ML20085K476
| ML20085K476 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/16/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20085K475 | List: |
| References | |
| NUDOCS 9506230392 | |
| Download: ML20085K476 (20) | |
Text
>
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWN 8 FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 PROPOGED TECHNICAL SPECIFICATION (TS) CHANGE TS-360 MARKED PAGES I.
AFFECTED PAGE LIST Unit 1 Unit 2 Unit 3 3.1/4.1-11 3.1/4.1-11 3.1/4.1-10 3.1/4.1-12 3.1/4.1-12 3.1/4.1-11 3.1/4.1-20 3.1/4.1-20 3.1/4.1-19 II.
MARKED PAGES See Attached t
l 9506230392 950616 DR ADOCK 05000259 PDR
TABLE 4.1.3 REACTOR PROTECTION SYSTEM (SCRAM) INSTRLNENTATION CALIBRAi!ON MININRt CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS e en E
Instrument Channel Grovo (1)
Calibration Minimoe Freauencvf21 IRM High Flum C
Comparison to APRM on Controlled Note (4)
Startups (6)
APRM High Flum Output Signal B
Heat Balance Once/T Cays Flow Blas Signal B
Callbrate Flow Blas Signal (7)
Once/ Operating Cycle LPRM Signal 5
IIP System T=ree (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 High Water Level in Scram Discharge Volume w
Electronic Lv1 Switches (LS-85-45-A. B. G. H)
A Calibrated Water Column (5)
Note (5) s*
Float Switches (LS-85-45C-F)
A Calibrated Water Column (5)
Note (5)
C Main Steam Line Isolation Valve Closure A
Note (5)
Note (5)
Turbine First Stage Pressure Permissive (PT-1-81A, B &'
Once/ Operating Cycle (9)
PT-1-91A, 8)
B Standard Pressure Source turbine Control Valve Fast Closure or Turbine Trip A
Standard Pressure Source
' Once/ Operating Cycle
>M Turbine Stop Valve Closure A
Note (5)
Note (5) o
=
to
=
N N
N
\\
\\
NOTES FOR TARf7 4.1.B
.${f2yjgg(
.A description of three groups is included in the bases of this 1.
specification.
Calibrations are not required when the systmas are not required to be l
2.
OPERABLE or are tripped..If calibrations are missed, they shall be performed prior to returning the system to an OFrWARLE status.
l d
3.
(Deleted)
Required frequency is initial startup following each refueling outage.
j 4.
Physical inspection and actuation of these position switches will be j
i 5.
performed once per operating cycle.
6.
On controlled startups, overlap between the IENs and APENs will be verified.
7.
The Flow Bias Signal Calibration will consist of calibrating the sensors, flow converters, and signal offset networks during each operating cycle.
i The instrumentation is an analog type with redundant flow signals that can be compared. The flow comparator trip and upscale will be functionally tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for further explanation of calibration fr.quency.
8.
- 3. :
1:t: H.=,ar = t::::::: - ' ' b t e- *'= L
=^==='= *= ^ = ;::r---
The individual LPEN meter readings will be adjusted as a
-eenposee'.
minimum at the beginning of each operating cycle before reaching 100 percent pov 9.
Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.
7 V~
TIP data for an inoperable measurement location may be replaced by data obtamed from that channal's redundant (symmetric) counterpest or by data obtained from the on-line core monitoring system, normalized with available operating measurements, provided the total number of simulated channals does not exceed nine.
(
AMENDMN NO. 212 BFN 3.1/4.1-12 Unit 1
4.1 EASE 1 (Cont'd)
The sensitivity of LPEM detectors-deseeeeee with exposure to neutron flux.
20 : rl - - " 2;;_
'- trly r--
r-rrer. The APEN system, which uses the LPEN readings to detect a change in thermal power, will be. calibrated every seven days using a heat balance to compensate for this change in-sensitivity. The REM system uses the LPEN reading to detect a localized change in thermal power.
It applies a correction factor based on the APEN output signal to determine the percent thermal power and therefore any-change in LPEN sensitivity is compensated for by the APEM calibration.
The technical specification limits of CNFLPD, CPR, sad APLBER are l
data mined by the use of the process computer or.other backup methods.
These methods use LPEN readings and TIP data to det==4ns the power distribution.
Cepensation in the process computer for changes in LPEN sensitivity will be made b ;;::_'r '-- 2 "-" re e "* *r-r e to update the computar calculated LPEN correction factors every 1000 effective full power hours.
