ML060950067
| ML060950067 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/30/2006 |
| From: | Cullen G Energy Northwest |
| To: | Brian Benney Office of Nuclear Reactor Regulation |
| References | |
| Download: ML060950067 (75) | |
Text
I Brian Benney - Columbia RCIC Room Temp Calculation for SBO Page 1 I Bra Bene Co.i
,I Roo Tem Caclto fo SB Pag 1 From:
"CULLEN, GREGORY V." <GVCULLEN~energy-northwest.com>
To:
"Brian Benney" <BJB@nrc.gov>
Date:
3/30/06 8:43PM
Subject:
Columbia RCIC Room Temp Calculation for SBO
- Brian, Per the Staff's request, please find attached the Calculation performed for the Room Temperature rise in the RCIC room during an SBO condition.
Please note that the method NUMARC 87-00 uses predicts conservative temperature conditions that are steady state, thus these results are valid for a continuous time period (well beyond the current coping time). Also included in the Calculation is the temperature rate of rise which allows a determination of the time available to perform any compensatory actions such as opening of the RCIC room doors.
The original calculation was modified by a Calculation Modification Record to include the effects of the RCIC barometric condenser issue raised in 1998. The increase in temperature has raised the steady state level frcm 131 F to 136 F with the RCIC room door open or from 133 F to 141 F with the RCIC room doors closed. I have included the CMR summary describing this condition and the results.
These values (RCIC room door open or closed) remained below the RCIC room equipment's qualification of at least 150 F.
Please also note that the design of the RCIC turbine governor electronic control module is located outside the RCIC room and is located in the remote shutdown room in the vital switchgear area in the Rad Waste building and will not see these temperature extremes during an SBO.
Greg Cullen Licensing Supervisor Columbia Generating Station This e-riail message and all attachments transmitted with it are for the sole use of the intended recipient(s) and may contain confidential and/or legally privileged information. Please DO NOT forward this e-mail outside of the recipient's company unless expressly authorized to do so herein. Any unauthorized review; use, disclosure or distribution is prohibited. If you are not the intended recipient, please contact the sender by reply e-mail and destroy all copies of the original message.
Warning: Although Energy Northwest has taken reasonable precautions to ensure no viruses are present in this e-mail, the agency cannot accept responsibility for any loss or damage arising from the use of this e-mail or its attachments.
CC:
<dxt @ nrc.gov>, "RHOADS, JERRAL E." <JERHOADS @ energy-northwest.com>
I c:\\temp\\GW)00001.TMP Page 1 I.
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Columbia RCIC Room Temp Calculation for SBO 3/30/06 8:42PM "CULLEN, GREGORY V." <GVCULLEN@energy-northwest.com:>
GVCULLEN@energy-northwest.com Recipients nrc.gov OWCrWPOO 1.HQGWDOO1 BJE; (Brian Benney) nrc.gov TWGWPOO2.HQGWDOO1 DXT CC (David Terao) energy.-northwest.com JERHOADS CC (JERRAL E. RHOADS)
Post Office OWGWPOO1.HQGWDOO1 TWGWPO02.HQGWDOO1 Route nrc.gov nrc.gov energy-northwest.com Files MESSAGE TEXT.htm Cal ME-02-89-21.pdf Cal Appendix A.pdf Cal Attachment I.pdf Cal MODs.pdf Mime.822 Options Expiration Date:
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- N.t C r u/>tJ r< )'1tl' VOL(J) THEN I = J 296 NEXT J 298 ELMIN = ELEV(I-1) + (ELEV(I)-ELEV(I-l))/(VOL(I)-VOL(I-1))*(VL-VOL(I-1))
300 T=TANKTr:GOSUB 10020:VFTANK=VF 310 VLMIN = VL 320 VV =
SYSVOL -
VL 325 REM Calculate SRV flow area 330 GOSUB 9p010 335 REM Calaculate SRV flow 340 GOSUB 3140 350 T = TPOOL 360 GOSUB :10020 370 POOLMASS = VPOOL/VF 380 POOLENG = POOLMASSP(TPOOL -
32!)
390 T=TCOL 395 FPOW= 1 400 GOSUB 10020 410 LMASS = VL /VF
420 SMASS VV/VG
)
430 NPRINT = 0 440 FILL - GRCIC + GHPCI 500 CLS 510 PRINT::PRIN'T:PRINT STATION BLACKOUT STUDY 520 PRINT" SYSTEM VOLUME = ";SYSVOL:PRINT " VLIQ = ";VL:PRINT VAPOR VOL =";VV:
PRINT " MASS LIQ = ";LMASS:PRINT " MASS STEAM = ";SMASS
)
530 PRINT " FLUID MASS (KIPS) = ";(LMASS+SMASS)/1000 540 LENERGY = LMASS : EF 545 REM Calculate Full Power Heat Rate 550 SENERG;Y = SMASS
- EG 560 ETOTAI.
(LENERGY + SENERGY) 570 QO = 10 A1000!*3413/3600!
590 TDQ =0!
600 OPEN "ADS.DAT" FOR OUTPUT AS f1 610 TDQ=1 1000 REM MAIN ITERATIVE LOOP 1005 DT =.15/FPOW:IF DT <.25 THEN DT =.25 1010 TIM TIM -
DT 1020 L = (
1030 K=0 1040 FOR J
= 1 TO NDHP 1050 IF TIM <= D(1,J) THEN 1070 1060 K = J 1070 NEXT 1080 REM Decay Heat 1090 Xl=LOG(D(1,K)):X2=LOG(D(1,K4-l))
1100 Z1=LOG(D(2,K)):Z2=LOG(D(2,K'-1))
1110 FPOW = EXP(Z1 (Z2 -Z1)/(X2 -
XI) * (LOG((TIM -
DT/2!)) -XI))
1120 DQ = FPO1'
- QO
- DT 1130 TDQ TDQ + DQ 1140 FPS FPS + FPOW
- DT 1150 REM ':RV Mass & Energy 1160 GOSULI 9140:SRVMASS = (SRV-ADSFLOW)*DT:SRVENG =SRVMASS*HG 1170 REM P1CIC INJECTION 1175 IF RVP > POFF THEN MRCIC = 0!:GOTO 1274 1180 IF TIM < TCP THEN GOTO 1250 11'90 IF TPOOL > TPS AND VPOOL. < VPMAX THEN GOTO 1250 1200 TZ=T:T=TPOOL:GOSUB 10020 1210 TRCI(' =TPOOL 1220 T=TZ 1230 VFRCIC = VF 1240 GOTO 1270 1250 TRCIC = TANKT 1260 VFRC]:C = VFTANK 1270 IF TIM => SRCIC THEN MRCIC = FILL/7.481/VFRCIC*DT/60 ELSE = 0.0
)
1274 IF TIM < SDEP THEN 1280 i275 IF SRVMASS > MRCIC AND MRCIC > 0 THEN MRCIC = SRVMASS 1280 ERCIC: = MRCIC*(TRCIC -
32!)
