ML19320D321
| ML19320D321 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/16/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| 632, NUDOCS 8007210244 | |
| Download: ML19320D321 (17) | |
Text
=
Q VINGINIA Er.ncrute Axn Pownie Co>tmxy Ricaixox1),VzsaorarA consi July 16, 1980 Mr. Harold R. Denton, Director Serial No. 632 Office of Nucicar Reactor Regulation N0/LEN:smv Attention:
Mr. B. Joe Youngblood, Chief Docket No. 50-339 Licensing Branch No. 1 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
AUXILL1RY FEEDWATER SYSTEM REQUIRDfENTS NORTil ANNA UNIT 2, On July 10, 1980, Vepco sent the NRC a letter responding to auxiliary feedwater system requirements.
Included in that letter was Attachment I which contained Table 2-1.
It has since been discovered that there was a typographical error in Table 2-1 and a revised table is enclosed.
Note that under Main Feedline Break Transient J, operator action should be 30 mins. Instead of 10 mins.
t It should also be noted that the information available in Section 15.4.2.2 of the North Anna FSAR does not include the results of a Westinghouse analysis of the most limiting feedwater break.
As referenced on page 8 of Attachment 1, Supplement 15.18 to the FSAR contains these results.
Should you have any questions or require additional information, please contact us.
Very truly yours, B. R. Sylvia Manager - Nuclear Operations and Maintenance LEN/smv:SZ1 8007210N [
TABLE 2-1 4
SUMMARY
OF ASSUMPTIONS USED IN AWS DESIGN VERIFICATION ANALYSES Lors of Feedwater Main Steamline Break Transient (s'.ation blackout)
Cooldown Main Feedline Break (con ta inment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (1021 of 2910 MWt)
(102% of 2910 MWt) case (I of 2775 MWt) b.
Time delay from 2 see (delay after 2 sec 2 sec 0 seconde event to Rx trip trip) e.
APWS actuation signal /
lo-lo SC level NA low-low SC level Feedwater iso!ation actuation signalt time delay for AWS flow I ainute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SC: 17 see af ter MSLB (which is
' time of W isolation) d.
SG water level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip 0% NR span feed mismats h) 2 e 20% NR span 1 e tube sheet c.
Initial SC inventory 74.600 lba/SC (at 104.500 lbs/SC 94.100 lba/SC 151.000 lba/SC trip) e 525.2'F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
AW pump design 1133 psia 1133 pain 1133 psig 1025 psig pressure 3,
Minimum i of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator APW flow action af ter 30 minutes) h.
RC pump status Tripped 6 reactor trip Tripped All operating Tripped L
fu11En ATJ IIS'F 100'F liO*r 120'F Temperature J.
Operator action none N/A 30 min.
30 min.
3 3
3 k.
MW purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3*F 1.
Normal blowdown none assumed none assumed none assumed none assumed ta.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown n.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RER e.
AW flow rate 680 CiM - constant variable 340 gpm - 1 min after 900 gpa to broken SC trip - 680 gpm 350 gpa to each intact S/C (af ter 30 minutes)
(max requirement)
TABLE 2-1 SLHMARY OF ASSUMPTIONS USED IN AFWS DESIGN VERIFICATION ANALYSES
- Loss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MWt) case (% i.f 2775 MWt) b.
Time delay from 2 see (delay after 2 see 2 sec 0 seconds event to Rx trip trip) c.
AWS actuation signal /
lo-lo SG 1evel NA low-low SC level Feedwater isolation actuation signalt time delay for AWS flow 1 minute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SGt 17 see af ter MSLB (which is time of W isolation) d.
SC water level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 @ 20% NR span 1 9 tube sheet
- e..
Initial SC inventory 74.600 lbm/SC (at 104.500 lbm/SC 94.100 lbm/SC 151.000 lba/SC trip)
@ 525.2*F Rate of change before See FSAM Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& afts T AWS actuation than 2000 sec.
decay heat See FSAR FI urn 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 S
f.
AW pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
Minimum i of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator A W flow action af ter 30 minutes) h.
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
Maximum AFW 120*F 100*F 120*F 120*F Temperature J.
Operator action none N/A 30 min.
30 min.
3 3
3 3
k.
M W purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3*F 1
Normal blowdown none assumed none assumed none assumed none assumed c.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown n.
Time et standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR o.
AW flow rate 680 CPM - constant variable 340 gpm - I min after 900 gpa to broken SC trip - 680 gpm 350 gpm to each intact S/C (af ter 30 minutes)
(max. requirement)
. TABLE 2-1
SUMMARY
OF ASSUMPTIONS USED IN AFVS DESIGN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102: of 2910 MWt) case (I of 2775 MWt) b.
