ML20054F882
ML20054F882 | |
Person / Time | |
---|---|
Site: | Midland |
Issue date: | 06/10/1982 |
From: | PLG, INC. (FORMERLY PICKARD, LOWE & GARRICK, INC.) |
To: | |
Shared Package | |
ML20054F881 | List: |
References | |
RTR-NUREG-0737, RTR-NUREG-737 PLG-0147, PLG-147, NUDOCS 8206180088 | |
Download: ML20054F882 (49) | |
Text
Revis:d June 10, 1982 TABLE 6.
NRC FAILURE DATA Events (x 10-6)
MTTR Q ([' mand) WASH-1400 Event CSTIGLOR
.0001 360 PTKCONDF J001A05F 0,.037, 1.0 JH00 J001A06F 0,.037, 1.0 JH00 J001BP3F JF00 J001BP4F JF00 J001B55F JF00 J001856F JF00 J001011F JK00 J001021F JK00 1 x 10-4 PCY0157C PCV00010 PCV00130 1 x 10-4 PCV0157C 1 x 10-4 PCV0142C PCV00150 1 x 10-4 PCV0142C PCV00250 1 x 10-4 PCV024-D PCV075-D 1 x 10-4 1 x 10-4 PCV076-0 2 x 10-4 PCV0133, 131C PCVU53AD 2 x 10-4 PCV0137, 138C PCVU53BD PLV75 AID
- 3.2 x 10-3 PLV75A20*
3.2 x 10-3 PLV75B1D*
3.2 x 10-3 3.2 x 10-3 PLV75B2D*
PM0105AA 4 x 10-3 PST3ACNT PM0177AA With Valve PM0177BA With Valve 1 x 10-4 PMVMS02C PM03126C PM075A1A With Valve PM075A2A With Valve PM075B1A With Valve PM075B2A With Valve PM08931A With Valve PM08932A With Valve PM08933A With Valve PM08934A With Valve 3.2 x 10-3 PMV177AD*
3.2 x 10-3 PMV177BD*
PMV3856C 1 x 10-4 3.2 x 10-3 PMV865AD*
PMV865BD*
3.2 x 10-3 1 x 10-4 PMV868AC PMV868BC 1 x 10-4 PMV870AD8 3.2 x 10-3
- Q(Demand) includes motor-operator, valve mechanical, and actuation relay failure rates.
8206180008 820616 PDR ADOCK 05000329 A
PDR 0213A060882
Revised June 10, 1982 TABLE'6 (continued)
Events (x 10-6)
MTTR Q (Demaad) WASH-1400 Event PMV870BD*
3.2 x 10-3 PMV89310*
7.2 x 10-3 7.2 x 10-3 PMV89320*
7.2 x 10-3 PMV89330*
7.2 x 10-3 PMV8934D*
1 x 10-3 PPW W3AA PPM 105AF PPM 105BF 1 x 10-3 PPMTURBF PSTM00AF With Valve PSTM00BF With Valve PSTM05AF With Valve PSTM05BF With Valve PTB1G05A 4 x 10-3 PXV001AC 1 x 10-4 PXV0168C 1 x 10-4 PXV0153C PXV001BC 1 x 10-4 PXV0002C 1 x 10-4 PXV0004C 1 x 10-4 PXV0014C 1 x 10-4 PXV0017C PXV009A0 5 x 10-4 PXVTESTY PXV00980 5 x 10-4 PXVTESTY 1 x 10-4 PXV037-C PXV278-C 1 x 10-4 PXV279-C 1 x 10-4
- Q(Demand) includes motor-operator, valve mechanical, and actuation relay failure rates.
Note: All other events were contained in th'e events listed above, therefore, no failure rates were assigned. All data taken from WASH-1400 or NUREG-0611.
0213A060882
.e Revised June 10. 1982
=,
TABLE 9.
