ML20065F260
| ML20065F260 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/31/1994 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20065F253 | List: |
| References | |
| NUDOCS 9404110290 | |
| Download: ML20065F260 (38) | |
Text
-
i ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT (BFN)
UNITS 1 and 3 1
PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-319 MARKED PAGES l
Unit 1 3.2/4.2-18 3.2/4.2-19 3.2/4.2-22 3.2/4.2-23 3.2/4.2-46 3.2/4.2-47 3.2/4.2-67 Unit 3 3.2/4.2-18 3.2/4.2-19 3.2/4.2-21 3.2/4.2-22 3.2/4.2-45 3.2/4.2-46 3.2/4.2-66 II.
MARKED PAGES See attached.
j 9404110290 940331 PDR ADOCK 05000259 j'
P PDR
[
c* to TABLE 3.2.B (Continued)
S$
re Hinimum No.
Operable Per Trio Sysfl1 Function Trio Level Settina Action Remarks 1
HPCI Trip System bus power.
N/A C
1.
Monitors availability of monitor power to logic systems.
1 RCIC Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
1(2)
Instrument Channel -
1 Elev. 551' A
1.
Below trip setting will Condensate Header Low open HPCI suction valves Level (LS-73-56A & B) to the suppression chamber.
1(2)
Instrument Channel -
i 7" above instrument zero A
1.
Above trip setting will open Suppression Chamber High HPCI suction valves to the Level suppression chamber.
2(2)
Instrument Channel -
1 583" above vessel zero A
1.
Above trip setting trips RCIC Reactor High Water Level turbine.
E' 1
Instrument Channel -
1 450" H O (7)
A 1.
Above trip setting isolates 2
RCIC Turbine Steam Line RCIC system and trips RCIC y
High flow turbine.
4Q I ;t..
..t Ch.....;l MC0" A
fi..; t-i p ;;t t * ; * :;'-t;;
SCIC Ct;-- C.; C;;;;
- ,,. _...' Llr,IC:C
^
'./. L,...L i. --t ' :;.
3(2)
Instrument Channel -
150 psig A
1.
Below trip setting isolates
.RCIC Steam Supply RCIC system and trips RCIC Pressure - Low turbine.
(PS 71-1A-D) 3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates RCIC Turbine Exhaust RCIC system and trips RCIC Diaphra p Pressure -
turbine.
High (PS 71-11A-D).
C/3 h.
IT1 o
k M
2
=
9 n
g CO s*1.2 CII G3 09
TABLE 3.2.8 (Continued)
Minimum No.
Operable Per c
a,
' Trio Sys(1)
Function Trio Level Settina Action Remarks p =
r n!
2(2)
Instrument Channel -
1583" above vessel aero.
A 1.
Above trip setting trips HPCI Reactor High Water Level turbine.
1 Instrument Channel -
190 psi (7)
A 1.
Above trip setting isolates HPCI Turbine Steam Line HPCI system and trips HPCI High Flow turbine.
~
i_m.
__aan__
r..i...
_ f!l:T ITT'_'_' Ti""";
_1_
u, Laae'_ 1 J__
_2 ir,_.
- une,
_ ;1I: _ :: r.."_' '"'
"r'"
J rz.:f.'. "_ ""- '
'r'
'~-
3(2)
Instrument Channel -
<1100 psig A
1.
Below trip setting isolates HPCI Steam Supply HPCI system and trips HPCI Pressure - Low turbine.
(PS 73-1A-D) 3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates HPCI Turbine Exhaust HPCI system and trips HPCI Diaphragm (PS 73-20A-D) turbine.
1 Core Spray System Logic N/A B
1.
Includes testing auto ti initiation inhibit to e-Core Spray Systems in l
other units.
,3 1
[s 1
RCIC System (Initiating)
N/A B
1.
Includes Group 7 valves.
Logic 2.
Group 7: The valves in Group 7 are automatically actuated by i
only the following condition:
1.
The respective turbine steam supply valve not fully closed.
38 1
RCIC Systen (Isolation)
N/A B
1.
Includes Group 5 valves.
Logic 2.
Group 5: The valves in Group c,
gg 5 are actuated by any of the Q
following conditions:
q a.
