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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:
* 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
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:==
==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.
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.
Included in that letter was Attachment I which contained Table 2-1.
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.
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.
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
Very truly yours, B. R. Sylvia Manager - Nuclear Operations and Maintenance LEN/smv:SZ1 8007210N [


4 TABLE 2-1
TABLE 2-1 4


==SUMMARY==
==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)
OF ASSUMPTIONS USED IN AWS DESIGN VERIFICATION ANALYSES Lors of Feedwater Main Steamline Break Transient (s'.ation blackout)
: 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)
Cooldown Main Feedline Break (con ta inment) c.
: b. Time delay from             2 see (delay after       2 sec             2 sec                     0 seconde event to Rx trip             trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (1021 of 2910 MWt)
: 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);
(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
Flow to SC: 17 see af ter MSLB (which is
                                                                                                    ' time of W isolation)
' time of W isolation) d.
: 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
SG water level at (lo-lo SC level)
: 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
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.
    & af ter AWS actuation                                                 than 2000 sec.
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
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)
& af ter AWS actuation than 2000 sec.
: 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.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
: 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
AW pump design 1133 psia 1133 pain 1133 psig 1025 psig pressure 3,
: 1. Normal blowdown             none assumed             none assumed     none assumed               none assumed ta. Sensible heat               see cooldown             Table 2-2       see cooldown               see cooldown
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.
: n. Time at standby / time       2 hr/4 hr               2 hr/4 hr       2 hr/4 hr                 N/A to cooldown to RER
RC pump status Tripped 6 reactor trip Tripped All operating Tripped L
: 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)
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
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)
- Loss of Feedwater Main Steamline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) c.
: b. Time delay from             2 see (delay after       2 see             2 sec event to Rx trip 0 seconds trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: 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);
(102% of 2910 MWt) case (% i.f 2775 MWt) b.
Flow to SGt 17 see af ter MSLB (which is time of W isolation)
Time delay from 2 see (delay after 2 see 2 sec 0 seconds event to Rx trip trip) c.
: 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
AWS actuation signal /
: e. . Initial SC inventory       74.600 lbm/SC (at       104.500 lbm/SC     94.100 lbm/SC trip) 151.000 lba/SC
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);
                                                            @ 525.2*F Rate of change before     See FSAM Figure 15.2.31 N/A               turnaround greater
Flow to SGt 17 see af ter MSLB (which is time of W isolation) d.
      & afts T AWS actuation                                                                            FSAR Table 6.2-11 than 2000 sec.
SC water level at (lo-lo SC level)
decay heat                 See FSAR FIS urn 15.1-6                     See FSAR Figure 15.1-6     See FSAR Figure 6.2-1
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
: f. AW pump design             1133 psia               1133 psia         1133 psig pressure                                                                                          1025 psig
: e..
: 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                                                                                                         ,
Initial SC inventory 74.600 lbm/SC (at 104.500 lbm/SC 94.100 lbm/SC 151.000 lba/SC trip)
action af ter 30 minutes)
@ 525.2*F Rate of change before See FSAM Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
: h. RC pump status             Tripped @ reactor trip Tripped           All operating             Tripped
& afts T AWS actuation than 2000 sec.
: 1. Maximum AFW                 120*F                   100*F             120*F                     120*F Temperature J. Operator action           none                     N/A               30 min.                   30 min.
decay heat See FSAR FI urn 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 S
: 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
f.
: c. Sensible heat             see cooldown             Table 2-2         see cooldown               see cooldown
AW pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
: n. Time et standby / time     2 hr/4 hr               2 hr/4 hr to cooldown to RHR 2 hr/4 hr                 N/A
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.
: 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                 .
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
(af ter 30 minutes)       (max. requirement)
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                                                                         *
. TABLE 2-1


