ML19323A503
| ML19323A503 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/14/1980 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Schwencer A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| References | |
| TAC-44632, NUDOCS 8004210283 | |
| Download: ML19323A503 (4) | |
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15219 April 14, 1980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Revised Submittal For Information On Auxiliary Feedwater System Gentlemen:
On March 25, 1980, we submitted additional information on the requirements for the Beaver Valley auxiliary feedwater system as requested in*your letter dated January 22, 1980. Subsequently, we were notified by our NSSS vendor that there were several additions or corrections to Tables 1B-1, 2-1 and 3-1 of the submittal. Therefore, please find attached the three revised tables which should replace the tables in the original submittal. The areas of revision are indicated by a vertical line in the right margin.
Should you have any questions, please contact this office.
Very truly yours, i
l l
'[..
C. N. Dunn Vice President, Operations Attachment f
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0004210283
TABLE 10-1 Criteria for Auxiliary Feedwater System Design Basis Conditions Condition or Additional Design Transient Classification
- Criterla*
Criteria Loss of Main Feedwater Condition II
' Peak RCS pressure not to exceed design pressure. No consequential fuel failures Station Blackout Condition II (sameasLMFW)
Pressurizer does.not fill with 1 single motor driven aux.
feed pump feeding 2 SGsc Steamline~ Rupture Condition IV 10CFR100' dose limits.
containment design pressure not exceeded Feedline Rupture Condition IV 10 CFR 100 dose limits.
Core does not uncover RCS design pressure not l
exceeded Loss of all A/C Power N/A Note 1 Same as blackout assuming turbine driven pump Loss' of Coolant Condition III 10 CFR 100 dose limits 10 CFR 50 PCT limits Condition IV IOCFR100 dose. limits 10 CFR 50 PCT limits Cooldown N/A 1000F/hr 5470F to 3500F oRef:
ANSI N18.2 (This information provided for those transients performed.in the FSAR).
Note 1 Although this transient establishes the basis for AFW pump powered by a diverse power source, this is not evaluated relative to typical criteria since multiple failures must be assumed to postulate this transient.
Fidkr4Lfirm
TABLE 2-1 Suonary of Asstrnptions Used in AfWS Design Verification Analyses Loss of Feedwater Main $temallne Break Transient (station blackout)
Cooldown Hain Feedline Break (containment) a.
Max reactor power 102% of ESO rating 2660 MWt 102% of ESD rating O. 30, 102% of rated (102%of,2114MWt)
(102% of 2114 MWt)
(%of2660MWt) b.
Time delay from 2 sec 2 sec 2 sec variable event to Rx trip c.
AFWS actuation sig-10-10 SG 1evel NA low-low SG level Assumed imediately nal/ time delay for 1 minute Osec(nodelay)
AFWS flow d.
SG water level at (10-10 SG 1evel)
NA (10 SG 1evel + stean-N/A time of reactor trip 0% NR span feed mismatch) 2 9 20% i;R span 1 9 tube sheet e.
Initial SG inventory 60,700 lbm/SG (at 100,832 lbm/SG 93; d Ibm /SG consistent with power trip) 9 516.80F Rate of change before See FSAR Figure 14.1.31 N/A turnaround.c 2055 N/A
& af ter AFWS actuation sec.
decay heat See FSAR Figure 140-6 See FSAR Figure 14D-6 See FSAR Figure 14D-6 f.
AFW pump design 1133 psia 1133 psia 1133 psia N/A pressure g.
Minimin f of SGs 2 of 3 N/A 2 of 3 N/A which must receive AFW flow h.
RC pump status Tripped 9 reactor trip Tripped Tripped 9 reactor trip All operating l
1.
Maximus AFW 1200F 1000F 1200F equal to main feed temperature temperature J. Operator action none N/A 10< min.
10 min, 3
3 3
k.
MFW purge voline/ temp.
100 ft /4350F 150 f t /
3 305 f t /436.20F 800ft/ loop (fordryout 436.20F time) 1.
tiormal blowdown non's assaied none assumed none assumed none assumed m.
Sensible heat see cooldown Table 2-2 see cooldown N/A n.
Time at standby / time 2 hr/4 hr
' 2 hr/4 hr 2 hr/4 hr N/A to cooldown to RIR o.
AFW flow rate 350 GPH - constant variable 350 gpo - constant 1595 GPM (constant) to (min. requirement)
(after10 min.)
broken SG.
(min. regolroment)
(max. requirement)
Revised Page
TABLE 3-1 3
Auxiliary Feedwater Flow (1) to Steam Generators Following an Accident / Transient with Selected Single Failure - GPM Single Failure Elec. Train TD Pump M0 Pump CV(2)
Accident / Transient Failure Failure Failure Failure A
B C
D 1.
Loss of Main FW 1050 700 1050 1400
'2.
Feedline Rupture (3)
(3)
(3)
(3) 3.
Blackout 1050-700 1050 1400 4.
Cooldown 1050 700 1050 1400 5.
Main Steamline (3)
(3)
(3)
(3)
Rupture 6.
Main steamline
<1440
<1440
<1440
<1440 Rupture l
Notes:
(1) Items 1 thru 5 are minimum expected flows to intact loops; item 6 is maximum possible ficw to the faulted loop.
(2) Including only those CVs in the AFWS.
" Failure" is interpreted as failure to close on reverse flow permit flow in tne normal direct;on is not considered. failure of the CV to open to i
(3) Ten minute operator action is required to isolate AFW flow to faulted loop.
Prior to operator action, flow is 0 gpm to unfaulted loops; after operator action, flow is >350 gpm to unfaulted loops.
Revised Page
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