RCIC Steaminne Space
.f!l
=at High Temperature
.o; cm b.
RCIC Steamline High Flow c.
RCIC Steamline Low a
Pressure C73 03 d.
RCIC Turbine Enhaust CCI Diaphragm High Pressure 1 (16)
ADS Logic N/A A
.m._
.-.~
_._.....-._....-_.-___.___.m.
-.m.
.m.
._.m.
IABtE 3.2.s (Continued) n..m s, so t)ksratole 9tc It1L.intll.
_ _ _ _ _._ f uncilon it.in LeveLicLLlaa_..Actiga _
SsmHLL_
leluj Instr. ment Caiannel g loger A
l.
Al,ove trip set tles st ar t s Core T rac s auus t a t (Cuse Spea, Arca Spray area cooler f ans.
r Cualer tan) illut kuk Ar ca Cooler f an logic N/A A
6460)
Core Spray Area Cooler fan N/A A
togic It II)'
Ins t t asient Cha.uw I -
it/A A
l.
St ar a > susk5u p..nps Al. e1 Cure 5psay Motors A or C Cl. anJ DI Start 18511 Inst rasient Channel -
N/A
.A l.
. St a r t s SHk5u posgs A l, 3 3 Core 5ps'ay Mutor s B os D Cl. and D3 Start til2)
Inst ran=nt Chaeutel -
- It/A A.
1.
Starts Rhe5W pieups Al. 83 Cure Spray toop i Accident Cl, and D3 y
5 snel i15)-
e.
N till)
Iso t e a.nent Chasuic t -
- N/A A
1.
Starts fruksu p.,s Al. Bl.
Core Spray toop 2 Accident Cl. and D3
.a Si.nai tisi l'
i eu
- 2 till)
- kokSu Insttate nostc N/A tit) 4
-kPI togic
.N/A (17)
. Trips rec trculat ion passips on tuslaine control valve i
fast closure or stop valve i
closure e 1er pu es.
0 1
. us es unit I j'
m t
E 4
~. +
-s.
~
,... '.. J.
NOTES FOR TABLE 3.2.B 1.
Whenever any CSCS System is required by Section 3.5 to be-OPERABLE, there shall be two OPERABLE trip systems except as noted.
If a requirement of-the-first column is reduced by one, the indicated action shall be taken.
If the same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken.
Action:
A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, tr.ke action B.
B. : Declare the system or component inoperable.
C.
Immediately take ar. tion B until power is verified on the trip system.
I D. sNo_ action required Q ndicators are considered redundant.
L l AVD TNSEET -8) 2.
In only one trip system.
i 3.
Not considered'in a trip system.
Oclekd.
ch;;;;l f;;; :: h ph ;ical 1 ::tien (th;;; ;;; ' le;;tien;}
4.A 2c.ic ; :::
s in th: :: 1r lire rpree.
5.
With diesel power, each RHRS pump is scheduled to start immediately and-each CSS pump is sequenced to start about 7 sec later.
6.
With normal power, Lone CSS and one RHRS pump is schsduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 sec. with similar pumps starting after about 14 sec, and 21 sec.,
at which time the full complement of CSS and RHRS pumps would be operating.
7.
The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not ocet while ensuring the initiation of isolation following a postulated. team line break.
4 Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent above maximum steady state flow while also ensuring the l
initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
J 9.
The head tank is designed to assure that the discharge piping from the CS and RHR pumps are full. The pressure shall be maintained at or above the i
values listed in 3.5.H, which ensures water in the discharge piping and
{
up to the head tank.
BFN 3.2/4.2-23 Unit 1
.m.
