.530 57.00 1261.649 1.518 57.50 1251.945 1.506 O 58.00 58.50 59.00 1242.399 1233.022 -
1223.850 1.495 1.484 1.473 -
59.50 1214.838 1.452 x 60.00 1205.985 - 1.451 60.50 - 1197.292 1.441 61.00 1188.751 1.431 61.50 1180.363 1.all 62.00 1172.118 1.411 '
62.50 1164.021 1.401 63.00 1156.061 1.392 63.50 1148.241 1.382 64.00 1140.555 1.373 64.50 1133c003 1.364 '
65.00 1125'.577 1.355 65.50 1113.281 1.346 66.00 1121.109 1.378 66.50 1104.056 1.329s 67.00 1097.124 1.321 67.50 1090.309 1.313 68.00 1083.608 1.305 68.50 1077.020 1.297 69.00 1070.544 1.239 69.50 1064.175 1.282 70.00 1057.914 1.274 -
70.50' 1051.746 1.267 71.00' .3045.665 1.259 ,
71.50 '1039.690 1.252 72.00 1033.821 1.245 72.50 1018.052 1.238 y 73.00 1022.385 1.231 73:50 1016.816 1.225 O 74.00 1011.338' 1.218 74.50 1005.951 1.212 75.00 1000.658 1.205 75.50 995.456 1.199 76.00 990.342 1.193 76.50 985.316 '
1.167 77.00 980.375 1.131 77.50 975.220 1.175 O 78.00 78.50 79.00 970.453 945.760 961.143
.1.169
'1.163 1.158 79.50 956.602 1.152 80.00 952.132 1.147 80.50 947.733 1.142 E1.00 943.400 1.136 O 81.50 82.00 82.50 939.134 934.934 930.797 1.131 1.126 1.121 1 6.2-163 NOVEMBER, 1986 WAPWR-CS T328e:1d J
r l
i \
%, i st ,
it\_
TABLE 6.2-40 (SHEET 4 Of 9) s CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME 8REAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (8TU/SEC A 10E6) 83.00 926.722 1.116 w 83.50 922.709 1.111
~Vi i 84.00 918.756 1.107 e N 84.50 914.863 1.102
- u 85.00 911.026 1.097 9 85.50 907.247 1.093 0 86.00 86.50 87.00 87.50 903.522 899.853 896.236 892.673 1.088 1.084 1.079 1.075 88.00 889.161 1.071 88.50 885.698 1.067 89.00 882.285 1.063 89.50 878.922 1.059 90.00 875.605 1.055 -
90.50 872.335 1.051 91.00 869.110 1.047 91.50 865.930 1.043 92.00 862.794 1.039 92.50 859.698 1.035 93.00 856.643 1.032 93.50 853.630 1.028 O 850.668 1.025
'94.00 94.50 847.752 1.021 l '95.00 844.881 1.018
, 95.50 842.054 1.014 l -',- 96.00 839.271 1.011 96.50 836.530 1.008 97.00 833.829 1.004 97.50 831.168 1.001 98.00 828.545 .998 98.50 825.960 .995 99.00 823.409 .992 99.50 820.893 .989 100.00 818.410 .986 101.00 814.731 .981 102.00 810.009 .976 103.00 805.418 .970 104.00 500.938 .965 l
O 105.00 106.00 107.00 796.571 792.314 788.165
.959
.954
.949 108.00 784.122 .944 109.00 780.176 .939 110.00 776.325 .935 111.00 772.566 .930 112.00 768.896 .926 0- 113.00 114.00 765.313 761.814
.922
.917 115.30 758.399 .913 116.00 755.067 .900
! 117.00 751.815 .905 118.00 748.641 .901 l
0 119.00 120.00 121.00 745.543 742.520 739.568
.898
.894
.890 l WAPWR-CS 6.2-164 NOVEMBER, 1986
- 4328e:1d 1
i l
l i
l TABLE 6.2-40 (SHEET 5 of 9)
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT-ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY O ,
(SEC) 122.00 123.00 (LBM/SEC) 736.686 733.872,
/
(BTU /SEC A 10E6)
.887
.884 124.00 731.113 .t80 '
125.00 728.439 .877 126.00 725.816 .874 127.00 723.254 .871 h 128.00 720.749 .868
'- / 129.00 718.301 .865 130.00 715.908 .862 131.00 713.568 .859 132.00 711.278 .856 133.00 709.038 .854 i 134.00 706.848 .851 e 135.00 704.705 .848 136.00 701.607 .846 -
137.00 700.553 .843 138.00 698.543 .841 139.00 696.575 .838 140.00 694.646 .836 141.00 692.756 .834 142.00< 690.905 .832 143.00 689.091 .829 0 -
144.00' 145.00 146.00 687.312 685.568 683.858
.827
.825
.823 147.00 682.180 .821 148.00 680.534 .819 149.00 678.919 .817 150.00 677.335 .815 151.00 675.779 .813 152.00 674.251 .811 153.00 672.750 .810 154.00 671.276 .808 l 155.00 669.828 .806
)
156.00 668.404 .804 l 157.00 667.004 .803 158.00 665.627 .801 159.00 664.273 .799 160.00 662.941 .798 O. 161.00 162.00 661.630 660.340
.796
.795
, 163.00 659.071 .793 164.00 657.819 .792 165.00 656.586 .790 166.00 655.371 .789
'~'g 167.00 654.175 .787 168.00 652.995 .786 169.00 051.832 .784 ',
170.00 650.685 .783 171.00 649.553 .782 172.00 648.437 .780 173.00 647.335 .779 174.00 646.248 .778 l
175.00 645.174 .776 i 176.00 644.113 .775 177.00 643.064 .774 WAPWR-CS 6.2-165 NOVEMBER, 1986 4328e:1d I
I l
l TABLE 6.2-40 (SHEET 6 of 9) l 1
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY
/N (SEC) (LBM/SEC) (BTU /SEC X 10E6) 178.00 642.026 .772 179.00 641.000 .771 180.00 639.985 .770 181.00 638.982 .769 182.00 637.989 .768 183.00 637.006 .766 O 184.00 185.00 186.00 636.033 635.071 634.120
.765
.764
.763 187.00 633.178 .762 188.00 632.245 .761 189.00 631.320 .760 190.00 630.404 .758 191.00 629.497 .757 192.00 628.597 .756 -
193.00 627.705 .755 194.00 626.821 .754 195.00 425.943 .753 196.00 625.072 .752 197.00 624.209 .751 198.00 623.352 .750 199.00 622.500 .749 O 200.00 202.00 204.00 621.654 620.392 618.055
.748
.746
.743
.741 206.00 616.223 208.00 614.392 .739 210.00 612.608 .737 212.00 610.866 .735 214.00 609.155 .733 216.00 607.465 .731 218.00 605.792 .729 220.00 604.137 .727 222.00 602.498 .725 224.00 600.876 .723 226.00 599.270 .721 228.00 597.682 .719 230.00 596.107 .717 232.00 594.543 .715 234.00 592.992 .713 l t 236.00 591.452 .711 238.00 589.924 .709 240.00 588.406 .708 242.00 586.897 .706 244.00 585.395 .704 245.00 583.903 .702 O 248.00 250.00 252.00 582.420 580.943 579.474
.700
.699
.697 254.00 578.013 .695 256.00 576.557 .693 258.00 575.104 .691 260.00 573.658 .690 0 262.00 264.00 266.00 572.221 570.783 569.348
.688
.686
.684 6.2-166 NOVEMBER, 1986 WAPWR-CS 4328e:1d
TABLE 6.2-40 (SHEET 7 Of 9)
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (BTU /SEC K 10E6) 268.00 567.921 .683 270.00 566.499 .681 272.00 565.084 .679 274.00 563.667 .678 276.00 562.252 .676 278.00 560.841 .674 280.00 559.433 .672 O\ 282.00 284.00 558.030 556.629
.671
.669 286.00 555.234 .667 288.00 553.842 .666 290.00 552.454 .664 292.00 551.069 .662 294.00 549.688 .661 296.00 548.310 .659 -
298.00 546.937 .657 300.00 545.565 .656 302.00 544.198 .654 304.00 542.833 .652 306.00 541.473 .651 4 308.00 540.115 .649 310.00 538.760 .647 O 312.00 314.00 316.00 537.409 536.061 534.715 533.373
.646
.644
.643 318.00 .641 320.00 532.033 .639 322.00 530.698 .638 324.00 529.365 .636 326.00 528.035 .634 328.00 526.708 .633 330.00 525.384 .631 332.00 524.066 .630 334.00 522.748 .628 336.00 521.433 .626 338.00 520.122 .625 340.00 518.814 .623 342.00 517.511 .622 344.00 516.210 .620 O 346.00 348.00 350.00 514.911 513.616 512.324
.619
.617
.615 352.00 511.036 .614 354.00 509.750 .612 356.00 508.468 .611 358.00 507.187 .609 O 360.00 362.00 364.00 505.912 504.639 503.370
.608
.606
.605 366.00 502.103 .603 368.00 500.838 .601 370.00 499.577 .600 372.00 498.311 .598 O 374.00 376.00 378.00 497.200 495.952 494.579
.597
.596
.594 WAPWR-CS 6.2-167 NOVEMBER, 1985 T328e:1d I
L
TABLE 6.2-40 (SHEET 8 of 9)
CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY (SEC) (LBM/SEC) (RTV/SEC A 10E6) 380.00 493.252 .592 382.00 492.133 .591 384.00 490.897 .589 386.00 489.679 .588 388.00 488.383 .586 390.00 487.175 .585 O 392.00 394.00 396.00 485.991 484.773 483.542
.583
.582
.580
.579 398.00 482.312 400.00 481.077 .578 404.00 479.103 .575 408.00 477.402 .573 412.00 474.932 .570 416.00 475.005 .568 .
420.00 470.075 .564 424.00 468.182 .562 428.00 465.336 .558 432.00 463.558 .556 436.00 460.565 .553 440.00 458.934 .551 444.00 455.547 .547 O 448.00 452.00 456.00 455.179 449.128 434.341 397.184
.546
.539
.521 476 460.00 464.00 376.718 450 468.00 306.412 .365 472.00 -240.677 .285 476.00 163.275 .193 480.00 116.470 .137 484.00 89.402 .104 488.00 71.202 083 492.00 63.401 .074 496.00 90.045 .105 500.00 65.799 .077 504.00 59.721 .069 508.00 63.804 .074 512.00 63.887 .074 O 516.00 520.00 524.00 62.275 61.945 62.215
.072
.072
.072 528.00 62.254 .072 532.00 62.076 .072 536.00 61.990 .072 540.00 62.014 .072 O 544.00 548.00 552.00 62.029 62.008 61.990
.072
.072
.072 556.00 61.988 .072 560.00 61.989 .072 O ><
1800.00 se 61.954 sr
.072 6.2-168 NOVEMBER, 1986 WAPWR-CS 4328e:1d
t TABLE 6.2-40 (SHEET 9 of 9) i CASE 12: 1.0 FT2 SPLIT RUPTURE AT HOT ZERO POWER MSIV FAILURE TIME BREAK FLOW BREAK ENERGY O (SEC) 1804.00 (LBM/SEC) 62.094 (BTU /SEC K 10E6)
.072 1808.00 62.803 .073 i 1812.00 37.294 .043 1816.00 .025 .000 18 '0.00 .000 .000 20'd0.00 0.000 0.0b0 0
F O
O O
WAPWR-CS 6.2-169 NOVEMBER, 1985 T328e:1d
TABLE 6.2-41 SEQUENCE OF EVENTS FOR CASE 5 DOUBLE-ENDED RUPTURE FROM HZP O
Event Time Break occurs 0.0 O Low steamline pressure setpoint (555 psia) 0.35 l reached Reactor trip 2.35
. Hi-1 containment pressure setpoint (5.75 psig) 2.39 reached Steamline/feedline isolation 7.35 Safety injection system on 63.0 Fan cooler operation begins 75.39 Hi-3 containment pressure setpoint 148.0 (24 psig) reached Containment spray on 218.2 Peak containment pressure (33.22 psig) reached 405.0 '
3 Steam generator dryout (water volume less than 1 ft ) 410.0 EFWS flow terminated to the faulted steam generator 1800.0 0
WAPWR-CS 6.2-170 NOVEMBER, 1986 4328e:1d
TABLE 6.2 SEQUENCE OF EVENTS FOR CASE 6 1.1 FT2 SPLIT RUPTURE FROM 102 PERCENT POWER O Event Time 4
Break occurs 0.0 O Hi-1 containment pressure setpoint (5.75 psig) reached 10.43 Reactor trip 12.43
~
Feedwater isolation' 17.50
.Hi-2 containment pressure setpoint (13.75 psig) reached 29.32 Steamline isolation 36.32 Safety injection on 80.0 ,
Fan cooler operation begins 83.43 Peak' containment temperature (315'F) reached 85.0 Hi-3 containment pressure setpoint (24 psig) reached 71.7 O Containment spray on 141.9 l
Peak containment pressure (28.81 psig) 229.0 Steam generator dryout 240.0 EFWS flow terminated to the faulted steam generator 1800.0 O
6.2-171 NOVEMBER, 1986 WAPWR-CS 4328e:1d
- . _ - . - . = - . . . . .
O FIGURE 6.2-1 DOUBLE ENDED PUMP SUCTION BREAK NAX SI 49.9 O I s /
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NOVEMBER, 1986 WAPWR-CS i 4328e:1d
l-FIGURE 6.2-2 DOUBLE ENDED PUMP SUCTION BREAK MIN SI O ....
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NOVEMBER, 1986 WAPWR-CS T328e:1d
FIGURE 6.2-3 0.6 DOUBLE ENDED PUMP SUCTION BREAK MIN SI O ....
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q NOVEMBER, 1986'o WAPWR-CS T328e:1d
l l
i FIGURE 6.2-4 P
2 i 3 FT PUMP SUCTION SPLIT BREAK MIN SI i
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APWR COttAteREst lefECRiff asAtvlls O i l NOVEMBER, 1986 WAPWR-CS 4328e:1d
I l
FIGURE 6.2-5 t
DOUBLE ENDED COLD LEG BREAK NIN SI 1
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NOVEMBER, 1986 WAPWR-CS 4328e:1d
l FIGURE 6.2-6 DOUBLE ENDED HOT LEG BREAK MIN SI e...
O /
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O WAPWR-CS NOVEMBER, 1986 T328e:1d
l l
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l FIGURE 6.2-7 l
DOUBLE ENDED PUMP SUCTION BREAK MAX SI Ill.6 lO j u
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APWR C0tfAltREtt 15fEChifV ABALYllt O
WAPWR-CS NOVEMBER, 1986 4328e:1d l
l
..________,_,I
g FIGURE 6.2-8 DOUBLE ENDED PUMP SUCTION BREAK MIN SI l
l 1
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to io to 1: to to tint <steemos> osi:6iss C APWR cott At WMi nt tattCR!tV ANAt75t$
' NOVEMBER, 1986 WAPWR-CS 4328e:1d
FIGURE 6.2-9 O.6 DOUBLE ENDED PUMP SUCTION BREAK NIN SI
\
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APWR C0gfAlqM[gf lgf[CRify Ag&tygl3 WAPWR-CS NOVEMBER, 1986 4328e:1d
FIGURE 6.2-10 2
3 FT PUMP SUCTION SPLIT BREAK HIN SI
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r
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fiRI (SttotDS) esi,gssg A8WR COntAlentti latgCRITV ABALT$lt O
O WAPWR-CS NOVEMBER, 1986 4328e:1d
2 FIGURE 6.2-11 t
DOUBLE ENDED COLD LEG BREAK MIN SI I
ses.4 O . m
'% ;", , O 1
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[ =-
g mg E s 1 o
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+
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it a g, e 9, t ,,e flRE tlECOIOli 03/27/35 ADWR C0tfAREMit? ItitCAlfV AEALT$ll l
O lO 1
NOVEMBER, 1986 WAPWR-CS 4328e:1d
e e
FIGURE 6.2-12 DOUBLE ENDED HOT LEG BREAK MIN SI
' 300.0 ,
.+l
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, 140.6
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' to to flRE tttt050$1 08/19/85 ApWR C0tfAltnftt lattCalff ARALYllt NOVEMBER, 1986 WAPWR-CS 4328e:1d
t O O O O O O O 1
i I
i i
FIGURE 6.2-13 HEAT TRANSFER COEFFICIENT VS. TIME DOUBLE ENDED PUMP SUCTION, MAX SI 3 3 I I
l
! 300_ .
l 1 !
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ZF l 8' 200--
ut t'
tE Es i
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) :
z 100- -
1
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4 5 10 0 jo l jo 2 jo 3 10 10 Time (sec) NOVEMBER, 1986
- WAPWR-CS i T328e:1d i
i
O FIGURE 6.2-14 APWR CONTAINMENT INTEGRITY CASE 1 DOUBLE-ENDED BREAK AT 102 PC POWER i ....
O s .. ,
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NOVEMBER, 1986 WAPWR-CS T328e:1d
L i
f FIGURE 6.2-15 APWR CONTAINMENT INTEGRITY l
~
CASE 1 J
DOUBLE-ENDED BREAK AT 102 PC POWER nl..
- a k
- j7 1 ,
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i f
a NOVEMBER, 1986 f WAPWR-CS
! 4328e:1d i
i
. . _ _ _ ~ _ . _ . _ . . . _ _ . _ - _ _ , .--__ _ _ ._ _ _ _ _ _ ._ ..._ , _ -. , _
t
- O FIGURE 6.2-16 APWR CONTAINMENT INTEGRITY CASE 2 DOUBLE-ENDED BREAK AT 75 PC POWER i
- O
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NOVEMBER, 1986 WAPWR-CS 4328e:Id
. . . _ - .. . _ _ _ . . . = - . . -. -. _. - _ _ _ . _ - . .. . __ .
