ML20010G764
| ML20010G764 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/17/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-105, NUDOCS 8109220502 | |
| Download: ML20010G764 (4) | |
Text
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SNUPPS Starriardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockvil:e, Meryland 20850 Executive Director (301) 8694010 September 17, 1981 SLNRC 81-105 FILE: 0290 SUBJ: RSB Review
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Mr. Harold R. Denton, Director 9 p[gsA-
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Office of Nuclea-Peactor Regulation g
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7 U.S. Nuclear Regulatory Commission 7887 Q' 8
Washington, D.C. 20555 7g Yh')
i Docket Nos.: STN 50-482, STN 50-483, and STN 50-486 f,
Ref: SLNRC 81-83, dated September 1, 1981, Same subject
~*
Dear Mr. Denton:
The referenced letter provided information required by the NRC's Reactor Systems Branch.
Enclosure B to the reference was tables from WCAP-7769 marked-up with SNUPPS parameters.
In discussions with the NRC, it was determined that additional information on this subject was required. This information is provided in the enclosure.
Very ruly yours,
\\ RN+r Nicholas A. Petrick RLS/dck/3b2 Enclosures cc:
J. K. Bryan, UE G. L. Koester, KGE D. T. McPhee, KCPL W. A. Hansen, NRC/ Cal I
T. E. Vandel, NRC/WC
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8109220502 810917 "DR ADOCK 05000482 A
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Enclosure to SLNRC 81-105 Required safety valve capacity (peak surge rate into pressurizer following-loss of load without trip):
3
= 1,200,000 lbm/hr = 41.15 ft /sec Actual installed. safety valve capacity (at 2500 psia + 3% accumulation):
3
= 1,260,000 lbm/hr = 43.21 ft /sec Ratto = 1,260,000 = 1.050 1,200,000
+++
Define the following ratios:
(REQUIRED SAFETY VALVE FLOW TO SHOW " ACCEPTABLE")
(RESULTS FOR TRANSIENTS IN TABLE 2-3
)
N, (ACTUAL SAFETY VALVE CAPACITY)
Wsvr-M
- Wsyc
,(ACTUAL SAFETY VALVE CAPACITY)
(REQUIRED SAFETY VALVE SIZING CAPACITY [ PEAK SURGE RATE])-
Wsvr
_Wpsur Consider tin plants:
@ = representative 4-loop plant in WCAP-7769
@ = SNUPPS O!, =
= 0.86 (1).
c V
.o(
=hy (2)
Enclosure to SLNRC 81-105 Page 2 1.056 (3)
=
1
= k surl p
k I
1.050 (4)
=
=
2 psur2 from (1) and (2)
N
"$1 2
( s 2
assume that Wsvrp _
W
~ y svri then
!W y
syc1 q 1
@svc2 2
The validity of this assumption is contingent upon the parameters in Table 2-2 being sufficiently close to those for SNUPPS that the expected transient response would be the same.
M 2 = (0.86) hl W 2 = 0.862 If it is assumed that the safety valve flow required to show accept-ability for the transients in Table 2-3 for SNUPPS is greater than that required to show acceptability in the WCAP-7769-4-loop plant by an amount proport.ional to the' amount by which the peak surge rate for SNUPPS is greater than the peak surge rate for the WCAP-7769 4-loop plant, then
_ W surp Wsvrp -
h W
~_ 41.15 p
svri psuri 41.0 4
q q
~
e-w-
,,,.ew
,s-vn w n
,,-w ps a,---
~wg-
_,,aw_.
e.
Enclosure to SLNRC 81 105 Page 3 t 1refore W
=H svc1 prar2 2
1 svc2 psurij
.15 2 = (0.86) h N 2 = 0.865 l
l s