)
1290 REM MASS AND ENERGY BALANCE 1300 ETOTAL ETOTAL + DQ -
SRVENG + ERCIC 1310 LMASS = LMASS + MRCIC 1320 SMASS = SMASS -
SRVMASS 1330 POOLMIASS
= POOLMASS +SRVMASS 1340 POOLENG POOLENG 4 SRVENG j
1350 IF TRCIC = TPOOL THEN POOLMASS = POOLMASS -
MRCIC:POOLENG = POOLENG -
ERCIC 1360 TPOOL
= POOLENG/POOLMASS + 32!
1370 REM Determine coolant temperature and pressure J
1380 TRIAL = T 1390 TRIALl =TRIAL 1400 GOSUEI 10020 J
1410 MASS = LMASS + SMASS 1420 X = (SYSVOL - MASS*VF)/(MASS*(VG -
VF))
1430 ECALC =
(1!-X)*MASS*EF + X*MASS*EG
)
1440 EERR = ETOTAL -
ECALC 1450 IF AEIS(EERR/ETOTAL) <.001 THEN 1520
1460 1470 1480 1490 1500 1510 1520 1530 1540 1550 1560 1570 1580 1590 1600 1610 1620 1630 1640 1650 1660 1670 1680 1690 1700 1710 1720 1730 1740 1750 1760 1770 1780 RCIC 1790 POOL 1800 1810 1820 1822 1824 1825 1826 1828 1829 1830 1840 1850 1860 1870 9000 9010 9020 9030 9040 9050 9100 9110 9120 9130 9140 9150 9160 9170 9180 91.90 TRIAL = TRIALl TRIALI TRIAL +SGN(EERR)*.25 T
TlIAL1 L= L + 1 IF L < 20 GOTO 1400 REM Calculate liquid & steam mass and pool water volume RVP = P LMASS = (1! -
X)*MASS SMASS = X
- MASS VL =
LMASS*VF IF VL => VLMIN THEN 1590 VLMIN = VL TMIN :=TIM TZ = T:T = TPOOL:GOSUB 10020 VPOOL = POOLMASS*VF T = TZ NPRINT NPRINT -
1 IF NPRINT < NPROUT THEN 1010 PRINT "
WNP2 STATION BLACKOUT STUDY" PRINT:PRINT "
TIME = ";TIM;" seconds":PRINT:PRINT:
PRINT PRINT PRINT PRINT PRINT PRINT PRINT PRINT PRINT PRINT PRINT PRINT Temp
" Press
" Decay Heat (full power seconds)
" Total Decay Heat (BTL')
n Fractional Power
" Liquid Mass
" Steam Mass
" Fraction Steam
" SRV Flow (lb/sec)
" SRV Energy removal (BTU/sec)
" Decay Heat (BTU/sec)
" RCIC Flow (Lb/sec)
= of;T
= ";RVP
= ";FPS
= "TDQ
= ";FPOW
= ";LMASS
= ";SMASS
= ";SRVMASS/DT
= ";SRVENG/DT
= ";DQ/DT
= ";MRCIC/DT;"
RCIC Temp = ";T Pool Volume = ";V PRINT " Pool Mass
= ";POOLMASS;"
PRINT " Pool Temp
= ";TPOOL PRINT Minimum Vessel Vol
= ";VLMIN;"
- ";TMIN;" SEC's" PRINT " Vessel Liquid Volume
= ";VL FOR J = 1 TO 10:IF VL s VOLCI) THEN I = J:NEXT EL = EILEV(I-1) ; (ELEV(I)-ELEV(I-1))/(VOL(I)-VOL(I-l))*(VL-VOL(I-1))
PRINTIII,TIM,T,LMASS,TDQ,RVP,TPOOL,SRVMASS/DT,MRCIC/DT IF EL < ELMIN THEN ELMIN = EL PRINT
" Collapsed water elevation
= ";EL PRINT
" Min collapsed water level
= ";ELMIN;" c time = ";TMIN NPRINT = 0 IF TIM => TMAX THEN END IF VLMIN => TAF THEN GOTO 1000 PRINT "
water level is below TAF END REM Safety Relief Valve Diameter = 4.84 in.
AVALVL = 3.14159
- 4.84^2 /4 A(1) 2!
- AVALVE FOR I = 2 TO 5:A(I) = 4! A AVALVE:NEXT AADS NDP!
REM K::0.9*Kd;Kd=0.87 REM flow =(51.5*0.9*0.87)*A*P = 40.3245*A*P KV=40.. 3245 IF TIM => SDEP THEN 9270 FOR N: 1 TO 5 IF SFI.OW(N) = 0 AND RVP > SRSET(1,N) THEN NOPN(N) = NOPN(N) + 1 IF NOI'N(N) > NSRV THEN SRSET(1,N) = SRSET(3,N):SRSET(2,N)=SRSET(4,N)
NEXT
9200 FOR N = 1 TO 5:IF RVP => SRSET(1,N) OR SFLOW(N) > 0! THEN SFLOW(N) = XV *RV
)
P
- A(N) 9210 NEXT 9220 FOR N = 1 TO 5:IF RVP < SRSET(2,N) THEN SFLOW(N) = 0!
)
9230 NEXT 9240 SRV=0!:FOR N = 1 TO 5:SRV SRV + SFLOW(N):NEXT:SRV = SRV + ADSFLOW 9250 SRV - SRV/3600!
l 9260 RETURN 9270 IF RVP > MAXP OR ADSFLOW > 0! THEN ADSFLOW = KV
- RVP
- AADS/3600! ELSE ADS FLOW = 0!
K 9280 SRV = 0!
9290 IF RVP < MINP THEN ADSFLOW=0!
9300 RETURN 1
10000 REM STEAM & WATER PROPERTIES 10010 REM LIQUID DENSITY 10020 Z=LOG (T) 10030 IF l'<=400! THEN P = -27.763 -
Z*(23.7433 + Zf(-8.696379 + Z'(1.41067 -
Z*7
.776381E-02))) ELSE P = -30.1085 Z*(8.31929 + Zt(-.736689 + Z*(.0846587 -
Z*4.
65022E-03)))
I 10040 P=EXP(P) 10050 IF T<=400! THEN VF =.0903737 -
Z*(-.0694378 -
Z*(.0242644 -
Z*(-3.76979E-03 + Z*2.20412E-04))) ELSE VF =.537042 + Z*(-.164 + Z*(.0174162 -
Z*(-1.80483E-
)
03 + Z*1.7639E-04)))
10060 IF T<=400! THEN VG = 25.9245 -Z*(-16.8828 + Zt(6.35612 + Zt(-1.06006 + Zt.
0587298))) ELSE VG = -.653905 + Z*(3.31586 + Z*(-.450342 -
Zt(.0161685 -
Z*4.581
)
17E-03)))
10070 VG = EXP(VG) 10080 IF T<=400! THEN HF = 2068.48 Z"(-2011.26 s Z+/-(726.624 - Z*(-117.646 + Z*
7.43066))) ELSE HF = 9238.74 -
Zt(-3030.65 - Z*(330.586 + Zt(-32.5873 + Z*3.4437 2)))
10090 IF T<=400! THEN HG = -1043.94 ' Zt(1910.76 + Z*(-640.327 + Zt(93.7205 -
Z*
4.94574))) ELSE HG = -10684.8 1 Z*(3606.67 -
Z*(-350.019 + Zt(33.1046 -
Z*3.3211 9)))
10100 EG HG -
Pt.18509*VG I
10110 EF HF -
P*.18509*VF 10120 RETURN 11000 REM DECAY HEAT DATA 11010 REM TIME,SEC 11020 DATA 0.00001,0.9,2.1,5.,6.93,9.03,15.93,30.,100.,150.