- O FIGURE 6.2-17 APWR CONTAINMENT INTEGRITY q CASE 2 DOUBLE-ENDED BREAK AT 75 PC POWER i....
i
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ose.,
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' is ie ' is is timi tittttD$l title /41 area (CtfAlentet lat(Grit? AtAttill O
WAPWR-CS NOVEMBER,1986 1328e:1d
i O
FIGURE 6.2-18 APWR CONTAINMENT INTEGRITY O CASE 3 DOUBLE-ENDED BREAK AT 50 PC POWER O
i s 10.0 , ,
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10 10 10
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. Vint flitct05) 11/2018%
Apun (OntAlentet inflCally AsALvtil O ,
NOVEMBER, 1986 WAPWR-CS 1328e:1d
h O
FIGURE 6.2-19 APWR CONTAINMENT INTEGRITY O- CASE 3 DOUBLE-ENDED BREAK AT 50 PC POWER 108.8 O
= A 3
J G
O res.e '
J A 2
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E O e.e 10 10 to 10 10 s
to ftpl t$ttCBDS) 11/2014%
Apua tottalentet lettCalif AWAttstl O
NOVEMBER,1986 WAPWR-CS
'4328e:1d
O .
FIGURE 6.2-I0 APWR CONTAINMENT INTEGRITY p '
CASE 4
< DOUBLE-ENDED BREAK AT 25 PC POWER
- Ill ll
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V
(
NOVEMBER, 1986 WAPWR-CS
%328e:1d
O "
! FIGURE 6.2-21 l
APWR CONTAINMENT INTEGRITY CASE 4 DOUBLE-ENDED BREAK AT 25 PC POWER
- i. ..
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WAPWR-CS NOVEMBER, 1986 i' '
4328e:1d i
I i
i
- - , - , - ---.-,--------,,,n-,- -a.,__ . , - - - - - -
1 FIGURE 6.2-22 APWR CONTAINMENT INTEGRITY CASE 5 s t
DOUBLE-ENDED BREAK AT HOT ZERO POWER i
.... , g i
3 '
7:
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- 10 le to 10 10 10 tlRE ($lteatti 11/20#81 Aput (041Albatti ititChl1T Ab4LTSlt O
.J NOVEMBER, 1985 WAPWR-CS T328e:la
4 O
FIGURE 6.2-23 l
APWR CONTAINMENT INTEGRITY CASE 5 DOUBLE-ENDED BREAK AT HOT ZERO POWER si...
~ ~
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/
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l WAPWR-CS NOVEMSER, 1986 I l
l 4328e:1d l
1
1 a
I FIGURE 6.2-24 APWR CONTAINMENT INTEGRITY CASE 6 1.1 FT2 SPLIT BREAK AT 102 PC POWER i...
m
/ \
i
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\
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sins esagesc5: sisistas apua gestAtangst it ECRitt AtALYSIS l
n Q
NOVEMBER,1986 WAPWR-CS ,
T328e:1d
l l
am '
1 O
FIGURE 6.2-25 APWR CONTAINMENT INTEGRITY CASE 6 1.1 FT2 SPLIT BREAK AT 102 PC POWER i
1 E
j ..... , ,
= ; ' s 1 .
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es f w F %.
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4
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l l
NOVEMBER, 1986 WAPWR-CS 4328e:1d
O FIGURE 6.2-26 APWR CONTAINMENT INTEGRITY CASE 7 1.1 FT2 SPLIT BREAK AT 75 PC POWER l I'
/
\
l 3
- s... '
t
=
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- 10 10 10 t0 le le 1 Int tSEC0bOS) 11120/85 Apua testAtentet tutECRtly AuALYlls O
O NOVEMBER, 1985 WAPWR-CS 4328e:1d
FIGURE 6.2-27 APWR CONTAINMENT INTEGRITY CASE 7 1.1 FT2 SPLIT BREAK AT 75 PC POWER s
~
o i.... ,
e i .
c u C
-1 L3
- o....
. 3 I 5 f
= i....
l "
mm O ...
io '
is to is ie io TInf ESIC0tDll ti/20/85 APWR COtfAltR(Et ItttGRl1T ARALT$1l NOVEMBER, 1985 WAPWR-CS T328e:1d
O FIGURE 6.2-28 APWR CONTAINMENT INTEGRITY O CASE 8 1.1 FT2 SPLIT BREAK AT 50 PC POWER
/~ \
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l 3
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t o 10 10 10 le to TIMI ($ttokoll 11/20#41 APWa C0kTAlentti IRTECRITY Ah4LISit O
O WAPWR-CS NOVEMBER, 1986 4328e:1d
O FIGURE 6.2-29 l APWR CONTAINM.ENT INTEGRITY l CASE 8 1.1 FT2 SPLIT BREAK AT 50 PC POWER O l
= l j..... .
i <
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t J,s.... 3 e
/
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i.
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l NOVEP.BER, 1986 WAPWR-CS T328e:1d
FIGURE 6.2-30 APWR CONTAINMENT INTEGRITY CASE 9 1.1 FT2 SPLIT BREAK AT 25 PC POWER I
I , ,
/
- N -
- / 1
=
3
=...
s I i \
T
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l
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APWR CetfAlBRtti $3fECRITY ABALTlll l
l NOVEMBER, 1986 WAPWR-CS T328e:1d
FIGURE 6.2-31 APWR CONTAINMENT INTEGRITY CASE 9 1.1 FT2 SPLIT BREAK AT 25 PC POWER l
t l
j ..... ; N
. 2 r .
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O FIGURE 6.2-34 APWR CONTAINMENT INTEGRITY CASE 11 DOUBLE-ENDED BREAK MSIV FAILURE HZP O
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NOVEMBER, 1986 WAPWR-CS 4328e:1d
O FIGURE 6.2-36 APWR CONTAINMENT INTEGRITY CASE 12 1.0 FT2 SPLIT BREAK MSIV FAILURE HZP
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NOVEMSER, 1985 WAPWR-CS 4328e:1d
O 6.2.2 Containment Heat Removal System The functional performance objective of the containment heat removal system, as 'an engineered safety features system, is to reduce the containment
^
O temperature and pressure following a LOCA or main steam line break (MSLB) ,
inside containment accident, by removing thermal energy from the containment atmosphere. These cooling systems also serve to limit offsite radiation levels by reducing the pressure differential between the containment O atmosphere and the external environment, thereby diminishing the driving force for the leakage of fission products from the containment to the environment.
Two separate systems are utilized to perform the containment heat removal
! function: the containment fan cooler system and the cor.tainment spray portion of the Integrated Safeguards System (her4after referred to as Containment SpraySystem).
6.2.2.1 Containment Fan Cooler System O The containment fan cooler system functions following a DBA to remove heat energy from the containment atmosphere, thereby reducing the containment pressure and decreasing leakage of fission products to the environment. The containment fan cooler system transfers energy from the containment atmosphere to the component cooling water system (CCW) for rejection to the ultimate heat sink. (See Subsection 9.2.2 and 9.2.5 of RESAR-SP/90 PDA Module 13," Auxiliary System").
The containment fan cooler system also functions during normal plant operation to maintain the temperature of the containment atmosphere within design limits specified for that mode of operation. The normal function of the system is addressed in Subsection 9.4.6 of RESAR-SP/90 PDA Module 13, " Auxiliary Systems."
l l
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O WAPWR-CS 6.2-172 NOVEMBER, 1986 3672e:1d I
_ _u_ . . _ ,
O 6.2.2.1.1 Design Bases 6.2.2.1.1.1 Safety Design Bases SAFETY DESIGN BASIS ONE - The containment fan cooler system, in conjunction with the containment spray system, is capable of removing heat energy from the containment atmosphere following a DBA to prevent overpressurization of th'e containmentstructure(GDC-50).
SAFETY DESIGN BASIS TWO - The containment fan cooler system, in conjunction -
'with the containment spray system is capable of reducing and maintaining containment pressure and temperature to acceptably low levels following a DBA. A single failure of an active component coincident with a loss of offsite power will not prevent the system from performing its heat removal function (GDC-38).
SAFETY DESIGN BASIS THREE - The containment fan cooler system is designed to O withstand the effects of a safe shutdown earthquake without loss of function, and is protected against internal missiles, flooding, pipe whip and jet forces (GDC-2 and 4).
l SAFETY DESIGN BASIS FOUR - The containment fan cooler system is designed to permit testing of active components during plant operation. Provisions are made to permit periodic inspection of the significant components (GDC-39 and 40).
SAFETY DESIGN BASIS FIVE - The containment fan cooler system is placed into ;
operation automatically following a DBA. The actuation system is designed in accordance with IEEE Standard 279.
6.2.2.1.1.2 Power Generation Design Bases Power generation design bases for the containment fan cooler system are presented in Subsection 9.4.6.1.2 of RESAR-SP/90 PDA Module 13, " Auxiliary Systems".
WAPWR-CS 6.2-173 NOVEMBER, 1986 3672e:1d
G b 6.2.2.1.2 System Description 6.2.2.1.2.1 General Description O
O The containment fan cooler system consists of multiple recirculation cooling units each connected to an associated recirculation fan. The containment atmosphere is drawn through the cooling units by the recirculation fans, with heat energy being transferred to the component cooling water system by air-to-water heat exchange coils. The cooled atmosphere then passes through a short section of ductwork connecting the cooling unit to the recirculation fan, passes through the fan itself and is discharged to the lower levels of the containment volume for additional heat absorption. Following a DBA, a large quantity of condensate is formed on the heat exchange coil surfaces.
This condensate is collected in the base 'of the cooling unit housing and drains to the containment sump by gravity.
6.2.2.1.2.2 Component Description O The containment recirculation cooling units are located on the operating floor I
level, and consist of a structural steel framework supporting demisters and l cooling coils mounted on three vertical faces. Air enters the housing through the demisters and cooling coils and exits through a duct connection in the l
base of the unit.
The recirculation fans are located beneath the cooling unit on the elevation below the operating floor, and are oriented for vertical downblast discharge. '
The fans are of the direct driven vane axial type, with two-speed electric l
drive motor. The fan is connected to the recirculation cooling unit by a straight section of removable ductwork.
All materials and finishes exposed to the harsh DBA environment are suitably selected for their intended service. The cooling coils are constructed from copper or copper-nickel tubes with copper fins and stainless steel frames.
The cooling unit housing will be constructed from a combination of coated carbon steel and stainless steel. The fan housing will be coated carbon steel.
l WAPWR-CS 6.2-174 NOVEMBER, 1986 3672e:1d I
l
O 6.2.2.1.2.3 System Operation During normal plant operation, three of the four coolers will operate with fans in high speed to maintain containment air temperature below the design 1
value. Two coolers receive cooling water from train A of the component cooling water system, and two coolers receive cooling water from train B of the component cooling water system.
Upon receipt of a safety injection signal, one of the train A coolers will start in low speed, and one of the train B coolers will start in low speed.
If previously operating in high speed, these two units will automatically shift to slow speed operation. The remaining train A cooler and train B l ope i o er o y ee to p d dd na h removal capacity and to prevent local boiling within the cooling coils. In
! the event of a single failure, adequate heat removal capacity is provided by ,(,,c) one operating cooling unit. Each unit is capable of removing a minimum of[]
x 106 Btu per hour under design accident conditions assuming appropriate fouling of the heat exchange surfaces and conservative component cooling water temperature.
6.2.2.1.3 Codes and Standards Equipment and materials utilized in the containment fan cooler system conform to the requirements and recommendations of the codes and standards listed below as applicable:
a) Heat exchange cooling coil ratings conform to standards of the
~
Air-Conditioning and Refrigeration Institute (ARI). Tubes, headers and other CCW pressure boundary components are constructed in accordance with the ASME Boiler and Pressure Vessel Code,Section III, Class 3.
b) Fan ratings conform to standards of the Air Moving and Conditioning Association (AMCA).
O -
WAPWR-CS 6.2-175 NOVEMBER, 1986 3672e:1d
O c) Housings for the recirculation cooling units and their outlet ducts conform to applicable standards of the Sheet Metal and Air Conditioning Contractors National Association (SMACNA).
O d) Fan motors conform to applicable standards of the National Electrical Manufacturers Association (NEMA).
e) Environmental qualification of electrical equipment conforms to b] applicable standards of the Institute of Electrical and Electronics Engineers (IEEE).
6.2.2.1.4 Safety Evaluation Safety evaluations are numbered to correspond to the safety design bases of Subsection 6.2.2.1.1.1.
SAFETY EVALUATION ONE
- Results of the containment analysis presented in Subsection 6.2.1 demonstrate that the containment fan cooler system, in conjunction with the containment spray system, is capable of removing sufficient heat energy from the containment atmosphere following a DBA to prevent overpressurization of the containment structure. Analyses assume the most degrading single failure along with approprite fouling of heat exchange surfaces and the conservatively calculated maximum value for component cooling water temperature.
SAFETY EVAI.UATION TWO - Results of the containment analysis demonstrate the capability of the containment fan cooler system, in conjunction with the containment spray system, to achieve a rapid cooldown of the containment atmosphere following a DBA. Radiological analysis assuming the worst single active failue coincident with a loss of offsite power demonstrates an offsite radiation exposure within the guidelines of 10CFR100. A single active failure analysis is presented in Table 6.2-43.
SAFETY EVALUATION THREE - The containment fan cooler system is designed to Seismic Category I requirements, and will remain functional following a design basis earthquake. The trains are physically separated for missile protection 6.2-176 NOVEMBER, 1986 WAFWR-CS 3672e:1d
. . . . . . . .~
.O and are protected from loss of function due to pipe whip and jet forces. All components including interconnecting ductwork are designed to withstand the maximum pressure differentials they are subjected to during .the DBA.
Components are located above the maximum. calculated post-accident water level for flood protection. Since all components are located within the containment structure, the system is inherently protected from effects of external missiles, tornadoes, hurricanes and other appropriate natural phenomena.
SAFETY EVALUATION FOUR - The system design incorporates features that permit periodic simulation of a safety injection signal to verify proper sequencing of equipment and. positioning of active valves. General equipment condition can be visually inspected at appropriate intervals. Mechanical readiness is demonstrated by the system in its normal operating mode, thereby assuring a source of reliable post-accident heat removal.
SAFETY EVALUATION FIVE - The actuation signal for the containment cooling system is derived from a containment high pressure signal used to initiate safety injection. A sudden rise in containment pressure is a positive indication an accident has occurred that requires the heat removal function.
6.2.2.1.5 Inspection and Testing Requirements Performance characteristics of the containment cooling system will 'be verified I through qualification testing of essential components as follows:
l a) A heat exchange coil section will be performance tested to demonstrate its ability to remove latent and sensible heat ander simulated post-
, Os accident conditions. The chemical environment will also be simulated to demonstrate compatibility with 'the materials and selected coil geometry throughout a range of coolant temperatures. Alternatively, f
coils will be qualified based on previous testing of similar heat .
exchange coils.
O .
6.2-177 NOVEMBER, 1986
}{APWR-CS 3672e:1d
O b) A recirculation fan will be performance tested in accordance with -the applicable AMCA test codes to verify predicted characteristics.
Additionally, all fans will be operated during containment integrated leak rate testing to demonstrate adequate motor capacity in the dense atmosphere.
c) The fan assembly with drive motor will be qualified by similarity to a unit that has been previously tested to demonstrate its post-accident capabilities. Qualification will be in accordance with applicable IEEE Standards.
d) The recirculation unit housing, ductwork, and fan housing will be tested, either individually or collectively, under simulated post-accident pressure differentials to demonstrate structural integrity.
Initial functional testing of the containment cooling system will verify fan flow rates, cooling water flow distribution, dynamic balance of rotating elements, operation of controls and interlocks, and proper emergency alignment and response time.
Periodic testing during plant operating life will be conducted to verify proper cooling water flow, mechanical condition of equipment, and emergency alignment and response time. Recirculation fans will be operated during each containment integrated leak rate test to verify their operability in the dense atmosphere.
6.2.2.1.6 Instrumentation Application The containment cooling system is normally controlled and monitored from the main control room. Upon receipt of the safety injection signal, the emergency actuation logic is electrically sealed in to prevent inadvertant manual action that could trip the containment cooling system. Status lights are provided to inform the operator of the system alignment, position of significant CCW O~ NOVEMBER, 1986 WAPWR-CS 6.2-178 3672e:1d
O v
valves, and other pertinent parameters. Containment atmosphere temperature is also monitored both normally and following an accident to inform the operator of conditions within the containment structure.
6.2.2.2 Containment Spray System i
The containment spray function is performed by the integrated safeguards system (ISS). Those components within the ISS that perform a CSS function are
) the four low head pumps, the Emergency Water Storage Tank (EWST) and the associated valves, piping, and instrumentation. Within the containment, two
' redundant sets of spray ring headers are used to provide containment atmosphere coverage. The ISS is described in detail in RESAR-SP/90 PDA Module 1,
" Primary Side Safeguards System."
t 6.2.2.2.1 Design Bases The CSS,. in conjunction with the containment fan cooler system, and the containment passive heat sinks is capable of removing sufficient sensible heat and subsequent decay heat from the containment following the hypothesized LOCA or main steam line break accident to maintain the containment design pressure, in accordance with 10CFR50, Appendix A, General Design Criterion 38, i " Containment Heat Removal."
The CSS is designed to remove fission products from the containment atmosphere I in order to reduce the inventory of fission products available for leakage from the containment in accordance with 10CFR50, Appendix A, General Design Criterion 41, " Containment Atmosphere Cleanup."
The CSS is designed to permit appropriate periodic inspection and testing to ensure its integrity and operability in accordaace with 10CFR50, Appendix A, General Design Criterion 39, " Inspection of Containment Heat Removal System",
and General Design Criterion 40, " Testing of Containment Heat Removal System."
WAPWR-CS 6.2-179 NOVEMBER, 1986 3672e:1d
O Missile protection, protection against the dynamic effects' associated with the postulated rupture of piping, and seismic design are discussed in Subsections 3.5, 3.6, and 3.7, respectively of RESAR-SP/90 PDA Module 7 " Structural /
Equipment Design."