.m.._
. =_
TABLE 4.2.B (Continued)
SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS Function functional Test
- Calibration Instrument Check Instrument Channel -
(1) once/3 months none RNR Pump Discharge Pressure C to D 'rJ rz Instrument Channel -
(1) once/3 months
'none Cors Spray Pump Discharge Pressure g
Core Spray Sparger to RPV d/p (1) once/3 months once/ day Trip System Bus Power Monitor once/ operating Cycle N/A none Instrument Channel -
(1) once/3 months none Condensate Header Low Level (LS-73-56A, B)
Instrument Channel -
(1) once/3 months none Suppression Chamber High Level Instrument Channel -
(1) once/3 months once/ day Reactor High Water Level Instrument Channel -
(1) once/3 months none RCIC Turbine Steam Line High Flow ts
.,__i_.___. c6 ___i _
sis
~ " ' - - - -
___m<_
to
- .-.,, _ _..__ K._. o u
_ "!..!..! : 3_.1. _ - - -
Na to Instrument Channel -
once/31 days once/18 months once/ day
[
RCIC Steam Supply Low Pressure cn Instrument Channel -
once/31 days once/18 months once/ day RCIC Turbine Exhaust Diaphrage High Pressure
-)AoD 1usear-e BFN-Unit I
~
m Zc3 Em Z-4 Z
CO P
rT1 w
~D M
do m
os Ei$
CE3 CE3
TABLE 4.2.B (Continutd)~
St%VEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIA1E OR CONTROL THE CSCS -
Function Functional Test Calibration Instrument Check Instrument Channel -
(1) once/3 months none HPCI Turbine Steam Line High Flow c to
- 3 eg
,__m_
--_a n _ _ _ _1 sis
--~.is
- 6.
p*
E55'5^9 E5E: 5hr. uap
~ ~~~ ~ ' ~
'-- ; n'.a 6*
Instrument Channel -
once/31 days once/18 months once/ day HPCI Steam Supply Low Pressure Instrument Channel -
once/31 days once/18 months once/ day HPCI Turbine Exhaust Diaphragn High Pressure Core Spray System Logic once/18 months (6)
N/A
-RCIC System (Initiating) Logic once/18 months N/A N/A RCIC System (Isolation) Logic once/18 months (6)
N/A HPCI System (Initiating) Logic once/18 months (6)
N/A HPCI System (Isolation) Logic once/18 months (6)
N/A f
ADS Logic once/18 months (6)
N/A tog LPCI (Initiating) Logic once/18 months (6)
N/A
,o LPCI (Containment Spray) Logic once/18 months (6)
N/A-s A
Core Spray System Auto Initiation once/18 months (7)
N/A N/A 4
Inhibit (Core Spray Auto Initiation).
LPCI Auto Initiation Inhibit
'once/18 months (7)
N/A N/A~
(LPCI Auto Initiation)
BFN-Unit 1 3m 2
C3 E
m Z
Cf3 Z
TI"I 9
o do CM cxs CD oca CC3
-1 i
3.2 BASES (Cont'd)
FEB 051987 steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Section 14.6.2 FSAR. An alarm with a nominal setpoint'of 1.5 x normal' full-power background is provided also.
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 825 psig.
The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping.. Tripping of this instrumentation results in actuation of HPCI isolation valves. Tripping logic for the high flow is a 1-out-of-2 logic, and all sensors are required to be RAbh perable.)
fo Mf High temperature in the vicinity of the HPCI equipment is sensed by four sets of four bimetallic temperatureEswitches. The 16 temperature switches are arranged in two trip systems with eight temperature switches in each trip system.
}pp yNgER 7-D ]
-!t ~ PCI-trip ::tting: e f 90 p:1 f er hi;h fir" - ' '^^** '-- h'eh----
t;;.,:::t
- ::: :::S th t :: : : re cr-1 pr:r::t:f f fic:1: p;;d::t
- 1:::: i: rithin l' 8 t-e.
- d t: p:::t::: in:tr :-tetirr cre-crr- ;:f "r r----
2
- th t f r th: "PCI.
Th: trip ::tt' ; ef '99" M 0 fer hi;h fle r-f g
-200*F f:: t_;:::tz : ::: b:::d := th: :: : criter'
- the "PCI; High temperature at the Reac'or Cleanup System floor drain could indicate t
a break.in the cleanup system. When.high temperature occurs, the cleanup system is isolated.
The instrumentation which initiates CSCS action is arranged in a dual bus system. As for other~ vital instrumentation arranged in this fashion,-the specification preserves the ef fectiveness of the system even during periods when maintenance or testing is being performed. An exception to this is when logic functional testing is-being performed.
The control rod block functions are provided ~ to prevent excessive control rod withdrawal so that MCPR does not-decrease to 1.07.
