ML20083M050
| ML20083M050 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/11/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20083M038 | List: |
| References | |
| NUDOCS 9505190093 | |
| Download: ML20083M050 (19) | |
Text
. _ _ _ _ - _ _ _ _ _ _ _ _ _
i j
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BRONNS FERRY NUCLEAR PLANT (BFN)-
UNITS 1, 2 AND 3
,l l
l PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-359 l
NARKED PAGE8 i
l 1.
AFFECTED PAGE LIST l
}
Unit 1 Unit 2 Unit 3 J
1 3.1/4.1-5 3.1/4.1-5 3.1/4.1-3 l
3.3/4.1-4 3.1/4.1'8 3.1;'4.1-10 3.1/4.1-15 II.
MARKED PAGES l
See attached.
i 1
1 1
1 1
J I
9505190093 950511 PDR ADOCK 0500 9
l-P
+.[*' ;
NOTES FOR TABfE 3.1.A' There shall be two o_ggthMe or tripped trip systems for each function.
'1.
If the minintan numbe? 5T{pegabit instrument channels per trip system cannot be met for one trip sysFem, trip the inoperable channels or entire 1
trip. system within one hour, or, alternatively, take the below listad action for that trip function. If the minimum number of.gpargle, instrument channels cannot be met by either trip system,~t W appYopriate action listed below (refer to right-hand. column of Table) shall be
. An inoperable channel need not be placed in the tripped condition taken.
where this would cause the trip function to occur. In these cases, the inoperable channel shall be restored to gor g y status within two hours, or take the action listed below for that trip Tunction.
b e rods and complete insertion of all Initiate insertion of pgetA_}is. In refueling mode, suspend all A.
opetabli rods within f"oisiTou operatT5ns involving core alterations and fully insert all opgg,le
~
control rods within one hour.
B.
Reduce power level to IBM range and place mode switch in the.
STARTUP/ HOT Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within I
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30 percent of rated.
2..
5 as disp)arge voi high bypaa may be u in sh own af to reactor p' ass s#am dise e volum as o ten I
ot ipa a r
3.
Bypassed if reactor pressure is less than 1055 psig and mode switch not
]
in RUN.
I 4.
Bypassed when turbine first stage pressure is less than 154 pais.
5.
IBMs are bypassed when APRMs are onscale and the reactor mode switch is I
in the RUN position.
1 6.
The design permits closist ff any two lines without a scram being j
initiated.
7.
When the reactor is suberitical and the reactor water temperature is less
. l than 212 F, only the following trip functions need to be Leg g }p j
0 A.
Mode switch in shutdown The scram discharge volume f
B.
Manual scram high water level bypass may be used in SHUTDOWN or REFUEL to t
C.
High flux IRM bypass the scram discharge volume high-high water level l
D.
Scram discharge volume high level
[,#*",",]1""11",r rt t
trip. A control rod withdraw E.
APRM 15 percent scram block is present when this j
scram signal is bypassed.
BFN 3.1/4.1-5
]
Unit 1 1
j :,*
i 1
6 i
I NOTES FOR TARfF 3.1.A 1.
.There shall be two OPERABLE or tripped trip systems for each function.
If the minimum number of OPERABLE-instrument channels per trip system cannot be met for one trip system, trip th channels or entire l
trip system within one hour, or, alternatively, t the below listed action for that trip function. If the minimum number of OPERABLE instrument channels cannot be met by either trip system, the appropriate action listed below (refer to right-hand column of Table) shall be taken. An channel need not be placed in the tripped condition where this o d cause the trip function to occur. In these cases, the l
I channel shall be restored to OPERABLE status within two hours, r ake the action listed below for that trip function.
A.
Initiate insertion of OPnant.m rods and complete insertion of all OPERABLE rods within four hours. In refueling mode, suspend all operations involving core alterations and fully insert all OPERABLE control rods within one hour.
B.
Reduce power level to IBM range and place mode switch in the STARTUP/ HOT Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
i C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power,to less than 30 percent of rated.