==SUMMARY==
==SUMMARY==
OF ASSUMPTIONS USED IN AFVS DESIGN VERIFICATION ANALYSES Loss of Feedwater                                                   Main Steamline Break Transient                 (station blackout)       Cooldown         Main Feedline Break           (containment)
OF ASSUMPTIONS USED IN AFVS DESIGN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) c.
: b. Time delay from           2 sec (delay after       2 sec             2 sec                     0 seconds event to Rx trip         trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: c. A W S actuation signal / lo-lo SC level           NA               low-low SG 1evel         Feedwater isolation actuation signal:
(102: of 2910 MWt) case (I of 2775 MWt) b.
time delay for #5VS flow I minute                                   1 minute                 Safety Injection Signal 0 see (no delay);
Time delay from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
Flow to SG: 17 sec af ter MSLB (which is time of W isolation)
A W S actuation signal /
: 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
lo-lo SC level NA low-low SG 1evel Feedwater isolation actuation signal:
: 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
time delay for #5VS flow I minute 1 minute Safety Injection Signal 0 see (no delay);
    & af ter AWS actuation                                               than 2000 sec.
Flow to SG: 17 sec af ter MSLB (which is time of W isolation) d.
decay heat                 5:3 PSAR Figure 15.1-6                     See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
SG water level at (lo-lo SC level)
: f. A W pump design           11 O psis               1133 psia         1133 psig                 1025 psig pressure
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.
: 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)
Initial SG inventory 74,600 lbm/SG (at 104.500 lbm/SC 94.100 lbs/SC 151.000 lba/SG trip)
: 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
@ 525.2'F Rate of change before See FSAR FJgure 1%2.31 N/A turnaround greater FSAR Table 6.2-11
: j. Operator action           none                     N/A               30 min.                   30 min.
& af ter AWS actuation than 2000 sec.
: 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
decay heat 5:3 PSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: 1. Normal blowdown           none assumed             none assumed     none assunied             none assumed U. Sensible heat             see cooldown             Table 2-2         see cooldown             see cooldown
A W pump design 11 O psis 1133 psia 1133 psig 1025 psig pressure g.
: 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)
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)
TABLE 2-1 SLHMARY OF ASSUMPTIONS (JSID IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steamline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) c.
: b. Time'<teley from           2 sec (delay after       2 sec             2 sec                     0 seconds event to Rx trip           trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: c. AWS actuation signal /     lo-lo SC level           NA                 low-low SC level         Feedwater isolation actuation signal:
(102% of 2910 MWt) case (I of 2775 MWt) b.
time delay for AWS flow   I minute                                   1 minute                 Safety Injection Signal 0 see (no delay);
Time'<teley from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
Flow to SC: 17 see af ter MSLB (which is time of W isolation)
AWS actuation signal /
: 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
lo-lo SC level NA low-low SC level Feedwater isolation actuation signal:
: 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
time delay for AWS flow I minute 1 minute Safety Injection Signal 0 see (no delay);
  & af ter AWS actuation                                               than 2000 sec.
Flow to SC: 17 see af ter MSLB (which is time of W isolation) d.
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)
SG water level at (1o-10 SC level)
: h. RC pump status           Tripped @ reactor trip   Tripped           All operating             Tripped
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.
: 1. Maximum A W               l40*F                   100'F             120'F                     120'F Temperature
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
: j. Operator action         r me                     N/A               30 min.                   30 min, 3
& af ter AWS actuation than 2000 sec.
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
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
: s. Time at standby / time   2hr/4hr                   2 hr/4 hr         2 hr/4 hr                 li/A                                       .
AW pump design 1133 psia 1133 psia 1133 psig 1025 pais pressure 3
to cooldown to RdR
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.
: 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                 *
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
(af ter 30 minutes)       (max. requirement)
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)
TABLE 2-1 StatMARY 4W ASSUMPT!ONS USFD IN AFWS DES!CN VERIFICATION ANALYSES Loss of Feedwater Main Steam 11ne Break Transient (station blackout)
: 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)
.Cooldown Main Feedline Break (containment) c.
: b. Time delay from           2 sec (delay af ter       2 see             2 sec                     0 seconds event to Rx trip         trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: e. AFWS actuation signal /   10-10 SG 1evel           NA                 low-low SG 1evel         Feedvater isolation actuation signal:
(102% of 2910 MVt) case (I of 2775 MWt) b.
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)
Time delay from 2 sec (delay af ter 2 see 2 sec 0 seconds event to Rx trip trip) e.
: 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
AFWS actuation signal /
: 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
10-10 SG 1evel NA low-low SG 1evel Feedvater isolation actuation signal:
    & af ter AFWS actuation                                                 than 2000 sec.
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.
decay heat               See FSAR Figure 15.1-6                       See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
SG water level at (lo-lo SG 1evel)
: f. A W pump design           1133 psia                 1133 psia         1133 psig                 1025 psig pressure
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.
: 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)
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
: h. RC pump status           Tripped @ reactor trip   Tripped           All operating             Tripped
& af ter AFWS actuation than 2000 sec.
: i. Maximum A W               120*F                     100'F             120*F                     120*F Temperature j, Operator action           none                     N/A               30 min.                   30 min.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: 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
A W pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
: 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)
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)
c, TABLE 2-1 StDO8ARY OF ASStfMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steaaline Break Transient' (station blackout)
: b. Time' delay from           2 see (delay after-       2 see             2 sec                     0 seconds event to Rx trip           trip)
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)
: 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);
(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
Flow to SC: 17 sec af ter MSLB (which is
                                                                                                            ' time of N isolation)
' time of N isolation) d.
: d. SC water level at         (lo-lo SC level)         NA                 (lo SC level
SC water level at (lo-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
NA (lo SC level
: 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
* steam-Same as initial level before event time of reactor trip,
            & af ter AFWS actuation                                                 than 2000 sec.
01 NR span feed mismatch) 2 @ 20% NR span 1 @ tube sheet c.
decay heat               See FSAR Figure 15.1-6                       See FSAR Figure 15.1-6     See FSAR Figure 6.2-1
Initial SC inventory 74.600 lbm/;C (at 104.500 lbm/SC 94.100 lbm/SC 151.000 Ibe/SC trip)
: 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                     ,
@ 525.2*F Rate of change before See FSAR Figure 15.2.31 N/A turnaround greater-FSAR Table 6.2-11
        ' A N flow action af ter 30 minutes)
& af ter AFWS actuation than 2000 sec.
: h. RC pump status           Tripped @ reactor trip     Tripped           All operating               Tripped
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: 1. Maximum AN               120*F                     100*F             120*F                       120*F Temperature
AN p;mp design 1133 psia
: j. Operator action           none                       N/A               30 min.                     30 min.
-1133 psia 1133 psig 1025 pois pressure 3
: k. NN purge volume / temp.             3                      3                  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
                                    -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
' A N flow action af ter 30 minutes) h.
  - c. Seasible heat             see cooldown               Table 2-2         see cooldown               see cooldown
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
: c. Time at standby / time   2 hr/4 hr                 2 hr/4 hr         2 hr/4 hr                 N/A to cooldown to RHR                                                                                                                           .,
Maximum AN 120*F 100*F 120*F 120*F Temperature j.
: e. AW flow rate             680 CPM - constant         variable           340 gpm - 1 min af ter     900 spo to broken SC
Operator action none N/A 30 min.
,                                                                                  trip - 680 spo             350 sps to each intact 5/C -               .
30 min.
(af ter 30 minutes)       (max. requ1Fement)
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                                                                               <
TABLE 2-1 SL401ARY OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steamline Break Transient (station blackout)
SL401ARY OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater                                                     Main Steamline Break Transient                                     (station blackout)       Cooldown           Main Feedline Break     ,  (containment)
Cooldown Main Feedline Break (containment) c.
: 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)
Max reactor power 102% of ESD rating 2963 W t 102% of ESD rating 0% (of rated) - worst (102% of 2910 W t)
: b. Time delay from                               2 sec-(delay after       2 sec               2 see.
(102% of 2910 W t) case (I of 2775 Wt) b.
event to Rx trip O seconds trip)
Time delay from 2 sec-(delay after 2 sec 2 see.
: r. . AFhS actuation signal /                       lo-lo SC level           NA.                 Iow-low SC level time delay for AF1C flow                     1 minute                                                               Feedwater isolation actuation signal:
O seconds event to Rx trip trip)
1 minute                 Safety Injection Signal 0 see (no delay);
: 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
Flow to SC: 17 see after MSLB (which is
                                                                                                                                ~ time of W isolation)
~ time of W isolation) d.
: 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
SC water level at (lo-lo SC level)
: 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
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
            & af ter AWS actuation                                                                                              FSAR Table 6.2-11 than 2000 sec.
: 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
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
& af ter AWS actuation than 2000 sec.
: 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)
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
: h. RC pump status                               Tripped 6 reactor trip   Tripped           All operating             Tripped
AFW pump design 1133 psia 1133 psia 1133 psig 1025 pois pressure g.
: 1. Maximum AW                                   120'F                   100*F             120'F                     120*r Temperature J. Opeeator action                             none                     N/A               30 min.                     30 min.
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.
: 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
RC pump status Tripped 6 reactor trip Tripped All operating Tripped 1.
: 1. Normal blowdown                               none assumed             nw w umed         none ascumed               none assumed
Maximum AW 120'F 100*F 120'F 120*r Temperature J.
: u. Sensible heat                                 see cooldown             Table 2-2         see cooldown               see cooldown
Opeeator action none N/A 30 min.
: n. - Time at standby / time                         2 hr/4 hr               2 hr/4 hr to cooldown to RHR 2 hr/4 hr                 N/A
30 min.
: 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)
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
1 TABLE 2-1