6.2.2.2.2 System Design o Piping and instrumentation diagrams for the CSS portion of the ISS are shown in Figure 6.3-1, sheets 1 through 7 of.RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System." These diagrams show the relative location of CSS components, where the components tie together with other ISS components and piping, and the instrumentation and controls associated with the CSS components.
A design flow rate of ~ [ ] gpm at a containment pressure of ( ~j psig +(a,c)
] foot diameter spherical containment. +(a , c)
! has been established for an assumed [
This design flow rate is based on an assumed spray ring header layout and nozzle type, orientation and spacing that would ensure that the maximum containment volume coverage was obtained. A SPRAYC0 1713A spray nozzle has been assumed with a pressure drop of [ ] psig at a spray nozzle design flow +(a,c) rate of ( ~) gpm. Each low head pump is capable of providing approximately +(a,c)
( ) gpm at a [ ] psi containment pressure, therefore two of the four low +C"'*)
+(a,c) head pumps are required to meet the [ ] gpm spray design flow rate.
- a. Component Design s Components within the ISS that perform a CSS function are the four low head pumps, the EWST and the associated valves, piping, and instrumentation.
Design parameters for the low head pumps and EWST are provided in Table 6.3-2 of RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System." Discussion of their design features is provided in Subsection 6.3.2.2 of RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System."
~
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WAPWR-CS 6.2-180 NOVEMBER, 1986 3672e:1d
m U Containment Spray Headers Within the containment, two redundant sets of spray ring headers are used (see O Figure 6.3-1, sheet 7 of RESAR-SP/90 PDA Module 1). One half .of each set of V .
ring headers would be assigned to one spray subsystem. A staggered assignment of ring header sections to each spray subsystem assures the' maximum containment l coverage with any two low head pumps operating. For example, each low head pump would deliver to 1/2 of an inner ring, 1/2 of a middle ring, and 1/2 of an outer ring. However, the 1/2 inner. ring and 1/2 outer ring would provide spray to the opposite side of the containment from the 1/2 middle ring. A -
second low head pump would be assigned to deliver to the matching spray headers segments so that the operation of two low head pumps delivering to
- matching ring header segments assure 100 percent containment coverage with 100 percent of the required spray flow.
A 90 degree relative orientation between the two sets of ring headers is also necessary to assure that the maximum containment coverage will be obtained with any two low head pumps operating. This orientation would ensure a 75 percent containment coverage with 100 percent of the required flow even if the two operating spray systems are delivering to unmatched ring header segments.
For an ISS powered by four emergency electrical power trains, each low head spray pumping system can be assigned to any one of the four groups of ring headers (each group consisting of 1/2 inner, 1/2 middle, and 1/2 outer ring).
I For an ISS powered by two emergency electrical power trains, spray subsystems -
assigned to the same electrical train must be assigned to deliver to a matched set of ring headers to ensure 100 percent containment coverage with a single electrical train failure.
1 Spray Nozzles The spray nozzles are hollow cone ramp bottom nozzles, type SPRAYC0 1713A Figure 6.2-38 and Table 6.2-44. Eitch nozzle is flow tested over a range of inlet pressures to determine that the actual flow rate at [ ] psig meets the+(*' )
l design flow rate of [ ] gpm Figure 6.2-39. Figure 6.2-40 shows mean +(8'C) droplet size distribution. The nozzles are oriented to ensure thorough O. WAPWR-CS 6.2-181 NOVEMBER, 1986 3672e:1d
m u
o coverage of the containment volume. Typical spray patterr s for these nozzles in the vertical, horizontal, and doinward spray positions are provided in Figures 6.2-41, 6.2-42 and .6.2-43, respectivcTy.
O b. System Operation s.
j In the event of a high containment pressure signal ("P" signal) during reactor power operations, the four low head pumps would receive an automatic signal to O- star.t and the containment spray header isolation valves (9009A, B, C, D _and 9011A, B, C, 0) would receive an automatic signal to open. The low head pumps-would function as containment spray pusps and would draw sucticn from the EWST and deliver to the containment spray headers, which are located in the top of the containment building. y
- c. Component Interlocks i
Component interlocks use,d in tho d'.fferent modes of ISS operation are listed in Subsection 6.3.2.1 of RESAR-SP/90 PDA Module 1, " Primacy Side Safeguards -
System." Interlocks specifically utilized for CSS operations are as follows: V
/
The containment isolation Phase "B" and containment spray initiation signal-.
("P") initiates the following actions: -
(1) The four low head pumps start ,
(2)The containment spray header inner containawnt, isolation valves open (9011 A, B, C, D) b
.(3) The n,ormally open containment spray header outer containmnt isolation valves receive a confirmatory "P" signal to open, if closed (9009 A, B, C, D) v
- d. Operator Actions .
No operatcr actions are required for CSS injection.
O, NOVEMBER, 1986 WAPWR-CS 6.2-182 3672e:1d
s
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- 2. antainment Recirculation Sump
. !, - Watar spilling from an RCS break and the CSS would fill the lower containment
- 'i subcompartments and then spill back into the EWST.
ThereareYourindependentandphysicallyseparatedsumppits provided in the in-containment EWST. Each of these four EWST sump pits are assigned to a
/~ ' separateISSsubsystem,thesuctionpipingforoneISShighhead pump and one ISS low head pump is connected to it.s individual EWST sump pit. The EWST and the four EWST pump pits meet the intent of Regulatory Guide 1.82.
Large area vertical trash racks and fine screens are provided for each of the four EWST sump pits to collect debris. The EWST and EWST sump pits are located in the containment base mat and constructed of stainless steel liner
,; plates.
A' minimum water level will be maintained in the EWST during any postulated LOCA to insure adequate NPSH, low screen approach velocities, and no vortexing.
6.2.2.2.3 Design Evaluation O , i Plan and elevation drawings of the containment showing the expected spray
-l patterns will .be provided in the integrated PDA. An analysis of the beat removal effectiveness of the'sprsys will also be provided.
.(
NPSH calculations,',for the low he~ad pumps are performed in accordance with the recommendations of 9egulatory Guide 1.1.
A failure mode and effects analysis is provided in Table 6.2-45.
. 6.2.2.2.'a Tests and Inspections o ,
- a. Preoperational Testing The. objectives and procedures of preeperational testing are to:
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1 6.2-183 NOVEMBER, 1985 WAPWR-CS s.
3672e:1d , ;
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s (1) Demonstrate that the system is adequate to meet the design pressure and temperature conditions. Components are tested in ,conformance with applicable codes.
O (2)Demonsthatethatthespraynozzles in the centainment spray header are clear of obstructions, by passing air through the test connections.> The nozzle design parameters are verified by prototype testing in the vendor's I
facilities.
(3) Verify that the proper sequencing of valves and pumps occurs on initiation of the CSS, and demonstrate the proper operation cf remotely operated
. valves.
(4) Verify the operation of the low head pumps; each pump is run at minimum flow and the flow directed back to the pump suction. During this time, the minimum flow will be adjusted to that required for routine testing,
- b. Operational Testing The CSS is designed to permit periodic determination of proper system operabiHty. The' objectives and procedures of operational testing are to:
(1) Verify that the proper sequencing of valves and pumps occurs on initiation of the containment spray actuation signals, and demonstrate the proper operation of remotely-operated valves.
i (2) Verify the operation of the low head pumps. Periodic testing-each pump is run at minimum flow to verify pump start and developed head. In addition, full pump flow testing capability via the full flow test line to the EWST is provided.
- c. Inspection The pressure-containing systems are inspected for leaks from pump seals, valve packings, flange joints, and safety valves during system testing. The components of~ the system outside the containment are accessible for U leaktightness inspection during periodic flow tests.
6.2-184 NOVEMBER, 1986
}{APWR-CS 3672e:1d
i O 6.2.2.2.5 Instrumentation Requirements ,
Instrumentation within the ISS is discussed in Section 6.3.5 of RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System."
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!O l WAPWR-CS 6.2-185 NOVEMBER, 1986 !
i 3672e:1d
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l TABLE 6.2-43 (SHEET 1 of 2) l CONTAINMENT FAN COOLER SYSTEM i SINGLE ACTIVE FAILURE ANALYSIS Component Failure Mode Effect on Operation Failure Detection Method ,
- 1. Recirculation Fan a) Fails to start and run Heat removal capacity Control room indication of fan j in low speed. reduced. Redundant status.
i train sufficient to
) meet applicable safety
- design bases (Note
Non-running fan cooler in affected train i
availabio for manual start by operator).
b) Trips during accident Same a: 1.a) Control room indication of fan i scenario and fails to status.
I restart.
c) Fails to stop on demand Remote potential for Control room indication of fan when containment pres- creating negative pres- status.
- sure and temperature sure inside containment.
l return to normal. Vacuum breakers provided
- to ensure pressure 2 equalization.
d) Starts but runs at high (Same as 1.a) Excessive Control room indication of fan speed heat removal can result status.
in local boiling of CCW in cooler resulting in .
reduced CCW flow and reduced heat removal.
Can result in excessive recirculation fan motor load and failure of fan motor.
WAPWR-CS 6.2-186 NOVEMBER, 1986 3672e:Id .
O O O O O O O TABLE 6.2-43 (SHEET 2 of 2)
CONTAINMENT FAN COOLER SYSTEM SINGLE ACTIVE. FAILURE ANALYSIS Component Failure Mode Effect on Operation Failure Detection Nethod e) Two recirculation fans (Same as 1.a) Excessive Control room indication of fan on one train start and heat removal can result status.
run in higher than design CCW temperature in affected CCW train. Can result in local boiling of CCW in cooler, re-sulting in reduced CCW flow and reduced heat removal.
loss of component cooling Same as 1.a) Control room indication of valve
- 2. Recirculation position.
Cooling Unit water due to valve closure.
No valve
- CCW is always aligned to recirculation fan cooling unit designated to operate post-accident.Item 2 is repositioning is required to occur and therefore these are no postulated active failures.
included for information only.
NOVEMBER, 1986 WAPWR-CS 6.2-187 3672e:1d l
TABLE 6.2-44 CONTAINMENT SPRAY SYSTEM COMPONENT PARAMETERS Low Head Pumps See Table 6.3-2 (1) .
Emergency Water Storage Tank See Table 6.3-2 (1)
Spray Headers Number 2 sets Spray Nozzles
- Number, per set - 376(2)
, total - 752(2)
Type SPRAYC01713A Design Flow per Nozzle, gpm [ ]++((a a,c), c)
- Pressure Drop at Design Flow, psig [ ]
Orifice Diameter, in [ ] +(a,c)
O lO O
(1) Information is provided in RESAR-SP/90 PDA Module 1, " Primary Side Safeguards System."
(2) Based on a [ ] ft diameter spherical containment. +(a.c)
WAPWR-CS 6.2-188 NOVEMBER, 1986 3672e:1d
4
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i TABLE 6.2-45 FAILURE MODE AND EFFECTS ANALYSIS - INTEGRATED SAFEGUARD SYSTEM (ISS) i CONTAINMENT SPRAY FUNCTION j Component Fatlure Mode CSS Function Effoct on Systom Operation Failure Detoction Method Remarks I
j 1) Low head pump Fails to deltver Delivery of containment Failure results in reduced re- Open pump switchgear circuit No. I ARRH/CS working fluid spray fluid to spray dundancy of containment spray breaker indication at CB.
(Pump No. 2. 3, headers from EWST. function. Spray f unction - Circuit breaker overcurrent 4 analogous) maintained by spray subsystem trip indication at CB. Cir-
- 8. C D and 100% of spray flow cuit breaker close position requirement provided by two monitor light; low-head pump low head pumps. discharge coolant flow in-dication (FI-908) at C8.
4
- 2) Low-head pump Fails to open on Valve opens on *P* signal Failure results in no spray Valve position indication spray header iso- demand to admit pumped spray flow delivered to associated (closed to open position
! 1ation valve header spray header. (Remaining; change) at C8. Valve open 9011A (90118. C. same as 1 above). Operator position monitor light and D analogous) can manually open valve and alarm at C8; low-head pump
[
restore subsystem to oper- discharge coolant flow in-atton. Note continuous pump dication (FI-908) at C8.
protection provided by mini-1 flow line.
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VAPwR-CS 6.2-189 NOVEMBER. 1986 i -
3672e:1d
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O NOVEMBER, 1986 WAPWR-CS 3672e:1d l
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CAPACITY Wanni Figure 6.2-39 Containment Spray Nozzle Capacity Curve NOVEMBER,1986 EAPWR-CS 3672e:1d
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O 6.2.3 Secondary Containment Functional Design The function of the secondary containment is to collect any fission products which could leak from the primary containment structure into the annular O secondary containment ' air volume (annulus) and contiguous areas following a designbasisaccident(LOCA),andisdesigned to ' provide radiation s'hielding as well as missile protection for the steel containment and other safety related structures. The secondary containment ~ provides a low leakage rate O barrier between the primary containment and the environment to control all leakage from the containment building. The system is comprised of: (a) a reinforced concrete shield building and a wrap-around reactor external building surrounding the containment, adjacent vaults, and penetration areas; and (b) an annulus air cleanup system, described in Subsection 9.4.5 of RESAR-SP/90 PDA Module 13, " Auxiliary Systems", which maintains a pressure lower than ambient. in the annulus to prevent the uncontrolled release of radioactivity into the environment.
6.2.3.1 Design Bases 6.2.3.1.1 Secondary Containment The secondary containment is:
A. designed for a 3 psig differential pressure.
B. designed to withstand the transient pressure and temperature conditions produced in the annulus between the primary and secondary containment as a result of either a LOCA within containment or a high energy pipe rupture within the containment annulus.
C. capable of withstanding the external pressure conditions resulting from the maximum wind pressure postulated for the site, and the external pressure drop resulting from a tornado.
D. designed to provide radiation shielding as well as missile protection for the steel containment.
O NOVEMBER, 1985 WAPWR-CS 6.2-190 3672e:1d
O E. designed to withstand a safe shutdown earthquake.
6.2.3.1.2 Annulus Air Cleanup System O The annulus air cleanup system (AACS) is:
A. capable of reducing the reactor building annulus pressure to a (water gauge) following an accident and n
v negative 0.50 inches w.g.
maintaining it at or below that level uniformly for up to one year. .
B. capable of processing the atmosphere of the reactor building annulus while maintaining the design negative pressure differential.
C. designed to permit periodic inspection and monitoring of functional capability.
D. designed in accordance with Regulatory Guide 1.52.
O E. designed to Seismic Category I and Safety Class 2 requirements.
F. designed to retain functional capability while experiencing a loss of offsite power concurrent with a LOCA and any single active component failure.
6.2.3.2 System Design 6.2.3.2.1 Secondary Containment O The secondary containment is comprised of a[ ] meter diameter reinforced H"'d concrete shield building and a wrap-around reactor external building. These structures completely enclose the containment, forming a second barrier to the uncontrolled escape of radioactive sources in the event of an accident. The annulus formed by the primary containment and secondary containment is shown in Figures 1.2-2 (sheets 1 through 9) of RESAR-SP/90 PDA Module 3,
" Introduction and Site".
O WAPWR-CS 6.2-191 NOVEMBER, 1986 3672e.1d
i l
O A more detailed description of the concrete shield building and the reactor external building is given in Subsection 1.2.3 of RESAR-SP/90 PDA Module 3
" Introduction and Site," and Subsection 3.8.4 of RESAR-SP/90 PDA Module 7,
" Structural / Equipment Design". Applicable codes, standards and specifications applied in the design of this structure are discussed in Subsection 3.8.4.2 of RESAR-SP/90 PDA Module 7.
l 6.2.3.2.2 Features in Support of the Secondary Containment All piping penetrating the primary containment structure is sealed at the 4
containment structure and at the secondary containment in such a way as not to be ,overstressed by thermal or seismic-induced motion. Electrical penetrations are sealed and anchored at the containment structure.
The ECCS recirculation lines are enclosed in a sleeve which extends out to a vessel which encloses the first isolation valve outside the containment. This enclosure serves to contain any leakage from the recirculation line and the first isolation valve.
- All personnel doors and equipment hatches in the containment shield building and the reactor external building will be under administrative control. The
! doors will be provided with position indicators and alarms having readout and I alarm capability at the primary and secondary alarm stations. These doors must be closed to ensure a negative pressure in the reactor building annulus.
) 6.2.3.2.3 Annulus Air Cleanup System This system has two functions: (1) to produce a negative pressure post-accident in the annular air volume between the primary and secondary containment; and (2) to collect any hazardous materials that might leak into these areas from the containment structure or equipment / systems located within the reactor external building, so they may be disposed of in a controlled j manner. Both these functions are performed by redundant filter trains, redundant fans, dampers and controls, and a common discharge ductwork system to the unit plant vent. Further detail is provided in Subsection 9.4.5 of i RESAR-SP/90 PDA Module 13, " Auxiliary Systems".
WAPWR-CS 6.2-192 NOVEMBFR, 1986 is72.1d
O The annulus air cleanup system also serves the four integrated safeguards systems (ISS) compartments, referred to as the safeguard component areas, and which are considered to be an integral part of the annulus volume.
O All components of the annulus air cleanup system, required to operate following an accident, are Safety Class 2, seismic Category I.
l p 6.2.3.2.4 Reactor Building Annulus Bypass Leakage b
The maximum allowable leakage from the primary containment structure, fol'1owing an accident, is 0.15% of the mass of its atmosphere per day. This would occur at maximum pressure. During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a LOCA, the containment heat removal systems reduce the pressure -
the driving force behind the leakage - to less than one-half the maximum. The direct leakage to the environs of radioactive contaminants from the containment will be within the guidelines of 10CFR100.