The' trip logic for this function is 1-out-of-n:
e.g., any trip on one of six-APRMs, eight IRMs, or four SRMs will result in a rod block.
The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.
The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration. This'does not significantly increase the risk of an inadvertent control rod withdrawal, as the other channel is available, and the RBM is a backup system to the written-sequence for wit; rawal of control rods.
BFN 3.2/4.2-67 Unit 1
. -. ~ _.
NSERT A (Table 3.2.B) 2 RCIC Steam Line Space s155'F E
1.
Above trip setting
. isolates RCIC-system
. Torus Area-and trips RCIC: turbine.
j High Temperature.
l 2
RCIC Steam Line Space-s180*F E
1.
Above trip setting i
isolates.RCIC system-RCIC Pump Room Area and trips RCIC turbine.
High Temperature 2
HPCI Steam.Line Space s180*F E
1.
Above-trip setting isolates HPCI system Torus Area and trips HPCI' turbine.
.High Temperature 2-HPCI Steam Line Space s200*F E
1.
Above trip setting.
isolates HPCI system HPCI Pump Room Area.
and trips HPCI. turbine.
High Temperature.
INSERT B able 3.2 S notes) to' OPERABLE
' Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s)'
status or place the inoperable channel (s) in-the tripped E.
condition.
INSERT C (Table-4.2.3) f RCIC Steam Line Space (1)
Cnce/3 months none Torus Area Hign Temperature RCIC Steam Line Space (1)
Once/3 months.-
none RCIC Pump Room Area Hign Tenperature HPCI Steam Line~ Space ill Cnce/3 months.
none-Torus Area Hign Temperature HPC: Steam Line Space (1)
Once/3 months none
.HPCI Pump Rocm Area High Temperature t.
4
NSERT D (Bisaa Ssetion 3.2)
Etch trip systtm con 3icts of two^ h l$
Ch annt Etch chann31 contcins ons temperature switch located in the pump room and three temperature switches located in the torus area.
The RCIC high flow and.high area temperature sensing instrument channels are arranged in the same manner as the HPCI system.
The HPCI high steam flow trip setting of 90-paid and the RCIC high steam flow trip setting of 450" H,0 have been selected such that the trip setting is high enough to prevent spurious tripping during pump startup but low enough to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
The HPCI and RCIC steam line rpace temperature switch trip settings are high enough to prevent spurious isolation due te normal temperature excursions in the vicinity of the steam supply piping.
Additionally, these-trip settings ensure that the primary containment isolation steam supply valves isolate a break within an acceptable time period to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
i
TABLE 3.2.B (Continued)
Hinimum No.
E*
Operable Per y; E Trip Sy1111_
Function Trio Level Settina Action Remarks u
1 HPCI Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
I RCIC Trip System but power N/A C
l '. Monitors evallability of monitor power to logic systems.
1(2)
Instrument Channel -
1 Elev. 551' A
1.
Below trip setting will Condensate Header Low open HPCI suction valves Level-(LS-73-56A & B) to the suppression chaster.
2(2)
Instrument Channel -
1 7" above instrument zero A
1.
Above trip setting will open Suppression Chamber High HPCI suction valves to the Level suppression chamber.
2(2)
Instrument Channel -
1 583" above vessel zero A
1.
Above trip setting trips RCIC P
Reactor High Water Level tu-bine.
ra2 1
Instrument Channel -
1 450" H O-(7)
A 1.
Above trip setting isolates 2
RCIC Turbine Steam Line RCIC system and trips RCIC
-y High Flow turbine.
~*
)
! :trr :-t C':nn;!
- 00
".... ;rt,, eet;;i.; 0;;h te;-
5:0 St;= M ; 5;;;;--
OC!C ;,.;;
..dti p "!C
"' f ': ;: :tur:
t ; i". :.
3(2)
Instrument Channel -
150 psig A
1.
Below trip setting isolates RCIC Steam Supply RCIC system and trips RCIC Pressure - Lew (PS 71-1A-D) turbine.
3(2)
Instrument Channel -
1 20 psig A
1.