2.
Se an dis rge volget high as may used in'8 o
l ass am die ge vol scram scram p air b y
a with r
ek tor rot sy set.j l
3 3.
(Deleted) 4.
Bypassed when turbine first stage pressure is less than 154 pais.
5.
IBMs are bypassed when APRMs are onseale and the reactor mode switch is in the RUN position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is suberitical and the reactor water temperature is less than 212'T, only the following trip functions need to be OPERABLE:
)
A.
Mode switch in SHUTDOWN W '
i B.
'Ibe scram discharge volume high water level bypass may be used in SHUTDOWN C.
High flux IRN or REFUEL to bypass both the scram l
discharge volume high-high water level and D.
Scram discharge voltase high level scram pilot air header low pressure scram j
signals in order to reset the reactor E.
APRM 15 percent scram protection system trip. A control rod withdraw block is present when these
)
F.
Scram pilot' air header low pressure scram signals are bypassed.
BPN 3.1/4.1-5 Unit 2
TA8Lt 3.1.A REACTOR PROTECTION SYSTEM (SCmut) INSTHLSelTAfl0N REQUIREMENTS c to Min. No. of
&Q Operable et Instr.
Modes in Which Function Channels Insat te Omerable w
Per Trip Shut-Startup/
jystem (1)(231 Tris Function Trls Level Settine h gefuel (71 glat Standby 33g Actlen (1) 2 High Water level in West Scram-Discharge Tank (LS-85-45A-0) 1 50 Gallons X(2)
X(2)
)(
X 1.A 2
High Water Level in East Scram Discharge Tank' (L5-as-45E-M) i 50 Gallons X(2)
X(2)
X X
1.A 4
Main Steam Line 1101 Valve Closure X(6) 1.A or 1.C Isoletten Valve Closure w
2 Turbine Centrol 1550 psig X(4) 1.A er 1.0 Valve Fast 8
8 C
Closure er Turbine irly Y
4 Turblee Step 1101 Valve Closure X(4) 1.A er 1.9 8
Valve Closure
~
2 Turbine First not 1154 pelg X(10)..
-X(IS)
X(IS) 1.A er 1.0 (19)
St er.ssere Permissive W
Y g
f_ f,_ g/) b SD ry f
A.,
Ha../a, q
r,,,, -c l
. M w
CE r..
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t NovES FOR v1Rf2 3.1.A There shall be two OPERABLE or tripped trip systems for each function.
1.
If the minimum number of OPERABLE instrument' channels per trip system M channels or entire cannot be met for one trip system, trip the I f# "a 8 the below listed trip system within one hour, or, alternatively, t If the minimum number of OPERARLE action for that trip function.
instrument channels cannot be met by either trip system, the appropriate action listed below efer to right-hand column of Table) shall be J
channel need not be placed in the tripped condition taken. An I cause the trip function to occur. In these cases, the who e this g fr/ rhannel shall be restored to OPERABLE status within two hours, I
or take the action listed belov for that trip function.
i 1
Initiste insertion of OPERABLE rods and complete insertion of all _
A.
OPERABLE rods within four hours. In refueling mode, suspend all operations involving core alterations and fully insert all OPERABLE control rods within one hour.
Reduce power level to IRM range and place mode switch in the l
B.
STARTUP/ HOT STANDBY position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Reduce turbine load and close main steam line isolation valves within C.
a hours.
D.
Reduce power to less than 30 percent of rated.
2.-
Se die evolumehQlfbypassma used in a own or nel t ass se dischar olume a w th contro
- h1^_
or ote o
eset.
3.
DELETED Bypassed when turbine first stage pressure is less than 154 peig.
4.
IBMs are bypassed when APRMs are onseale and the reactor mode switch is 5.
in the RUN position.
The design permits closure of any two lines without a scram being 6.
initiated.
When the reactor is suberitical and the reactor water temperature is less 7.
than 212'F, only the following trip functions need to be OPERABLE:
A.