PUMP TRAIN UNAVAILABILITY DUE TO TEST AND MAINTENANCE ~
l mo" Q maintenance turbine = 4.5
- 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />
= 5.78 x 10-3 n ns x,3 h rs Q maintenance motor
= 5.78 x 10
=
4.5 months ct
- 73 ours Q test turbine
= 15 minutes hour month
= 3.42 x 10-4 x
m nth 60 minutes 730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> (operator error)
Q test motor
= 15 minutes hour month
= 3.42 x 10-4 x
x month 60 minutes 730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> (operator error)
System Unavailability Due to Test and Maintenance Q systemT+M = (Q maintenance turbine + Q test turbine)
(Q systEa with turbine pump down)
+ (Q maintenance motor + Q test motor)
(Q system with motor pump down) 0215C060982
_h--.
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9 MIDLAND AUXILIARY FEEDWATER SYSTEM -
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MIDLAND UNITS 1 AND 2 G 2510 217
Pickard, Lo a and Garrick, Inc.
'. Jur}e,10, 1982 COW ARISON OF DOUBLE CROSSOVER AND THREE 100 PERCENT CAPACITY PUMP AFW DESIGNS A reanalysis of the Midland auxiliary feedwater system ( AFWS) was performed to evaluate a proposed modification which adds a third 100 percent capacity pump.
Figures A and B present the simplified fault trees which were used to quantify these AFW analyses. Table A presents the point value failure rates used for these analyses.
The results of the analyses are presented for two cases:
failure of the AFWS on demand; and failure of the AFWS within 15 minutes. These results are compared to the double crossover design presently installed at Midland. Each case is analyzed for three initiating events:
loss of main feedwater; loss of offsite power; and loss of all AC power.
Tables B-1 and B-2 present the results of the analyses and the comparisons for each of the initi. ting events and cases analyzed.
The assumptions used for these analyses are based upon discussion with the author of NUREG-0611 on January 26, 1982. The major assumptions are:
1.
A value of 3.7 x 10-2 is used as the frequency of failure of a single EDG based upon Table 11-5.3 of the RSS (WASH-1400).
(NUREG-0611 analysis used a value of approximately 3 x 10-2.)
No diesel recovery is included in these analyses.
2.
The unavailability of an AFW pump due to maintenance is 5.78 x 10-3 based upon NUREG-0611.
3.
Operator recovery from some failures is included. The time allowed for operator recovery is approximately 15 minutes for motor-driven pump failure and 5 minutes for turbine-driven pump failure (the time to dry out of the steam generators was used in NUREG-0611 analysis).
4.
The 'ailures which are recoverable by operator action and the actions l
required are:
a.
Loss of the Emergency Diesel Generator Supply to Bus 1A05 (Double Crossover Design). Operator action consists of starting the motor-driven AFW pump on bus 1A06. This action must be taken at bus 1A06 (the switchgear room), and requires the use of the
" kirk-key" for the motor-driven AFW pump breaker.
b.
Overspeed Trips of the Turbine-Driven AFW Pump. Two basic operator actions are required; in the control room, the trip and throttle valve must be closed; in the turbine-driven pump room the mechanical overspeed trip must be reset.
1 l.
1 0216C060982 i
a.
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I Based upon a review of Nuclear Power Experience (NPE), approximately 50 percent of the turbine-driven pump failures to start are recognized and recovered by plant operators within a short period of time. Recoverable failures are of two general types; overspeed trips on initial start, and inadvertant trip and throttle valve closures prior to pump start.
5.
All Operator Frequencies of Error Are Based Upon the Following Assumptions a.
The plant procedures for loss of main feedwater present the indications available to the operator for determining a loss of auxiliary feedwater flow.
b.
The loss of main feedwater procedures includes the recovery options available to the operator for a loss of auxiliary feedwater flow.
"c The operators are trained to recognize the symptoms of a loss of auxiliary feedwater flow and the cause of the loss of flow.
d.
Operator training has been carried out on the procedures for starting the motor-driven AFW pump on the opposite Class 1E bus.
e.
The operator priorities for a loss of main feedwater flow are:
(1) Recover auxiliary feedwater flow.