Above trip setting isolates RCIC Turbine Erhaust RCIC system and trips RCIC w
Diaphragm Pressure - High turbine.
m
>4 u
M GN L
Cas
-a O
CD i
m
TABLE 3.2.B (Continued)
Hinimum No.
c: to Operable Per S@ Trio Sys(1)
Function Trio Level Settino Action Remarks n
u 2(2)
Instrument Channel -
1583" above vessel zero.
A 1.
Above trip setting trips HPCI Reactor High Water Level turbine.
1 Instrument Channel -
190 psi (7)
A 1.
Above trip setting isolates HPCI Turbine Steam Line HPCI system and trips HPCI High Flow turbine.
_ [INUN S22 [
[55F E!. 29N.,r! 21332
... N A
_ g
_y - - us 7.. y -
w---
u. e 3(2)
Instrument Channel -
1100 psig A
1.
Below trip setting isolates HPCI Steam Supply '
HPCI system and trips HPCI Pressure - Low turbine.
(PS 73-1A-D) u 3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates
-l HPCI Turbine Eshaust HPCI system and trips HPCI O
Diaphragm (PS 73-20A-D) turbine.
i L
1 Core Spray System Logic N/A B
1.
Includes testing auto I
initiation inhibit to G
Core Spray Systems in
~
other units.
1 1
RCIC System (Initiating)
. N/A B
1.
Includes Group 7 valves.
Logic l
2.
Group 7: The valves in Group 7 are automatien11y actuated by t
only the following condition:
1.
The respective turbine steam supply valve not g
fully closed.
ts E
1 RCIC System (Isolation)
N/A B
1.
Includes Group 5 valves.
Q Logic
-4 2.
Group 5: The valves in Group I
at 5 are actuated by any of the P
following conditions:
p.a a.
RCIC Steamline Space High Temperature g
g b.
RCIC Steamline High Flow c=3 N
c.
RCIC Steamline Low 4
Pressure p
d.
RCIC Turbine Exhaust Diaphragm High Pressure 1 (16)
ADS Logic N/A A
-TABLE 3.2.8 (Continued)
Minimum No.
c: co Operable Per flE2 Trio Sys(11 Fonction Trio tevel Settino Action Remark t et u,
1(10)
Instrument Channel -
1100*F A
1.
Above trip setting starts RHR Thermostat (RHR Area area cooler fans.
Cooler Fan) 2(10)
Instrument Channel -
N/A A
1.
Starts Core Spray area cooler Core Spray A or C Start fan when Core Spray motor starts.
2(10)
Instrument Channel -
N/A A
1.
Starts Core $ pray area cooler Core Spray B or D fan when Core Spray motor starts.
1(10)
Instrument Channel -
1'100*F A
1.
Above trip setting starts Core Thermostat (Core Spray Area Spray area cooler fans.
Cooler Fan) 1(10)
RHR Area Cooler Fan Logic -
N/A A
I#
1(10)
Core Spray Area Cooler Fan N/A A
RJ Logic
,s-;,
1(11)
Instrument Channel -
N/A A
1.
Starts RHRSW pumps A3, 81, a
Core Spray Motors A or C
.C3, and D1
[3 Start 1(11)
Instrument Channel -
N/A A
1.
Starts RHR$W pumps A3, 81, Core Spray Motors B or D C3, and D1 Start 1(12)
Instrument Channel -
N/A-A 1.
Starts RHRSW pumps A3, Bl.
Core Spray Loop 1 Accident C3, and D1 Signal (15) 1(12)
Instrument Channel -
N/A A
1.
Starts RHRSW pumps A3. B1, lE Cere Spray Loop 2 Accident C3, and D1 Signal (15) 1 RPT Logic N/A (17)'
1.
Trips recirculation pumps on turbine *ontrol valve fast closure or stop valve closure > 30% power.
ggg pd 1(13)
RHRSW Initiate Logic N/A (14) typ C5 AD TNsERT-A1
^
t W
e
>v-
NOTES FOR TABLE 3.2.B 1.
Whenever any C3CS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted.
If a requirement of the first column is reduced by one, the indicated action shall be taken.
If the same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken.
Action:
A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.
B.
Declare the system or component inoperable.
C.
Immediately take action B until power is verified on the trip system.
D.
No action required; indita. ors are considered redundant.
EADD IAISERT-81 2.
In Inly one trip system.