As a minimum the individual LPEN meter readings will be adjusted at the beginning of each operating cycle before reaching 100 percent pows 0
\\'k N
'T using the TIP system and/or process computer AMENDMENT NO. I 9 7 BPN 3.1/4.1-2o Unit 1
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NOTES FOR TAntr 4.1.B 1.
A description of three groups is included in the bases of this specification.
2.
Calibrations are not required when the systems are not required to be OPERAELE or are tripped. If calibrations are missed, they shall be performed prior to returning the system to an OPERABLE status.
3.
(Deleted) 4 Required frequency is initial startup following each refueling outage.
5.
Physical inspection and actuation of these position switches will be performed once per operating cycle.
6.
On controlled startups, overlap between the IBMs and APEMs will be i
verified.
7.
The Flow Bias Signal Calibration will consist of calibrating the sensors, flow converters, and signal offset networks during each operating cycle.
The instrumentation is an analog type with redundant flow signals that i
can be compared. The flow comparator trip and upscale will be functionally tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for further explanation of calibration frequency.
8.
1 - --;1rt: =, nr :;=;n --in-tr e-a g_- a - te ^- -- ---
-eenpeseh The individual LPEM meter readings will be adjusted as a minimum at the beginning of each operating cycle before reaching 100 percent powe 9.
Calibration consists of the adjustment of the primary sensor and
{
associated components so that they correspond within acceptable range and i
accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.
TIP data for an inoperable measurement location may be replaced by data obtained from that channel's redundant (symmetric) counterpart or by data obtained from the on-line core monitoring system, normalized with available operating measurements, provided the total number of simulated channels does not exceed nine.
l BFN 3.1/4.1-12 AMENDMENT NO. 2 2 7 Unit 2
MY 2 Q g 4.1 EMIS. (Cont'd)
The sensitivity of LPRM detectors-doosseses.with exposure to neutron flux.
The APRM system, which uses rath r cir>
" 2;;r- '--!r!r e---!--!
d the LPRM readings to detect a change in thermal power, will be calibrate rt every seven days using a heat balance to compensate for t It applies a correction factor based on the APRM sensitivity.
change in ther=al power.
output signal to determine the percent. thermal power and therefore any ibration.
chan(c in LPEM Sensitivity is compensated for by the APRM cal The technical specification limits of CMPLPD, CPR, and APLHGR are determined by the use of the process computer or other backup methods.
These methods use LPRM readings and TIP data to determine the power distribution.
Compensation in the process computer for channes in LPRM sensitivity will be made.byJ;r '-- '--
'c!' r--r "" *-r---r-to update the computercalculated LPRM correction factors e As a minimum the individual LPRM meter readings will be adjusted at the beginning of each operating cycle before reaching 100 percent power.
using the TIP system and/or process computer 1
AMENDMENT NO. 214 3.1/4.1-20 85 Unit 2
l i
i TA8tE 4.1.8 j
REAC10R PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION I
MINIlR31 CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS i
I c: tw l
r@
Instrument Channel Grous (1)
Calibration Minimum Freauencvf21
~
w IRM High Flum C
Comparison to APRM on Controlled Note (4)
~
5tartups (6)
APRM High Flun Output Signal 8
Heat Balance Once Every 7 Days Flow 81as Signal 8
Calibrate Flow Blas Signal (7)
Once/ Operating Cycle 8
TIP System !ce a rn (8).
Every 1000 Effective Full LPRM Signal Power Hours A
Standard Pressure Source Every 3 Months High Reactor Pressure A
Standard Pressure Source Every 3 Months High Drywell Pressure Reactor low Water Level A
Pressure Standard Every 3 Months i
High Water Level in Scram a
Discharge Volume
[
Float Switches Calibrated Water Column (5)
Note (5)
A (LS-85-45C-F)
Electronic Lvl Switches Callbrated Water Column Once/ Operating Cycle (9)
(L5-85-45-A, 8. G. H)
B
~
4 Note (5)
Main Steam Line Isolation Valve Closure A Note (5)-
Turbine First Stage Pressure Standard Pressure Source Every 6 Months A
Permissive Turbine Control Valve Fast Closure Standard Pressure Source Once/ Operating Cycle.
or Turbine Irlp 4
Note (5)
A Note (5)
Turbine Stop Valve Closure E
9 a
8
~
00 C)l 4
I
4 I
i l
$@ 2 '7 g
~
NOTES FOR TARfT
- t. 1.E A description of three groups is included in the Bases of this 1.
' specification.
Calibrations are not required when the systems are not required to be 2.
OFEEABLE or are tripped. If calibrations are missed, they shatt be performed prior to returning the system to an OPEtaRf2 status.
~
3.
(Deleted)
Required frequency is initial startup following each refueling outage.