Mode switch in shutdown
'Ihc scram discharge volume high water level bypsse may be used in SHUTDOWN B.
Manual scram or REFUEL to bypass both the scram C.
Nigh fluz IRN discharge volume high-high water level and 4
scram pilot air header low pressure scram D.
Scram discharge vol me high level signals in order to reset the reactor protection system trip. A control rod withdraw block is present when these -
E.
- E"* *" bYP"*d-l
- p. 5;c.. p:u.,4.L L.7m.1m 3.1/4.1-4 BFN Unit 3
?..
TABLE 4.1.A (Continued)
Grove (21 Functlenal Test Minisus Freauencvf31 c tw
$, Q High Water Leve' In Scram Discharge e
Tant Float Switches (LS-85-45C-F)
A Trip Channel and Alarm Once/ Month Electronic Level Switches (LS-85-45A. 8. G. M) 8 Trip Channel and Alarm (7)
Once/ Month Mala Steam Line Isolation valve Closure A
Trip Channel and Alarm Once/3 Months (8)
Turbine Control Valve Fast Closure or turbine trly A
Trip Channel and Albra Once/ Month (1)
Turbine First Stage Pressure A
Trip Channel and Alarm Every three months Permissive Turbine Stop Valve Closure A
Trip Channel and Alaru Once/ Month (1) la w L A /d & M. d e A
py ch.~,in/4%~
me/C %//s o
huan (n 85-1r At, s?, Af
+ 02) 2 E
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TABLE 4.1.8 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMJM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS c: te rE Instrument Channel Grous (1)
Calibration Minimum Fr_ s:::wf21 w
IRM High Flux C
Comparison to APRM on Controlled Note (4)
Startups (6)
APRM High Fluu Output Signal 8
Heat Balance Once Every 7 Days Flow Blas Signal 8
Calibrate Flow Slas' Signal (7)
Once/ Operating Cycle LPfet Signal 8
TIP System Traverse (8)
Every 1000 Effective Full Power Hours High Reactor Pressure A
Standard Pressure Source Every 3 Months High Drywell Pressure A
StandardfressureSource Every 3 Months Reactor Low Water Level A
Pressure Standard Every 3 Months High Water Level in Scram u.
Discharge Volume C
Float $ witches e-(LS-85-45C-F)
A Callbrated Water Column (5)
Note (5)
Electronic Lvl Switches 4
(L5-85-45-A. 8. G, H)
B Calibrated Water Column Once/ Operating Cycle (g)
Main Steam Line Isolation valve Closure A Note (5)
Note (5)
Turbine First Stage Pressure Standard Pressure Source Every 6 Months Permissive A
Turbine Control Valve Fast Closure or Turbine Trip A
$tandard Pressure Source Once/ Operating Cycle
' Turbine stop Valve Closure A
Note (5)
Note (5) s nu nn 6~
0-P8 M e>
m.s r,,',-. w er-u,u, cw sw m Y
g w
g A.7, s3 1, + s.2)
N P
C)I
- - ~.
I:
/w Scram f$
- ir deaeke fM/sm '
3.1 38333,(cont'd) be acce==adated which would result in slow scram times or partial control To preclude this occurrence, level switches have been rod insertion.
provided in the instrument voltane which alarm and scram the reactor when the volume of water reaches 50 gallons. As indicated above, there is sufficient volume in the piping to aer==adate the scram without impairment of the scram times or amount of insertion of the control rods. This function shuts the reactor doun while sufficient volume r
remains to accr==adate the discharge water and precludes the situatim in which a scram would be required but not be able to perform its function adequately.
A source range monitor (SIBI) system is also provided to supply additional t
neutron level information during startup but has no scram functions.
l Thus, the IIDI is required in the REPUBL Reference Section 7.5.4 FERR.
In the power range the APIDI system provides required and STARTUP modes.
protection. Reference section 7.5.7 FBAR. 'mus, the IRC System is not required in the RtRI mode. The APRMs and the IRMs provide adequate coverage in the STARTUP and intermediate range.