11030 DATA. 200.,250.,300.,350.,400.,450.,500.,600.,700.,800.
11040 DATA 900.,1000.,2000.,3000.,10000.,100000.
11050 REM DECAY HEAT FRAC.
11060 DATA 1.0,0.9330,0.7662,0.5005,0.385,0.2955,0.1491,0.0471,0.04267,0.03928 11070 DATA 0.03588,0.03465,0.03342,0.03218,0.03095,0.03020,0.02945,0.02795,0.027 00,0.02604 11080 DATA 0.02533,0.02463,0.02089,0.01893,0.0119,0.00668 12000 REM SRV RELIEF SETPOINTS (ON,OFF) 12010 DATA 1091.,1041.,1101.,1051.,1111.,1061.,1121.,1071.,1131.,1081.
12020 REM SRV SAFETY SET POINTS (OPEN,CLOSE) 12030 DATA 1163,1113,1175,1125,1185,1135,1195,1145,1205,1155 12050 REM volume vs elevation data 12060 DATA 0,18.026,30.525,36.88,40.79,42.08,46.9,48.92,54.,72.54
)
12070 DATA 0,4914.,8124.,10335.,11681.,12079.,13571.,14282.,15837.,21005.
)
i?&o. 0 APPENDIX C INITIATIVE 5 COPING WITH A STATION BLACKOUT EVENT
INITIATIVE 5 COPING WITH A STATION BLACKOUT EVENT APRIL 1989 Prepared by: ______
R.L. Heid D.T[ Thonn
PURPOSE The intent of this initiative is to assess the capability of WNP-2 to mainiain adequate core cooling and appropriate containment integrity during a sta:ion blackout in accordance with the requirements of NRC Regulatory Guide 1.155 (Ref.
1), NU1MARC 87-00, Section 7 (Ref 2). NRC approved guidelines and procedures for assessing station blackout coping capability, has been utilized for this review.
The coping method utilized at WNP-2 is the "Alternate AC Approach", however, the "AC-Independent" approach in which available process
- steam, DC power andcompressed air are utilized to operate equipment necessary to achieve safe shutdown conditions until off-site or emergency power is restored is also evaluated.
That is, the analysis addresses both approaches to establish that each is a viable approach to responding to the NRC Station Blackout rule and NUMAC 37-00.
The assessment procedure addresses the following topics:
- 1) Condensate inventory for decay heat removal.
- 2) Assessing the Class IE battery capacity.
- 3) Compressed air.
- 4) Effects of loss of ventilation, and
- 5) Containment isolation.
- 1. CONDENSATE INVENTORY FOR DECAY HEAT REMOVAL The calculation (Ref. 10) to determine the adequacy of condensate inventory for decay heat removal during a station blackout for the required four hour duration was performed in accordance with the procedure outlined in Section 7.2.1 of NUMARC 87-00.
Plant Rating The plant thermal rating as listed in the WNP-2 Operating License is:
3323 MWt. (Ref. 3).
Required Condensate The number of gallons of condensate required for decay heat removal is:
Condensate Required = plant MWt rating x 22.12 gal + C Where C = the gallons required for cooldown, when required by procedure, and system leakage. For WNP-2, C = 30,721.85 gal. (Ref. 10).
The required condensate for a WNP-2 station blackout therefore is:
Condensate Required = 3323 MWt x 22.12 gal + 30,721.85 gals.
MWt
= 104,226 gals.
- 1. 125V DC Battery 81-1 can carry its SBO loading for four hours with 10.9% margin and no load shedding.
margin and no load shedding.
- 3. 250V DC Battery B2-1 can carry its SBO loading for four hours with 12.5% capacity margin provided the following:
A. Feedwater Turbine Emergency Lube Oil Pumps RFT-EOP-1A and 1B must be shed in one hour.
B. Main Turbine Generator Emergency Lube Oil Pump TG-EOP-1 must be shed in two hours.
C. It is desirable, but not necessary, to shed Emergency Gas Seal Oil Pump if it can be done in hours.
the Generator less than four
- 4. t24V with
loading for four hours DC Battery BO-2A and 2B can carry its SBO loading for four hours 3.2% margin and no load shedding.
- 3. COMPRESSED AIR The assessment of the availability of sufficient air reserves to ensure the operability of air operated valves required for decay heat removal has been performed in accordance with the guidelines of NUMAC 87-00, Section 7.2.3.
The RCIC, HPCS, ADS systems and containment isolation valves were initially reviewed to identify all air operated valves that would be cycled during a station blackout.
The valves identified by system are:
RCIC EPN FAILURE SIZE POSITION RCIC-V-54 RCIC-V-4 RCIC-V-5 RCIC-PCV-15 RCIC-V-25 RC]V-V-26 II
' II ill lii C
C C
C C
C DESCRIPTION Condensate Valve Condensate Valve Turbine Oil Cooler Water Pressure Control Valve Steam Line Condensate Drain Isolation Valve Steam Line Condensate Drain Isolation Valve Sample Point Isolation Valves RC]C-V-19A 3/4" 0o
ADS MS--RV-3D 6R10 C
ADS Safety Relief Valve MS--RV-4A 6R10 C
ADS Safety Relief Valve MS--RV-4B 6R10 C
ADS Safety Relief Valve MS--RV-4C 6R10 C
ADS Safety Relief Valve MS--RV-4D 6R10 C
ADS Safety Relief Valve MS--RV-5B 6R10 C
ADS Safety Relief Valve MS--RV-5C 6R10 C
ADS Safety Relief Valve Containment Isolation CSP-Y-5 24" 0
Reactor Building to CSP-V-6 24"'
0 Suppression Pool Vacuum CSP-V-9 24" 0
Breakers HSC -
No air operated valves Of the valves listed above, the CSP-5, -6, and -9, valves can be supplied from a Class 1 backup compressed nitrogen system consisting of a ten cylinder header connected to the accumulator normally supplying these three valves and designed to provide a 10 to 15 day nitrogen supply between cyclinder changes.
The accumulator when supplied from the backup header is isolated from the inoperative CAS by a check valve.
The ADS System safety relief valves MS-RV-3D, 4A, 4B, 4C, 4D, 5B, 5C, supply header isolates automatically on loss of air from the normal supply and is supplied from the ADS accumulator backup compressed gas manifold subsystems which provide 150 psig nitrogen from banks of high pressure compressed nitrogen cylinders designed to provide a 30 day supply.