3.
Not considered in a trip system.
1)e le bed.
- 4. A 0: quires ::: :henn:1 fr:= ::ch ph cie:1 1:0:ti n (th::: ::: A 1;;atians) j in th; :::::: line ep:::.-
5.
With diesel power, each RHRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 seconds later.
6.
With normal power, one CSS and one RHRS pump is scheduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 seconds with similar pumps starting after about 14 seconds and 21 seconds, at which time the full complement of CSS and RHRS pumps would be operating.
7.
The RCIC snd HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break.
Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
9.
The head tank is designed to assure that the discharge piping from the 33 and RER pumps are full. The pressure shall be maintained at or ahava t'>
values listed in 3.5.H, which ensures water in the discharge piping and up to the head tank.
BFN 3.2/4.2-22 Unit 3
TABLE 4.2.8 (Cont'd)
SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check 3.$
Instrument Channel -
(1) once/3 months none re RHR Pump Discharge Pressure Instrument Channel -
(1)
.once/3 months none Core Spray Pump Discharge Pressurs Core Spray Sparger to RPV d/p (1) once/3 months
-once/ day.
Trip System Bus Power. Monitor once/ operating Cycle N/A.
none.
Instrument Channel -
(1) once/3 months none Condensate Header Level (LS-73-56A B)
Instrument Channel -
(1) once/3 months none-Suppression Chamber High Level Instrument Channel -
(1) once/3 months once/ day Reactor High Water Level u
Instrument Channel -
(1) once/3 months none N
RCIC Turbine Steam Line High Flow N
- t
.;.-t C':
- ?
- ,c.;; '
x;;.t'.;
N
'C!C S' r
'8 0 ?,-
- "if.
I v-.,_-._-*__-__
Instrument Channel -
once/31 days
'once/18 months once/ day RCIC Steam Supply Low Pressure Instrument Channel -
once/31 days once/18' months once/ day-RCIC Turbine Exhaust Diaphrage -
4 High Pressure la d,i
.. App resRr-e l
-CJ
~5E rri 2
BFN-Unit 3 C/3 2
TT1 9
~n g
2-N cas
- 03 mcc CD CD I
r l
l I-l TABLE 4.2.B (Cont'd)
SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check C tu
- []
Instrument Channel -
(1) once/3 months none c,
HPCI Turbine Steam Line High Flow u,
,__m_____.
ru.
,,s
.___is
___it-
- ;-'~' :; _-- ;: _ _ _ m a
-~
~ ~
yj y="= <r---
r Instrument Channel -
once/31 days once/18 months once/ day HPCI Steam Supply Low Pressure Instrument Channel -
once/31 days once/18 months once/ day HPCI Turbine Exhaust Diaphragm High Pressure Core Spray System' Logic once/18 months-(6)-
N/A RCIC System (Instiating) Logic once/18 months N/A N/A RCIC System (Isolation) Logic once/18 months (6)
N/A f
HPCI System (Initiating) Logic once/18 months (6)
N/A N
N HPCI System (Isolation) Logic once/18 months
.(6)
N/A k
ADS Logic once/18 months (6)
N/A g
Ia LPCI (Initiating) Logic once/18 months (6)
N/A G
LPCI (Containment Spray) Logic once/18 months (6)
N/A 3>
Em Z
g BFN-Unit 3 I
m Z
O H
TT1 1
z tJ O.
g W
w O
a co 4
ve N
T*
?-
w
! k-3.2 BASES (Cont'd) i EB 051987 steam line isolation valve closure, fission product reaease is limited so.
j Jthat 10 CFR 100 guidelines are not exceeded for.this accident.. Reference Section 14.6.2 FSAR. An alarm with a nominal setpoint of 1.5 x normal i
full-power background is provided alse.
Pressure instrumentation is provided to close th'e main steam isolation:
valves in RUN Mode when the main steam line pressure drops below 825 psig.
l The HPCI high flow and; temperature instrtusentation are provided to detect a break in the HPCI steam piping.: Tripping of-this. instrumentation results in actuation of:HPCI isolation valves.. Tripping. logic for the high f1_ow is a 1-out-of-2 logic, and allLsensors are required to be
) operable.1 i
g A f M p' e /
High temperature in the vicinity of the.HPCI equipment;is sensed by four sets of four binetallic temperature switches.. The 16 temperature switches'are arranged in two: trip systems _with eight temperature switches in each trip system. [ ADD - IM.SER T - D l
- t.e ::70: t.ip.eettinge of ^0 pei.fer high flew r.