Time delay from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
A W S actuation signal /
lo-lo SC level NA low-low SG 1evel Feedwater isolation actuation signal:
time delay for #5VS flow I minute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SG: 17 sec af ter MSLB (which is time of W isolation) d.
SG water level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip Ot NR span feed mismatch) 2 @ 20% NR span 1 @ tube sheet c.
Initial SG inventory 74,600 lbm/SG (at 104.500 lbm/SC 94.100 lbs/SC 151.000 lba/SG trip)
@ 525.2'F Rate of change before See FSAR FJgure 1%2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AWS actuation than 2000 sec.
decay heat 5:3 PSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
A W pump design 11 O psis 1133 psia 1133 psig 1025 psig pressure g.
Minimum f of SGs 2 if 3 N/A 1 of 3 (1 min af ter N/A which must receive trip) 2 of 3 (operator AW flow action after 30 minutes) h.
RC pump status Tr:eped @ reactor trip Tripped All operating Tripped 1
Maxi:num AN 120*F 100'F 120*F 120'F Temperature j.
Operator action none N/A 30 min.
30 min.
3 3
k.
M W purge volume / temp.
159.6 ft /437.6'F 100 ft /
214 ft /433.3'F 218 ft /441'F 434.3'F 1.
Normal blowdown none assumed none assumed none assunied none assumed U.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown n.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 'er N/A to cooldown to RH3 e,
A W flow rate 680 CPM - constant variable 340 gpm - 1 min af ter 900 gpa to broken SC trip - 680 gpm 350 gym to each intact S/0 (after 30 minuten)
(max requirement)
TABLE 2-1 SLHMARY OF ASSUMPTIONS (JSID IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MWt) case (I of 2775 MWt) b.
Time'<teley from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
AWS actuation signal /
lo-lo SC level NA low-low SC level Feedwater isolation actuation signal:
time delay for AWS flow I minute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SC: 17 see af ter MSLB (which is time of W isolation) d.
SG water level at (1o-10 SC level)
NA (lo SG 1evel + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 0 20% NR span 1 @ tube sheet c.
Initial SG inventory 74.600 lbm/SC (at 104.500 lbm/SC 94.100 lbm/SG 151.000 lbm/SG trip) 9 525.2*F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater FSAP. Table 6.2-11
& af ter AWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
AW pump design 1133 psia 1133 psia 1133 psig 1025 pais pressure 3
Minimum i of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator A W flow action af ter 30 minutes) h.
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
Maximum A W l40*F 100'F 120'F 120'F Temperature j.
Operator action r me N/A 30 min.
30 min, 3
3 3
k, N W purge volume / temp.
1:P.6 ft /437.6*F 100 ft /
214 ft /433.3'F 218 ft /441*F 434.3*F 1,
Normal blowdown none assumed none assumed pono assumed none assumed D.
Sensible heat see cooldown Table 2-2 see cooldown ses cooldown i
s.
Time at standby / time 2hr/4hr 2 hr/4 hr 2 hr/4 hr li/A to cooldown to RdR c.
AW flow rate 680 CPM - constant variable 340 gpm - 1 min after 900 gpm to broken SG trip - 680 spa 350 gym to each intact S/G (af ter 30 minutes)
(max. requirement)
TABLE 2-1 StatMARY 4W ASSUMPT!ONS USFD IN AFWS DES!CN VERIFICATION ANALYSES Loss of Feedwater Main Steam 11ne Break Transient (station blackout)
.Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MVt) case (I of 2775 MWt) b.
Time delay from 2 sec (delay af ter 2 see 2 sec 0 seconds event to Rx trip trip) e.
AFWS actuation signal /
10-10 SG 1evel NA low-low SG 1evel Feedvater isolation actuation signal:
time delay for AFWS flow 1 minute 1 minute Safety Injection Signal 0 sec (no delay)1 Flow to SC: 17 sec af ter MSLB (which is time of W isolation) d.
SG water level at (lo-lo SG 1evel)
NA (lo SG 1evel + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 9 20% NR span 1 @ tube sheet c.
Initial SG inventory 74.600 lbm/SG (at 104.500 lbm/SG 94.100 lbm/SG 151.000 lba/SG trip) 0 525.2*F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AFWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
A W pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
Minimum i of SCs 2 of 3 N/A 1 of 3 (1 min af ter N/A which must receive trip) 2 of 3 (operator AFW flow action af ter 30 minutes) h.