4.
Physical inspection and actuation of these position switches will be 5.
1 performed once per operating cycle.
On controlled startups, overlap between the IBMs and APEMs will be f
- 6..
verified.
The Flow Bias Signal Calibration will consist of calibrating the sensors, 7.
flow converters, and signal offset networks during each operating cycle.
The instrumentation is an analog type with redundant flow signals that can be compared. The flow comparator trip and upscale will be functionally tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for.further explanation of calibration frequency.
S 1 :- ;1rtr !!P,;:
- . n;- r
"'trr r "- L" r'- "- : " ;::::
8.
f The individual LPEN meter readings will be adjusted as a
-eempuses.
mini=== at the beginning of each operating cycle before reaching 100 percent pov Calibration consists of the adjustment of the primary sensor and 9.
associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.
V V
TIP data for an inoperable measurement location may be replaced by data obtained from that chanaal's redundant (symmetric) counterpart or by data obtained from the on-line core monitoring system, q
normalized with available operating measurements, provided the total number of simulated channels does not exceed nine.
l I
AMENDMET NO. I 8 5 BFN 3,1/4.1_12 Unit 3 I
-y
4.1 343E1 (Cont'd)
W DE C HANG ES The sensitivity of LPEN detectors-desseeeee-with exposure to neutron flux, st
-ir - ' r;;: - -d--trly e rt _-r
- er.
The APEN system, whie.h uses the LPIM readings to detect a change in thermal power, will be calibrated every seven days using a heat balance to compensate for this change in sensitivity. The ERM system uses the LPEM reading to detect a localized change in thermal power.
It applies a correction factor based on the APEM output signal to determine the percent thermal power and therefore any change in LPEM sensitivity is compensated for by the APEM calibration.
The technical specification limits of CMPLPD, CPE, and APLEGE are l
determined by the use of the process computer or other backap methods.
These methods use LPEM readings and TIP data to determine the power distribution.
j Compensation in the process computer for changes in LPEM sensitivity will be made bg= ;:rfr '- 2 '-' rrr- "" - r crr to update the computer ca culated LPEN correction factors every 1000 effective full power hours.
As a mini p the individual LPEM meter readings will be adjusted at the beginnine of each operating cycle before reaching 100 percent power.
using the TIP system and/or process computer i
a BPR 3,1/4,1_19 AMENDMENT NO. I7O Unit 3
e ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT '(BFN)
UNITS 1,.2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-360 REVISED PAGES I.
AFFECTED PAGE LIST Unit 1 Unit 2 Unit 3 3.1/4.1-11 3.1/4.1-11 3.1/4.1-10 3.1/4.1-12 3.1/4.1-12 3.1/4.1-11 3.1/4.1-20 3.1/4.1-20 3.1/4.1-19 II.
REVISED PAGES See Attached l
s
,.s.<
3 TABLE 4.1.0 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUNENTATION CALIBRATION E"
MINIMJM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS rE Instrument Channel Group fil-Calib' ration Minimum Freauenevf2)
IRM High Flux C
Comparison to APRM on Controlled Note'(4)
Startups (6)
APRM High Flux Output Signal 8
Heat Balance Once/7 Days Flow Bias Signal B
Calibrate Flow Bias Signal (7)
Once/ Operating Cycle LPRM Signal 8
TIP System (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 u
High Water Level in Scram Distharge Volume N
Electronic Lv1 Switches (LS-85-45-A, 8. G. H)
A Calibrated Water Column (5)
Note (5)
Float Switches
~
1.
(L3-85-4SC-F)
A Calibrated Water Column (5)
Note (5) i Main Steam Line Isolation Valve Closure A
- Note (5)
. Note'(5)
Turbine First Stage Pressure Perufssive (PT-1-81A, 8 &
PT-1-91A. 8) 8 Standard Pressure Source Once/ Operating Cycle (9)
Turbine Control Valve Fast Closure or Turbine Trip A
Standard Pressure Source-Once/ Operating Cycle Turbine Stop Valve Closure A
Note (5)
Note (5) 1
~-
.nv.
. ~ ~. -~,
s n-.
c v
m-v--,
e e
ws
-,e
?
~, -, -
n.-~
v. ~,
+2 u
<- s
> ~
f, i
m y _ n NOTES FOR TABLE 411.B'
. 1.'
A description of three groups is included in the bases of this specification.
2.
Calibrations are not required when the systems are not required to be-OPERABLE or are tripped.- If calibrations are missed, they shall be J
Performed prior to returning the system to an OPERART.R status.
'3.-
.(Deleted) 4.