All the RCIC air operated valves, except for RCIC-PCV-15 and RCIC-19A and B, fail closed on loss of air which is also the normal operating position.
There will, therefore, be no effect on system operation due to loss of air to these valves.
RCI:C-PCV-15 maintains cooling water pressure to the turbine lube oil cooler at 75 psig.
On loss of air, the valve would fail open.
System operation, however, would not be effected because of a restricting orifice which would limit flow to design flow rates and a relief valve (RCIC-RV-19) which would prevent overpressurization.
RC:[C-V-19A is a sample line isolation valve that would fail open on loss of air.
The line, however, is also isolated manually in the sample hood.
There would, therefore, be no loss of function or coolant due to a loss of air to the valve.
Since all of the air operated valves identified above have a backup source of compressed nitrogen available to assure operability for at least 10 days or have no effect on system operation, manual valve operation is not necessary or required.
RCIC System The heat generation rates calculated for the station blackout event for the RCIC; pump room are based on electrical equipment loads from RCIC pump room motors and the steam turbine, pump and piping in the room. Based on these loads and using the calculation procedures of Attachment L,
a room temperature of 1310 F was calculated that could be reduced to 123 F with the two room doors open.
(Ref. 10)
In addition to equipment located in the RCIC pump room, instrumentation that would cause RCIC system isolation during a station blackout was assessed.
Automatic isolation of the system is initiated by : 1)
RCIC equipment area and/or pipe routing area high temperature, 2) RCIC equipment area high differential tempreature, or 3) high RCIC steam flow or instrument line breaks.
The temperature elements associated with isolation signals 1) and 21 above are located in the RCIC equipment room and RCIC steam line pipe chase areas with the temperature switches located in instrument rack H13-P642 located on the 501' level of the reactor building.
RCIC steam flow and pressure measuring taps are located on the RCIC steam piping in containment.' Sensing lines exit through containment penetration X-7:1C, D, E, P and X-38C, D E, G and terminate in pressure and differential pressure switches mounted in instrument rack E-IR-P029 located on the 471' level of the reactor building.
Based on the large area and lack of heat generated during a station blackout, no temperature increases are anticipated on the 471' or 501' levels of the reactor building as a result of.a station blackout.
Steam Tunnel No equipment, instrumentation, piping or containment penetrations associated with the operation or isolation of the RCIC system are located in the WN'-2 steam tunnel.
The steam tunnel is therefore not considered a dominant area of concern.
Sumnary The final steady state room air temperatures for the dominant areas are:
AREA TEMPERATURE, r Door Opened Door Closed HPCS Pump Room 123 HPCS Electrical Equipment Room 104 HPCS SW Pump House 151 RCIC Pump Room 131 133
All of the areas evaluated, are below the final temperature of 1800F for which mechanical, electrical and electronic equipment associated with HPCS and RCIC system operation can be assumed to function during a four hour station blackout (Ref. 8).
While opening the RCIC pump room doors has some benefit for temperature reduction, it is not required to satisfy the 180 F criterion.
Based on the above evaluation, no modification or associated procedure changes are required to provide reasonable assurance for equipment operability.
- 5. CONTAINMENT ISOLATION NUMARC 87-00 requires that containment isolation valves be reviewed to ensure that an appropriate containment integrity can be provided during a station blackout event for the required four hour duration should it become necessary.
Appropriate containment integrity is further defined as the capability for valve position indication and closure of certain containment isolation valves is provided independent of the preferred or Class lE power supplies.
The containment isolation valves requiring this capability are those valves that may be in the open position at the onset of a station blackout.
Per NUMAC 87-00 procedure, the list of containment isolation valves was first reviewed and all valves meeting the following criteria were excluded from further consideration:
- 1) Valves normally locked closed during operation.
- 2) Valves that fail close on loss of AC power or air.
- 3) Check valves.
- 4) Valves in non-radioactive closed-loop systems not expected to be breached in a station blackout, and
- 5) all valves less then 3 inch nominal diameter.
Attachment II lists all 267 penetration isolation valves and the CRD lines isolation valves for the 110 containment penetrations listed in the WNP-2 FSAR Table 6.2-16 (Ref. 5).
The initial review of these valves eliminated 204
- valves, which met one or more of the five criterion, from consideration.
Of the remaining 63 valves, 44 valves are motor opera.ted valves that are normally closed and fail as-is on loss of power.
These valves, though not locked closed, are verified closed by procedure before start up and can only be opened manually during the station blackout event.
In addition, any valve position change prior to the station blackout would be annunciated in the control room and corrected.
The normally clcsed fail-as-is motor operated gate valves were, therefore, not considered valves of concern. Exclusion of these valves, although not provided for in NUMAC 87-00, has been found acceptable by the NRC (Ref. 12).
NUHARC 87-00 next requires that isolation valves which must be cycled to maintain safe shutdown during the station blackout be addressed.
Based on WNP-2 Station Blackout Procedures (Ref. 6), both the RCIC and HPCS Systems can be utilized to maintain safe shutdown.
The isolation valves requiring cycling to put the RCIC and HPCS systems in or out of service are:
Penetration Valve No.
Function X-6 HPCS-V-4 HPCS line to Reactor X-31 HPCS-Y-15 HPCS Pump Suction from Suppression Pool X-33 RCIC-V-31 RCIC Pump Suction from Suppression Pool X-2 RCIC-V-13 RCIC line to Reactor X-4L5 RCIC-V-8 RCIC Turbine Steam Supply X-64 RCIC-V-69 RCIC Turbine Cond. Return to Suppression Pool X-4 RCIC-V-68 RCIC Turbine Exhaust HP(CS-V-4 and HPCS-V-15 are both normally closed AC motor operated valves located outside containment which must be opened before the HPCS system can be put in service. Both valves are powered from HPCS Div. 3, MCC 4A, which is operable during the station blackout and can be opened from the control room. Position indication is provided both in the control room and locally by an indicator on the motor operator.
RC!'C-V-8, -13,
-31, -68 and -69 are DC motor operated valves located outside containment.
The valves can be operated as necessary during RCIC system operation from the control. room utilizing power supplied from the Class 1E batteries.
Position indication is provided both in the control room and locally by indicators on the motor operators.
The remaining 14 valves of the 19 identified in Attachment II as containment isolation valves requiring closure capability have been evaluated as shown in Table 1.
Of these 14 valves, only two, RCC-V-21 and either RCC-V-5 or RCC-V-L04 would have to be closed manually if containment isolation were required.
All three of these valves are located about 13 feet above the 501' floor elevation but are easily accessible by a permanently installed ladder -and platform.
Temperatures inthis area 'will not exceed 104 F. The area, during operation, is designated as a radiation zone V (radiation levels greater than 100 mrem/hr) with access secured and controlled.
- Entry, however, is allowed under H.P. supervision, for the short period necessary for valve closure and radiation levels during a station blackout should drop well below 100 mrem/hr.