The high reactor pressure, high drywell pressure, reactor low water levol i
g and scram discharge volume high level scrans are required for STRRTUP and i
RUN modes of plant operation. They are, therefore, required to be operational for these. modes of reactor operation.
The requirement to have.the scram functions as indicated in Table 3.1.1 OPERABLE in the REFUEL mode is to assure that shifting to the REFUEL made during reactor power operation does not diminish the need for the reactor protection system.
Because of the APISI downscale limit of 2,3 percent uhen in the RUN mode e
and high level limit of.$15 percent when in the STRRTUP Node, the transition between the STRRTUP and Rtaf Modes must be made with the APRN instrumentation indicating between 3 percent and 15 percent of rated i
In addition, the IRN system power or a control rod scram will occur.
of scale) or a l
must be indicating below the.High F1 tat setting (120/125 scram will occur when in the STRRTUP Mode. For normal operating conditions, these limits provide assurance of overlap between the IIst-system and AP5BI system so that there are no " gaps" in the power level indications (i.e., the power level is continuously monitored from beginning of.startup to full power and from full power to shutdown).
When power is being reduced..if a transfer to the STARTUP made is made and the IRMs have not been fully inserted (a maloperational but not impossible condition) a control rod bloctc ismediately occurs so that reactivity insertion by control rod withdrawal cannot occur.
'Ibe low scram pilot air header pressure trip performs the same function as the high water level in the scram discharge instrument volume for fast fill events in which the high level instrument response time may be inadequate. A fast fill event is poshdae~1 for certam degraded control air events in which the scram outlet valves n==r enough to allow 5 gpm per drive leakage into the scram discharge volume but not enough to cause control rod insertion.
3.1/4.1-15 j
BrN-Unit 3 f
.p ENCLOSURE 3 TENNES8EE VALLEY AUTHORITY
. BROWN 8 FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2 AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE T8-359 REVISED PAGE8 I.
AFFECTED PAGE LIST Unit 1 Unit 2 Unit 3 l
3.1/4.1-5 3.1/4.1-5 3.1/4.1-3 i
3.1/4.1-6 3.1/4.1-6 3.1/4.1-4 3.1/4.1-5 3.1/4.1-8 3.1/4.1-10 3.1/4.1-15 II.
REVISED PAGE8 See attached.
~
-=
in. 4 ij? ' ' ;
2 N' NOTES FOR TABLE 3.1.A' 1.
There shall be two OPERABLE or tripped trip systems for each function.
If the minimum number of OPERABLE instrument channels per trip system cannot be met for.one trip system, trip the inoperable channels or catire trip' system within'one hour, or, alternatively, take the below lirced action for that trip function. If the minimum number of OPERABLy.
l instrument channels cannot be met by~either trip system, the appropriate action listed below (refer to right-hand column.of Table) shall'be taken. An inoperable channel need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, the inoperable channel shal1~be restored to OPERABLE status within two hours, l or take the action listed below for that trip function.
]
A.
Initiate insertion of OPERABLE rods and complete insertion of_all OPERABLE rods within four hours. In refueling mode, suspend all
?
operations involving core alterations and fully insert all OPERABLE control reds within one hour.
B.
Reduce power level to IRM range and place mode switch in the STARTUP/ HOT Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30 percent of rated.
2.
The scram discharge volume high water level bypass may be used in f
SHUTDOWN or REFUEL to bypass the scram discharge volume high-high water level scram signal in order to reset the reactor protection system trip.
A control rod withdraw block is present when this scram signal is bypassed.
3.
Bypassed if reactor pressure is less than 1055 psig and mode switch not in RUN.
4.
Bypassed when turbine first stage pressure is less than 154 pais.
5.
IRMa'are bypassed when APRMs are onscale and the reactor mode switch is i
in the RUN position.
i r
6.
The design permits closure of any two lines without a scram being initiated.
l
[
7.