RC pump status Tripped @ reactor trip Tripped All operating Tripped i.
Maximum A W 120*F 100'F 120*F 120*F Temperature j,
Operator action none N/A 30 min.
30 min.
3 3
3 3
k.
MW purge volume /terp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3'F 218 ft /441*F 434.3*F 1
Normal blowdown none assumed none assumed none assumed none assumed t!.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown n.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR o,
AW flow rate 680 GPM constant variable 340 gpm - 1 min af ter 900 sps to broken SG trip - 680 spa 350 spe to each intact S/C (af ter 30 minutes)
(max. requirement)
c, TABLE 2-1 StDO8ARY OF ASStfMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steaaline Break Transient' (station blackout)
Cooldown Main Feedline Break (containment) e, Meu reactor' power 102% of ESD rating 2963 MWt 102% of ESD rating 01 (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MWt) case'(I of 2775 MWt) b.
Time' delay from 2 see (delay after-2 see 2 sec 0 seconds event to Rx trip trip) c.
.A NS actuation signal /-
lo-lo SC IcVel NA _
low-low SC level Feedwater isolation actuation signalt tias delay for ANS flow 1 minute 1 minute Safety Injection Signal 0 sec (no delay);
Flow to SC: 17 sec af ter MSLB (which is
' time of N isolation) d.
SC water level at (lo-lo SC level)
NA (lo SC level
- steam-Same as initial level before event time of reactor trip,
01 NR span feed mismatch) 2 @ 20% NR span 1 @ tube sheet c.
Initial SC inventory 74.600 lbm/;C (at 104.500 lbm/SC 94.100 lbm/SC 151.000 Ibe/SC trip)
@ 525.2*F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater-FSAR Table 6.2-11
& af ter AFWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
AN p;mp design 1133 psia
-1133 psia 1133 psig 1025 pois pressure 3
Minimum f of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator
' A N flow action af ter 30 minutes) h.
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
Maximum AN 120*F 100*F 120*F 120*F Temperature j.
Operator action none N/A 30 min.
30 min.
3 3
3 3
k.
NN purge volume / temp.
-159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3'F 1
Normal !, lowdown none assumed none assumed none assumed none assumed
- c.
Seasible heat see cooldown Table 2-2 see cooldown see cooldown c.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR e.
AW flow rate 680 CPM - constant variable 340 gpm - 1 min af ter 900 spo to broken SC trip - 680 spo 350 sps to each intact 5/C -
(af ter 30 minutes)
(max. requ1Fement)
TABLE 2-1 SL401ARY OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 W t 102% of ESD rating 0% (of rated) - worst (102% of 2910 W t)
(102% of 2910 W t) case (I of 2775 Wt) b.
Time delay from 2 sec-(delay after 2 sec 2 see.
O seconds event to Rx trip trip)
- r..
AFhS actuation signal /
lo-lo SC level NA.
Iow-low SC level Feedwater isolation actuation signal:
time delay for AF1C flow 1 minute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SC: 17 see after MSLB (which is
~ time of W isolation) d.
SC water level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 9 20% NR span 1 9 tube sheet
- o.. Initial SG inventory 74.600 lbm/Sc (at 104.500 lba/SC 94.100 lba/SC 151.000 lba/SC tilp) 6 525.2*F Rate of change before Sco FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
AFW pump design 1133 psia 1133 psia 1133 psig 1025 pois pressure g.
Minimum f of SCs 2 of 3 N/A 1 of 3 (1 min af ter N/A which s:ust receive trip) 2 of 3 (operator A W flow action af ter 30 minutes) h.
RC pump status Tripped 6 reactor trip Tripped All operating Tripped 1.
Maximum AW 120'F 100*F 120'F 120*r Temperature J.
Opeeator action none N/A 30 min.
30 min.
3 3
3 3
k.
MW purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3'F 218 ft /441*F 434 1*r 1.
Normal blowdown none assumed nw w umed none ascumed none assumed u.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown
- n. - Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR o.
AfW flow rate 680 CPM - constant variable 340 gpm - 1 min af ter 900 gym to broken SC trip - 680 gym 350 gym to each intact S/C (af ter 30 minutes)
(max. requirement)
1 TABLE 2-1
SUMMARY
OF ASSUMPTIONS USED IN A WS DESICN VERIFICATION ANALYSES Loss of Feedw. ster Main Steamline Break Transient (ntation blackout)
Cooldown h in Feeditne Break (con ta inment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MWt) case (I of 2775 MWt) b.
Time delay from 2 sec (delay af ter 2 sec 2 sec 0 seconds a rent to Rx trip trip) c.