Based on the above review, all valves identified as "Valves of Concern" or requiring closure can be:
- 1) positioned as necessary for the operation of the HPCS and/or RCIC systems from the control room utilizing DC motor operators and Class 1E battery power or HPCS, Div. 3 power,
- 2) closed to ensure containment integrity either locally by manual operation or remotely utilizing DC motor operators or
- 3) have an isolation valve in series that is capable of closure by either 1) or 2) above.
Position indication for all valves closed manually have local mechanical indication and all DC motor operated valves have DC powered indication in the control room.
Containment integrity can therefore be provided during a WNP-2 station blackout for the required four hour duration and no plant modifications or procedure changes will be required.
Technical Specification Minimum Volume Requirements The two condensate storage tank volume during normal operation is normally a total of about 350,000 gallons with the minimum tank volume required to meet technical specification requirements (Ref. 4) set at 135,000 gallons.
Condensate Storage Tank Based on the above information, the condensate storage tank minimum Technical Specification capacity of 135,000 gallons exceeds the SB0 condensate inventory requirement of 104,226 gallons by 30,774 gallons and if the normal capacity of 350,000 gallons in the condensate storage tanks is considered, an additional 215,000 gallons are available.
The condensate requirements for SB0, therefore, can be met utilizing only the condensate storage tanks.
Additional backup condensate makeup sources will not be required.
The WNP-2 Station Blackout Procedure, PPM 5.4.1 Revision 5, however, calls for transfer of the suction from the CST to the suppression pool.
To be conservative, the calculation assumed the transfer does not take place.
Also the PPM states that cooldown should be initiated.
This is included to be consistent with other procedures and as a reasonable action for a station blackout condition.
However, no specific need to cooldown has been identified for a station blackout as defined in NUMAC 87-00.
The NUMAC document only requires inclusion of the cooldown inventory requirement if the cooldown is required to minimize reactor pump seal leakage and to maintain decay heat removal (Section 7.2.1, step 2).
This is not the case for WNP-2.
Seal failure protection is not required for WNP-2 as the condensate inventory can provide the required 25gpm/pump gross failure leakage term.
For a four hour station blackout adequate decay heat removal can be provided by the HPCS, SRV action and suppression pool.
As such, cooldown in PPM 5.4.1 is a desirable action that can be terminated at any time if inventory becomes a concern. It is not an action that must be taken to assure the core remains covered (for BWRs momentary uncover is acceptable) and decay heat removal is provided which are the basic requirements of the rule (NUMAC 87-00, Section 2.1).
- 2. CLASS 1E BATTERY CAPACITY Battery capacity calculations have been performed pursuant to NUMAC 87-00, Section 7.2.2, to verify that the WNP-2 Class lE batteries have sufficient capacity to meet the station blackout loads.
These calculations verify that the Class 1E batteries have sufficient capacity to meet the station blackout loads for four hours assuming that certain loads on the 250T DC battery B2-1, not needed to cope with a station blackout, are stripped. These loads are identified in Plant Procedures PP 5.4.1.
The capability of the existing Class IE batteries to supply the station blackout (SBO) loads for four hours was evaluated in calculation CMR 86-062 for the SB0 loading conditions described in NUMAC 87-00 and using the battery calculation methods provided in IEEE Standard 485.
These calculations demonstrated that the 1E batteries at their end of life capacity and at *the normal minimum battery room temperature can carry the SBO loads as follow:
TABLE 1 WNP-2 CONTAINMENT ISOLATION VALVES REQUIRING CLOSURE PENLI:.
VALVE CONT.
1 OPERATOR I
1tiTK
}
IOIIUiUr NTS NO.
EPN LOCATION TYPE POWER (See Attached (Note 8)
(Note 8)
Notes 1-9) 22 17A 17B 45,21 119 66 67 5
46 14 MS-V-16 MS-V-19 RFW-V-65A RFW-V-65B RCIC-V-63 CSP-V-9 CSP-V-5 CSP-V-6 RCC-V-104 RCC-V-5 RCC-V-21 RCC-V-40 RWCU-V-I RWCU-V-4 I
0 0
0 I
0 0
0 0
0 0
I I
0 MO MO MO MO MO AO AO AO MO MO MO MO MO MO AC DC AC AC AC Air Air Air AC AC AC AC AC DC Main Steam Line Main Steam Line FW Long Term Isolation FW Long Term Isolation RCIC Turbine Steam Supply R.B. To Wetwell Vac. Brkr.
R.B. To Wetwell Vac. Brkr R.B. To Wetwell Vac. Brkr.
RCC Cont. Supply Header RCC Cont. Supply Header RCC Cont. Return Header RCC Cont. Return Header RWCU Line From Reactor RWCU Line From Reactor
Not:es to Valves of Concern Table
- 1.
MS-V-16, RCIC-V-63, RCC-V-40 and RWCU-V-1 are AC powered isolation valves located inside containment which cannot be closed on loss of AC power and are not accessible for manual closure.
These valves, therefore, remain open during the station blackout event.
Each of the valves, however, are in series with isolation valves that can be closed either manually or by DC powered motor operators such that containment isolation integrity can be maintained.
- 2. MS-V-19 is a DC motor operated valve located outside containment.
The DC powered valve can be closed remotely from the control room or by local manual operation.
Position indication is provided in the control room and locally with an indicator on the motor operator.
This valve is in series with MS-V-16 and its closure assures the isolation of penetration X-22.
- 3. RFW-V-65A & B are AC powered motor operated valves located outside containment in the steam tunnel which cannot be closed on loss of AC power and are not accessible for manual closure because of high steam tunnel temperatures.
These valves remain open during the station blackout event but have no effect on containment isolation integrity because they are the third isolation valve in each feedwater line designed to be closed after the loss of feedwater flow to eliminate by pass leakage.
Two check valves (RFW-V-1OA & B and RFW-V-32A & B) in each line provide containment isolation of penetrations 17A and 17B.
- 4. CSP-V-5, -6, and -9 have spring-to-open, air-to-close operators,:hat would fail open on loss of air.
These valves, however have a dedicated 30 day air supply from a Class 1 storage rack to maintain the valves in a closed position when the normal air supply is assumed lost during the station blackout event.
Valve position indication is provided locally by an indicator on the valve shaft.
The capability of valve closure on loss of air during the station blackout assures the isolation of penetrations X-5, X-66 and X-67.
- 5. RCC-V-104 and RCC-V-5 are AC powered motor operated valves located in series in the RCC containment supply header outside containment.
I3oth of these valves have handwheel operators that can be engaged to close the valve locally. Position indication is provided locally on the motor operator.
The ability to manually close either of these valves assures the isolation of penetration X-5.
- 6. RCC-V-21 is an AC powered motor operated valve located outside containment.
The valve is accessible and can be closed manually by a handwheel on the operator.
Position indication is also provided by an indicator on the motor operator.
This valve is in series with RCC-'-40 and its closure assures the isolation of penetration X-46.
- 7. RWCU-V-4 is a DC motor operated valve located outside containment. The DC powered valve can be closed either remotely from the control room or locally by manual operation.