When the reactor is suberitical and the reactor water temperature is less than 212 F, only the following trip functions need to be OPERABLE:
l 0
I A.
Mode switch in shutdown 1
i B.
Manual scram C.
High flux IRM BFN 3.1/4.1-5 Unit 1
4 NOTES FOR TABLE 3.1.A (Cont'd)
D.
Scram dise'e ge volume high level E.
8.
Not required to be OPERABLE when primary containment integrity is not required.
9.
(Deleted) 10.
Not required to be OPERABLE when the reactor pressure vessel head is not bolted to the vessel.
11.
The APRM downscale trip function is only active when the reactor mode switch is in RUN.
12.
The APRM downscale trip is automatically bypassed when the IRM instrumentation is OPERABLE and not high.
13.
Less than 14 OPERABLE LPRMs will cause a trip system trip.
14.
Channel shared by Reactor Protection System and Primary Containment and Reactor Vessel Isolation Control System. A channel failure may be a channel failure in each system.
15.
The APRM 15 percent scram is bypassed in the RUN Mode.
16.
Channel shared by Reactor Protection System and Reactor Manual Control System (Rod Block Portion). A channel failure may be a channel failure in each system. If a channel is allowed to be inoperable per Table 3.1.A, the corresponding function in that same channel may be inoperable in the Reactor Manual Control System (Rod Block).
17.
Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
18.
This func. tion must inhibit the automatic bypassing of turbine control valve fast closure or turbine trip scram and turbine stop valve closure scram whenever turbine first state pressure is greater than or equal to 154 psig.
19.
Action 1.A or 1.D shall be taken only if the permissive fails in such a manner to prevent the affected RPS logic from performing its intended i
function. Otherwise, no action is required.
20.
(Deleted) 21.
The APRM High Fit ' and Inoperative Trips do not have to be OPERABLE in the REFUEL Mode 11 the Source Range Monitors are connected to give a ncncoincidence, High Flux scram, at 5 x 105 cps. The SRMs shall be OPERABLE per Specification 3.10.B.1.
The removal of eight (8) shortins links is required to provide noncoincidence high-flux scram protectira from the Source Range Monitors.
3.1/4.1-6l BFN Unit 1 s
- g NOTES FOR TARYJ 3.1 A 1
1.
There shall be two OPERABLE or. tripped trip systems for each function.
I If the minimum number of OPERABLE instrument channels per trip system cannot be met for one trip system, trip the inoperable channels.or entire l-trip-system within one hour, or, alternatively, take the below listed action for that trip function. If the minimum number of OPERABLE instrument channels cannot be met tv either trip system,'the appropriate action listed below (refer to right-hacd column of Table) shall be taken.. An inoperable channel need her he placed in the tripped condition l where this would cance the trip function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within two hours, l' or take the actior. listed below for that trip function.
A.
Initiate insortion of OPERABLE rods and complete insertion of all OPERABLE rods within four hours.
In refueling mode, suspend all operations involving core alterations and fully insert all OPERABLE control rods within one hour.
B.
Reduce power level to IRM range and place mode switch in the STARTUP/ HOT Standby position within 8. hours.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30 percent of rated.
2.-
The scram discharge volunc high water level bypass may be used in SHUTDOWN or REFUEL to bypass both the scram discharge volume high-high water level and scram pilot air header low pressure scram signals in order to reset the reactor protection system trip. A control rod withdraw block is present when these scram signals are bypassed.
3.
(Deleted) 4.
Bypassed when turbine first stage pressure is less than 154 psig.
5.
IBMs are bypassed when APRMs are onseale and the reactor mode switch is I
in the RUN position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is suberitical and the reactor water temperature is less than 212 F, only the following trip functions need to be OPERABLE:
l 0
A.
Mode switch in SHUTDOWN 1
B.
Manual scram C.
High flux IRM D.
Scram discharge volume high level BFN 3.1/4.1-5 Unit 2 g-
r; e j.
i
~
NOTES FOR TABLE 3.1.A (Cont'd)~-
E.