Although an annulus air cleanup system has been provided to minimize leakage to the environs, a significant number of lines penetrate the containment and terminate in areas not treated by this cleanup system. Therefore, all leakage attributed to penetrations and isolation valves, requiring Type B and Type C tests per 10CFR50, Appendix J, is conservatively assumed to bypass the cleanup system. The total allowable leakage for Type B and Type C tests and for f
combined bypass leakage is 0.60 L, in accordance with Appendix J acceptance l
criteria.
6.2.3.3 Design Evaluation O The secondary containment will be evaluated, at the final design stage, to determine the adequacy of the structure (s) and associated equipment to achieve its functional goal - a negative pressure differential. Additionally, the ability of the system to withstand damage from a high energy line rupture within the annulus and contiguous areas.
l l
l O WAPWR-CS 6.2-193 NOVEMBER, 1986 3672e:1d
_ _ _ ~ , _ . . _
r U 6.2.3.4 Tests and Inspections Pre-operational testing of the secondary containment annular enclosure and the associated exhaust system will be addressed.in the FDA.
Periodic testing of the annulus air cleanup system exhaust fans will be established for the FDA Testing will include a visual surveillance of the secondary containment penetrations and related seals.
6.2.3.5 Instrumentaticn Requirements The system monitoring instrumentation and controls will be provided in the control room. Further information on the functional capability of this system and associated safety-related systems will be provided at the final design stage.
6.2.4 CONTAINMENT ISOLATION SYSTEM O The containment isolation system allows the normal or emergency passage of fluids through the containment boundry while preserving the ability of the boundry to prevent or limit the escape of fission products that may result from postulated accidents.
The containment isolation system consists of the piping, valves, and actuators -
required to isolate the containment following a loss-of-coolant accident (LOCA),steamline rupture, fuel handling accident inside the containment, small breaks in the reactor coolant system (RCS), or releases of radioactivity from systems within the containment. The design of the containment isolation system satisfies the requirements of TMI Action Plan Task II.E.4.2 as described in the following paragraphs.
O O WAPWR-CS 6.2-194 NOVEMBER, 1986 3672e:1d
O 6.2.4.1 Design Bases 6.2.4.1.1 Safety Design Bases O SAFETY DESIGN BASIS ONE - The containment isolation system is protected from the effects of natural phenomena, such as earthquakes, tornadoes, hurricanes, floods, and external missiles (GDC-2).
b d SAFETY DESIGN BASIS TWO - The containment isolation system is designed to remain functional after a safe shutdown earthquake and to perform its intended function following the postulated hazards of fire, internal missiles, or pipe breaks (GDC-3 and 4).
SAFETY DESIGN BASIS THREE - The containment' isolation system is designed and fabricated to codes consistent with the quality group classification assigned by Regulatory Guide 1.26 and the seismic category assigned by Regulatory Guide 1.29. The power supply and control functions are in accordance with Regulatory Guide 1.32.
SAFETY DESIGN BASIS FOUR - In the event of a LOCA, the containment isolation system providee isolation of lines penetrating the containment which are not required for operation or the engineered safety features (ESF) systems to minimize the release of radioactive materials to the atmosphere.
SAFETY DESIGN BASIS FIVE - Upon failure of a main steam line, the containment isolation system isolates the steam generators as required to prevent excessive cooldown of the RCS or overpressurization of the containment.
SAFETY DESIGN BASIS SIX - To control the release of radioactivity to the l
outside atmosphere, the containment isolation system isolates the containment atmosphere following a fuel handling accident inside the containment.
1 O SAFETY DESIGN BASIS SEVEN - The containment isolation system is designed in accordance with 10 CFR 50, Appendix A, General Design Criterion 54.
j O WAPWR-CS 6.2-195 NOVEMBER, 1986 3672e:1d
O SAFETY DESIGN BASIS EIGHT
- Each line which penetrates the containment and which is either a part of the reactor coolant pressure boundary (RCPB) and connects directly to the containment atmosphere or does not meet the requirements for a closed system as def.ined in item nine below, except instrument sensing lines, is provided with containment isolation valves in accordance with 10 CFR 50, Appendix A, General Design Criteria 55 and 56.
SAFETY DESIGN BASIS NINE - Each line which penetrates the containment and is O neither part of the RCPB nor connected directly to the atmosphere of the containment and which satisfies the requirements of a closed system is j
provided a containment isolation valve in accordance with 10 CFR 50, Appendix I A, General Design Criterion 57. A closed system is not a part of the RCPB nor connected directly to the atmosphere of the containment and meets the following additional requirements:
o The system is protected against missiles and the effects of high
, energy line break.
O o The system is designed to Seismic Category 1 requirements.
o The system is designed to American Society of Mechanical Engineers
! Section III, Class 2 requirements.
o The system is designed to withstand temperatures at least equal to the containment design temperature.
o The system is designed to withstand the external pressure from the containment structural acceptance test.
o The system is designed to withstand the design basis accident transient and environment.
O SAFETY DESIGN BASIS TEN
- Instrument lines penetrating the containment are provided with isolation valves in accordance with 10 CFR 50, Appendix A, General Design Criteria 55 and 56. The containment pressure transmitters and ,
O WAPWR-CS 6.2-196 NOVEMBER, 1986 3672e;1d
O reactor vessel level instrumentation system (RVLIS) are designed in accordance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.141. Six l' containment pressure sensors are provided as sealed systems with bellow seals
< inside the containment, liquid filled capillaries between the seals, and the i sensing element outside containment. RVLIS consists of six level sensors and i has bellow seals inside the containment, liquid filled capillaries between the i
seals, and a secondary isolator seal outside the containment between the containment penetration and the transmitter. These instrument lines are f
closed systems both inside and outside containment, are designed to withstand
! the containment pressure and temperature conditions following a loss of
. coolant accident, and are designed to withstand dynamic effects.
i SAFETY DESIGN BASIS ELEVEN - The containmant isolation system is designed to remain functional following a safe shutdown' earthquake (SSE).
. 6.2.4.1.2 Power Generation Design Basis The containment isolation system as a whole has no power generation design basis. Power generation design cases associated with individual components of l
the containment isolation system are discussed in the section describing the system of which they are an integral part.
6.2.4.2 System Description 6.2.4.2.1 General Description Each piping system which penetrates the containment is provided with containment isolation features which serve to minimize the release of fission l
products following a design basis accident. Provisions are made to allow for passage of emergency fluid through the boundary following a postulated accident. The arrangement for each piping penetration will be provided at the FDA stage. NRC Standard Review Plan 6.2.4 and Regulatory Guide 1.141 provide acceptable alternative arrangements to the explicit arrangements given in General Design Criteria 55, 56 and 57. Each penetration is designed so that O WAPWR-CS 6.2-197 NOVEMBER, 1986 3672e.1 d
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O in the event that a single failure is postulated, the containment integrity is maintained. Table 6.2-46 lists each penetration and provides a summary of the containment isolation valve characteristics.
For those systems which have automatic isolation valves or for which remote-manual isolation is provided, Subsection 6.2.4.5 describes the power supply and associated actuation system. Power-operated (air, motor, electrohydraulic, or solenoid) containment isolation valves have position O indication in the control room.
(
~Two modes of valve actuation are considered in Table 6.2-46. The actuation signal which occurs directly as a result of the event initiating containment isolation is designated as the primary actuation signal. The post-accident valve position is a , consequence of the primary actuation signal. If a change in valve position is required at any time following primary actuation, a -
secondary actuation signal is generated which places the valve in an alternative position. The closure times for automatic containment isolation valves are provided in Table 6.2-46 (Note 7).
The containment purge system is designed in accordance with Branch Technical Positio'n CSB 6-4. The purge lines are open only during a cold shutdown condition and are provided with an isolation valve capable of 10-s closure.
Since the main purge valves are shut whenever the RCS temperature is above 200*F, the valves are not qualified to shut against post-LOCA containment pressure. An analysis of the radiological consequences and the effect on the containment backpressure due to the release of containment atmosphere will be presented at the time of the integrated PDA.
In the event of a LOCA, the secondary shield wall .and other protective features prevent any missiles or high energy line break effects from damaging or degrading the performance capability of the containment isolation system.
Sections 3.5 and 3.6 of RESAR-SP/90 PDA Module 7 " Structural / Equipment Design", discuss in detail the missiles and pipe break effects, and Section 3.8 of RESAR-SP/90 PDA Module 7, " Structural / Equipment Design", discusses the internal structures, including the secondary shield wall. The actuators for O WAPWR-CS 6.2-198 NOVEMBER, 1986 3672e:1d
L I
t O power-operated containment isolation valves inside the containment are located above the maximum anticipated containment water level. In addition, lines associated with those penetrations which are considered closed systems inside i the containment are protected from the effects of a LOCA.
Provisions are made to ensure that closure of the containment isolation valves is not inhibited by entrapped debris in the valve body. For the majority of the systems, the fluid is domineralized water; thus, process fluid quality does not affect valve' operation. .For containment purge lines, screens are t
provided in the lines inboard of the isolation valves. For the containment i sump lines, including the containment emergency sump, screens are provided to l prevent large debris from entering the system.
Some other defined bases for containment isolation are provided in NRC j . Standard Review Plan 6.2.4 and Regulatory Guide 1.141. Conformance with Regulatory Guide 1.141 is provided to the extent specified in Section 1.9.
For the emergency core cooling system (ECCS) and containment spray system penetrations, the acceptability of the alternative arrangement lies upon provisions for the detection of possible leakage from these lines outside the containment. Subsection 9.3.3 of RESAR-SP/90 Module 13 " Auxiliary Systems" describes the leak detection provisions that have been made in the plant drainage system. Other provisions, such as containment water level and system i
flow, temperature, and pr:ssure instrumentation may be used by the operator.
The containment penetrations associated with the secondary side of the steam generators are .not subject to General Design Criterion 57. The valves associated with these penetrations do not receive a containment isolation ,
O signal and are not credited with effecting containment isolation in the safety analyses. The barriers against fission product release to the environment are the steam generator tubes and the piping associated with the steam generators.
In addition to containment isolo lon, Table 6.2-46 also contains systems which are required for post-LOCA mit ation. Since these systems, su:h as the ECCS, perform additional safety-relato ' unctions, they are associated with ESF and are so indicated in Table 6.2-46.
O '
WAPWR-CS 6.2-199 NOVEMBER, 1986 3672e:1d
O 6.2.4.2.2 Component Description Codes and standards applicable to the piping and valves associated with containment isolation are listed in Table 3.2-1 of RESAR-SP/90 PDA Modulo 7
" Structural / Equipment Design". Containment penetrations are classified as Safety Class 2 and Seismic Category 1.
Section 3.11 of RESAR-SP/90 PDA Module 7 " Structural / Equipment Design" O- provides the post-LOCA environment that is used to qualify the operability of power-operated isolation valves located inside the containment.
The containment penetrations are designed to meet the stress requiroments of NRC Branch Technical Position MEB 3-1 and the classification and inspection requirements of NRC Branch Technical Position ASB 3-1, as described in Section 3.6 of RESAR-SP/90 PDA Module 7, " Structural / Equipment Design". Section 3.8 of RESAR-SP/90 PDA Module 7, " Structural / Equipment Design", discusses the interface between the piping system and the steel containment.
O 6.2.4.2.3 System Operation During ' normal operation, many penetrations are not isolated. Lines which are not required for the passage of emergency fluids are automatically isolated upon receipt of isolation signals, as discussed in Subsections '6.2.4.3 and 6.2.4.5 of this module and Section 7.3 of RESAR-SP/90 PDA Module 9
" Instrumentation & Control and Electric Power". Essential lines which penetrate the containment are closed loops within the containment or provide flow paths into or out of the RCS and can be isolated by remote-manual operation when dictated by the emergency system functional requirements.
Lines not in use during power operation are normally closed and remain closed under administrative control during reactor operation.
Upon detection of abnormal radioactivity levels indicative of a fuel handling accident during refueling or other release, the isolation valves in the containment purge system are closed to minimize any fission product release to the environment.
O WAPWR-CS 6.2-200 NOVEMBER, 1986 3672e.1d i
O 6.2.4.3 Design Evaluation Safety evaluations are lettered to correspond to the safety design bases.
A. Containment isolation signals automatically isolate process lines which are nonessential as identified in Table 6.2-46. Nonessential
- lines are those lines which are not required to mitigate or limit an 1 accident and which, if required at all, would be required for long term recovery only, a.g., days or weeks following an accident.
Lines which are required to mitigate an accident or which, if unavailable, could increase the magnitude of the event are designated i as essential lines. Table 6.2-46 identifies the associated line as essential or nonessential and shows'the automatic isolation signal for each penetration, if applicable.
The containment isolation system utilizes diversity in the parameters I sensed for the initiation of containment isolation. The two redundant train-oriented containment isolation phase A signals (CIA-A, CIA-B) are initiated on receipt of any of the following signals:
- 1. Any signal initiating a safety injection:
I o Manual or automatic safety injection actuation.
! 2. Containment high radiation.
- 3. Manual containment isolation actuation.
Containment isolation phase B (CIB) is initiated by containment high-3 pressure or manual actuation of the containment spray system.
O B. Upon failure of a main steam line, the steam generators are isolated to prevent excessive cooldown of the RCS or overpressurization of the containment.
O WAPWR-CS 6.2-201 NOVEMBER, 1986 3672e:1d
.. . . _ =. . . - - . -, .. .. -_ . -.
i J s i
O The two redundant train oriented steam line isolation signals (SLI-A, SLI-B) are initiated upon receipt of any of the following signals:
I
- 1. Containment high-3 pressure. . .
- 2. Manual actuation r
For main steam line breaks resulting in a high steam line pressure rate or containment high-2 pres,sure signal, only the main steam line isolation valves (MSIVs), MSIV bypass valves, main feedwater isolation valves, and the main feedwater isolation bypass valves are shut to 1 1
prevent excessive cooldown of the RCS. When the main steam line break f causes a low steam line pressure signal, a safety injection signal I
( -
(followed by containment isolation) is generated as well as the steam i line isolation signal.
,The main steam line isolation valves, MSIV bypass valves, and piping are designed to prevent uncon+ rolled blowdown from more than one steam generator. The main steam line isolation valves and MSIV bypass valves will shut fully within 5 seconds after SLI is initiated. The blowdown rate is restricted by steam flow restrictors located within i
the steam generator outlet steam nozzles in each blowdown path. For main steam line breaks upstream of an isolation valve, ' uncontrolled blowdown from more than one steam generator is prevented by the isolation valves in the unaffected steam lines and by the isolation valve in the affected line. For main steam line breaks downstream of an isolation valve, blowdown from more than one steam generator is
( O prevented by the main steam isolation valves on each main steam line.
Failure of any one of the above components relied upon to prevent uncontrolled blowdown of more than one steam generator will not permit a second steam generator blowdown *o occur. Piping restraints and pipe whip barriers between the main steam lines prevent a rupture in one line from causing a blowdown from more than one steam generator.
No single active component failure will result in the failure of more O WAPWR-CS 6.2-202 NOVEMBER, 1986 3672e:1d
-a v. 4- . -
O than one main steam isolation valve to operate. Redundant main steam isolation signals, described in Subsection 7.3.1.1.2 of RESAR-SP/90 PDA Module 9,." Instrumentation & Controls and Electric Power", are fed to redundant parallel activation vent valves to ensure isolation valve C closure in the event of a single isolation signal failure.
The effect on the RCS after a steam line break resulting in single j steam generator blowdown and the offsite radiation exposure after a steam line break outside containment are discussed in detail in Subsection 15.1.5 of RESAR-SP/90 PDA Module 6/8, " Secondary Side Safeguards Systems / Steam and Power Conversion System". The containment pressure transient following a main steam line break inside containment is discussed in Section 6.2 of this module.-
The containment purge system is automatically isolated following an C.
abnormal release of radioactivity in the containment during a fuel handling accident by either of two redundant train-oriented containment ventilation isolation signals.
The preaccess purge supply and exhaust valves, which are only open in the cold shutdown condition, are designed to shut in less than 10 seconds.
i D. The containment isolation system is designed in accordance with 10 CFR l
50, Appendix A, General Design Criterion 54. Leakage detection capabilities and the leakage detection test program are discussed in Subsection 6.2.6 of this module. Valve operability tests are also discussed in Subsection 3.9.3.2.2 of RESAR-SP/90 PDA Module 7,
" Structural / Equipment Design". Redundancy of valves and reliability of the isolation system are ensured by conformance with the other
. safety design bases stated in Section 6.2. Redundancy and reliability of the actuation system are covered in Section 7.3 of RESAR-SP/90 PDA Module 9, " Instrumentation & Controls and Electric Power".
O WAPWR-CS b.2-203 NOVEMBER, 1986 3672e.1d
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f 3
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i -
.(
O The valves listed in Table 6.2-46 which have an o en $41ve , hoittion upon a loss of a:tuation power are motor-operated. Th[ use of motor-operated valves which fail as is upon loss of actuat hg power in s O lines penetrating the containment. is based upon the consideration of k what valve' position ensures the greatest planc safety. Furthermore, each .of these valves that fails as isjisprovidedwithredadant backup valves to' ensure that no single failure will prevf;nt thehystem' j
as a whole from performing its isolk'. ion function, e.g., a chec% , valve d inside the containment and, motor-operated valve outside thej containment or two motor-operated valvss in series, each powered frosj , ' '
a separate ESF bu's.
E. Lines which penetrate the contsinmerd and which either are part 'o ? the RCPB, connect directly to the containment atmosphere, or do not meat the requirements for a closed system, except instrument sensing -lines, ' \
are provided with one of the following valve arraneaments conforming
.to the requirements of 10 CFR 50, Appendix A, General Design Criteria O 55 and 56, as follows:
C'
- 1. One locked closed isolation valve inside and one locksf closed isolation valve outside containment.
N
- 2. One automatic isolation valve inside and one locked closed isolation valve outside containment.
- 3. One locked closed isolation valve insida and one automatic isolation valve outside containment. (A simple check valve is not used as the automatic isolation valve outside containment.)