Position indication is provided in the control room and locally by an indicator on the motor operator.
This valve is in series with RWCU-V-1 and its closure assures the isolation of penetration X-14.
- 8. Definitions:
I 0
MO AO AC DC Inside containment Outside containment Motor operated Air operated AC - normal power si DC power supplied ft upply rom the Class 1E batteries
REFERENCES
- 1. Regulatory Guide 1.155, "Station Blackout", August 1988
- 2.
NIIMARC 87-00, "Guidelines and Technical Basis for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors", November 1987.
- 3.
WNP-2 Operating License, NPF-21
- 4.
WNP-2 Technical Specifications, Paragraph 3.5.2.e.2
- 5.
WNP-2 FSAR, Volume 12, Table 6.2-16 "Primary Containment Isolation"
- 6.
PFPM 5.4.1, "Station Blackout Procedure", February 8, 1989
- 7. Telecon, R.L.
Heid to D. Ross,
Subject:
Steam Tunnel Insulation and Insulation Surface Temperatures", dated March 4, 1989.
- 8.
NUIMARC 87-00, Appendix F, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors", dated October, 1988.
- 9.
Burns & Roe Calculation #9.21.02, Rev. 1, Dated May 11, 1983
- 10.
WFPPSS Calculation #ME-02-89-21, Rev. 0, Dated April 21, 1989
- 11.
Burns & Roe Calculation #9.24.00, Rev. 6, Dated March 28, 1978 12,
- Memo, J.M.
- McGarry, et al to Plant-Specific Station Blackout Licensing Support Meeting Attendees,
Subject:
Station Blackout Licensing Issues, Dated April 26, 1989
- 4. EFFECTS OF LOSS OF VENTILATION The purpose of this assessment is to determine the average temperatures; of domfinant areas containing equipment necessary to achieve and maintain a safe shutdown during a station blackout.
Dominant areas are defined by three factors: 1) their containing equipment normally required to function early in a station blackout to remove decay heat, 2) the presence of significant heat generation terms (after AC power is lost) relative to their free volume, and 3) the absence of heat removal capability in a station blackout without operator action.
For WNP-2, these areas and their respective equipment to be evaluated consist of:
- 1) HPCS rooms - decay heat removal equipment
- a. HPCS Pump Room
- b. HPCS Electrical Equipment Room
- 2) RCIC room - decay heat removal equipment
- 3) Main Steam Tunnel - decay heat removal system isolation instrumentation for high temperature.
The HPCS pump and electrical equipment rooms are not technically considered areas of concern in that cooling is maintained during the station blackout.
The design calculations,
- however, were reviewed to determine room temperatures during an emergency because of their importance to the station blackout reponse.
Station blackout steady state temperatures for the dominant areas of concern, TDAC, were calculated in accordance with NUMAC 87-00 Section 7.2.4.
The calculation procedure is listed in Attachment I.
The results of each dominant area evaluation are as follows:
HPCS System When the HPCS system is operational during the station blackout event, the HVCS ventilation system is also operational because the HPCS pump and diesel room ventilation fans and the HPCS SW pump supplying cooling water to the fan coil units are all powered from the HPCS diesel generator through dedicated HPCS switchgear and motor control centers.
The HPCS switchsgear (SM-4) and motor control center (MCC-4A) are located in the HPCS diesel generator equipment room where cooling is provided by the DMA-CC-31 and DMA-CC-32 cooling coil fan units.
Cooling is provided in the HPCS pump room by fan coil unit RRA-FC-4.
Temperatures in the HPCS Pump Room, HPCS electricalo equipment room and HPCS SW Pump House were calculated to be 123 F, 104 F and 151 F, respectively.
(Ref. 9, 10, 11)
ATTACHMENT I NUMAC 87-00, Section 7.2.4 EFFECTS OF LOSS OF VENTILATION
GLIDELLNES AN"D TEMCHNICAL BAS ES FOR.-Q7MARC I~TflAnIYSNIIR0S.3 NUMARC 37-0 7.2.4 EFFECTS OF LOSS OF VENTILATION Dtscussrion The purpose of this secdon is tO deterine the avenge st)ady sta terap ie in dominant arts containing equipmnt necessary to achiev and wzintain safe shutdown during a sdion blackout. Appendix E provides the basis for the procedure coneaned in this secdoo. This temperatre provides a reference point for reasonably assuring the openbilicy of tquipment needed to cpe with a stoion blackout using the medhodologies outlined in Appendix F.
Plants utilizing an Alternate AC capability need not complete this review if the Alternate AC source is used to power ESF ventilation systems and is available within 10 minutes (see Seecion 7.1').
Procedure Step 1:
Dominant Area Geometry Record in A(l) AA(2)
A(3), and A(4). as ppropriate. the estimated total room surface area, xcluding floors but including ceilin a=d walls, nvearured square nmter for the following roons/quadnants (as applicable):
(1) Stew¶ Drivefl AFW Pmnx Rom (PWR]' onlv A(1) =
(2) WPC PCS Room (MWR. onlyv A(2)=
(3)
RCTC Room (BWRS onl)
A(3)-
(4) Main atzm tmrel (FRMW only)
A(4) =
Step 2:
Dominant Area Heat Generatdo Rates Record in Q(I), Q(2), Q(3), and Q(4). as approriar-the beat genentonl rates. mtatured U War=: for dte following rooms/quadrats (as plicable):
(1)
Stpim Driven AFW Time Rrem (YWRi} oniy Esdnusat the bceat g oit arn for diii oonquadrant amt enu r in Q( l)
(z) HtITTPC5 Room (RW'R, onlyv Estimate thehe gtenern at for diti rvoquadnt and enr in Q(2)
Q(2)-
7-13
GUMELLNES A.N(D TECXHNICA-L BASES FOR NLNARC LirTIATrMSN'AR 70 NUMARC 87.OO (3) RCICgoom (1WR~t ol)
Esdmam the hoat generadon mam for this room~quadraxn and enter in Q(3)
(4)
Main sg-n hificl (BWP-v anrv)
Estimate the heat generadio ratc fcc the txmne1 and enter in Q(4). The heut unsfer correlaton prusenred in Appendix E is adequzz to estinare the beat unsfer ftmm hot StEamI pipes to fte sutroundint air. Thermal rwiiadon heat mosfer may be neglocted.
Q(4)
NOTE.-
See supporting infonnadion for the methodology used information to determine the generation rates for Yarlous equipment configurations.
step 3:
Determinie thi Wall Temperatures Detemine the upper bound for wagl temperature, in 'C primr to loss of vendlation. A tcnpwrz= of(40 C (104' F) may be r~souablc for nezedy all rooms~qiza&mns. This tempentrre is late used as the Inital i tnesupatre for the roorr~quadthn in Steps 4 and S.
It is assumed that the wall tevq=arc doms not change zpprodably thxvughour the mansient a~s showM in Appendix!E (2.r C).