==SUMMARY==
==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)
OF ASSUMPTIONS USED IN A WS DESICN VERIFICATION ANALYSES Loss of Feedw. ster Main Steamline Break Transient (ntation blackout)
: 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)
Cooldown h in Feeditne Break (con ta inment) c.
: b. Time delay from         2 sec (delay af ter     2 sec             2 sec                     0 seconds a rent to Rx trip       trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: c. AFWS actuation signal / lo h 3G level           NA                 low-low SG level         Feedvater isolation actuation signal:
(102% of 2910 MWt) case (I of 2775 MWt) b.
time delay for AWS flow I minute                                   I minute                 Safety Injaction Signal 0 see (no delay);
Time delay from 2 sec (delay af ter 2 sec 2 sec 0 seconds a rent to Rx trip trip) c.
Flow to SG: 17 see after MSLB (which is time of W isolation)
AFWS actuation signal /
: 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
lo h 3G level NA low-low SG level Feedvater isolation actuation signal:
: 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
time delay for AWS flow I minute I minute Safety Injaction Signal 0 see (no delay);
      - & after AFWS actuation                                             than 2000 sec.
Flow to SG: 17 see after MSLB (which is time of W isolation) d.
decay heat               See FSAR Figure 15.1-6                     See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
SG water level at (lo-lo SG 1evel)
: f. AW pump design           1133 psia               1133 psia         1133 psig                 1025 psig pressure
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.
: 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
Initial SG inventory 74.600 lbm/SG (at 104.500 lbm/SG 94.100 lba/SG 151.000 lbs/SG trip)
: 1. Maximum AW               120*F                   100*F             120*F                     120*F Temperature J. Operator action         none                   N/A               30 min.                   30 min.
@ 525.2*F Rate of change before See FSAR FJgure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
' 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
- & after AFWS actuation than 2000 sec.
: 1. Normal blowdown           none assumed           none assumed     none assumed               none assumed
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: c. Sensible heat           see cooldown           Table 2-2         see cooldown               see cooldown
AW pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
: c. Time at standby / time   2 hr/4 hr               2 hr/4 hr         2 hr/4 hr                 N/A to cooldown to RHR                                                                                                                     *
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.'
: 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               .
RG pump status Tripped @ reactor trip Tripped All operating Tripped 1.
(af ter 30 siinutes)     (max requirement)                     ,
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                                                                             (
X TABLE 2-1
(