F. : Scram pilot' air header low pressure L*
.8.
Not' required to be OPERABLE when primary containment integrity is not required.
9.
(Deleted) 10.
Not required to be OPERABLE when the reactor pressure: vessel head is not bolted to the vessel.
1
- 11. The APRM_downscale trip function is only. active when the reactor mode switch is in RUN.
I 12.
The APRM downscale trip is automatically bypassed when the IRN' instrumentation is OPERABLE and not high.
14.
Channel shared by Reactor Protection System and Primary Containment.and i
Reactor Vessel Isolation Control System. A channel failure may be a i
channel failure in each system.
15.
The APRM 15 percent scram is bypassed in the.RUN Mode.
l 16.
Channel shared by Reactor Protection System and-Reactor Manual Control System (Rod Block Portion). A channel failure may be a channel. failure in each system. If a channel is allowed to be inoperable per Table 3.1.A, the corresponding function in that same channel may be inoperable in the Reactor Manual Control System _(Rod Block).
17.
Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
~
i a
- 18..This function must inhibit the automatic bypassing of turbine control valve fast closure or turbine trip scram and turbine stop valve closure scram whenever turbine first stage pressure is greater than or equal to 154 pais.
- 19. Action 1.A or 1.D shall be taken only if the permissive fails in such a manner to prevent the affected RPS logic from performing its intended function. Otherwise, no action is required.
20.
(Deleted) 21.
The APRM High Flux and Inoperative Trips'do not have to be OPERABLE in theREFUELModeiftheSource'RangeMonitogsareconnectedtogivea noncoincidence, High Flux scram, at 5 x 10 cys. The SRMs shall be OPERARTR per Specification 3.10.B.1.
The removal of eight (8) shorting links is required to provide noncoincidence high-flux scram protection from the Source' Range Monitors.
BFN 3.1/4.1-6 Unit 2 s
~;
o
~~
TABLE 3.1.A REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS c tn Min. No. of E@
Operable Instr.
Modes in Which Function u
Channels Must Be Operable Per Trip Shut-Startup/
System (11f23) Trio Function Trio Level Settine h Refuel f7) Hot Standby
.Ry1 Action (1) 2 High Water Level in West Scram Discharge Tank (LS-85-45A-D) 1 50 Gallons X(2)
X(2)
X X
1.A 2
High Water Level in East Scram Discharge Tank (LS-85-45E-H) 1 50 Gallons X(2)
X(2)
X X
1.A 4
Main Steam Line 110% valve Closure X(6) 1.A or 1.C Isolation Valve Closure 2
Turbine Control 1.550 psig X(4) 1.A or 1.D W
Valve Fast L
Closure or Turbine Trip 7
4 Turbine Stop 1101 Valve Closure X(4) 1.A or 1.D w
Valve Closure 2
Turbine First not 1154 psig X(18)
X(18)
X(18) 1.A or 1.D (19)
Stage Pressure Permissive 2
Low Scram Pilot
},50 psig X(2)
X(2)
X X
1.A Air Header Pressure
IIU..
(,,.
NOTES FOR TABLE 3.1.A 1.
There shall be two OPERABLE or tripped trip systems for each function.
If the minimum number of OPERABLE instrument channels per trip system
. l cannot be met for one trip system, trip the inoperable channels or entire trip system within one hour, or, alternatively, take the below listed l
action for that trip function. If the minimum number of OPERABLE l
instrument channels cannot=be met by either trip system, the appropriate i'
action listed below (refer to right-hand column of Table) shall be F
taken. An inoperable channel need not be placed in the tripped condition l where this would cause the trip function to occur. In these cases,'the inoperable channel shall be restored to OPERABLE status within two hours, l-or take the action listed below for that trip function.
A.
Initiate insertion of OPERABLE rods and complete insertion of all OPERABLE rods within four hours. In refueling mode, suspend all i
t operations involving core alterations and fully insert all OPERABLE control rods within one hour.
