ML19320D321

Forwards Revised Table 2-1 of 800710 Response to NRC Request for Info Re Auxiliary Feedwater Sys Requirements.Info Available in Section 15.4.2.2 of FSAR Does Not Include Westinghouse Analysis of Limited Feedwater Break

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

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• 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 [ l

4 TABLE 2-1

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.

k. 3 3 MW purge volume / temp. 159.6 ft /437.6*F 100 ft / 214 ft 3/433.3*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 event to Rx trip 0 seconds 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-time of reactor trip 0% NR span Same as initial level before event 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 trip) 151.000 lba/SC

@ 525.2*F Rate of change before See FSAM Figure 15.2.31 N/A turnaround greater

& afts T AWS actuation FSAR Table 6.2-11 than 2000 sec.

decay heat See FSAR FIS urn 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 pressure 1025 psig

g. Minimum i of SCs 2 of 3 which must receive N/A 1 of 3 (1 min after N/A 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.

k. M W purge volume / temp. 3 159.6 ft /437.6*F 100 ft /3 3 214 ft /433.3*F 218 ft 3/441*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 to cooldown to RHR 2 hr/4 hr N/A

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.

k. 3 3 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

k, N W purge volume / temp. 1:P.6 ft /437.6*F 100 ft / 214 ft 3/433.3'F 218 ft 3/441*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.

k. MW purge volume /terp. 3 3 3 159.6 ft /437.6*F 100 ft / 214 ft /433.3'F 218 ft 3/441*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.

k. NN purge volume / temp. 3 3 3

-159.6 ft /437.6*F 100 ft / 214 ft /433.3*F 218 ft 3/441*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.

event to Rx trip O seconds trip)

r. . AFhS actuation signal / lo-lo SC level NA. Iow-low SC level time delay for AF1C flow 1 minute Feedwater isolation actuation signal:

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-time of reactor trip 0% NR span Same as initial level before event 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

& af ter AWS actuation FSAR Table 6.2-11 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 pressure 1025 pois

g. Minimum f of SCs 2 of 3 N/A which s:ust receive 1 of 3 (1 min af ter N/A 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.

k. MW purge volume / temp. 3 159.6 ft /437.6*F 3 100 ft / 3 214 ft /433.3'F 218 ft 3/441*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 to cooldown to RHR 2 hr/4 hr N/A

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.

' k. M W purge volume / temp. 159.6 ft 3/437.6*F 100 ft / 214 ft 3/433.3*F 218 ft 3/441*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.

k. M W purge volume / temp. 3 3 3 159.6 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 event to Rx trip 0 seconds trip)

c. AfvS actuation signal / lo-lo SG 1evel NA low-low SG 1evel time delay for AWS flow Feedvater isolation actuation signal:

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-time of reactor trip 0% NR span Same as initial level before event 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

& after AFWS actuation FSAR Table 6.2-11 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 pressure 1025 pois 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

k. N N purge volume / teep. 159.6 ft /437.6'F 100 ft / 214 ft 3/433.3*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.

k. M N purge volume / temp. 3 159.6 ft /437.6*F 100 ft / 214 ft /433.3*F 218 ft 3/441*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-time of reactor trip 01 NR span Same as initial level before event 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

& after A WS actuation FSAR Table 6.2-11 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 pressure 1025 peig

g. Minimum i of SGs 2 of 3 N/A 1 of 3 (1 min af ter which must receive N/A 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,

k. MI4 purge volume / temp. 3 159.6 ft /437.6*F 3 100 ft / 3 214 it /433.3*F 218 f t3/441*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 to cooldown to RHR N/A 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

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