I
- 4. One automatic isolation valve inside and one automatic isolation ,
valve outside containment. (A simple check valve is not used as the automatic isolation valve outside containment.)
l O WAPWR-CS 6.2-204 NOVEMBER, 1986 3672e:1d l
l t - . - _ . - - . _ . - _ - - . , - . _ _ - , . - . _ _ _ . _ . , . _ . . , _ . . _ . _ _ - _ . - - - - - - _ - - _ _ _ _ . , _ -
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( Isolation valves outside ' containment are located as close to the containment as practical, and upon loss of actuating power,
\ air-operated automatic isolation valves fail closed.
h, 9 Each line which penetrates the containment and is neither part of the F. ,
RCPfi nor connected directly to the containment atmosphere and b: satisfies the requirer.ents of a clased system has at least one containment isolation valve which is either automatic, locked closed, or capable of remote-manual . operation. The valve is outside the containment and located as close to the containment as practical. A simple check valve is not used as the automatic isolation valve. This design- is in compliance with 10 CFR 50, Appendix A General Design Criterion 57.
y G. Instrument lines penetrating the containment are provided with isolation valves in accordance with General Design Criteria 55 or 56,
and the containment pressure instrument lines are designed in
['
accordance with Regulatory Guide 1.11.
H. The containment isolation system is designed in accordance with Seismic Category 1 requirements as specified in Section 3.2 of E
RESAR-SP/90 PDA Module 7, " Structural / Equipment Design". The components (and supporting structures) of any system, equipment, or structure which is non-Seismic Category 1 and whose collapse could result in loss of a required function of the containment isolation i system through either impact or flooding are analytically checked to determine that they will not collapse when subjected to seismic O loading resulting from an SSE.
Air-operated isolation valves fail in the shut position upon loss of air if they are not required to operate after a design basis accident. Containment isolation system valves required to be operated after a design basis accident are powered by the Class 1E electric power system.
O WAPWR-CS 6.2-205 NOVEMBER, 1986 5672e:1a
(
6.2.4.4 Tests and Inspections Preoperational testing will be fully described in Chapter 14 " Initial Test Program", at time of the FDA. The containment isolation system is testable through the operational' sequence that is postulated to take place following an accident, including operation of applicable portions of the protection system and the transfer between normal and standby power sources.
O The piping and valves associated with the containment penetration are designed and located to permit preservice and inservice inspection in accordance with ASME Section XI.
Each line penetrating the containment is provided with testing features to allow containment leak rate tests in accordsnee with 10 CFR 50, Appendix J, as discussed in Subsection 6.2.6 of this module.
l l 6.2.4.5 ~ Instrumentation Application lO l
The generation of CIA, CIB, SLI, or CVI signals which automatically isolate l the appropriate containment isolation valves is described in Section 7.3 of RESAR-SP/90 PDA Modula 9 " Instrumentation & Controls and Electric Power".
For those valves for wnich automatic closure is not desired, based on the system safety function, remote-manual operation is available from the control room.
Sn'.dinment isolation valves which are equipped with power operators and which O are automatically actuated may also be controlled individually by positioning hand switches in the control room. Also, in the case of certain valves with actuators, a manual override of an automatic isolation signal is installed to permit manual control of the associated valve. The override control function can be performed only subsequent to resetting of the actuation signal; that Q is, deliberate manual action is required to change the position of containment isolation valves in addition to resetting the original actuation signal. The design does not allow ganged reopening of the containment isolation valves.
O WAPWR-CS 6.2-206 NOVEMBER, 1986 3672e:1d
O Reopening of the isolation valves must be performed on a valve-by-valve basis, or on a line-by-line basis. Safety injection signals take precedence over manual overrides of other isolation signals, for example, a safety injection signal causes isolation valve closure even though the high radiation signal is being overridden by the' operator. Containment isolation valves with power operators are provided with open/ closed indication, which is displayed in the control room. The valve mechanism also provides a local, mechanical indication of valve position.
All power supplies and control functions necessary for containment isolation are Class 1E, as. described in RESAR-SP/90 PDA Module 9 " Instrumentation &
Controls and Electric Power".
O O
O O WAPWR-CS 6.2-207 NOVEMBER, 1986 3672e:1d
O O O O O O O a
TABLE 6.2-46 (Sheet 1 of 7)
CONTAINMENT PENETRATION VALVE ARRANGEMENT
! SYSTEM LINE LINE Seismic Conn. Valve Valve Valve Position Act. System Direction No.-Type-Operator No.-Size,in. IRC / ORC Location Normal-Shut.-Acc. Signal Figure (1) (7) (2) (3)
SGIS Main Steam 4 - 32" yes / no out 1 gate - (4) outside 0-0-C MS 10.3-1 1 gate - motor outside 0-0-C none 1 globe - sol. outside C-C-C none 5 - safety outside C-C-C --
SGIS Main Feedwater 4 - 16" yes / no in 1 globe - (4) outside 0-0-C MF 10.3-1
! 1 - check inside ----- --
SGIS SG Blowdown 4 - 4" yes / no out 1 gate - motor outside 0-0-C EFW 10.3-1 1 gate - motor inside 0-0-C EFW EFWS Emergency SG 4 - 3" yes / yes in 1 globe - motor outside 0-0-O none 10.4-1 Feedwater 1 - check inside ----- --
1 gate - motor inside 0-0-O none ISS HHSI to RCS 4 - 4" yes / yes in 1 gate - motor outside 0-0-O none 6.3-1 1 check inside ----- --
j ISS HHSI miniflow 4 - 2" yes / yes in 1 globe - motor outside 0-0-O none 6.3-1 i to EWST 1 - check inside ----- --
l ISS Cont sump to 4 - 6" yes / yes out 1 gate - motor (5) 0-0-O none 6.3-1 l HHSI pump 1
i WAPWR-CS 6.2-208 NOVEMBER, 1986 1
3672e:1d j
i O O O O O 1
TABLE 6.2-46 (Sheet 2 of 7)
I CONTAINMENT PENETRATION VALVE ARRANGEMENT i ,
SYSTEM LINE LINE Seismic Conn. Valve Valve Valve Position Act. System i No.-Size,in. IRC / ORC Direction No.-Type-Operator . Location Normal-Shut.-Acc. Signal Figure j (1) (7) (2) (3)
ISS RHR pump to RCS 4 - 6" yes / yes in 1 gate - motor outside C-0-C none 6.3-1
- 1 - check inside ----- --
1 I ISS RHR pump to Cont 4 - 8" yes / yes in 1 gate - motor outside C-C-O none 6.3-1 j spray header 1 - check inside ----- --
i ISS RCS to RHR pump 4 - 8" yes / yes out 1 gate - motor outside C-0-C none 6.3-1 l 1 gate - motor inside C-0-C none i
ISS Cont sung to 4 - 12" yes / yes out 1 gate - motor (5) 0-0-O none 6.3-1 RHR pung .
t i
l ISS N2 to CRT 1 - 1" no / no in 1 globe - air outside C-C-C T 6.3-1 1 - check inside ----- --
ISS N2 to ACCUM 1 - 1" no / no in 1 globe - air outside C-C-C T 6.3-1 l 1 - check inside ----- --
i l CVCS Charging 1 - 4" yes / yes in 1 globe - air outside 0-0-C T 9.3-2 l 1 - check inside ----- --
l CVCS Letdown 1 - 4" yes / yes out 1 globe - air outside 0-0-C T 9.3-2 s 1 globe - air inside 0-0-C T CVCS RCP Seal 1 - 2" yes / yes in 1 globe - air outside 0-0-C T 9.3-2 ,
Injection 1 - check inside WAPWR-CS 6.2-209 NOVEMER, 1986 3672e:1d
O O O O O O O TABLE 6.2-46 (Sheet 3 of 7)
CONTAINMENT PENETRATION VALVE ARRANGEMENT SYSTEM LINE LINE Seismic Conn. Valve Valve Valve Position Act. System l i No.-Size,in. IRC / ORC Direction No.-Type-Operator Location Normal-Shut.-Acc. Signal Figure i (1) (7) (2) (3) 1 CVCS RCP Seal Return 1 - 2" yes / yes out 1 globe - motor outside 0-0-C T 9.3-2 1 globe - motor inside 0-0-C T 1 - 3/4" (vent) in 1 - check inside - --- --
CVCS Water to CRT & 1 - 1" no / yes in 1 globe - air outside C-C-C T 9.3-2 Accumulators 1 - check inside ----- --
SFPCS EWST / Ref. Cav. 1 - 3" no / no in 1 globe - air outside 0-0-C T 9.1-2
- Purif. Return 1 - check inside ----- --
SFPCS Ref. Cavity 1 - 6" no / no out 1 gate - manual outside C-0-C none 9.1-2 Purif. Out 1 gate - manual inside C-0-C none SS Cont. Air 2 - 3/4" yes / yes out 1 globe - sol. outside C-C-C T 9.3-1 Sample Out 1 globe - sol. inside C-C-C T SS Cont. Air 1 - 3/4" yes / yes in 1 -stop check- sol.outside C-C-C T 9.3-1 Sample In 1 - check inside ----- --
! SS RCS Sample Out 2 - 3/8" yes / yes out 1 globe - sol. outside C-C-C T 9.3-1 3 globe - sol. inside C-C-C T SS RCS Sample In 1 - 3/8" yes / yes in 1 -stop check- sol.outside C-C-C T 9.3-1 1 - check inside ----- --
WAPWR-CS 6.2-210 NOVEM ER, 1986 3672e:1d
- o o o o o o o TABLE 6.2-46 (Sheet 4 of 7)
CONTAINMENT PENETRATION VALVE ARRANGEMENT SYSTEM LINE LINE Seismic Conn. Valve Val've Valve Position Act. System No.-Sire,in. IRC / ORC Direction No.-Type-Operator Location Normal-Shut.-Acc. Signal Figure (1) (7) (2) (3)
- SS ISS ACCUM / CRT 1 - 3/8" yes / yes out 1 globe - sol. outside C-C-C T 9.3-1 i Sample Out 8 globo - sol. inside C-C-C T SS RCS Pressurizer 1 - 3/8" yes / yes out 1 globe - sol. outside C-C-C T 9.3-1 Vapor Sample 1 globe - sol. inside C-C-C T SS RCS Pressurizer 1 - 3/8" yes / yes out 1 globe - sol. outside C-C-C T 9.3-1 Liquid Sample 1 globe - sol. inside C-C-C T CCWS RHR HX Cooling 4 - 8" yes / yes out 1 gate - motor outside C-0-O none 9.2-1 Water Out (6) inside (6)
CCWS IRC Safety Loads 2 - 18" yes / yes in 1 gate - motor outside 0-0-0 none 9.2-1 Cooling Water 1 - check inside ----- --
CCWS IRC Non-Safety 1 - 12" no / yes in 1 gate - motor outside 0-0-C T 9.2-1 Loads Cooling 1 - check inside ----- --
Water l CCWS IRC Non-Safety 1 - 8" no / yes in 1 gate - motor outside 0-0-C T 9.2-1 l Loads Cooling 1 - check inside ----- --
l Water l
l l
i i
i WAPWR-CS 6.2-211 NOVEMBER, 1986 3672e:1d I
{
t
O O O O O O O 1
i TABLE 6.2-46 (Sheet 5 of 7)
CONTAINMENT PENETRATION VALVE ARRANGEMENT SYSTEM LINE LINE Seismic Conn. Valve Valve Valve Position Act. System i No.-Size,in. IRC / ORC Direction No.-Type-Operator Location Normal-Shut.-Acc. Signal Figure
- Safety Loads 1 gate - motor inside 0-0-0 P i Cooling Water 1 - 3/4" (vent) in 1 - check inside ----- --
) CCUS Containment Fan 4 - 8" yes / yes out 1 gate - motor outside 0-0-O none 9.2-1
] Coolers Cooling (6) inside (6)
Water LWPS Reactor Coolant 1 - 3" no / no out 1 -diaphragm- air outside 0-0-C T 11.2-1 Drain Tank Out 1 -diaphragm- air inside 0-0-C T d
LWPS Reactor Coolant 1 - 3/4" no / no both 1 -diaphragm- air outside 0-0-C T 11.2-1 Drain Tank Gas 1 -diaphragm- air inside 0-0-C T RCS PRT Gas 1 - 1" yes / no both 1 -diaphragm- air outside C-C-C T 5.1-2 1 -diaphragm- air inside C-C-C T i RCS PRT Makeup 1 - 3" yes / no in 1 -diaphragm- air outside C-C-C T 5.1-2
! 1 - check inside ----- --
, RCS RVLIS instrument 6 - 3/4" yes / yes NA 1 - hydraulic iso outside ----- --
5.1-2 lines l
l l
WAPWR-CS 6.2-212 NOVEMBER, 1986 3672e:1d
O O O O O O O I
3 TABLE 6.2-46 (Sheet 6 of 7)
CONTAINNENT PENETRATION VALVE ARRANGEMENT SYSTEM LINE LINE Seismic Conn. Valve Valve Valve Dosition Act. System No.-Size in. IRC / ORC Direction No.-Type-Operator Location Normal-Shut.-Acc. Signal Figure (1) (7) (2) (3)
HVAC Cont. Shutdown 1 - 42" no / no in 1 - butterfly-air outside C-C-C T 9.4-11 Purge Supply 1 - butterfly-air inside C-C-C T HVAC Cont. Shutdown 1 - 42" no / no out 1 - butterfly-air outside C-C-C T 9.4-11 Purge Exhaust 1 - butterfly-air inside C-C-C T HVAC Cont. Operating 1 - 6" no / no in 1 gate - motor outside C-C-C T later
. Purge Supply 1 gate - motor inside C-C-C T 3
HVAC Cont. Operating 1 - 6" no / no out 1 gate - motor outside C-C-C T later l Purge Exhaust 1 gate - motor inside C-C-C T l Fuel Transfer 1 - 36 no / no NA Dooble sealed hatch outside C-0-C* none . 3.1 Tube 1 gate inside C-0-C none Equipment Hatch 1- no / no NA Double sealed hatch inside C-C-C none later Personnel Hatch 1- no / no NA Double sealed hatch inside C-C-C none later Instrument Air later Service Air later Breathing Air later WAPWR-CS 6.2-213 NOVEMIER,1986 3672e:1d
TABLE 6.2-46 (Sheet 7 of 7)
CONTAINMENT PENETRATION VALVE ARRANGEMENT O
NOTES:
(1) This column indicates whether or not the penetration is connected to Seismic Category I equipment inside and outside the containment.
(2) This column indicates whether the valves are open or closed during normal plant operation, shutdowns, and accidents.
(3)The engineering safeguards actuation signals are developed in Subsection 7.1.1.1.2 of RESAR-SP/90 PDA Module 9, " Instrumentation &
Controls and Electric Power". The following is a list of those that are used to close containment isolation valves:
- "T" Containment Isolation Signal, Phase A "P" Containment Isolation Signal, Phase B "MS" Main Steam Isolation Signal "MF" Main feedwater Isolation Signal "EFW" Emergency Feedwater Signal (4) Special hydraulic / air cylinder operator.
(5) The sump line isolation valve is located outside of the containment O however it is enclosed in a can that is designed for containment pressure.
(6)The inside containment isolation is provided by a closed Seismic Category I system.
(7) All the containment isolation valves that automatically close on receipt of an engineered safeguards actuation signal will close in 10 seconds or less.
WAPWR-CS 6.2-214 NOVEMBER, 1986 3672e:1d
O 6.2.5 Combustible Gas Control in Containment Following a loss-of-coolant accident (LOCA), hydrogen may be produced inside the reactor containment by radiolysis of the core and sump solutions, by corrosion of aluminum and zinc, by reaction of the Zircaloy fuel cladding with water, and by release of the hydrogen dissolved in the reactor coolant and contained in the pressurizer vapor space. To ensure that the containment hydrogen concentration is maintained at a level low enough to preclude O endangering containment integrity, ,a combustible gas control system is provided. This subsection describes the systems that are pravided in '
~accordance with General' Design Criterion 41 to control the buildup of hydrogen within the containment.
- Five mechanisms for monitoring and controlling hydrogen inside the containment are considered
o Hydrogen recombiners.
o Containment hydrogen purge.
o Hydrogen igniters, o Containment hydrogen monitoring.
{ o Containment hydrogen mixing.
S.2.5.1 Design Bases 6.2.5.1.1 Electric Hydrogen Recombiners The following design bases apply to the electric hydrogen recombiners:
A. The recombiners are designed to sustain all normal and accident loads including safe shutdo'wn earthquake and pressure transients from a I design basis LOCA.
O B. The recombiners are designed for a lifetime of 40 years, consistent with that of the plant.
O WAPWR-CS 6.2-215 NOVEMBER, 1986 4324e:1d l
l
O C.
All materials used in the recombiners are selected to be compatible with the environmental conditions inside the reactor containment during normal operation or during accident conditions.
O D. Process capacity is such that the containment hydrogen concentration will' not exceed 4 volume percent based on the Nuclear Regulatory Commission (NRC) TID release model as indicated in Regulatory Guide 1.7.
E. Two redundant electric hydrogen recombiners are provided to meet the single-failure criterion.
F. The electric hydrogen recombiners are inspected and tested periodically. 'efer to the Technical Specifications for
. further details.
6.2.5.1.2 Containment Hydrogen Purge System O A. The containment air cleanup and purge systems provided for normal operation are also desigt.ed to aid in hydrogen control, if necessary, during and following a DBA.
B. The system is not designed as Seismic Category I, except for portions of the system that constitute part of the containment boundry and filters.
6.2.5.1.3 Hydrogen Igniters A. The hydrogen ignition system is designed to safely accommodate hydrogen generated by the equivalent of a 100% fuel-clad metal water reaction.
B. The system is designed to limit uniformly distributed hydrogen concentration in the containment to 10% during and following an accident.
O WAPWR-CS 6.2-216 NOVEMBER, 1986 T324e:1d
5 O
- V C. The igniters are powered from Class 1E power panels that have normal and alternate AC power supplies from offsite sources. In the event of loss of offsite power, the igniters -would be powered from the emergency diesel generators. In addition, the- hydrogen ignition system is designed as a Seismic Category I system.