AFWS actuation signal /
lo h 3G level NA low-low SG level Feedvater isolation actuation signal:
time delay for AWS flow I minute I minute Safety Injaction Signal 0 see (no delay);
Flow to SG: 17 see after MSLB (which is time of W isolation) d.
SG water level at (lo-lo SG 1evel)
NA (lo SG 1evel + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 9 20% NR span 1 0 tube sheet c.
Initial SG inventory 74.600 lbm/SG (at 104.500 lbm/SG 94.100 lba/SG 151.000 lbs/SG trip)
@ 525.2*F Rate of change before See FSAR FJgure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
- & after AFWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
AW pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
Minimum i of SGs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator A W flow action af ter 30 minutes) h.'
RG pump status Tripped @ reactor trip Tripped All operating Tripped 1.
Maximum AW 120*F 100*F 120*F 120*F Temperature J.
Operator action none N/A 30 min.
30 min.
3 3
3
' k.
M W purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3*F 1.
Normal blowdown none assumed none assumed none assumed none assumed c.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown c.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR o.
AW flow rata 680 GPM - constant variable 340 gpa - 1 min af ter 900 spa to broken SG trip - 680 gpm 350 spa to each intact S/G (af ter 30 siinutes)
(max requirement)
X TABLE 2-1
(
SUMMARY
OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) a.
Max reactor power-102% of ESD rating 2%3 MWt 102% of ESD rating 01 (of rated) - vorst (102% of 2910 MWt)
(102% of 2910 MWt) case (% of 2775 MWt) b.
Time delay from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
AFWS actuation signal /
10-10 SC level NA low-low SG 1evel Feedwater isolation actuation signal:
time delay for AWS flow I minute 1 minute Safety Injection Signal 0 sec (no delay);
Flow to SC: 17 see after MSLB (which is time of W isolation) d.
SC water level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 @ 20% NR span 1 @ tube sheet o.
Initial SC inventory 74,600 lba/SC (at
'104.500 lbe/SC 94.100 lba/SC 151.000 lba/SC trip)
@ 525.2*F Rate of charra before See FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AFWh actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
A W pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
Minimum f of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator AW flow action af ter 30 minutes) h.
RC pump status Tripped $ reactor trip Tripped All operating Tripped 1.
Maximum A N 120'F 100'F 120*F 120'F Temperature J.
Operator action none N/A 30 min.
30 min.
3 3
3 k.
M W purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3'F 1.
Normal blowdown none assurced none assumed none assumed none assumed c.
Sensible heat sie cooldown Table 2-2 see couldown see cooldown n.
Time at standby / time 2 h*/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to R11R e.
A W flow rate 680 CcM - constant variable 340 gpm - 1 min af ter 900 gpa to broken SC trip - 680 gpm 350 gpa to each intact S/C (af ter 30 minutes)
(max. requirement) 4
TABLE 2-1
SUMMARY
OF ASSUMPTIONS USED IN AWS DESIGN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break
' Transient (station blackout)
Cooldown Main Feedline Break (containment) n.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - vorst (102% of 2910 MWt)
(102% of 2910 MWt) case (% of 2775 MWt) b.
Time delay from 2 sec (delay af ter 2 sec 2 sec 0 seconds event to Rx trip trip) c.
AfvS actuation signal /
lo-lo SG 1evel NA low-low SG 1evel Feedvater isolation actuation signal:
time delay for AWS flow 1 minute 1 minute Safety injection Signal 0 sec (no delay);
Flow to SC: 17 see af ter MSLB (which is time of W isolation) d.
SG water level at (10-10 SG 1evel)
NA (lo SG 1evel + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 0 20% h1 span 1 6 tube sheet o.
Initial SG inventory 74.600 lba/SG (at 104.500 lbm/SC 94.100 lbm/SG 151.000 lba/SG trip) e 525.2*F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& after AFWS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
AW pump design 1133 psia 1133 pata 1133 psig 1025 pois pressure 3
Minimum i of SGs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator A,W flow action af ter 30 minutes) b.
RG pump status Tripped 9 reactor trip Tripped All operating Tripped 1.
himus AN 120'F 100'F Ifb'F 120*F Temperature J.
Operator action none N/A 30 min.
30 min.
3 3
k.
N N purge volume / teep.
159.6 ft /437.6'F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3*F 1.
Normal blowdown none assumed none assumed none assumed none assumed t2.
Sensible heat see cooldown Table 2-2 see cooldown see cooldewn s.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A 8
-to cooldown to RHR
~
c.