B.
Reduce power level to IRM range and place mode switch in the STARTUP/ HOT STANDBY position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
s D.
Reduce power to less than 30 percent of rated.
2.
The scram discharge volume high water level-bypass may be used in SHUTDOWN.or REFUEL to bypass both the scram discharge volume high-high
{
water level and scram pilot air header low pressure scram signals in order to reset the reactor protection system trip. A control rod l
withdraw block is present when these scram signals are bypassed.
1 l
3.
DELETED 4.
Bypassed when turbine first stage pressure is less than 154 peig.
5.
IRMs are bypassed when APRMs are onseale and the reactor mode switch is in the RUN position.
6.
The design permits closure of any two lines without a scram being initiated.
7.
When the reactor is suberitical and the reactor water temperature is less 0
than 212 F, only the following trip functions need to be OPERABLE:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge volume high level 1-BFN 3.1/4.1-4 Unit 3.
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NOTES'FOR TABLE 3.1.A (Crat'd)
F.
Scram' pilot air header low Pressure l
Not required to be OPERABLE when primary containment integrity is not 8.
required.
9.
(Deleted) 10.
Not required to be OPERABLE when the reactor pressure vesse1~ head is not bolted to the vessel.
-11.
The APRM downscale trip function is'only active when the reactor mode switch is in RUN.
~
instrumentation is OPERABLE and not high.
13.
Less than 14 OPERABLE LPRMs will cause a trip system trip.
14.
Channel shared by Reactor Protection System and Primary Containment and Reactor Vessel Isolation Control System. A channel failure may be a channel failure in each system.
15.
The APRM 15 percent scram is bypassed in the RUN Mode.
16.
Channel shared by Reactor Protection System and Reactor Manual Control System (Rod Block Portion). A channel failure may be a channel failure in each system. If a channel is allowed to be inoperable per Table 3.1.A, the' corresponding function in that same channel may be inopesable in the Reactor Manual Control System (Rod Block).
17.
Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MWt.
18.
This function must inhibit the automatic-bypassing of turbine control valve fast closure or turbine' trip scram and turbine stop valve closure scram whenever turbine first stage pressure is greater than or equal to 154 psig.
- 19. Action 1.A or 1.D shall be taken only if the permissive fails in such a manner to prevent the affected RPS logic from performing its intended function. Otherwise, no action is required.
20.
(Deleted)
- 21. The APRM High Flux and Inoperative Trips do not have to be OPERABLE in theREFUELModeiftheSourceRangeMonitogsareconnectedtogivea noncoincidence, High Flux scram, at 5 x 10 cps. The SRMs shall be OPERABLE per Specification 3.10.B.1.
The removal of eight (8) shorting links is required to provide noncoincidence high-flux scram protection from the Source Range Monitors.