6.2.5.1.4 Containment Hydrogen Monitoring System A. The hydrogen monitoring system. is a Class 1E, Seismic Category 1 system. It is designed to retain its integrity and operability under all conditions following a design basis accident (DBA), degraded core accident, and core melt accident.
B. All materials and equipment required by this system are selected to be compatible with the environmental conditions anticipated during accident operation and are suitable for a lifetime consistent with that of the plant.
C. The system measures the containment hydrogen concentration and alerts the operator in the event that a high hydrogen concentration is detected, in accordance with the requirements of Regulatory Guide 1.7.
D. -The hydrogen monitoring system consists of two identical' units that are completely independent of each other and are powered from independent Class 1E power sources. Therefore, assuming a single failure, capability is available to monitor the hydrogen concentration in the containment.
E. Proper shielding and other provisions are incorporated into the design
- to minimize personnel exposure and ensure that the required radiological analysis can be performed on the containment air sample.
O WAPWR-CS 6.2-217 NOVEMBER, 1986 T324e:1d
O 6.2.5.1.5- Containment Hydrogen Mixing 4 The following design bases apply to mechanisms or systems for mixing of hydrogen-bearing gases inside the reactor containment:
A. Local hydrogen concentrations inside the reactor containment shall be maintained at less than 4 volume percent during a DBA, and less than 10 volume percent during degraded core and/or a core melt accident.
B. Hydrogen mixing is facilitated by containment far, coolers that are designed to meet the same redundancy, environmental, seismic, and quality requirements as the hydrogen recombiner system as described in Subsection 6.2.5.1.1.
6.2.5.2 System Design 6.2.5.2.1 Electric Hydrogen Recombiners Each recombiner system consists of a control panel located in the control building, a power supply cabinet located on level B of the control building, l, and a recombiner located above the operating deck at el 328 ft in the containment. There are no moving parts or controls inside the containment.
, Heaters within the unit induce airflow by natural convection.
l l
l The regulated power supply to the recombiner contains an isolation transformer and a controller. This equipment will not be exposed to the post-LOCA environment. The controls for the power supply are located in the control building beside the power supply panel. The controls are manually actuated.
Each hydrogen recombiner consists of the following components:
A. A preheater section, consistin:; of a shroud placed around the central heaters to take advantage of heat conduction through the central walls, for preheating incoming air.
O WAPWR-CS 6.2-218 NOVEMBER, 1986 T324e:1d
l l
l O B. An orifice plate to regulate the rate of airflow through the unit.
l C. A heater section, consisting of four banks of metal-sheathed electric resistance heaters, to heat the hydrogen bearing gases. flowing through l f
it to the recombination temperature.
D. An exhaust chamber which mixes and dilutes the hot effluent with containment air to lower the temperature of the discharge stream.
E. An outer enclosure to protect the unit from impingement by containment spray.
The hydrogen recombiner has no need for external services except electrical power.
The containment atmosphere is heated within the recombiner in a vertical duct, causing, it to rise by natural convection. As it rises, replacement air is drawn through intake louvers downward through a preheater section which will temper the air and lower its relative humidity. The preheated air then flows 3
through an orifice plate, sized to maintain a 100-sf / min flowrate, to the heater section. The airflow is heated to a temperature above 1150'F, the temperature for the hydrogen-oxygen reaction. Any free hydrogen present reacts with atmospheric oxygen to form water vapor. After passing through the heater section, the flow enters a mixing section, which is a louvered chamber where the hot gases are mixed and cooled with containment atmosphere before the gases are discharged directly into the containment. The air discharge louvers are located on three sides of the recombiner. To avoid O short-circuiting previously processed air, no discharge louvers are located on the intake side of the recombiner.
Tests have verified that the hydrogen-oxygen recombination is not a catalytic surface effect associated with the heaters (Subsection 6.2.5.4) but occurs due to the increased temperature of the process gases. As the phenomenon is not a l
- catalytic effect, saturation of the unit cannot occur.
O WAPWR-CS 6.2-219 NOVEMBER, 1986 T324e:1d
l O Two recombiners are provided to meet the requirements for redundancy and independence. Each recombiner is powered from a separate safeguard bus and is provided with separate power and control panels.
The unit is manufactured of corrosion-resistant, high-temperature material.
The electric hydrogen recombiner uses commercial-type electric resistance heaters sheathed with Incoloy-800, which is an excellent corrosion-resistant material for this service. The recombiner heaters operate at significantly O lower power densities than similar heaters used in commercial practice.
The recombiner is operated manually from a control panel located in the control building. Emergency operating procedures direct that the hydrogen j concentration in containment be monitored.
To control the recombination process, the correct power input to bring the recombiner above the threshold temperature for recombination is set on the 4
controller. The correct power required for recombination depends upon l
containment atmosphere conditions and is determined when recombiner operation l
is required. For equipment test and periodic checkout, a thermocouple readout instrument is also provided in the control panel to monitor temperatures in the recombiner.
6.2.5.2.2 Containment Hydrogen Purge System The functional description of the containment air cleanup and purge systems are provided in Subsection 6.2.2 of this module and 9.4.6 of RESAR-SP/90 PDA '
Module 13, " Auxiliary Systems".
6.2.5.2.3 Hydrogen Ignition System (HIS)
The hydrogen ignition system is provided to control hydrogen concentration during and following degraded core and/or core melt accidents when a rapid release of hydrogen cannot be controlled by the hydrogen recombiners.
O WAPWR-CS 6.2-220 NOVEMBER, 1986
'4324e:1d
O The igniter assemblies are located in all areas of the containment. For enclosed areas inside containment two igniter assemblies are installed with each igniter fed from a separate power distribution panel. The exact quantity and location of the igniters will be determined at the final design stage.
The igniter assemblies are designed to include the following:
o A welded metallic enclosure that partially encloses the igniter and
' contains the transformer and associated electrical wiring.
o Provisions for access to the interior of the enclosure.
o A spray shield to protect the igniter from containment spray.
o An igniter capable of maintaining a 1700*F surface temperature, o ,A transformer capable of stepping down 120 volts AC power to the voltage necessary to achieve a minimum igniter temperature of 1700'F.
The system is actuated manually from the control room. Instrumentation for the HIS consists of two control room handswitches, one for each of the two Class 1E power divisions.
6.2.5.2.4 Containment Hydrogen Monitoring System Each redundant hydrogen monitoring train in the hydrogen monitoring system consists of a hydrogen analyzer and two associated sample lines with solenoid-operated isolation valves inside and outside the containment. These sampling lines are designed to be free of water traps (runs where liquid could l
accumulate) and are equipped with sufficient heat tracing to prevent condensation from the sample being supplied to the analyzers.
O After the sample has been analyzed, it is returned to the containment. The analyzers are located in accessible areas outside the containment. The l
hydrogen monitoring subsystem piping is desigud in accordance with the O WAPWR-CS 6.2-221 NOVEMBER, 1985 -
4324e:1d
O criteria of Regulatory Guide 1.26, Quality Group B. Sample lines are arranged to obtain samples from two locations within the containment for each train.
The operator may select either of these sampling points from the main control room.
~
The operation of the hydrogen gas analyzer is based on the measurement of thermal conductivity of the gaseous containment atmosphere sample. The thermal conductivity of the gas mixture changes in proportion to the changes in the concentration of the indivdual gas constituents of the mixture. The thermal cenductivity of hydrogen is far greater (approximately seven times the thermal conductivity of air) than any other gases or vapors expected to be
! present. The operation of the hydrogen monitoring system is not limited due to radiation, moisture, or temperature expected at the equipment location.
The monitors are designed to function under design pressure conditions of -2 to 60 psig.
The range of the monitors is 0 to 20 volume percent.
The output signal of the hydrogen monitors is indicated locally and recorded and alarmed in the control room. In addition to the high hydrogen alarm, a common malfunction alarm is located in the control room to indicate ' loss of power, low or high pressure, or low or high temperature.
The hydrogen monitoring system meets the requirements of TMI Action Plan Task II.F.1 regarding hydrogen monitoring.
6.2.5.2.5 Containment Hydrogen Mixing Hydrogen mixing is facilitated by the containment fan coolers, which take suction from above the operating deck and discharge to the lower levels of the ccntainment. Functional descriptions of the containment coolers are provided in Subsections 6.2.2 of this module and 9.4.6 of RESAR-SP/90 PDA Module 13
" Auxiliary Systems." A flow diagram for the containment cooling and ventilation systems is provided in Figure 9.4-11 of RESAR-SP/90 PDA Module 13.
O 6.2-222 NOVEMBER, 1986 WAPWR-CS 4324e:1d i
i .-- ._ - __ __________ __ .- _ _--- - - .-
- (
6.2.5.3 Design Evaluation 6.2.5.3.1 Hydrogen Production and Accumulation 6.2.5.3.1.1 Zirconium-Water Reaction
~
The major source of hydrogen immediately following a LOCA is caused by the ,
reaction of the Zircaloy fuel cladding with water. The extent of the zirconium-water reaction depends upon the effectiveness of the emergency core cooling systems (ECCS). An evaluation of the ECCS shows the zirconium-water reaction to be less than 0.3 percent.
Zirconium reacts with steam according to the following equation:
Zr + 2 H2 O
- Zr 02+2H2 + Heat The hydrogen produced is calculated as follows:
3 2 lb-mole H2 /lb-mole Zr 0.022 lb-mole H2 , 7.9 sf H 2 ,
91.22 lb Zr/lb-mole Zr lb Zr lb Zr i
I The NRC model suggested in Regulatory Guide 1.7 and Standard Review Plan 6.2.5
[
i conservatively assumes a 1.5 percent zirc-water reaction (five times the maximum amount calculated in the ECCS evaluations) (Reference [1]). There is approximately 82,350 lb of zirconium metal in the active portion of the reactor core. The hydrogen produced by the reaction of 1235 lb of zirconium 3
This hydrogen is assumed to be immediately released to the O
is 9758 sf .
containment atmosphere.
6.2.5.3.1.2 Radiolysis of Core and Sump Solutions Water radiolysis is a complex process involving reactions of numerous intermediates. However, the overall radiolytic process may be described by the equation:
HO:H2 2 + 1/2 02 6.2-223 NOVEMBER, 1986 ;
WAPWR-CS T324e:1d
O An extensive program was conducted by Westinghouse to investigate the radiolytic decomposition of the core cooling solution following the DBA.
During the inve:,tigation it became apparent that post-accident conditions in the containment create two distinct radiolytic environments. One environment exists inside the re'ctora vessel, where radiolysis can occur when energy emitted by decaying fission products in the fuel is absorbed by the cooling
. solution pumped through the reactor core. The other environment exisiis outside the reactor vessel, in the containmont sump soluticn, where radiolysis O can also occur when decay energy , emitted by dissolved fission products is absorbed by the sump solution. The two basic differences between the core environment and the siump environment that affect the rate of hydrogen production are the rate of energy absorption and the type of flow regime. The results of these investigations are discussed in Reference [1].
The rate of hydrogen production by radiolysis depends upon the rate of energy absorption by the solution. A detailed analysis of energy deposition in the reactor, core where decaying fission products are retained in the fuel shows that beta radiation (which represents roughly 50 percent of the total decay energy) is emitted at an energy level too low to permit its penetration of the fuel and cladding. As a result, roughly 50 percent of the total decay energy emitted by fission products in the fuel is absorbed by the fuel and cladding and therefore does not contribute significantly to the rate of energy absorption by the water. Furthermore, approximately 7 percent'of the gamma energy is absorbed by the core solution; the rest is absorbed by the fuel, cladding, or other core components.
In the containment sump, where fission products are assumed to be dissolved in O the sump solution, energy is emitted directly to the solution. Since the depth of the sump is relatively large compared to the penetrating capability of even gamma energy, effectively 100 percent of the decay energy of the fission products dissolved in solution is absorbed by the solution.
The other significant difference between the co-e and sump environment is the type of flow regime to which the products of radiolysis are exposed.
O WAPWR-CS 6.2-224 NOVEMBER, 1986 4324e:1d
O Radiolytic decomposition of water is a reversible reaction. In the core, where the products of radiolysis are continuously flushed away by the circulation of cooling solutions, there is little chance for hydrogen and oxygen to accumulate. Consequently, recombination of hydrogen and oxygen is assumed not to occur because significant quantities of the two reactants are not availab'le. The sump, however, is a relatively deep and static environment, where the products of radiolysis are removed by molecular diffusion. Experimental tests simulating sump conditions demonstrate that there is significant reverse reaction in the sump. Hence, there is an apparent reduction in the quantity of hydrogen produced per unit energy absorbed.
L The results of Westinghouse and Oak Ridge National Laboratory studies indicate maximum hydrogen yields of 0.44 molecules per 100 eV for core radiolysis and
! 0.3 molecules per 100 eV for sump radiolysis. The results of these studies l are published in References (2], (3), and (4]. This analysis, based on the conservative recommendations of Regulatory Guide 1.7 and Standard Review Plan 6.2.5, assumes a hydrogen yield of 0.5 molecules per 100 eV of energy absorbed for both core and sump radiolysis. The hydrogen production calculational assumptions of Regulatory Guide 1.7 are presented in Table 6.2-47.
1 Table 6.2-48 presents the total decay energy (8 + 1r) of the reactor core, j assuming full power cperation for 650 days prior to the accident, a TID-14844 (Reference (5]) release of 50 percent of the halogens and 1 percent of the other fission products, and the release of 100 percent of the noble gases to the containment. The derived total decay energy curve, presented in Figure ~
6.2-44, was compared to a decay energy curve based on American Nuclear Society
! O (ANS) 5.1-1979 (Reference (6]). For this comparison, the values given in ANS 5.1 for decay energy release rate at infinite irradiation time were adjusted to a 650-day irradiation time. The resultant values were multiplied by 1.2.
The comparison is presented in Figure 6.2-44. The Westinghouse decay energy curve is used exclusively for post-LOCA hydrogen production calculations.
Table 6.2-49 presents the decay energy released to the sump solution.
O WAPWR-CS 6.2-225 NOVEMBER, 1986 T324e:1d
6.2.5.3.1.3 Corrosion of Metals and Paints in Containment Following a LOCA, hydrogen may be produced inside the containment hy corrosion of aluminum and zinc. .
Extensive corrosion testing has been conducted to determina the behavior and compatibility of various materials with alkaline borste solution (References (7), (8) and(9]). Metals tested included Zircaloy, Inconel, alumiaum alloys, cupronickel alloys, carbon steel, galvanized carbon steel, and cepper. The tests showed that only aluminum and zine will corrode at a rato that will significantly add to the hydrogen accumulation in the containment atmosphere.
Aluminum is found in the containment as aluminum metal components. Zine will be in the form of either galvanized steel, zinc metal, or zine-based paint.
i Aluminum corrosion may be described by the overall reaction:
2 Al + 3 H2O
- A123 0 + 3 H2 Three moles of hydrogen gas are produced for every two moles of aluminum that i
is oxidized. Approximately 20 sf 3 of hydrogen gas are produced for each pound of aluminum corroded.
I The corrosion of zine may be described by the overall reaction:
Zn + H2O
- Zn(OH)2 + H2 Approximately 5.5 sf 3 of hydrogen gas are produced for each pound of zine corroded, t
The time-temperature cycle (Table 6.2-50) considered in the calculation of aluminum, and zine corrosion is a conservative stepwise representation of the O postulated post-accident containment temperature transient. The corrosion rates at the various steps were determined from the aluminum and zine i corrosion rate design curves shown in Figure 6.2-45. The corrosion data O WAPWR-CS 6.2-226 NOVEMBER, 1986 T324e:1d
O. include the effects of temperature and spray solution' pH (Reference (9]).
With these corrosion rates and the aluminum and zine inventory given in Table 6.2-47, the contribution of aluminum and zine corrosion to the hydrogen
- w accumulation in the containment following the DBA was calculated. No credit was taken for the protective shielding effects of insulation or enclosures; i.e., complete and continuous immersion in spray was assumed.
Calculations based on Regulatory Guide 1.7 are performed by increasing the corrosion rate during the final step of the post-accident containment 2
. temperature transient (Table 6.2-50) to 200 mils / year (15.7 mg/dm /h). The corrosion rates earlier in the accident sequence are the rates determined from Figure 6.2-45.
6.2.5.3.1.4 Hydrogen in the Primary Coolant
! During normal operation of the plant, hydrogen is dissolved in the reactor coolant and is also contained in the pressurizer vapor space. Following a LOCA, this hydrogen is assumed to ha immediately released to the containment atmosphere. The maximum equilibrium quantity of hydrogen from this source is 1492 sf3 .
The pressurizer vapor space hydrogen is based on the following:
c a. Reactor coolant hydrogen concentration of 35 cm3 (STP)/kg of coolant.
- b. Normal pressurizer heaters turned on 50 percent of the time and all of the heat going to the boiling water.
O c. Bypass spray rate of 1 gal / min,
- d. Normal liquid level in pressurizer (60 percent).
l
-- e. Pressurizer relief valves closed.
l O WAPWR-CS 6.2-227 NOVEMBER, 1986 4324e:1d
O 6.2.5.3.1.5 Hydrogen Mixing Experiments (References (10] through (15]) demonstrate that for the period of G high hydrogen evolution during and following blowdewn, bulk turbulence and b natural convective transport will be available to distribute and diffuse hydrogen throughout the containment.
- g. Following this period, long-term mixing within and between the lower volumes
\ of the containment and the region above the operating deck will be provided by l the containment sprays (if operating) and the emergency containment coolers. )
'The reactor vessel head vent system will provide for the release of any i 1
concentrated hydrogen from the primary loop at a controlled rate and in a location so as to allow complete dispersion due to the natural diffusion tendencier, of hydrogen and by augmented means such as the containment cooler discharge, which is ducted so as to maintain hydrogen concentration equilibrium between the upper and lower containment regions through forced convection.
