ML20196G218
| ML20196G218 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/29/1988 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20196G207 | List: |
| References | |
| NUDOCS 8803070083 | |
| Download: ML20196G218 (9) | |
Text
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- nockst No.,50-346' Licinin No. NPF-3 Strimi yo'. 1461 3
ge i
FORINFDMilDN DN!Y INSTRUMENTATION STEAM AND FEE 0 WATER RUPTURE CONTROL SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.2 The Steam and Feedwater Rupture Control System (SFRCS) instr' amen-tation channels shown in Table 3.3-11 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-12 and with RESPONSE TIMES as shown in Table 3.3-13.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
i
(
a.
With a SFRCS instrumentation channel trip setpoint less con-servative than the value shown in the Allowable Values column of Table 3.3-12, declare the channel inoperable and apply-the 1
applicable ACTION requirement of Table 3.3-11, until the channel is restored to OPERABLE status with-the trip setpoint adjusted consistent with the Trty Setpoint value.
b.
With a SFRCS instrumentation channel inoperable, take the action shown in Table 3.3-11.
i i
SURVEILLANCE REQUIREMENTS i
- 4. 3. 2. 2.1 Each SFRCS instrumentation channel shall be demonstrated 1
j' OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies
{
shown in Table 4.3-11.
4 4.3.2.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated i
OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing l
of each channel affected by bypass operation.
4.3.2.2.3 The STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME of each SFRCS function shall be demonstrated to be within the limit at 1 east once per 18 months. Each test shall include at least one channel l
per function such that all channels are tested at least once every N l
i times 18 months where M is the total number of redundant channels in a j
specific SFRCS function as shown in the "Total No. of Channels" Column i
of Table 3.3-11.
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STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION G4 G
MINIMINI M
TOTAL NO.
CHANNELS CHANNELS FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE ACTION E
Q 1.
Main Steam Pressure Low Instrument Channels
- 2 1
2 13#
a.
PS 3689A Steam Line 1 Channel 1 PS 36898 Steam Line 1 Channel I b.
PS 3689C Steam Line 2 Channel 1 m,q y
,;l
@g PS 36890 Steam Line 2 Channel 1 "llClg==3 g
<=
e.
=
c.
PS 3689E Steam Line 1 Channel 1 g
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PS 3689F Steam Line 1 Channel 1 i g?!
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75 N Y
d.
PS 3689G Steam Line 2 Channel 1 e 8 c, 2
PS-3689H Steam Line 2 Channel I w 8 g.
ym m
e.
PS 3687A Steam Line 2 Channel 2
,[G G@N mo FT=2 PS 36878 Steam Line 2 Channel 2' ggg Qq m m
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f.
PS 3687C Steam Line 1 Channel 2 5"5 O
gh 2
PS 3687D Steam Line 1 Channel 2 M
s", 5 ~
g.
PS 3687E Steam Line 2 Channel 2 C
Zr PS 3687F Steam Line 2 Channel 2 m
kC h.
PS 3687G Steam Line 1 Channel 2 PS 368711 Steam Line 1 Channel 2 9
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TABLE _3.3-11 (Continued)_
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-mw STEAM AND FEEtWATER RUPTURE CONTROL SYSTEM INSTRUE NTATION O$i i
G MIN!mM N
TOTAL. NO.
CHANNELS CHANNELS t
OF CHANNELS TO TRIP OPERABLE ACTION l
FUNCTIONAL UNIT-g
.4 2.
Feedwater/ Steam Generator i
Differential Pressure - High Instrument Channels 2
1 2
13#
a.
PDS 2685A -Feedwater/ Steam Generator 2 Channel 2 PDS 26858 Feedwater/ Steam Generator 2 Channel 2~
b.
PDS 2635C Feedwater/ Steam Generator 2 Channel 1 l
PDS 26850 Feedwater/ Steam Generator 2 Channel 1
.g i
R c.
PDS 2686A Feedwater/ Steam Generator 1 Channel 1 PDS 26868 Feedwater/ Steam Generator 1 Channel 1 C/lllr w
- c. -.
b d.
PDS 2686C Feedwater/ Steam Generator 1 Channel 2 g
POS 26860 Feedwater/ Steam Generator 1 Channel 2 gp 3.
Steam Generator Level - Low Instrument Channels 2
1 2
a.
LSLL SP988 Steam Generator 1 Channel 1 b
I LSLL SP989 Steam Generator 1 Channel 1
@M g
gC D
b.
LSLL SP9A6 Steam Generator 2 Channel 1
! =
)
3 l
g LSLL SP9A7 Steam Generator 2 Channel 1 O
g 3 i
E s
P P1 J
- c. -8.SLL SP9AS Steam Generator 2 Channel 2 Qg 3
o
}
g LSti. SP9A9 Steam Generator 2 Channel 2 i
j i
O j
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ECZE>
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~tzs TABLE 3.3-11 (Continued)
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STEAM AMD FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION O
MINIftM M
TOTALi:0.
CHANNELS CHANNELS FUNCTIONAL UNIT.
0F CHANNELS TO TRIP OPERABLE ACTION g
~~.
3.
Steam Generator Level - Iow Instrument Channels (continued) d.
LSLL SP986 Steam Generator 1 Channel 2 LSLL SP937 Steam Generator 1 Channel 2 4.
Loss cf RCP Channels 2
1 2
138 i
5.
Manual Initiation (Push buttoas) a.