. Required frequency is. initial startup following each refueling outage.
q Physical inspection and actuation of these position switches will be
- 5... performed once per operating cycle.
- 1 6.
On controlled startups, overlap between the IRMs and APRMs will be J
verified.
j 7.
The Flow Bias Signal Calibration will. consist of calibrating the sensors, flow converters, and signal offset networks during each operating cycle.
The instrumentation is an analog type with redundant flow signals that.
can be compared. The flow comparator trip and upscale will be functionally tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for further explanation of calibration frequency.
8.
The individual LPRM meter readings will be adjusted as a minimum at the
- i TIP beginning of each operating cycle before reaching 100 percent power.
data for an inoperable measurement location may be replaced by data obtained from that rhannel's redundant (symmetric) counterpart or by data obtained from the on-line core monitoring system, normalized with j
available operating measurements, provided the total number of simulated j
channels does not exceed nine.
9.
Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry,'so that'its output relay' changes state at or more conservatively than the analog equivalent of the trip level setting.
l 1
BFN 3.1/4.1-12 Unit 1
4.1 BASES (Cont'd)
The sensitivity of LPRM detectors changes with exposure to neutron flux.
lI The APRM system, which uses the LPRM readings to detect a change in thermal praer, will be calibrated every seven days using a heat balance to compensate for this change in sensitivity. The RBM system uses the LPRM r ' ding to detect a localized change in thermal power.
It applies a correction factor based on the APRM output signal to determine the percent thermal power and therefore any change in LPRM sensitivity is compensated for by the APRM calibration. The technical specification limits of j
CMFLPD, CPR, and APLHGR are determined by the use of the process computer or other backup methods. These methods use LPRM readings and TIP data to determine the power distribution.
Compensation in the process computer for changes in LPRM sensitivity wi?.1 be made by using the TIP system and/or process computer to update the l
computer calculated LPRM correction factors every 1000 effective full power hours.
As a minimum the individual LPRM meter readings will be adjusted at the beginning of each operating cycle before reaching 100 percent power.
)
l i
l BFN 3.1/4.1-20 Unit 1
9
TA8LE 4.1.5 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINItut CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS e-E Instrument Channel
-Group (1)
Calibration Minimum Freauencvf2) w IRM High Flum C
Comparison to APRM on Controlled Note (4)L Startups (6)
APRM High Flux Dutput Signal B
Heat Balance Once/7 Da s-s Flow Bias Signal B
Calibrate Flow Blas Signal (7)
Once/ Operating Cycle-LPRM Signal B
TIP System (8)
Every 1000 Effective Full -d' Power Hours High Reactor Pressure B
Standard Pressure Source Once/6 Months (9)
(PIS-3-22 AA, 88, C, D)
High Drywell Pressure B
Standard Pressure Source Once/18 Months (9) ~
(PIS-64-56 A-D)
Reactor Low Water Level 8-Pressure Standard Once/18 Months (9)
(LIS-3-203 A-0)
S High Water Level in Scram Discharge Volume 7
Float Switches (LS-85-45-C-F)
Calibrated Water Column Once/18 Months
~
Electronic Level Switches (LS-85-45 A, B, G. H)
B Calibrated Water Column Once/18 Months-(9)
Main Steam Line Isolation Valve Closure A
Note (5)
Note (5)
~
Turbine First Stage Pressure Permissive (PIS-1-81 A&B,_
PIS-1-91 A&B)
B Standard Pressure Source Once/18 Months (9)
Turbine Stop Valve Closure A
Note (5)-
Note (5)
Turbine Control Valve Fast Closure on Turbine Trip A
Standard Pressure Source Once/ Operating Cycle Low Scran Pilot Air Header Pressure (PS 85-35 A1,-
A Standard Pressure Source Once/18 Months A2, Si, & 82)'
t I.
d NOTES FOR TABLE 4.1.B 1.
A description of three groups is included in the bases of this specification.
2.
Calibrations are not required when the systems are not required to be OPERABLE or are tripped.
If calibrations are missed, they shall be performed prior to returning the system to an OPERABLE status.
3.
(Deleted) 4.
Required frequency is initial startup following each refueling outage.
5.
Physical inspection and actuation of these position switches will be performed once per operating cycle.
6.
On controlled startups, overlap between the IRMs and APRMs will be verified.
7.
The Flow Bias Signal Calibration will consist of calibrating the sensors, flow converters, and signal offset networks during each operating cycle.
The instrumentation is an analog type with redundant flow signals that can be compared. The flow comparator trip and upscale will be functionally tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for further explanation of calibration frequency.
8.