6.2.5.3.1.6 Conclusions Figure 6.2-46 shows bulk containment volume percent hydrogen versus time following a LOCA. With no recombiner the hydrogen concentration will reach 4 volume percent in 8 days. With a single 100-sf /3min recombiner started on the second day or when the bulk contain:nent concentration reaches 3.5 volume percent, the hydrogen concentration is quickly reduced, thus showing ample margin in the hydrogen control system.
I
! The hydrogen production rate and integrated hydrogen for each source are shown in Figures 6.2-47 and 6.2-48.
O O WAPWR-CS 6.2-228 NOVEMBER, 1986 T324e:1d
6.2.5.4 Tests and Inspections 6.2.5.4.1 Electric Hydrogen Recombiners The electric hydrogen recombiners underwent extensive testing in the Westinghouse development program. These tests encompassed the initial analytical studies, laboratory proof-of principal tests, and full-scale prototype testing. The full-scale prototype tests included the effects of:
- o. Varying hydrogen concentrations o Alkaline spray atmosphere o Steam effects o Convection currents o Seismic effects I
A detailed discussion of these tests is provided in References 16 through 23.
! Periodic operational tests and inspections will be performed in accordance l with the requirements of the plant specific Technical Specifications.
! Inspections will be performed to ensure the capability of the recombiner to perform its function. Testing is performed to verify operation of the control system and to verify functional performance of the heaters to the required temperature level.
l 6.2.5.4.2 Containment Hydrogen Purge System Safety-related equipment is qualified by the vendor to meet the codes and standards required by the system classification. Functional testing is performed after installation but prior to plant startup to verify the system performance capability. Periodic testing of the system components will be performed in accordance with plant procedures, which will be established by the plant specific applicant.
!O WAPWR-CS 6.2-229 NOVEMBER, 1986 l T324e:1d l
w O 6.2.5.4.3 Hydrogen Ignition System Safety-related equipment is qualified by the vendor to meet the codes and ,
standards required by the system classif.ication. Functional testing will be 4
Og performed after installation but prior to plant startup to verify the system ,
performance capability.
6.2.5.4.4 Post-Accident Hydrogen Monitoring System Safety-related equipment for this system is vendor qualified to meet the codes and standards required by the system classification. Functional and preoperational testing will be performed afte- installation and prior to plant
- st:rtup to verify the system performance capability. Periodic testing of the system and the isolation and sample selector valves will be performed in accordance with technical specification requirements.
6.2.5.5, Instrumentation Requirements O. 6.2.5.5.1 Electric Hydrogen Recombiner The recombiners do not require any instrumentation inside the containment for proper operation after a LOCA. The recombiners are started manually after a LOCA. The sampling system is used to obtain containment atmosphere samples that indicate when the recombiners should be actuated. Control measures can be initiated when the hydrogen concentration reaches 3 volume percent.
6.2.5.5.2 Hydrogen Ignition System O Centrol switches for manual operation of the igniters for each independent train are provided on the control panel in the control room.
6.2.5.5.3 Containment Hydrogen Monitoring System The control switches for the sample selector valves and containment isolation valves are located on the process control panel in the control . room. ,
O WAPWR-CS 6.2-230 NOVEMBER, 1986 4324e:1d
O Operation of the hydrogen analyzers is controlled remotely from the main control board. Hydrogen concentration is both indicated and recorded on the I main control board.
f} 6.2.5.6 Materials The materials of construction for the hydrogen control systems are selected for their compatibility with the post-LOCA environment.
The major structural components of the hydrogen recombiners are manufactured from 300-Series stainless steel. Incoloy-800 is used for the hetter sheaths and. for other parts such as the heat duct, which operates at high temperature.
There are no radiolytic or pyrolytic decomposition products from these materials.
6.2.5.7 References O 1. NRC- Regulations:
Regulatory Guide 1.7, Rev. 2, November 1978.
Standard Review Plan 6.2.5, " Combustible Gas Control in Containment,"
July 1981.
l i
! Branch Technical Position CSB 6-2, " Control of Combustible Gas Concentration in Containment Following a Loss-of-Coolant Accident."
O 2. Fletcher, W. D., Bell, M. J., and Picone, L. F., " Post-LOCA Hydrogen Generation in PWR Containments," Nuclear Technology 10, pp 420-427, 1971.
- 3. Zittel, H. E., and Row, T. H. , " Radiation and Thermal Stability of Spray
~ Solutions," Nuclear Technology 10, pp 436-443, 1971.
WAPWR-CS 6.2-231 NOVEMBER, 1986 4324e:1d
- . - - = . _
1 O 4. Allen, A. O., The Radiation Chemistry of Water and Aqueous Solutions, Princeton, N. J., Van Nostrand, 1961.
- 5. DiNunno, J. J., et al, "Cale.ulation.s gf. Di.s.tance Factors for Power and Test Reactor Sites," TID-14844, March 1962.
- 6. American Nuclear Society Standard ANS 5.1, " Decay deat Power in Light
- Water Reactors," August 29, 1979.
i Cottrell, W. B., "0RNL Nuclear Safety Research and Development Program 7.
Bi-Monthly Report for' July-August 1968," ORNL-TM-2368, November 1968.
- 8. Cottrell, W. B., "0RNL Nuclear Safety Research and Development Program Bi-Monthly Report for September -
October, 1968," ORNL-TM-2425, p. 53, January 1969.
l
- 9. Whyte, D. D., and Burchell, R. C., " Corrosion Study for Determining l
Hydrogen Generation from Aluminum and Zine During Post Accident Conditions," WCAP-8776, (Nonproprietary), April 1976.
- 10. " Natural Transport Effec.ts on Fission Product Behavior in the Containment Systems Experiment" BNWL-1457, December 1970.
- 11. " Nuclear Safety Quarterly _ Report-July, August, September, and October -
i 1967," BNWL-754, June 1968.
1
- 12. " Nuclear Safety Quarterly Report-August, September, and October 1966,"
BNWL-926, December 1968.
- 13. " Hydrogen Mixing Within the Drywell Prior to Drywell Containment Mixing System Actuation," GESSAR, Section 6.2.5.3.3.1, March 1975.
- 14. Roberts, A., et al., " Methane Layering in Mine Airways," Colliery Guardian, October 1962.
O WAPWR-CS 6.2-232 NOVEMBER, 1986 T324e:1d
_ _ _ . . _ _ _ . _ . . _ _ _ . _ _ _ _ _ . ~ . . _ _ _ . ____ _ -. _
.mz -
. - - , m _ _ . _ ..m . .
O 15. United States Atomic Energy Commission, 169th General Meeting of the Advisory Committee on Reactor Safeguards, May 9, 1974.
l C 16. Wilson, J. F., " Electric Hydrogen Recombiner for Water Reactor Containments," WCAP-7709-L (Proprietary), July 1971, and WCAP-7820 (Nonproprietary), December 1971.
p 17. Wilson, J. F., " Electric Hydrogen Recombiner for PWR Containments-Final Development Report," WCAP-7709-L, Supplement 1 (Proprietary), and
!. WCAP-7820, Supplement 1 (Nonproprietary), April 1972.
- 18. Wilson, J. F., " Electric Hydrogen Recombiner for PWR Containments-Equipment Qualification Report," WCAP-7709-L, Supplement 2 (Proprietary),
and WCAP-7820, Supplement 2 (Nonproprietary), September 1973.
Long Term Tests," WCAP-7709-L, Supplement 3 (Proprietary), and WCAP-7820, Supplement 3 (Nonproprietary), January 1974.
WCAP-7709-L, Supplement 4 (Proprietary), and WCAP-7820, Supplement 4 (Nonproprietary), April 1974.
- 21. Wilson, J. F., " Electric Hydrogen Recombiner Special Tests," WCAP-7709-L, Supplement 5 (Proprietary), and WCAP-7820, Supplement 5 (Nonproprietary), .
December 1975. ,
- 22. Wilson, J. F., " Electric Hydrogen Recombiner IEEE 323-1974 Qualification,"
WCAP-7709-L, Supplement 6 (Proprietary), and WCAP-7820, Supplement 6 (Nonproprietary), October 1976.
i Supplemental Test Number 2," WCAP-7709-L, Supplement 7 (Proprietary), and
! WCAP-7820, Supplement 7 (Nonproprietary), August 1977.
O WAPWR-CS 6.2-233 NOVEMBER, 1986 4324e:1d r
O TABLE 6.2-47 (SHEET 1 of 4)
PLANT PARAMETERS USED TO CALCULATE POST-ACCIDENT HYDROGEN PRODllCTION O
Core thermal power (MWt) 4200 3 6 Containment free volume (ft ) 3.09 x 10 Normal containment temperature (*F) 120 Weight of zirconium clad on active core (ib) 82,350 -
- Percent zirconium-water reaction (%) 1.5 Hydrogen recombiner flowrate (sf 3/ min) 100 Aluminum Inventory in Containment Weight Surface Component (ib) (ft 2)
O Flux map drive system 183 48 Nuclear instrumentation system 244 57 Digital rod position indicators 199 241 Control rod drive mechanism (CRDM) connectors 129 9736 Miscellaneous valves (nuclear steam supply 230 86 system)(NSSS)
Radiation monitoring system 4 4 Containment fan cooler return bend assemblies 765 3000 Communication equipment 6 10 Miscellanecis va'as (balance of plant (BOP)) 6 1 Contingency (NSSL) 250 85 Total 2:16 13,268 O
O WAPWR-CS 6.2-234 NOVEMBER, 1986 4324e:1d n' _ _ - _ _ _ _ _ -.
O TABLE 6.2-47 (SHEET 2 of 4)
ZINC INVENTORY IN CONTAINNENT O
Weight Surface 2
M (1b) (ft )
Decking, grating, cable trays, GS(a) 14,980 150,559 conduit, junction boxes, armored cables and metal clad cables Snubbers In(b) 11 555 Integrated reactor vessel (RV) ZBP(c) 17,734 180,100 head /CRDM shroud Miscellaneous BOP items ZBP 21,860 466,218 Total 54,585 797,432 O
O O WAPWR-CS 6.2-235 NOVEMBER, 1986 4324e:1d
. . ~
, O TABLE 6.2-47 (SHEET 3 of 4)
REGULATORY GUIDE 1.7 HYDROGEN PRODUCTION CALCULATIONAL ASSUMPTIONS l Core Cooling Solution Radiolysis Sources:
i Percent of total halogens retained in the core 50-Percent of total noble gases retained in the core O Percent of other fission products retained in the core 99
- Energy distribution:
Pergent of total decay energy (gama) 50 Percent of total decay energy (beta) 50 Energy absorption by core cooling solution:
Percent of gamma energy absorbed by solution 10 Percent of beta energy absorbed by solution 0 Hydrogen production:
l Molecules hydrogen produced per 100 eV energy 0.50 absorbed by solution l
O O
6.2-236 NOVEMBER, 1986 WAPWR-CS 4324e:1d
)
- -._ .-,, ,.,,,--..,~ __,,,_ . ,,.,_ _ ____ _ _ _
O TABLE 6.2-47 (SHEET 4 of 4) l O Sump Solution Radiolysis 1
i l Sources:
!O Percent of total halogens released to sump 50 solution Percent of noble gases released to sump solution 0 Percent of other fission products released to sump 1 solution Energy absorption by sump solution:
Percentoftotalenergy(betaandgamma)whichi- 100 absorbed by the sump solution Hydrogen production:
Molecules of hydrogen produced per 100 eV of energy 0.5 l
absorbed by the sump solution l
Lono-Term Aluminum Corrosion Rate Mils per year 200 Milligrams per square decimeter per h 16 >
tO a. GS galvanized steel i b. 2n - zine metal
- c. ZBP - zine-based paint
) WAPWD,-CS 6.2-237 NOVEMBER, 1986 T324e:1d
.-.,4:
l l
TABLE 6.2-48 CORE FISSION PRODUCT ENERGY AFTER 650 FULL-POWER DAYS Time After Reactor Trip Energy Release kate Integrated Energy Release (days) (watts /MWt x 10-3) (watt-day /MWt x 10-4)
O 1 3.887 0.574 5 2.595 1.777 10 2.211 2.967 20 1.760 4.934 30 1.475 6.541 40 1.291 7.919 50 1.163 9.143 60 1.086 10.259 70 0.992 11.289 O 80 0.926 0.867 12.249 13.139 90 100 0.814 13.979 i
l l O a. Assumes release of 50 percent of core halogens plus 1 percent other fission products; includes 100 percent of noble gases. Values are for total (S + r) energy.
O O WAPWR-CS 6.2-238 NOVEMBER, 1986 4324e:1d i
l l
t i V TABLE 6.2-49 FISSION PRODUCT DECAY DEPOSITION IN SUMP SOLUTION 1 Percent
) 50 Percent Other Fission Halogens Products Time After Energy Integrated Energy Integrated Energy Integrated Reactor Release Energy Release Energy Release Energy 4 Trip Rate Release Rate Release Rate O (days) (watt /MWt)
(watt-day /
MWtx10-2)
(watt-day /
MWtx10-1)
(watt-day /
MWtx10-2)
(watts /
MWtx10-1)
Release (watt-day /
MWtx10-3)
'l 145 4.27 3.78 0.536 18.28 0.481 3 49.4 5.88 2.90 1.18 7.85 0.707
- 5 31.0 6.65 2.59 1.73 5.69 0.838 10 18.2 7.82 2.22 2.92 4.03 1.07 20 7.63 9.03 1.77 4.89 2.53 1.39 I 30 3.22 9.54 1.49 6.51 1.81 1.61 l 40 1.36 9.76 1.30 7.90 1.44 1.77 60 0.241 9.89 1.08 10.3 1.10 2.02 80 0.043 9.91 0.935 12.3 0.940 2.22 100 0.008 9.92 0.822 14.0 0.823 2.39 O
O O WAPWR-CS 6.2-239 NOVEMBER, 1986 T324e:1d
e TABLE 6.2-50 POST-ACCIDENT CONTAINMENT TEMPERATURE TRANSIENT FOR HYDROGEN GENERATION ANALYSIS O
Time Interval Temperature
- (s) (*F)
O O-4 200 4-7 220 7 - 13 240 13 - 40 254 40 - 100 248 100 - 200 252 200 - 700 250 700 - 3000 240 3000 - 10,000 225 l 0 10,000 - 40,000 40,000 - 200,000 200 190 200,000 - 500,000 180 500,000 - 1,000,000 165 l 1,000,000 150(a) l
- a. The long-term aluminum carrosion rate of 200 mils per year begins.
I l
O O WAPWR-CS 6.2-240 NOVEMBER, 1986 T324e:1d
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O FIGURE 6.2-45 ALUMINUM AND ZINC CORROSION RATE DESIGN CURVES O 103 _
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- ALUMINUM CORROSION RATE DESIGN CURVE 2 -
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- ZINC CORROSION RATE 4 - DESIGN CURVE 2 -
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i l
20 LEGEND 1
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RECOMB DAY 2 16 -
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I FIGURE 6.2-46 CONTAINMENT HYOROGEN CONCENTRATION i
i NOVEMBER, 1986 WAPWR-CS l 4324e:1d 1
j 4
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PRODU CTION FROM ALL SOURCES !
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FIGURE 6.2-47 HYDROGEN PRODUCTION FROM ALL SOURCES NOVEMBER, 1986 WAPWR-CS 4324e:1d
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{ 6.2.6 Containment Leakage Testing The following sections are not intended to present a final description of the
^ methods to be used to ensure compliance with 10CFR50, Appendix A containment leak testing requirements for the RESAR-SP/90 design, but only represent the type of information to be supplied at the final design stage. Details on all primary and secondary containment penetrations and containment isolation barriers are not available at the preliminary design stage. Additionally, approval of the draft Regulatory Guide and Value/ Impact Statement, as published by the U.S. N.R.C. (October, 1986 - Division 1, Task MS-021-5) on Containment System Leakage Testing, could impact the requirements and the
! methods used to comply with the requirements.
The reactor containment, containment penetrations, and containment isolation barriers will be designed to permit periodic leakage rate testing as required by 10CFR50, Appendix A, General Design Criteria (GDC) 52, 53, and 54. The containment leak test requirements are outlined _ and the acceptance criteria for such tests are established in 10CFR50, Appendix J. The objective of the leakage rate testing is to ensure that the leakage from the containment is within the limits to be established in the Technical Specifications.
j Compliance with 10CFR50, Appendix J, Types A, B, and C, testing will be shown
) in the Final Design Application (FDA).
6.2.6.1 Containment Integrated Leakage Rate Test (Type A Test)
The design leakage rate for the containment is 0.15 percent free volume per day for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The actual leakage rate will be determined by using the methods and requirements of Appendix J to 10CFR50 for Type A tests.
i The acceptance criteria specified in Appendix J for the integrated leakage rate test (ILRT) includes a margin for possible deterioration of the O centainment leakage integrity during the service intervals between tests. The O WAPWR-CS 6.2-241 NOVEMBER, 1986 4324e:1d
O measured leakage rates (L tm at reduced test pressure and L,, at peak test pressure) will not' exceed 0.75 of the maximum allowable leakage rate values Ltand L,, respectively.
. 6.2.6.1.1 ILRT Protest Requirements Several pretest requirements are to be met before the ILRT is performed. The i
containment ILRT 'will follow the satisfactory completion of a series of local
, leakage tests. Local leak paths through the containment boundary, i.e.,
containment penetrations, are subjected to test conditions similar to those occurring during the ILRT to allow detection and correction of leak paths through the containment without pressurizing the entire containment i structure. These local leakage tests are the Type B and C tests described in Subsections 6.2.6.2 and 6.2.6.3.
i A general inspection of the accessible interior and exterior surfaces of the containment structures and components for any evidence of structural deterioration which may affect either the containment structural integrity or leaktightness will be made. Any evidence of structural deterioration will be evaluated and corrected if necessary before the Type A test is performed.