Steam Pressure - Low 4
2 4
14 Y
b.
Level Steam Generator - Low 2
1 2
14 2
c.
Feedwater a P - High 2
1 2
14 d.
Loss of RCP's 2
1 2
14
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Docket No. 50-346 Licente'No. NPF-3 Serial No.!1461 AD0lil0NAL CHANGES PREVIOUSLY PROPOSED BY LETTER S0fial No.,_]d Date_II/2/97 Page 5 o
3 TABLE 3.3-11 (Continued)
TABLENOTAT!g 7oo
- May be bypassed when steam pressure is below 650 psig.
Bypass shall be automatically removed when the steam pressure exr.eeds fr50 psig.
750 i The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 13 With the nunber of OPERABLE Channels one less than the Total flunber of Channels, startup and/or power operation may proceed until perfomance of the next required CHANNEL FUNCTI0fiAL TEST provided the incperable sec-tion of the channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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4 DAVIS-BESSE. UNIT 1 3/4 3-27 Amendment No. 31 l
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STEAM AND FEEDWATER RUPTURE 00kTa0L SYSTEM
,1, th5TidHENTATT5FTATF 5Eip01NTs Q
s.
v.
FUNCTIONAL UNITS TRIP $tTPOINTS ALLOWASLE VALUES Ey 1.
Steam Line Pressure - Low
> 591.5 psig
> 591.6 psig*
se 1586.6 psig**
III 26" H O
> 20*.H 0*
2.
Steam Generator Level - Low 2
a
> is.ar n o.*
2 z
~
3.
DifforentialPressure-High(2)
< 197.5 psid 3y; i 97.5 psid*
1 2gg i 199.5 psid**
2 I
b
< 1384.6 empsI 4.
Reactor Coolant Pumps - Loss of High 1 1384.6 amps Low 1 106.5 anos E' =
{ 10s.5 amps 8
{
D*$
Y 5
m
--4 Si
'g G
mg W##
IIIMeasured above the lower steam generator tubesheet, q
(2)Where differentisi pressure is steam generator minait fe* Muster pressure.
Q 3D NE Allowable Value for CHANNEL FUNCTIONAL TEST M-m 5
..Allowable Value for CliANNEL eJLLISRATI0li Allowable Value for CHANNEL FUNCTIONAL TEST and CHANNEL CAllthAT!0ft N
f, CD gag CD
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Dockst No. 50-346 L'ic:nna No. NPF-3 a
4 Ssiini No. 1461 TABLE 3.3-13 1
i STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMES ACTUATED EQUIPMENT RESPONSE TIME IN SECONDS 1.
Auxiliary Feed Pump 10 4
2.
Main Steam Isolation Valves 16 l
3.
Main Feedwater Valves a.
Main Control
<8 b.
Startup Control 7 13 c.
Stop Valve 7, 16 4.
Turbine Stop Valves
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i DAVIS-BESSE. UNIT 1 3/4 3-29 i
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Docket Uo'.~50-346
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Licpnse No. NPF-3 THEi Serial No. 1461 gg g g'
'Attachent 3 Page 9 3/4,7
[ N ST RU. MENT AT ICN_
i BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND bi@ hl I 515ILM INSTRUMENTATION y
e The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systams d
M ensure that 1) the associated action and/or trip will be initiated when 8
4 the parameter :nonitored by each channel or combination thereof exceeds 5 5 ",
its setpoint, 2) the specified coincidence logic is maintained 3) i EEw sufficient redundancy is maintained to permit a channel to be out of m"
service for testing or maintenance. and 4) sufficient system functional yE capability is available for RPS, SFAS and SFRC3 purposes from diverse
<o parameters.
5Mr 5g$I The OPERA 8!LITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility E
e design for the protection and mitigation of accident and transient con-8 v,
di t.i o ns. The integrated operation of each of these systems is consistent i
A with the assumptions used in the accident analyses.
'The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable t
S to the original design standards. The periodic surveillance tests N
h performed at the minimum frequencies are sufficient to demonstrate this 9 mi capability.
W*hdE The measurement of response time at the specified frequencies a
a-provides assurance that the RPS, SFAS, and SFRCS action function associated E*
with each channel is completed within the time limit assumed in the
@$3 safety analyses. No credit was taken in the analyses for those channels
< o ~g with response times indicated as not applicable.
m2 55 Reconse time may be deonstrated by any series of sequential.
g E
E overlapping or total channel test measurements provided that such test 2
2 demonstrate the total channel response time as defined. Sensor response a
time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sehsors with certified response times.
An SFRCS channel consists of 1) the sensing device (s). 2) associated i
6 3
logic and output relays including Isolation of Main Feedwater Non Essential Valves and Turbine Trip)(, and 3) power sources.
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e 4
1 w
E$3 Safety-grade anticipatory reactor trip is initiated by a turbine trip (above 25 percent of RATED THERMANL POWER) or trip of both main feedwater g=
pump turbines. This anticipatory tr.ip will operate in advance of the 58_
reactor coolant system high pressure reactor trip to reduce the peak' C3 8 a reactor coolant system pressure and thus reduce challenges to the power y Si 0 operated relief valve. This anticipatory reactor trip system was eE, installed to satisfy Ites !!.K.2.10 of NUREG-0737.
5 5
2 a
l A
DAVIS-8 ESSE Unit 1 8 3/4 3-1 Amendment No. 73