T(1 )
(4) MiintL-ijm nmne! IBw-R3 cnlv)
T(4)
- 7. 14
GMrELLNES AND TECX"(ICAL BASES FOR.NTLhRCr4MTLr'SMMIRC 7
.NLIAR C S740 Step 4:
Calculate the Steady State Room TemperatureFolowing Los ofVentiltion Calculate the steady st2Le ambient air temperatue I rC, using Equaion (E-18) for the foUowing rooms/qunadtan, assuming no adtical cooling or naturl cirulation to the outside enCDnirO (1) Steum riven AFW nin Roo mR) tnlv Tj(1) -[Q(lyAf()l( 3y4)
- T(1)
(2) t MP S R (vWRi oiv' TgI2) = EQ(2yA(2)1(3I4) T(2)=
(3)
CRrcRmrv (WR, mal-A TI(M) = [Q(3YA(3)](3Y4)
- T(3)
(4) Mainimn
- rmmel (WRvi cSMI Tf(4) = EQ(4yA(4)l(J'4) + T(4) =
Note that this equation is a simplified form of the complete steady stute solutdon. Heat tnsfer coeflkients and theml propertie hbae been evaluated in MKS unit Therefore, this dimensionaily inconsistent equation is valid only with the uni spe ed in Steps 142and I Step S:
Calculate the Efrect of Opening Arts Doors If it is feasible to open a door during the ew to allow rcnval ofhea through nantral ciruladon.
perform the following !tmps to detcraine the effect of opming the door.
i.l Recrd in H(I). H(2). H(3), and H(4). as appmpnaw. the height of the dbor. measured in 7-15
GCLELLYES.XD TECMNICAL BASES FOR NUMARC rUIA1IS NUNIsARC S7-CO
-It--atem Trkiven AFW Thmm gwnm rPWRggl tmtv H(1) =
(2)
TTPCSYr!
(nomEBW' arv H-)=-
(3) RMC Room (BzWRs onvly H(3)m(4) Main ite-!m nmnel ('W~s anmly H(4)
S.2 R
d in W(l), W(2). W(3), = W(4).,a cpyri the width of the door matsurmd in (2) SFnTICveS AFW mnRre3 m (PWRi onrv
.W(1) =____
(2)
R p3)
RCTC Room MWRs ontly W(3)
(4) M~ emnl(Wsmv W(4) 53
- Cul, d6e door fxor F fo the rollowing moms/ qudr~:
(I) S=mHnrLVeW AFW¢ mm m PWsoilv
- 7. 16
GUaELDTES A"D TECRMCAL BASES FOR.UMARC D UA7
,NUN ARC37-00 (2)
FPtTCRcM~jnv F(2) =H(2)312WC2)
(3) RCTC Rgm MWg nlyl FM3 =H(3)=W(3)
(4) Main -ttgi raymel fRWRy onl'fl IF(4) =H(4)3 2W(4) 5.4 CaltuLvc the stesdy-mtzt 2zmbient 2!r tewperatnre. In'* C. ushin Equazion (E.27) for the following roomm/qiiadran (1) Steftm Tjrivtu AFW'Purnt Room (PWRII only, T1<1)=4 + T(1 +,[Q(1)314I(A(1)3y4 1&B()O+1 (2) ki+/-rYP~rS ~mm(BWRa orlv)
TI. T(2) +[Q(2)31/44A(ZY4 + 1.I(2)0J6-53))
(3) RCTCRcgromfW~tnml T3)4+ T(3) [.3
/[()416.18F(3)OJ653))
(4)
Main nrm um~net rRWRA mbfy Tf(4)" + T(4) +[Q(4)-V4"I(4
+~4 16.I8F(4)OJ369))
Note that this equation is a simplified rorm Of the complfete steady state solution. Heat Uranser cotteffcin and thermal properdies bate been tyaluazed in MMK uniti. Therefore, this dimensionaly E~nusixtent equation is rlid only with the units specified In Steps 1, Z-and 3.
7-17
- 1 I
ft WASHINGTON PUILIC POWER v SUPPLY SYSTEM I
I
- . Cj g
8~~.
.g..
..........i-aXA CI....................
Applies to:
Calculation No.
Rev.
C M R - 9 8 - 0 0 4 8 M E, - 0 2 - 8 9 -2 1
0 This CMR has been filed against the current revision of the identified calculation, and must be closed out at a future date. All technical data needed to actually update the calculation has been included in this CMR package.
- 1. Purpose of CMR To update the RCIC room temperature during SBO considering failure of barometric level control (Ref PER 297-0936)
- 2. Input Data Summary (Use additional sheets if necessary)
The AC powered level switch RCIC-LS-1 1 will be inoperable during SBO. This will cause the condenser tank to overfill (if nof manually controlled by Operations) and block vacuum pull on the RCIC turbine gland seals allowing steam to enter the room. In addition, the overfilling of the condenser could plso lead to water on the floor since EDR sump will fill and will not be able to be pumped out. The heat load from gland seal steam and fron (potentially) warm water on the floor will be addressed to determine the upper bound on RCIC room temperature.Calc EQ-02-97-01 Rev. 0 will be used to determine amount of water entering the room. TM-2104 Rev 0 will be used for data on turbine gland seal leakage. References are listed on page 4 of this CMR
- 3. Predicted Result or conclusion When this CMR is incorporated into the calculation, the results/conclusions will be:
The new maximum RCIC room temperature will be 141 deg F with doors closed and 136 deg F with doors open.
See attached calculation sheets pgs 2-4.
[Note there is one other outstanding CMR to this calc.]
-Peit bus zfjsrso4 t-oZ.
wt-t tS vs-cl, i raseae I& ARPC 540 I vk.
Elm cI -
.l
- t s, 42 f
c (ODb a docs -,,A Adeb uPStt"5C
-i--
Prepared by / Date I Verified by / Date JR Zimmerschied JI ' 3-2(.K This CMR has been incorporated into Revision of the identified calculation Signature Date 968-19954 R2 (3/98)
7- -Page Cor.Vd On Page J NWASGINGTON wUuuc rowix VERIFICATION CHECKLIST FOR Oa A
SUPPLY SYSTEM CALCULATIONS AND CMRs 1.200 JOQ,]
Ca-lio/M X,.
t 0
/
i Calculalion/CMR T[
- 0 (> "I 1-verified using the following methods:
4, Checklist Below Revision D was 0 Alternate Calculations Checklist Item Clear statement of purpose of analysis Methodology clearly stated and sufficiently detailed and appropriate to proposed application Logical consistency of analysis Completeness of documenting references Completeness of documenting and updating output interface documents Completeness of input Accuracy of input data Consistency of input data with approved criteria Completeness in stating assumptions Validity of assumptions Calculation sufficiently detailed Arithmetical accuracy Physical units specified and correctly used Reasonableness of output conclusion Supervisor independency check (if acting as Verifier)
Did not specify analysis approach Did not rule out specific analysis options Did not establish analysis inputs If a computer program was used:
Is the program appropriate for the proposed application?
Have the program error notices been reviewed to determine if they pose any limitations for this application?
Is the program name, revision number and date of run inscribed on the output?
Is the program identified on the Calculation Method form?