200"7 fv. hieh t-
, ::tx ; :: :::h tint :: : r::;r;. i: p;r;;.thd. :d fi;;ier, p.40 ;t r:1:::: i: rithin 11-10:.
O.e 7,0!O high fic; nd in,_ :::t :: frt:r-tet!= ::: cr:- 0:d ' the r --- -
- t5ct f: th: HPO!. Se trip retti 0 cf'^59" eter fer '! h f - rf O
2^^*F fer t--,:rette: cre bered r e n criteri:' : *he 5?CI.
l High temperature at the Reactor Cleanup System-floor drain could indicate i
a break in the cleanup system.- When high temperature occurs, the cleanup l
system is. isolated.
The instrumentation which initiates.CSCS action is arranged in a dual bus system. As for.other vital instrumentation arranged in this fashion, the specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed. An exception to this is when logic functional testing is being performed..
The control rod block functions are provided to prevent excessive-contral rod withdrawal so that MCPR does not decrease to 1.07. -The trip logic for this function is 1-out-of-n:
e.g., any trip on one of six APRMs.
eight IRMs, or four SRMs will result in a rod block.
l The minimum. instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.
The l
minimum ins'.rument channel requirements for the. REM may be reduced by one for maintenance, testing, or calibration. This does not significantly_
increase the risk of'an inadvertent control rod withdrawal, as-the other channel is available, and the'RBM is a backup system to the written sequence for withdrawal of control rods.
I i
BFN 3.2/4.2-66
.i Unit 3 1
INSERT A Table 3,2.B) 2 RCIC Steam Line Space s155*F E
1.
Above trip setting isolates RCIC system i
Torus Area and trips RCIC turbine.
High Temperature RCIC Steam Line Space s180*F E
1.
Above trip setting isolates RCIC system 2
RCIC Pump Room Area and trips RCIC turbine.
High Temperature 2
HPCI Steam Line Space s180*F E
1.
Above trip setting isolates HPCI system Torus Area and trips HPCI turbine.
High Temperature s200*F E
1.
Above trip setting 2
HPCI Steam.Line Space
-isolates HPCI system HPCI Pump Room Area and trips HPCI turbine.
High Temperature C
INSERT B (Table 3.2.3 notes) to OPERABLE Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s) in the tripped E.
status or place the inoperable channel (s) condition.
7 INSERT C (Table 4.2.3)
RCIC Steam Line Space (1)
Once/3 months none Torus Area High Temperature RCIC Steam Line Space (1)
Once/3 months none RCIC Pump Rocm Area High Temcerature HPCI Steam Line Space (1)
Cnce/3 months-none Torus Area High Temperature HPCI Steam Line Space (1)
Once/3 months none HPCI Pump Room Area High Temperature i
w
INSERT (Bassa Section 3.2)
[ hunt 1Lg
- Each trip system consists of two/LL-a.
Etch chann31 contains ons temperature switch located in the pump room and three temperature switches located in the torus area.
The RCIC high flow and high area temperature sensing instrument channels are arranged in the same manner as the HPCI system.
The HPCI high steam flow trip setting of 90 psid and the RCIC high steam flow trip setting of 450" H:0 have been selected such that the trip setting is high enough to prevent spurious tripping during pump startup but low enough to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
The HPCI and RCIC steam line space temperature switch trip settings are high enough to prevent spurious isolation due to normal temperature excursions in the vicinity of the steam supply piping.
Additionally, these trip settings ensure that the primary containment isolation steam supply valves isolate a break within an acceptable time period to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
i i
1 2
(
t t
I l
I
l i
i ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY.
BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS l'and 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-319 REVISED PAGES I.