I I
L BFN 3.1/4.1-5 Unit 3 1
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TABLE 4.1.A (Continued)
La Grovo (2)
Functional Test Minimus Freauenewf3)
High Water Level in Scram Discharge Tank Float Switches (LS-85-45C-F)
A Trip Channel and Alarm Once/ Month Electronic Level Switches (LS-85-45A, 8. G. H)
B Trip Channel and Alarm (7)
Once/ Month Main Steam Line Isolation Valve Closure A
Trip Channel and Alann Once/3 Months (8)
Turbine Control Valve Fast Closure or turbine trip A
Trip Channel and Alarm Once/ Month (1)
Turbine First Stage Pressure A
Trip Channel and Alarm Every three months Permissive Turbine Stop Valve Closure A
Trip Channel and Alarm Once/ Month (1)
Trip Channel and Alarm Once/6 Months I#
Pressure (PS 85-35 A1, A2, 81, 0;
and 82)
=
4
=*z ls;
.J; TABLE 4.1.8
~ p 88 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION r5 MINIfRjM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS n
s.2 Instrument Channel Grous Q1' Calibration Minimus Freauencvf 2)
IRM High Flus C
Comparison to APRM on Controlled Note (4)
Startups (6)
APRM High Flus Output Signal 8
Heat Balance Once Every 7 Days, Flow Blas Signal B
Calibrate Flow Slas Signal (7)
Once/ Operating Cycle LPRM Signal 8
TIP System Traverse (8)
Every 1000 Effective Full Power Hours High Reactor Pressure A
Standard Pressure Source Every 3 Months High Drywell Pressure A
Standard Pressure Source Every 3 Months Reactor Low Water Level A
Pressure Standard Every 3 Months F
High Water Level in Scram Discharge Volume
-2 Float Switches (LS-85-45C-F)
A Calibrated Water Column (5)
Note (5) 7 Electronic Lvl Switches g
(LS-85-45-A. B. G. H)
B Calibrated Water Column
'Once/ Operating Cycle (9)-
Main Steam Line Isolation Valve Closure A Note (5)
Note (5)'
Turbine First Stage Pressure Permissive A
Standard Pressure Source Every 6 Months Turbine Control Valve Fast Closure or Turbine Trip A
Standard Pressure Source Once/ Operating Cycle Turbine Stop Valve Closure A
Note (5)
Note (5)
Standard Pressure Source Once/18 Months Pressure (PS 85-35 A1. A2. 81 and 82) l e --
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3.1 R&&&& (Cont'd)-
be accommodated-which would result in slow scram times or partial control rod insertion. To preclude this occurrence,. level switches have been provided in the instrument volume which alarm and scram the reactor when the volume'of water-reaches 50 gallons. As indicated above, there is sufficient volume in-the piping to accommodate the scram without impairment of.the scram times or amount of insertion of the control rods. This function shuts the reactor down while sufficient volume remains to accommodate the discharge water and' precludes the situation in which a scram would be required but not be able to_ perform its function adequately.
A source range monitor (SRM)' system is also provided to supply additional-neutron-level information during startup but has no scram functions.
Reference Section 7.5.4 FSAR. Thus, the IRM is required in the REFUEL and STARTUP modes. In the power range the APRM system provides required protection. Reference Section 7.5.7 FSAR. Thus, the IRM System is not required in the RUN mode. The APRMs and the IRMs provide adequate coverage in the STARTUP and intermediate range.
The high reactor pressure, high drywell pressure, reactor low water level, low scram pilot air header pressure and scram discharge volume l
high level scrans are required for STARTUP and RUN medes of plant t
operation. They are, therefore, required to be operational for these modes of reactor operation.
The requirement to have~the scram functions as indicated in Table 3.1.1 OPERABLE in the RE WEL mode is to assure that shifting to the REFUEL mode during reactor power operation does not diminish the need for the reactor protection system.
Because of the APRM downscale limit of 1 3 percent when in the EUN mode and high level limit of.115 percent when in the STARTUP Mode, tl6s transition between the STARTUP and RUN Modes must be made with the APRM instrumentation indicating between 3 percent and 15 percent of reted power or a control rod scram will occur. In addition, the IRM system l
sust be indicating below the High Flux setting (120/125 of scale) or a scram will occur when in the STARTUP Mode. For normal operating conditions, these limits provide assurance of overlap between the IRM system and APRM system so that there.are no " gaps" in the power level indicatione (i.e., the power level is continuously monitored from beginning of startup to full power and from full power to shutdown).
When power is being reduced, if a transfer to the STARTUP mode is made
~
and the IRMs have not been fully inserted (a maloperational but not impossible condition) a control rod block immediately occurs so that reactivity insertion by control rod withdrawal cannot occur.
The low scram pilot air header pressure trip performs the same function as the high water level in the scram discharge instrument volume for fast fill events in whfch the high level instrument response time may be inadequate. A fast fill event is postulated for certain degraded control air events in which the scram outlet valves unseat enough to allow 5 spa per drive leakage into the scram discharge volume but not enough to cause control rod insertion.
BFN-3.1/4.1-15 Unit 3 F
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