(2) Control RCS temperature using feed and bleed methods.
(3) Recover power to the Class 1E buses.
6.
The Auxiliary Feedwater Actuation System (AFWAS) Signal is Present During AFW pump testing, a full flow recirculation test valve is opened to allow full AFW flow at the rated pump discharge pressure to flow to the condensate storage tank. Upon a system demand, the full flow test valve must be closed to allow AFW pump flow to discharge to the once through steam generators (OTSGs). The full flow test valve is manually operated and is located in the vicinity of the associated AFW pump. The plant test procedure requires that an operator be present at the full flow test valve during testing. Because the associated AFW pump is running during the test, operator action is to close the full flow test valve will allow flow from the associated pump to go to the OTSGs. The frequency of operator error assigned for the demand case is 0.9.
The frequencies of operator error assigned for the 15-minute time limit are:
for the turbine-driven ptsnp, 0.01; and for the motor-driven pump, 0.005. The differences in 1
the error rates are due to the once through steam generator dryout time effect on the turbine-driven AFW pump.
Recovery from the identifled common cause failure of the AFW pump trains is also considered. This failure also involves the full flow test valves. The basic error consists of a common cause failure to reclose the test valves for both pump trains after pump testing.
2 0216C060982 l
t Recovery of this error prior to system actuation on demand is included in the frequency of system failure due to this cause.
Recovery from this failure may also occur after system demand.
Operator action to close the full flow test valves will allow pump flow to pass to the OTSGs. The indications which are available to the operators in the control room to diagnose this problem are:
test valve position indication, pump discharge pressure, and flow to the OTSGs. Recovery consists of sending an auxiliary operator to the AFW pump area to close the test valves. No recovery is quantified for i
the demand case. For the 15-minute time limit case, the frequency of operator error is 0.005.
4 r
3 0216C060982
i TABLE A.
NRC FAILURE DATA (Three 100% Pumps)
Events (x 10-6)
MTTR Q(Demand)
WASH-1400 Event IPPSW-AF 0
IPPSW-BF 0
IRUPTLUF 0
CSTIGLOR
. 0001 360 PTKCONDF J001A05F*
0,.037, 1 JH00 J001A06F 0,.037, 1 JH00 J001BP3F 0
J001BP4F 0
J001B55F 0
J001B56F 0
J001011F 0
J001D21F 0
PCV030AD 1 x 10-4 PCV0157C 1 x 10-4 PCV0157C PCV030B0 PCV031AD 1 x 10-4 PCV0142C PCV031BD 1 x 10-4 PCV0142C PCV032AD 1 x 10-4 PCV032BD 1 x 10-4 PCV032CD 1 x 10-4 PCV034AD 1 x 10-4 1 x 10-4 PCV034BD 1 x 10-4 PCV035AD 1 x 10-4 PCV035BD PCY024-D 1 x 10-4 PCV075-0 1 x 10-4 PCV076-D 1 x 10-4 PCVU53AD 2 x 10-4 PCV0133, 131C PCVU53BD 2 x 10-4 PCV0133, 138C 1 x 10-3 PHUO20AC 1 x 10-3 PHU020CC 3.4 x 10-3 PLV75 AID PLV75A2D 3.4 x 10-3 PLV75B1D 3.4 x 10-3 PLV75B2D 3.4 x 10-3 PMV177AD 3.2 x 10-3 3.2 x 10-3 PMV177BD PMV3856C 1 x 10-4 PMV865AD 3.2 x 10-3 PMV865BD 3.2 x 10-3 PMV868AC 1 x 10-4 1 x 10-4 PMV868BC 3.2 x 10-3 PMV870AD
- Values for J001A05F, J001A06F change depending upon the initiating event. LOMF: J001A05F, J001A06F = 0.0; LOOP:
J001A05F, J001A06r = 0.037; LOAC: J001A05F, J001A06F = 1.0.