. Following the completion of the Type C tests, the containment isolation valves will be positioned at their normal operational position and subsequently l
repositioned to their post-accident position by the normal method with no accompanying adjustment. Normal and accident positions for each isolation valve will be established at the' Final Design Approval (FDA) stage.
i Systems which are isolated following a loss-of-coolant accident (LOCA) must be properly isolated, drained, or vented to reflect their worst potential status to ensure that the Type A test results will accurately reflect the most restrictive LOCA conditions.
i l
Portions of the fluid systems, which are part of the reactor coolant pressure boundary and are open indirectly to the containment atmosphere due to the accident conditions, are, therefore, an extension of the boundary of the
- O WAPWR-CS 6.2-242 NOVEMBER, 1986 4324e:1d k
. . . - . . . _ . , , , _ . - . _ _ , _ _ - _ . . - - _ _ _ _ _ _ _ , , _ _ _ _ _ . _ , _ ,m.. . , . . _ . _ , _ . _ . _ _ . . _ _ _ _ _ _ _ . . _ _ _ . - . . . , _ _ . _ . .
b q t 7
O containment and are opened or vented to the containment atmosphere prior to and during the test. The applicable GDC or other defined criteria for the isolation valve arrangements provided will be established at the FDA stage.
1 Portions of the closed systems inside the containment that penetrate the containment and might rupture as a result of a LOCA are vented to the containment atmosphere. All vented systems are drained of water or other fluids to the extent necessary to ensure the exposure of the system containment isolation valves to the containment air test pressure and to ensure that they will be subjected to the post-accident differential pressure. Systems that are required to maintain the plant in a safe condition
. during the test, such as the ' essential service cooling water lines to the containment air coolers, are operable in their normal mode and need not be vented.
Systems that are normally filled with water and operating under post accident conditions, such as the containment heat removal system, need not be vented or l
drained. Systems which are not vented during Type A tests will be identified
. in the FDA.
The steam generator tubes and shell and the associated piping systems passing through the containment liner are considered an extension of the containment.
Therefore, the secondary side of the steam generator and connecting systems are not vented to the containment atmosphere. The penetrations associated with the secondary side of the steam generator will be identified for the FDA.
' Pressurized gas and water systems will be vented downstream of the outside isolation valve for the system and vented outside of the containment. This is done to preclude leakage into the containment and to expose the outside isolation valve to a low backpressure resulting in conservatively high leakage characteristics.
O The emergency water storage tanks, reactor coolant drain tank, pressurizer relief tank, core reflood tanks, accumulator tanks, and RCP standpipes are O WAPWR-CS 6.2-243 NOVEMBER, 1986 4324e:1d i
1
-..-_-. - - ~ ___ - - --__- _ _ _
_ - _ - _ _ _ - _ -_-___________._ _ _ _ - _ _ w - - __. --
l k
vented to the containment atmosphere. This is done to protect the tanks from the external pressure of the test and to preclude leakage to or from the tanks which would affect the accuracy of the test results.
O
- To protect differential pressure instruments, the equalizing valves are opened i
to prevent possible damage due to overranging. Load-cell readouts are removed from the containment.
i Additionally, the containment fan coolers are protected by operating them throughout the duration of the ILRT.
During preoperational testing, a structural integrity test- (SIT) is
- performed. The SIT is a pressure test conducted to verify that the
- ontainment structural response due to the induced load is consistent with the predicted behavior.
Following the preoperational SIT, the initial ILRT is performed.
O 6.2.6.1.2 ILRT Test Method The ILRT will be conducted in accordance with American National Standards Institute (ANSI) N45.4.(1) For penetrations which are exempt from Type B or C tests the leakage testing requirement of Appendix J is accomplished by the Type A test.
Containment dry bulb temperature, pressure, and dewpoint temperature are periodically monitored during the test. These data are analyzed as they are taken so that the leakage rate and its statistical significance are known as the test. progresses. Once the leakage rate has been found with sufficient accuracy, a known additional leak is imposed and the measurements are continued, giving additional verification of the leakage rate.
lO io
- i WAPWR-CS T324e
- 1d 6.2-244 NOVEMBER, 1986 I
. - - . . . . _ . - . . . . ~ . - - _ , - . . . - . _ . _ _ , _ - . _ - , - . . . . - - . _ . . , _ - _ _ . . , _ . _ . _ _ - _ - . . . -
. .. =. . _ - - . - . . _ -
i O The following aspects of Type A testing follow 10CFR50, Appendix J, guidelines without exception:
Protest requirements including a general inspection.
I O o o Conduct of tests.
o Acceptance criterion.
I o Periodic retest schedule.
o Inspection and reporting of tests.
! O o Failure of a periodic ILRT.
~
- 6.2.6.2 Containment Penetration Leakage Rate Tests (Type B Tests) l Containment penetrations whose design incorporates resilient seals, gaskets, or sealant compounds; airlocks and lock-door seals; equipment and access hatch seals; and electrical canister and modular type penetrations receive a preoperational and periodic Type B leakage rate test in accordance with-10CFR50, Appendix J.
O Electrical penetrations are of modular- or canistar-type design and their leakage testing provisions meet the requirements of Institute of Electrical and Electronics Engineers (IEEE) 317. Each of the modular-type electrical penetrations consists of a single header plate sealed to a nozzle on the containment exterior by double 0-rings with interspace connection.
I Feedthrough modules carrying conductors are sealed into the header plate by a 1 metal compression fitting assembly with interspace connection. The l' feedthrough conductors are sealed to the feedthrough module by double, high-temperature, thermoplastic seals with interspace connection. The seal interspaces (header plate 0-rings, feedthrough module compression fittings, and thermoplastic seals) are pressurized with nitrogen; the pressure is continuously monitored to detect leakage. Each of the canister-type electrical penetrations is similar in design to the modular type, except that the canister type extends through the length of the nozzle with header plates at each end, through which the conductor modules are sealed and terminate in electrical ceramic bushings. Each of the electrical penetrations is provided
!O i WAPWR-CS 6.2-245 NOVEMBER, 1986 T324e:1d
O with a local pressure gauge. The electrical penetrations for the personnel lock, escape hatch, and encapsulated valves are of the same design without the local pressure gauge.
Expansion bellows utilized on the fuel transfer tube penetration accommodate relative movement between the refueling poci liner and the containment penetration and do not form part of the containment pressure boundary.
Expansion bellows utilized on the containment emergency sump suction line h guardpipes accommodate relative movement between the auxiliary and handling buildings with respect to the containment and do not form part of fuel the containment pressure boundary.
The equipment hatch, personnel lock, and escape hatch doors are fitted with double seals with an interspace test connection. Clamps are provided for restraining the airlock doors when the seal interspace or airlock is pressurized. Test connections are located such that testing is accomplished without entering the containment. Two pressure gauges are provided, one inside the lock which penetrates the bulkhead at the inner airlock door to measure containment pressure and one located outside the airlock to penetrate the bulkhead at the outer airlock door to read lock pressure. Mechanical penetrations on the airlock are provided with double seals and test connections.
The containment leak rate penetrations are provided with blind flanges that have testable double 0-ring seals and are Type B tested.
Type B tests are conducted at calculated peak containment internal pressure.
The acceptance criteria and leakage rate limits will be given in the Technical Specifications. Test methods and equipment are described in Subsection 6.2.6.3.
6.2.6.3 Containment Isolation Valve Leakage Rate Tests Containment isolation valves are Type C tested in accordance with 10CFR50, Appendix J.
O WAPWR-CS 6.2-246 NOVEMBER, 1985 4324e:1d
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The process piping, instrumentation tubing, and personnel access penetrations will be provided at the FDA stage.
The CIVs for each piping penetration and process isolation valve for those piping penetrations where no GDC is applicable are tabulated in Table 6.2-46, together with the test type.
Type B and C tests are performed by local pressurization . utilizing either the O pressure decay or flowmeter method. For the pressure decay method, the test volume is pressurized with air or nitrogen to at least P,. The rate of
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decay of pressure of the known free air test volume is monitored to calculate the leakage rate. In the flowmeter method, pressure is maintained in the test volume by makeup air, nitrogen, or water (if applicable) through a calibrated flowmeter. The flowmeter fluid flowrate is'the isolation valve leakage rate.
Containment isolation valve leakage across the valve seat is determined in the direction out of the containment, in accordance with the requirements of 10CFR50 Appendix J for Type C testing, and the test fluid (liquid or gas) is the same as that expected during the accident.
Type C testing of the safety injection lines, containment spray lines, residual heat removal lines, high head safety injection lines of the chemical and volume control system, RCP seal injection lines, the containment emeigency sump lines to the residual heat removal and containment spray pumps, and nuclear service cooling water lines to and from the containment fan coolers is not performed. The justification for this is that these valves are either '
normally open at the time of a LOCA or are opened at some time after the accident to effect immediate and long term core cooling. Therefore, these lines are continuously water filled during emergency core cooling system operation either from the refueling water storage tank or from the containment emergency sumps and as such do not provide a credible path for leakage of the containment atmosphere. Furthermore, inservice testing and inspection of these isolation valves and the associated piping system outside the O WAPWR-CS 6.2-247 NOVEMBER, 1986 T324e:1d
containment is performed periodically under the inservice inspection requirements of ASME XI. During normal operation, the systems are water fii N , and degradation of valves or piping is readily detected.
O In the chemical and volume control system, the isolation valves in the charging line are Type C tested using water. This is justified in that these lines are filled with water in the event of a LOCA.
Isolation vrives connected to the secondary side of the steam generator, such as main steam isolation. valves, main steam relief valves, feedwater valves, blowdown lines, and blowdown sample lines are subjected to Type A tests. The steam generator is pressurized above containment pressure by the emergency feedwater system, which meets the single failure criteria. -
Containment pressure monitoring lines are considered an extension of the containment boundary, and therefore the isolation valves are not Type C tested.
Isolation valves will be positioned to their post-accident position by the O normal method with no accompanying adjustments. Fluid systems are properly drained and vented with the valves aligned to provide a test volume and atmospheric air backpressure on the isolation valve (s) being tested.
The test volume and holding vessel are pressurized to the test pressure P,,
as specified in the Technical Specifications. The pressure regulator (s) maintain the test volume at a minimum of P,. The airflow rate into the test volume is recorded, as is the pressure reading, at the intervals specified on the data form. These records are utilized to determine the leakage rate in cubic centimeters per minute.
For larger test volumes, a pressure decay method may be utilized to determine the leakage rate.
O The total leakage rate for Type B and C tests must be less than 0.6 L,.
O WAPWR-CS 6.2-248 NOVEMBER, 1986 T324e:1d
The criteria for determining the direction in which the test pressure is applied to the isolation valves are as folicws:
A. Gate Valves
- 1. Parallel Disc l a. Test in the design basis accident (DBA) direction.
O b. Testing can be performed between the discs if a test connection or drain is provided in the valve design.
- 2. Flexible Wedge
- a. Test in the DBA direction,
- b. Testing can be performed between the wedge sections if a test connection or drain is provided in the valve design.
- 3. Solid Wedge
- a. Test in the DBA direction.
B. Globe Valves l
If the DBA flow direction is over the disc (flow to close), the valve i may be tested in the reverse direction. However, if the DBA flow .
direction is under the dise (flow to open), then the valve must be tested in this direction.
C. Butterfly Valves Test in either direction.
O WAPWR-CS 6.2-249 NOVEMBER, 1986 4324e:1d
O D. Flanges Test in either direction.
O- The leakage rate test acceptance criteria for penetrations and isolation valves suoject to Type B and C tests will be given in the Technical Specifications.
6.2.6.4 Scheduling and Reporting of Periodic Tests Type A, B, and C tests will be conducted at the intervals specified in the Tec.hnical Specifications. Those intervals will be in accordance with Appendix J to 10CFR50, with the exception of the testing of the containment airlocks.
Containment airlocks will be tested prior to establishing containment
.integri ty, when maintenance has been performed on the airlock that could affect the lock sealing capability.
The test and test results will be the subject of a summary report submitted to the Nuclear Regulatory Commission after the completion of testing. The results of Type B and C testing will be included in the ILRT summary report.
The preoperational test report will contain a schematic of the leakage measuring system, instrumentation used, supplemental test method, test program, and analysis and interpretation of the leakage test data for the Type A test.
6.2.6.5 Special Testing Requirements O The secondary containment special testing requirements beyond those delineated for the primary containment will be provided at the FDA stage.
REFERENCE
- 1. " Leakage Rate Testing of Containment Structures for Nuclear Reactors,"
O WAPWR-CS 6.2-250 NOVEMBER, 1986 4324e:1d
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6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS Several plant features serve to reduce or limit the release of fission A products following a postulated loss-of-coolant accident (LOCA) or fuel handling accident. The features are the control room hability system (RESAR-SP/90, PDA MODULE 13, " Auxiliary Systems", Section 6.4 and Subsection 9.4.1), the reactor external building ventilation system (RESAR-SP/90, MODULE 13, Subsection 9.4.2) the annulus air cleanup and fuel building emergency Os exhaust systems (RESAR-SP/90, PDA MODULE 13, Subsection 9.4.5) and the containmentspraysystem(RESAR-SP/90PDAModule 1, " Primary Side Safeguards Systen, Subsection 6.5) to mitigate the consequences of an accident. The design of each of these engineered safety features (ESF) is discussed in the referenced sections. Chapter 15 (RESAR-SP/90 PDA MODULE 1) addresses the radiological consequences of postulated ' accidents and demonstrates the adequacy of the fission product removal and control systems.
The referenced sections provide the design bases and safety evaluations which demonstrate that the design and construction of these systems is commensurate with acceptable practices for ESF. This includes, but is not limited to, ensuring redundancy, isolation from nonsafety-related portions, seismic classification, conformance with Regulatory Guide 1.52 (Section 1.9),
suitability of material for the intended service, Class 1E power supply from onsite or offsite sources, qualification testing, and capability for inspection and testing.
6.5.1 Engineered Safety Features Filters The control room heating, ventilation, and air-conditioning (HVAC) system and the reactor external building ventilation system, the annulus air cleanup and fuel building emergency exhaust systems constitute the systems containing engineered safety features filters. These systems are described in the f modules referenced above. The performance of the systems under postulated accident conditions is discussed in Sections 15.6 of RESAR-SP/90 PDA MODULE 1.
O WAPWR-CS 6.5-1 NOVEMBER,1986 6088e:1d
O 6.5.1.1 Design Bases Refer to referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
O 6.5.1.2 System Design .
Refer to the referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
O v 6.5.1.3 Design Evaluation Ref'er to the referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
6.5.1.4 Tests and Inspections Refer to the referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
6.5.1.5 Instrumentation Requirements O Refer to the referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
6.5.1.6 Materials Refer to the referenced RESAR-SP/90 PDA Module 13 sections listed in 6.5 above.
6.5.2 Containment Spray System (Fission Product Removal)
The containment spray system (CSS) is a subsystem of the integrated safeguards O system (ISS). Following a postulated loss-of-coolant accident (LOCA), the CSS sprays the interior of the containment to reduce the containment temperature and pressure and to remove airborne iodine activity from the containment atmosphere. -
O The basic description of the CSS is provided within Subsection 6.2.2 of RESAR-SP/90 PDA Module 1 and this module. Included in the referenced section are the descriptions of the various components of the CSS and the discussion O, WAPWR-CS 6.5-2 NOVEMBER, 1986 6088e:1d
O of the containment heat removal function of the CSS. The actuation times for the CSS are event dependent and are described in the individual accident analyses. In addition refer to Subsection 6.5.2 of RESAR-SP/90 PDA Module 1 for discussion on the design bases, system design and evaluations, testing and L) materials of the Containment Spray System.
6.5.3 Fission Product Control Systems 6.5.3.1 Primary Containment The SP/90 containment con'sists of a spherical steel structure which" forms a continuous, leak tight membrane. Layout drawings of the containment structure and the related items are given in the general arrangement drawings of Section 1.2 of RESAR-SP/90 PDA Module 3, " Introduction and Site".
The containment walls, penetrations, and isolation valves function to limit the release of radioactive materials subsequent to postulated accidents, such that the resulting offsite doses are less than the guideline values of 10 CFR O' 100. Containment parameters affecting fission product release accident analyses are given in Table 6.5.2-1 of RESAR SP/90 PDA Module 1.
Long-term containment pressure and temperature response to the design basis accident are shown in Section 6.2 of RESAR-SP/90 PDA Module 1. Relative to this time period, the spray system is operated to reduce iodine concentrations and containment atmospheric temperature and pressure commencing with system initiation, as discussed in 'Section 6.2 of RESAR-SP/90 PDA Module 1, and ending when containment pressure has returned to normal.
O The containment minipurge system may be operated for personnel access to the.
containment when the reactor is at power, as discussed in Subsection 9.4.6 of RESAR-SP/90 PDA Module 13. For this reason, the radiological assessment of a loss-of-coolant accident assumes that the minipurge valves are open at the O initiation of the event. However, the minipurge valves receive automatic signals to shut from diverse parameters. The valves are designed to close within 5 seconds.
D WAPWR-CS 6.5-3 NOVEMBER, 1986 6088e:1d
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l O The fission product removal capability of the containment spray system is discussed in Subsection 6.5.2 of RESAR-SP/90 PDA Module 1.
Redundant, safety-related hydrogen recombiners are provided in the containment O as the primary means of controlling post-accident hydrogen concentrations. A containment purge systcu is provided for backup hydrogen control.
Containment combustible gas control systems are discussed in detail in Subsection 6.2.5 of this module.
I 6.5'.3.2 Secondary Containment The SP/90 has a n eondary containment which is described in Subsection 1.2.3 of P.ES?.R-SP/90 iTA Wule 3 and whose function in the control of fission {
products in discussed in Subsection 9.4.5 of RESAR-SP/90 PDA Module 13.
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O O WAPWR-CS 6.5-4 NOVEMBER, 1986 608Be:1d
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