If so, is it listed in chapter 10 of the Engineering Standards Manual?
Other Elements Considered 7
/I
/.......
z114 010
/' //W all -
/ V If a separate verifier was used for validating these functions or a portion of these functions, sign and initial below.
Based on the foregoing, the calculation is adequate for the purpose intended.
2 0/1' V~eriirInitipi 9
1910-
-IU4-i
-1E-I
Prepared By:
Date: 5f-ReviewedBy/
_f 2,
Calculation:
Assumptions:
- 1)
Water for the barometric condenser will come from the suppression pool and is 140 deg F.
This is conservative since Ref 3 (PPM 5.6.1 Rev 5) states preference will be to use water from the CST. Per a commitment to the NRC, suction from the suppression pool will be switched back to CST if the pool exceeds 140 deg F (Ref I.GO2-91-091).
- 2)
All the water delivered to the barometric condenser will end up on the floor as per Ref 2 (EQ-02-97-01).
- 3)
Inoperability of the level switch will not be compensated for by Operator action Conservative vs. Ref. 3)
Analysis:
The original calculation uses methodology from NUMARC 87-00 (App D of this calculation) to determine RCIC room temperature during a SBO. From pg 7-15 of NUMARC 87-00 the final temperature in the RCIC room is:
TK(3) = [Q(3)/A(3)]10'5 I + T(3)
The term Q(3) included heat loads from the walls and floors, from equipment (electrical equipment, pump & turbine) and from piping. The heat load from steam from the RCIC turbine gland seals will be added to the value of Q(3) and resubstituted in the formula to determine a final RCIC room temperature.
Per Ref. 4 (GE Spec 23A1862AA) steam is delivered at maximum of 1210 psia. Per Ref. 5 (02E 51-07,51,1) the steam supply quality for RCIC is considered dry saturated steam. The Availability of the steam to produce work is given by:
W.
= [h1 - T0S1] - [h2 - TOS2]
Ref 6 (Mechanical Engineer's Reference Manual)
From steam tables for saturated steam at 1210 psia: h = 1183.4 BTU/Ibm, s, = 1.366 BTU/lbm deg R.
T. is assumed to be 134 deg F byjudgement (note the original calculation had 133 deg F as the final 1 emperature). Variations in actual value will not have much effect on final outcome.
134 degF =594 degR From steam tables for saturated liquid at 134 deg F: h2 = 101.9 BTU/lbm, S2 = 0.1883 BTU/lbm deg R.
Prepared By:
A14 Date: //1/$h Reviewed ByC 8e:0 pg 3
4 W,= [1183.4 BTU/lbm -594 degR x 1.366 BTU/lbm degR] -
[101.9 BTU/lbm-594 degRx0.1883 BTU/lbmdegR]
W..
= 372 BTU/lbm - (-9.95 BTU/Ibm) = 382 BTU/Ibm Fronr Ref 7 attachment 2 (TM2104 rev 0) the steam leakage from the RCIC gland seals is ].00 Ibm/hr.
Total work available is 382 BTU/lbm x 100 Ibm/hr = 38200 BTU/hr. Per pg 7-13 convert units to Watts: 1 Watt - 3.413 BTLJ/hr 382C'0 BTU/hr x.293 Watts/BTU/hr = 11191 Watts Tf = [(28572 W + 11191 w)/04.73m2]i0. + 40 deg C = 60.6 deg C = 141 deg F Ref 2 (EQ-02-97-01 Rev 0) determined that water from the RCIC barometric condenser would overflow into the room if the level switch was inoperable and Operations did not compensale by going to manual control. Since water from the condensate will normally come from the CST the effect of condenser tank overflow would be to cool off the RCIC room. In a worst case scenario, the RCIC pump will be drawing water from the suppression pool which will be heated by RCIC turbine exhaust steam and SRV discharges. The maximum allowable temperature for the RCIC pump is 140 deg F (Ref. 4 23A1862AA). The pump discharge is diverted to cool the turbine oil cooler and then is sprayed into the barometric condenser. If the suppression pool was allowed to get to 140 deg F, the water into the condenser would be higher than 140 deg F due to heat gain from the lube oil cooler. However, the efficiency of the cooler would be low at this high of a cooling water temperature so the delta T across the heat exchanger would be low. The final outcome is that by the time the water floods onto the RCIC room floor it is not expected to be much different than the final room temperature calculated above. Therefore the effect can be neglected.
On page 5.015 of calculation ME-02-89-21 rev 0, a final temperature for the RCIC room with open doors is calculated. Substituting the new Q gives:
TB = 4 deg C + 40 deg C + [(28572 W + 11191 W)075 /( (704.73)°75 m2I+ 16.18 m2 x (4.95 >0.9653))]
Prepared By Date: §/§i/
Reviewed Byw epte:
5l 4
T: = 58 degC= 136 degF Note that this is well below the 160 deg F leak detection isolation set point (Ref 3 PPM 5.6.1).
Refe~rences:
- 1)
Letter Supply System to NRC G02-91-091 dtd 5/7/91 "Additional Information Regarding SBO (TAC No. 68626)
- 2)
Calc. EQ-02-97-01 Rev 0 Evaluation of active Failure of RCIC-LS-1 I in Seismic Event
- 3)
PPM 5.6.1 Rev 5 Station Blackout
- 4)
GE Spec 23A1862AA Rev 12 Reactor Core Isolation Cooling System CVI 02-02E'51-03,4,12
- 5)
CVI 02-02E51-07,51,1 EPRI Terry Turbine Maintenance & Troubleshooting Guide
- 6)
Mechanical Engineer's Reference Manual MR Lindeburg 1990 Profession Publications, Inc.
- 7)
TM-2104 Rev 0 RCIC Operation Without Barometric Condenser
t WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCUMENT TRANSMITTAL TO BE COMPLETED BY ORIGINATOR
- 1. Transmittal No.
PAGE 1 TO: Washington Public Power Supply System OF P.O. Box 968
/70(
Richland, WA 99352
- 9. Initiating Doc. No.
- 21. Prority Attention: Records Management M/D 964 Peg
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- 3. From:
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- 4. Purchase Order/Contract No.
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- 6. Originator Remarks S. Supply System Cognizant Engineer Ik
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- 14. Receipt Adcnowledged LPwxj(:Y.
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- 6. Engr. Req. Resoonse Date 1
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- 19.
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- 5.
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- 18. Design ALARA
- 17. ComponentlS)stem Anal.
- 18. Penetrations
- 17. Mechanical Er gineenng f
- 18. ASME Code Compliance W.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __I_
- 17. ElecthicaVll&C Engineering
- 18. ControlSys.Failure v22z;ZtV)/ ~
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- 18. Equip. Enginec ring If
- 18. App. R/Electrical Sep.
- 18. Human Factor;
- 18. Health Safety/Fire Protection
- 18. Emergency Prup.
- 18. Security
- 18. Environmental
- 18. Quality Assurance
- 18. MEL Input Cood.
- 18. Project Engineer
_L 968-12310 RS (494)