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Forwards Analysis Performed for B&W 177 Fuel Assembly, Lowered Loop PWR Loss of All Ac/Dc Power Transient
	ML19312E437
Person / Time
Issue date:	04/07/1980
From:	Throm E; Office of Nuclear Reactor Regulation
To:	Rosztoczy Z; Office of Nuclear Reactor Regulation
References
	NUDOCS 8006040404
	Download: ML19312E437 (31)
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APR 7 1980

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Z. R.~ Rosztoczy, Chief, Analysis Branch, DSS e,

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P. E. Morian, Leader Systems Analysti Section, AB. DSSE..

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E. D. Thron, Systems Analysis Section, AB, DSS

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SUBJECT:

BW 177 FA-LL LOSS OF POWER TRANSIENT

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References:

(1) NUREG-0565, " Generic Evaluation of SmaIl Break Loss-of-Coolant Accident Behavior in Babcock &

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(2) Sheron, B. W., "Doctanentation of Loss of AC/DC 4

Power Calculations." memo ~randum for files,

~i March 4, 1980.

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The RELAP4/ LOD 7 (V.92) cosputer program was used to perfom two analysesl

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transient. These analyses are intended to be used to ess.ablish the time

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available for operator action prior to the beginning of core uncovery..

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w: L r T The'snell break LOCA model? developed by EG&G Idaho was~used (refemnce 1).

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.+ A to undel the safety mitef valves. The nodal diagram is shown in Figure 1.

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m During the review of the results of the analyses a discrepancy was found in the initial ~ secondary side mass inventory. The MLAP4 model, which was initialized by the computer program, was found to contain a liquid r-mass total of 53,145 lbs. A check of FSAR data indicates this value should be closer to 110,000 lba, a facter of two difference.

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The mass inventory discrepancy say have been a contributor in the

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diffemnces noted between the staff and the BW analyses presented in L.

:)i/.7 refemnce 1, section 4.1.3 These can be seen in Figures 4-2 and 4 is.

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of reference 1.. The prisery system plateau is longer for the BW 7/s -

analyses, and the secondary side pressum remains higher for a similar m

period. This is an' indication that there is a secondary side mess

..O inventory discrepancy in the direction indicated.

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The two analyses differed in the reactor trip setpoint. One case assumed the trip to occur on a high pressure of 2430 psia in the hot leg.

The second case assumeo a pressure of 2250 psia.

In both cases the PORV and safety relief valves (SRVs) were modeled to open on differential pressure between the pressurizer and containment of 2285 psid and 2475 psid, respectively. The major event sequences are provided in Table 1.

Figures 2 through 18 show the important system parameter.

The procedure developed by B. Sharon, reference 2, was applied to the 2250 psia trip case.

This procadure is intended to provide a consoraative estimate of the time available to a reactor operator, following a complete loss of power transient, prior to the beginning of core uncovery.

The analysis of the 2250 psia trip case is provided in Appendix A.

Appendix B is the decay heat calculation used to determine the time ofaa given event.

The point at which the energy added to the system by the reactor core exceeds the energy removed through the steam generai.or: agrees with the hand calculation for dryout. There is, however, about 5% of the initial mass remaining in the secondaries in the RELAP4 analysis.

The time needed to raise the entire primary system to the SRVs set = point, t500 psia, also agrees well with the hand calculation method. The important assumption is the initial primary system internal energy. By selecting a conservative value, such as used by Sheron, i.e., that the system is

, saturation, the energy needed to get to 2500 psia will be less than actual. A conservative estimate of the time is therefore l

calculated. Sheron accounts for the energy needed to raise the core meta' temperature. The energy needed to raise the primary vessel and pipe metal temperature is not accounted for by Sheron, again a conservative assumption.

The time needed to arrive at the point when the core is beginning to uncover also agrees with with the hand calculation wher. the primary metal heat capacity and the residual water inventory is taken into account. The method used by Sheren is conservative in that is is assumed that the entire mass alpove the core must be evaporated to arrive at core uncovery.

The values presented in Appendix A are based on the results obtained from the RELAP4 analysis, and core uncovery occurs at 1880 seconds. By applying the method as used by Sheron core uncovery would be calculated, for this case at 1400 seconds.

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The hand calculation would result in a core uncovery time of 1400 seconds.

versus the 1880 seconds time from the analysis with RELAP4..

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h secondary side mass iriventory discrepancy should be investigated to determine where the error originated.