A N flow rate 680 GPM - constant variable 340 gpm - 1 min af ter 900 gpa to broken SG trip - 680 gpm 350 gym to each intact S/G (af ter 30 minutes)
(max. requirement)
TABLE 2-1 SL?1 MARY OF ASSUMPTIONS USID IN AWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steauline Break Transient (station blackout)
Cooldown Main Feedline Break (contairunent) c.
Mas reactor powee 102% of ESD rating 2963 MWt 102% of ESD rating 01 (of rated) - vorst (102% of 2910 MWt)
(102% of 2910 MWt) case (I of 2775 MWt)
- b.
Time delay from 2 sec (delay after 2 see 2 sec 0 seconds event to Rx trip trip) e.
A WS actuation signal /
lo-lo SC level NA low-low SC level Feedwater isolation actuation signal time delay for AWS flow I minute 1 minute Safety Injection Signal O sec (no delay);
Flow to SGt 17 sec af ter MSLB (which is time of W isolation) d.
SC vater level at (lo-lo SC level)
NA (lo SC level + steam-Same as initial level before event time of reactor trip 0% NR span feed mismatch) 2 9.20% NR span 1 @ tube sheet c.
Initial SC inventory 74.600 lbm/SC (at 104.500 lbm/SC 94.100 lbm/SC 151.000 lbs/SC trip) 9 525.2*F Rate of change before See FSh Tigure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& af ter AFWS actuation than 2000 sec.
decay heat See F3AR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
AN pump design 1133 psia 1133 psia 113' psig 1025 psig pressure 3
Minimum i of SCs 2 of 3 N/A 1 of 3 (1 min after N/A which must receive trip) 2 of 3 (operator AFW flow action af ter 30 minutes) h.
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
Maximum AN 120'F 100'F 120*F 120*F Temperature j.
Operator action none N/A 30 min.
30 mia.
3 3
k.
M N purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 ft /433.3*F 218 ft /441*F 434.3*F 1.
Normal blowdown none assu:r.ed none assumed none assu:ed none assumed c.'
Sensible heat see cooldown Table 2-2 see cooldown see cooldown n.
Time at standby / time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to tooldown to RHR e.
AN flow rate 680 CPM - constant variable 340 gpm - 1 min af ter 900 spa to broken SC trip - 680 gym 350 spa to each intact $/p (af ter 30 minutes)
(max. requiremant)
TABLE 2-1
SUMMARY
OF ASSUMPTIONS USED IN ANS DESICN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
Cooldown Main Feedline Break (containment) c.
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
(102% of 2910 MWt) case (% of 2775 MWt) b.
Time delay from 2 see (<1elay af ter 2 sec 2 sec 0 seconds event to Rx trip trip) c.
A NS actuation signal /
1o-13 SG 1evel NA low-low SG 1evel Feedwater isolation actuation signalt time delay for AWS flow 1 minute 1 minute Safety Injection Signal 0 see (no delay);
Flow to SG: 17 see af ter MSLB (which in time of W isolation) d.
SG water level at (lo-lo SG Icvel)
NA (lo SG 1evel + steam-Same as initial level before event time of reactor trip 01 NR span feed mismatch) 2 @ 20% NR span 1 0 tube sheet c.
In!;;al SG inventory 74.600 lba/SG (at 104.500 lbm/SG 94,100 lbm/SG 151.000 lba/SC, trip)
@ 525.2*F Rate of change before Sse FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
& after A WS actuation than 2000 sec.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
AN pu:np design 1133 psia 1133 psia 1133 psig 1025 peig pressure g.
Minimum i of SGs 2 of 3 N/A 1 of 3 (1 min af ter N/A which must receive trip) 2 of 3 (operator A W flow action af ter 30 minutes) h.
RC pump status Tripped 8 reactor trip Tripped All operating Tripped 1.
Maximum A W 120'r 100'F 120'F 120*F Temperature J.
Operator action none N/A 30 min.
30 min, 3
3 3
3 k.
MI4 purge volume / temp.
159.6 ft /437.6*F 100 ft /
214 it /433.3*F 218 f t /441*F 434.3'F 1
Normal blowdown none assumed none assumed none assumed none assumied c.
Sensible heat see cooldown Table 2-2 see cooldown see cooldown a.
Time at staedby/ time 2 hr/4 hr 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RHR g
O.
AN flow rate 680 CPM - constant variable 340 gpm - 1 min af ter 900 gpm to broken SG.
trip - 680 gpm 350 rpm to each intact S/0 (af ter 30 minutes)
(max, requirement) 9