==SUMMARY==
==SUMMARY==
OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES Loss of Feedwater                                                     Main Steamline Break Transient               (station blackout)       Cooldown         Main Feedline Break           (containment)
OF ASSUMPTIONS USED IN AFWS DESICN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) a.
: b. Time delay from         2 sec (delay after       2 sec             2 sec                     0 seconds event to Rx trip         trip)
Max reactor power-102% of ESD rating 2%3 MWt 102% of ESD rating 01 (of rated) - vorst (102% of 2910 MWt)
: c. AFWS actuation signal / 10-10 SC level           NA                 low-low SG 1evel         Feedwater isolation actuation signal:
(102% of 2910 MWt) case (% of 2775 MWt) b.
time delay for AWS flow I minute                                   1 minute                 Safety Injection Signal 0 sec (no delay);
Time delay from 2 sec (delay after 2 sec 2 sec 0 seconds event to Rx trip trip) c.
Flow to SC: 17 see after MSLB (which is time of W isolation)
AFWS actuation signal /
: 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
10-10 SC level NA low-low SG 1evel Feedwater isolation actuation signal:
: 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
time delay for AWS flow I minute 1 minute Safety Injection Signal 0 sec (no delay);
      & af ter AFWh actuation                                             than 2000 sec.
Flow to SC: 17 see after MSLB (which is time of W isolation) d.
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
SC water level at (lo-lo SC level)
: 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)
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.
: h. RC pump status           Tripped $ reactor trip   Tripped           All operating             Tripped
Initial SC inventory 74,600 lba/SC (at
: 1. Maximum A N               120'F                   100'F             120*F                     120'F Temperature J. Operator action         none                     N/A             30 min.                   30 min.
'104.500 lbe/SC 94.100 lba/SC 151.000 lba/SC trip)
: 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
@ 525.2*F Rate of charra before See FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
: 1. Normal blowdown         none assurced           none assumed     none assumed               none assumed
& af ter AFWh actuation than 2000 sec.
: c. Sensible heat           sie cooldown             Table 2-2         see couldown               see cooldown
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f,
: n. Time at standby / time   2 h*/4 hr               2 hr/4 hr         2 hr/4 hr                 N/A to cooldown to R11R
A W pump design 1133 psia 1133 psia 1133 psig 1025 psig pressure g.
: 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
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
TABLE 2-1