It appears that the secondary side

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model currently used for small break LOCA analysis with RELAP4, is not sufficient to adequately describe the system performance. The error should be identified and corrected and a suitable model should be developed for future small break LOCA analyses.

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Table 1 MAJOR EVENT SEQUENCES RELAP4 Babcock C Wilcox 177 FA-LL Loss of Power Transient Event 2250 psia Trip 2430 psia Trip Tine of reactor scram 0.2 - 0.25 seconds 20 seconds Time at which heat added by core exceeds heat removed by S.G.s 440 seconds 1 second Time at which PORV opens 480 seconds 20 seconds Time at which safety relief valves open 1350 seconds

20 seconds Time at which S.G. secondaries are dry 1040 seconds 380 seconds Time at which core begins to uncovei-1880 seconds 1040 seconds i

l NOTES: * - SRVs open for a short period of time at 950 seconds, primary system pressure then drops below set point until 1350 seconds when the entire primary reaches 2500 psia.

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s APPENDIX A

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Part 1. Time required to dry out S.G. secondaries Initial mass inventory m=53,145 lba Themodynamic properties 18 (psia) 860.

1060.

h (BTU /lba) 520.0 551.6 g

h (BTU /lbm) 1197.7 1190.7 Q

= m x dh = 53145[ (1190.7-551.6) + (551.5-520.0) ]

gg

= 3.57 x10 BTU From Appendix 6B(decay heat calculation) with reactor trip at 0.0 seconds TD0 = 475 seconds assume 0.2 to a 0.25 trip delay would result in a full power heat input of QFP = 0.22 x10 ETU, therefore DO = 440 seconds (Figure 16 shows that the decay heat exceedes the heat removal capacity of the S.G.s at approximately 440 seconds)

Part 2. Time required to bring primary system up bo SRVs set-point of 2500 psia Initial system condition 2120 psia, 620 F, pressurizer near full From Tabel A-1, System Volumes are 11,318 ft liquid 775 ft steam 12,093 ft total primary volume l

U-A-2 Thennodynamic properties P (psia) 2120.

2500.

Temperature 620 F h (BTU /lbm) 644.

v (ft /lbs) 0.024333 Temperature (saturation) ( F) 644.1 668.1 h (BTU /lbm) 686.1 731.7 p

h (BTU /lbm) 1128.9 1093.3 v (ft /lbm) 0.026259 0.028594 g

v (ft /lba) 0.172472 0.13068 Initial mass inventory m = V /v = 12093/0.024333 = 4.97 x10 lbm Final volume after expansion of fluid V g=m9 g=

14,211 ft v

therefore (14211-12093) = 2,118 ft must be released through the PORV and SRVs, or the equivalent mass m

= (V -V,./v g

= 8.7 x10 lba (Figure 14 m

= 9.5 x10 lba released through PORV and SRVs)

Q

=m x dh = 4.97 x10 ( 731.7 - 644. ) = 4.33 x1G BTU pp

9DO + 9PP FP = 7.68 x10 BTU

~O SUM Heat added to the core and primary system metal is taken from the RELAP4 analysis at 1300 seconds, Q

= 5.0 x10 BTU CM QSUM " OSUM^9CM "

From Appendix B, T

= 1400 seconds pp (Figure 14 T

= 1350 seconds) pp

r A-3 Part 3. Time required to start core uncovery From Table A-1, volume above core is 8611.3 ft (excluding pressurizer and surge line). The RELAP4 analysis allows for the drainging of the surge line, 3

therefore v~gg = 8681.3 ft.

Figure A-1 is provided to show the geometric relationship ot' the primary sys', ems nodes (by area and elevation) with respect to the top of the reactor core and with respect to the surge line elevation.

The mass of water to be evaporated to uncovery the core is

= 8681.3/0.13068 ft /lba = 6.64 x10* lbm a

QCU " "o x dh = 6.64 x10 ( 1093.3-731.7 ) = 2.40 x10 BTU At the time of core uncovery the stored heat in the core and primary metal is taken from the RELAP4 analysis as QCM = 8.06 x10 BTU

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= m,g xv gg 3

therefore only (86?l.3-1452) = 7230 ft is evaporated 1

QCU = (7230/O.13068)(1093.3-731.7)

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1971 ANS INTEGRAL DECAY

EAT CALCULATION 0

0 INI71AL POWER LEVEL IS 2689.**Tw 0

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ML19312E437

Text

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