ML19340A141
| ML19340A141 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/10/1976 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML19340A139 | List: |
| References | |
| BAW-1425, NUDOCS 8001100606 | |
| Download: ML19340A141 (6) | |
Text
- - -.
O REVISION 2 TO BAW-1425 OCONEE 2, CYCLE 2 RELOAD REPORT 8001100 [O6
4 C'
4 (6/10/76):
Revision ~
' u;ed in -the analysis are 1.087 and' 3.10 ' inches, respectively.. He results of Jthe 'two'ef fects' are -5.93% and '-3.47% change
- in :the minimum hot channel DNBR.
.l'2
[.
~
t F
tnd peaking marg n,. respectively. The changes in.these margins are sumarized i
in Table 6-1, which includes comparisons of other pertinet cycle 1 and 2 data.
}
~
-i We DNBR' analysis has.been based on a core configuration consisting of 177
. Mark B fue~ assemblies.
We incorporation 'of - two Mark -C demonstration fuel l;
i
'a:semblics in. batch 4 in(place: of two Mark 'B assemblies, results in 'an increase
~ in.the overall marginf to DNB, as ' discussed in reference 2.
T
~ *Change from unic. ified values. These are actually an improvement over cycle 1' densified conditions.
7 6-3 Babcock &Wilcox 4
=
{
y y
.p
t 4
~
f
- p.
' Cycle 1 and 2 Maximum Design Conditions Table 6-1.
1 Cycle 2 Cycle 1
{
2568 2568 Design-power level, MWt 2200 2200 System pressure,. psia 107.6 100.0 Reactor coolant flow, % design flow Vessel' inlet coolant temperature, 554.0 555.9 100% power, F-Vessel outlet coolant temperature, 603.8 602.2
-100% power, F
_Ref design radial-local power -
1.78 1.78 peaking factor-1.5 cosine
' 1.5 cosine Ref. design axial flux shape 141.1 (dens.)
~
144 (undens.)
' Active fuel length, in.
-Avg heat flux, 100% power, 171,470 174,995 2
Btu /h-ft Max heat flux,100% power, 457,825 467,236 2 (for DNBR calc) iBtu/h-ft B&W-2 W-3 CHF correlation 1.55 1.98
. Minimum DNBR (max design ~ conditions, (114% power)
(112% power)
(
no densif penalties)
~
Hot channel factors
~
1.011 1.011 1.014
- Enthalpy rise 1.014 0.98 Heat flux 0.98-Flow area
-Densification effects
-5.93 4
-6.08 2
~ Change'inLDNBR margin, %
4
-3.47
-2.82 Change in power peaking margin, %
i
- i:
?I Ba'bcock & \\Vilcox 6-4^
iD
Revis' ion-2'(6/10/76)
'8..
PROP 0 SED MODIFICATIONS T0' TECHNICAL SPECIFICATIONS c
i ne' Technical' Specifications have been revised, for cycle 2 operation.
Ch'anges
. were the -results of the following:
1.
Using the_ B&W CHF-correlation rather - than W-3,- as discussed in section 6.1.
2.
Using a 95/95 confidence level rather than 99/95, as discussed in
'section 6.1.
3.
Using 107.6%' of ' design flow rather than 100%, as discussed in section 6.1.
4.
Usir.g tns Final Acceptance Criteria LOCA Analysis for restricting peaks during operation, as discussed,in section 7.14.
- 5.
Revising' the' assumptions on which the flux flow RPS setpoint is based.
This setpoint now accounts-for signal noise on the basis of data accumulated from operating B&W reactors.
6.
An analysis incorporating the effecti, of fuel rod bow on core parameters.
7.
The_ penalty on core coolant flow due to an assumed open vent valve has been eliminated based on a vent valve surveillance program performed 2
during each refueling shutdown.
Based on the Technical-Specifications derived from the analyses presented '
in this report, the Final Acceptance Criteria ECCS limits will not be exceeded, nor will the thermal ' design criteria be violated.
Figures 8-1 through 8-14 illustrate revisions to' previous Technical Specification safety limits.
8 Babcock & Wilcox s
e
(,
2600 2400 Acceptable
{
Operation w
to C2.
2200 E
a 0
3 2000 Unacceptable t;
o Operat. ion O
-l 1800
/
1600 560 580 600 620 040 660 Reactor Outlet Temperature F
e e
UNIT 2. CYCL.E 2 CORE PROTECT 10N SAFETY 1.l!AIT
- Figure 8-1 9-
.~
O j
S h
e 6
O O
e W
.s e
W.
2600-l s
.2400 sb Acceptable D.N Operation J
$g 2200 m
E 5
2000
/
0 Unacceptable Operation
~
1800
.f e
1600 560 580 600 620 640 660 Reactor Outlet Temperature F REACIOR COOLANT FLOW
-CURYE LBS/HR POWER PUldPS OPERATING (TYPE OF LIMIT) 1 141.3 x 106 (100%)
112%
Four Pumps (DNBR Limit)
.2 105.6 x 106 (74.7%)
86%
Three Pumps (DNBR Limit) 3 69.3 x'106 (49.0%)
58%
One Pump in Each loop 3
, -(Quality Limit)
UNIT 2 CYCLE 2
- CORE PROTECTION SAFETY LIMITS Figure 8-3 9
9 4
e e
e 6