4 0215C060182
TABLE A (continued)
Events (x 10-6)
MTTR Q(Demand)
WASH-1400 Event 3.2 x 10-3 PMV870BD PMV9831D 7.2 x 10-3 7.2 x 10-3 PMV9832b PMV9833D 7.2 x 10-3 PMV98340 7.2 x 10-3 1 x 10-4 PMV856AC PPM 105AF 5.0 x 10-3 PPMFW3AA 1.0 x 10-3 PPMTURBF PPM 105BF 5.0 x 10-3 PPMFW3BA PPM 105CF 4 x 10-3 PTB1G05A PXV001AC 1 x 10-4 PXV0168C 1 x 10-4 PXV0153C PXV001BC 1 x 10-4 PXV003A PXV0038 1 x 10-4 1 x 10-4 PXV111A PXV1118 1 x 10-4 PXV009A0 5 x 10-4 PXVTESTY 5 x 10-4 PXVTESTY PXV009B0 5 x 10-4 PXVTESTY PXV009C0 PXV037-C 1 x 10-4 1 x 10-4 PXVDVLAC PXV003CC 1 x 10-3 1 x 10-4 PXV096A PXV0968 1 x 10-4 NONRECF*
0.5, 1.0 RECFAIL*
0.5. 1.0 5 x 10-3 OPERRORS*
POPERRTU*
0.1. 1.0 N0SIG-A NOSIG-B l
- The first value shown is used in the 15-minute recovery cases j
analyzed.
Note: All other events were contained in the events lised above, therefore, no failure rates were assigned. All data taken from WASH-1400 or NUREG-0611.
l l
l 5
5 0215C060982
TA8LE B-1.
COMPARISON USING NRC DATA THREE 100% AND DOUBLE CROSSOVER DESIGN (No Recovery of Failures)
DC0 Three Pump loss of Main Feedwater Random 3.3 x 10-5 4,4 x 10-7 Maintenance 6.6 x 10-5 7.3 x 10-7 Test 3.5 x 10-6 3.9 x 10-8 Common Cause 8.4 x 10-6 8.4 x 10-6 System 1.1 x 10-4 9.6 x 10-6 Loss of Offsite Power Random 2.5 x 10-4 1.2 x 10-5 Maintenance 2.8 x 10-4 1.4 x 10-5 Test 1.5 x 10-5 7.3 x 10-7 Common Cause 8.4 x 10-6 8.4 x 10-6 System 5.5 x 10-4 3.5 x 10-5 Loss of All AC Random 6.2 x 10-3 6.2 x 10-3 Maintenance 5.8 x 10-3 5.8 x 10-3 Test 3.1 x 10-4 3.1 x 10-4 Common Cause 8.4 x 10-6 8.4 x 10-6 System 1.2 x 10-2 1.2 x 10-2 6
0215C060982
TABLE B-2.
C0WARIS0N USING NRC DATA THREE 100% AND DOUBLE CROSS 0VER DESIGN (Recovery of Certain Failures Within 15 Minutes)
DC0 Three Pump Loss of Main Feedwater Random 2.3 x 10-5 3.4'x 10-7 Maintenance 5.6 x 10-5 6.0 x 10-7 Test 2.6 x 10-8 2.7 x 10-10 Common Cause 4.2 x 10-8 4.2 x 10-8 System 7.8 x 10-5 9,9 x 10-7 Loss of Offsite Power Random 3.0 x 10-5 8.5 x 10-6 Maintenance 6.5 x 10-5 1.3 x 10-5 Test 3.2 x 10-8 7.0 x 10-9 Common Cause 4.2 x 10-8 4.2 x 10-8 System 9.5 x 10-5 2.1 x 10-5 Loss of All AC Random 4.4 x 10-3 4,4 x 10-3 Maintenance 5.8 x 10-3 5.8 x 10-3 Test 3.4 x 10-6 3.4 x 10-6 Common Cause 4.2 x 10-8 4.2 x 10-8 System 1.0 x 10-2 1.0 x 10-2 7
0215C060982
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