==SUMMARY==
==SUMMARY==
OF ASSUMPTIONS USED IN AWS DESIGN VERIFICATION ANALYSES Loss of Feedwater                                                     Main Steamline Break
OF ASSUMPTIONS USED IN AWS DESIGN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break
                      ' Transient               (station blackout)       Cooldown           Main Feedline Break         (containment)
' Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) n.
: b. Time delay from         2 sec (delay af ter     2 sec               2 sec event to Rx trip 0 seconds trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - vorst (102% of 2910 MWt)
: c. AfvS actuation signal / lo-lo SG 1evel           NA                 low-low SG 1evel time delay for AWS flow                                                                        Feedvater isolation actuation signal:
(102% of 2910 MWt) case (% of 2775 MWt) b.
1 minute                                     1 minute                 Safety injection Signal 0 sec (no delay);
Time delay from 2 sec (delay af ter 2 sec 2 sec 0 seconds event to Rx trip trip) c.
Flow to SC: 17 see af ter MSLB (which is time of W isolation)
AfvS actuation signal /
: 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
lo-lo SG 1evel NA low-low SG 1evel Feedvater isolation actuation signal:
: 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
time delay for AWS flow 1 minute 1 minute Safety injection Signal 0 sec (no delay);
                        & after AFWS actuation                                                                        FSAR Table 6.2-11 than 2000 sec.
Flow to SC: 17 see af ter MSLB (which is time of W isolation) d.
decay heat               See FSAR Figure 15.1-6                     See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
SG water level at (10-10 SG 1evel)
: 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                                                                                                     ,
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.
action af ter 30 minutes)
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
: b.     RG pump status         Tripped 9 reactor trip   Tripped           All operating             Tripped
& after AFWS actuation than 2000 sec.
: 1. himus AN                 120'F                   100'F             Ifb'F                     120*F Temperature J.     Operator action         none                     N/A               30 min.                   30 min.
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
3
AW pump design 1133 psia 1133 pata 1133 psig 1025 pois pressure 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
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.
: 1. Normal blowdown         none assumed             none assumed       none assumed             none assumed t2. Sensible heat           see cooldown             Table 2-2         see cooldown             see cooldewn
RG pump status Tripped 9 reactor trip Tripped All operating Tripped 1.
: s. Time at standby / time   2 hr/4 hr               2 hr/4 hr         2 hr/4 hr                 N/A                                       8
himus AN 120'F 100'F Ifb'F 120*F Temperature J.
                    -to cooldown to RHR
Operator action none N/A 30 min.
                                                                                                                                                  ~
30 min.
: 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)
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)
TABLE 2-1 SL?1 MARY OF ASSUMPTIONS USID IN AWS DESICN VERIFICATION ANALYSES 1.oss of Feedwater Main Steauline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (contairunent) c.
  - b. Time delay from         2 sec (delay after       2 see             2 sec                   0 seconds event to Rx trip         trip)
Mas reactor powee 102% of ESD rating 2963 MWt 102% of ESD rating 01 (of rated) - vorst (102% of 2910 MWt)
: 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);
(102% of 2910 MWt) case (I of 2775 MWt)
Flow to SGt 17 sec af ter MSLB (which is time of W isolation)
- b.
: 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
Time delay from 2 sec (delay after 2 see 2 sec 0 seconds event to Rx trip trip) e.
: 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
A WS actuation signal /
        & af ter AFWS actuation                                               than 2000 sec.
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);
decay heat               See F3AR Figure 15.1-6                     See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
Flow to SGt 17 sec af ter MSLB (which is time of W isolation) d.
: 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                   ,
SC vater level at (lo-lo SC level)
AFW flow                                                             action af ter 30 minutes)
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.
: h. RC pump status           Tripped @ reactor trip   Tripped           All operating             Tripped
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
: 1. Maximum AN               120'F                     100'F             120*F                   120*F Temperature
& af ter AFWS actuation than 2000 sec.
: j. Operator action         none                     N/A               30 min.                   30 mia.
decay heat See F3AR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: 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
AN pump design 1133 psia 1133 psia 113' psig 1025 psig pressure 3
: 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
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.
: n. Time at standby / time   2 hr/4 hr                 2 hr/4 hr         2 hr/4 hr                 N/A to tooldown to RHR
RC pump status Tripped @ reactor trip Tripped All operating Tripped 1.
: 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)
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
TABLE 2-1