The individual LPRM meter readings will be adjusted as a minimum at the I
beginning of each operating cycle before reaching 100 percent power. TIP data for an inoperable measurement location may be replaced by data i
obtained from that channel's redundant (symmetric) counterpart or by data obtained from the on-line core monitoring system, normalized with available operating measurements, provided the total number of simulated channels does not exceed nine.
I I
9.
Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within srceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.
I
{
4 BFN 3.1/4.1-12 Unit 2
4.1 BASES (Cont'd)
The sensitivity of LPRM detectors changes with exposure to neutron flux.
l' The APRM system, which uses the LPRM readings to detect a change in d
thermal power, will be calibrated every seven days using a heat balance to compensate for this change in sensitivity. The RBM system uses the LPRM reading to detect a localized change in thermal power.
It applies a correction factor based on the APRM output signal to determine the percent thermal power and therefore any change in LPRM sensitivity is compensated for by the APRM calibration. The technical specification limits of CMFLPD, CPR, and APLHGR are determined by the use of the process computer or other backup methods. These methods use LPRM readings and TIP data to determine the power distribution.
Compensation in the process computer for changes in LPRM sensitivity will be made by using the TIP system and/or process computer to update the l
computer calculated LPRM correction factors every 1000 effective full power hours.
As a minimum the individual LPRM meter readings will be adjusted at the beginning of each operating cycle before reaching 100 percent power.
BFN 3.1/4.1-20 Unit 2
Es;.
TA8LE 4.1.5 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION c os SE MINittM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRtmENT CHANNELS et Instrument Channel Group (1)
Calibration Minisum Freauencvf2)
IRM High Flus C
Comparison to APRM on Controlled Note (4)
Startups (6)-
APRM High Flux Dutput Signal B
Heat Balance Once Every 7 Days Flow Blas Signal B
Calibrate Ficw Blas Signal (7)
Once/ Ope ra ting ~ Cycle LPRM Signal 8
TIP System (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 High Water Level in Scram ta Discharge Volume Float Switches (LS-85-45C-T)
A Electronic Lvl Switches Calibrated Water Column (5)
Note (5)
.y (LS-85-45-A, B, G H)
B Calibrated Water Column Once/ Operating Cycle (9) o 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) t c
~.. - ~.. - - -. -
+
NOTES FOR TABLE 4.1.B 1.
A description of three groups is included in the Bases of this specification.
2.
Calibrations are not required when the systems are not required to be l
OPERABLE or are tripped. If calibrations are missed, they shall be
. Performed prior to returning the system to an OPERABLE status.
3.
(Deleted).
4.
Required frequency is initial startup.following each refueling outage.
5.
Physical inspection and-actuation of these position switches will be performed once per operating cycle.
6.
On controlled startups, overlap between the IRMs and APRMs will be verified.
1
-7.
The Flow Bias Signal Calibration will consist of calibrating the sensors, flow converters, and signal offset networks during each operating cycle.-
The instrumentation is an analog type with redundant flav signals that can be compared. The flow comparator trip and upscale w!11 be functionally. tested according to Table 4.2.C to ensure the proper operation during the operating cycle. Refer to 4.1 Bases for further explanation of calibration frequency.
8.
The individual LPRM meter readings will be adjusted as a minimum at the i
beginning of each operating cycle before reaching 100 percent power. TIP data for an inoperable measurement location may be replaced by data obtained from that channel's redundant (symmetric) counterpart or by data obtained from the on-line core monitoring system,. normalized with available operating measurements, provided the total number of simulated channels does not exceed nine.
9.
Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at'or more conservatively than the analog equivalent of the trip level setting.
BFN 3.1/4.1-11 Unit 3
5 4.1 DASIS. (Cont'd)
The sensitivity of LPRM detectors changes with exposure to neutron flux.
l The APRM system, which uses the LPRM readings to detect a change in i
thermal power, will be calibrated every seven days using a heat balance to compensate for this change in sensitivity. The RBM system uses the LPRM reading to detect a localized change in thermal power.
It applies a correction factor based on the APRM output signal to determine the percent thermal power and therefore any change in LPRM sensitivity is compensated for by the APRM calibration. The technical specification limits of CMFLPD, CPR, and APLHGR are determined by the use of the process computer or other backup methods. These methods use LPRM readings and TIP data to determine the power distribution.
Compensation in the process computer for changes in LPRM sensitivity will be made by using the TIP system and/or process computer to update the l
computer calculated LPRM correction factors every 3000 effective full power hours.
As a minimum the individual LPRM meter readings will be adjusted at 'che beginning of each operating cycle bet' ore reaching 100 percent power.
i BFN 3.1/4.1-19 Unit 3