==SUMMARY==
==SUMMARY==
OF ASSUMPTIONS USED IN ANS DESICN VERIFICATION ANALYSES Loss of Feedwater                                                   Main Steamline Break Transient                 (station blackout)     Cooldown         Main Feedline Break           (containment)
OF ASSUMPTIONS USED IN ANS DESICN VERIFICATION ANALYSES Loss of Feedwater Main Steamline Break Transient (station blackout)
: 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)
Cooldown Main Feedline Break (containment) c.
: b. Time delay from         2 see (<1elay af ter     2 sec           2 sec                     0 seconds event to Rx trip         trip)
Max reactor power 102% of ESD rating 2963 MWt 102% of ESD rating 0% (of rated) - worst (102% of 2910 MWt)
: 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);
(102% of 2910 MWt) case (% of 2775 MWt) b.
Flow to SG: 17 see af ter MSLB (which in time of W isolation)
Time delay from 2 see (<1elay af ter 2 sec 2 sec 0 seconds event to Rx trip trip) c.
: 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
A NS actuation signal /
: 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
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);
    & after A WS actuation                                                                      FSAR Table 6.2-11 than 2000 sec.
Flow to SG: 17 see af ter MSLB (which in time of W isolation) d.
decay heat               See FSAR Figure 15.1-6                   See FSAR Figure 15.1-6   See FSAR Figure 6.2-1
SG water level at (lo-lo SG Icvel)
: f. AN pu:np design         1133 psia               1133 psia       1133 psig pressure                                                                                    1025 peig
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.
: 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                                                                                                     ,
In!;;al SG inventory 74.600 lba/SG (at 104.500 lbm/SG 94,100 lbm/SG 151.000 lba/SC, trip)
action af ter 30 minutes)
@ 525.2*F Rate of change before Sse FSAR Figure 15.2.31 N/A turnaround greater FSAR Table 6.2-11
: h. RC pump status         Tripped 8 reactor trip   Tripped         All operating             Tripped
& after A WS actuation than 2000 sec.
: 1. Maximum A W             120'r                     100'F           120'F                     120*F Temperature J. Operator action         none                     N/A             30 min.                   30 min,
decay heat See FSAR Figure 15.1-6 See FSAR Figure 15.1-6 See FSAR Figure 6.2-1 f.
: 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
AN pu:np design 1133 psia 1133 psia 1133 psig 1025 peig pressure g.
: c. Sensible heat           see cooldown             Table 2-2       see cooldown             see cooldown
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.
: 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.'
RC pump status Tripped 8 reactor trip Tripped All operating Tripped 1.
AN flow rate             680 CPM - constant       variable         340 gpm - 1 min af ter   900 gpm to broken SG .
Maximum A W 120'r 100'F 120'F 120*F Temperature J.
trip - 680 gpm           350 rpm to each intact S/0                   *
Operator action none N/A 30 min.
(af ter 30 minutes)       (max, requirement) 9
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}}

Latest revision as of 03:15, 1 January 2025

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)
v • d • e


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

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