AFFECTED PAGE LIST Unit 1 3.2/4.2-18 3.2/4.2-19 3.2/4.2-22a 3.2/4.2-23 l
3.2/4.2-46 3.2/4.2-47 3.2/4'.2-67 3.2/4.2-68 l
t Unit 3 3.2/4.2-18 3.2/4.2-19 l
3.2/4.2-21a i
3.2/4.2-21b 3.2/4.2-22 3.2/4.2-45 i
3.2/4.2-46 3.2/4.2-66 3.2/4.2-67 II.
REVISED PAGES See attached.
TABLE 3.2.B (Continued) c: oo Minimum No.
fl 32 Operable Per Trio Svsfl)
Function Trio Level Settina Action Remarks n
1 HPCI Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
1 RCIC Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
1(2)
Instrument Channel -
1 Elev. 551' A
1.
Below trip setting will Condensate Header Low open HPCI suction valves Level (LS-73-56A & B) to the suppression charber.
l(2)
Instrument Channel -
17" above instrument zero A
- 1. _ Above trip setting will open Suppression Chamber High HPCI :uction valves to the Level suppression chamber.
2(2)
Instrument Channel -
1583" above vessel zero A
1.
Above trip setting trips RCIC Reactor High Water Level turbine.
u
$a 1
Instrument Channel -
1 450" H O (7)-
A 1.
Above trip setting isolates 2
'~
RCIC Turbine Steam Line RCIC system and trips RCIC f"
High Flow turbine.
3(2)
Instrument Channel -
150 psig A
1.
Below trip setting isolates 00 RCIC Steam Supply RCIC system and trips RCIC Pressure - Low turbine.
-(PS 71-1A-D) 3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates RCIC Turbine Exhaust RCIC system and trips RCIC Diaphragn Pressure --
turbine.
High (PS 71-11A-D)
TABLE 3.2.B (Continued) c: c3 Hinimum No.
[Ly Operable Per Trio Sysfll_
Function Trio Level Settina Action Remarks re
"~
2(2)
Instrument Channel -
1583" above vessel zero.
A
- 1.. Above trip setting trips HPCI Reacter High Water Level turbire.
1 Instrument Channel -
190 psi (7)
A 1.
Above trip setting isolates HPCI Turbine Steam Line HPCI system and trips HPCI High Flow turbine.
3(2)
Instrument Channel -
1100 psig A
1.
Below trip setting isolates HPCI Steam Supply HPCI system and trips HPCI Pressure - Low turbine.
(PS 73-1A-D) 3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates HPCI Turbine Exhaust HPCI system and trips HPCI Diaphragn (PS 73-20A-D) turbine.
1 Core Spray System Logic N/A B
1.
Includes tasting auto initiation inhibit to c2 Core Spray Systems in li other units.
I RCIC System (Initiating)
N/A B
1.
Includes Group 7 valves.
4 Logic Cs 2.
Group 7: The valves in Group 7 are automatically actuated by only the following condition:
1.
The respective turbine steam supply valve not fully closed.
1 RCIC System (Isolation)
N/A B
1.
Includes Group 5 valves.
Logic 2.
Group 5: The valves in Group 5 are actuated by any of the following conditions:
a.
RCIC Steamline Space High Temperature b.
RCIC Steamline High Flow c.
RCIC Steamline Low Pressure d.
RCIC Turbine Exhaust Diaphragm High Pressure 1 (16)
ADS Logic N/A
.A
-.m.m...~
._ _~3
.__m
.._.m
... _._.s-
__e....
t 2
4 f
TABLE 3.2.B (Continued)
@Q Hinimum No.
rz Operable Per Trio Sys(1)
Function Trio level Settina -
Action' Remarks
';i 2
RCIC Steam Line Space 1155'F E
1.
Above trip setting Torus Area isolates RCIC system High Temperature and trips RCIC turbine.
2 RCIC Steam Line Space 1180*F.
E 1.
Above trip setting RCIC Pump Room Area isolates RCIC systee
' High Temperature
.and trips RCIC turbine.
2 HPCI Steam Line Space il80*F
.E 1.-
Above trip setting --
Torus Area isolates HPCI system High Temperature and trips HPCI turbine.
2 HPCI Steam Line Space 1200*F E
1.
Above trip setting HPCI Pump Room Area isolates HPCI system High Temperature and trips HPCI. turbine.
e s
.LJ t
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I PO PO PJ j
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==
m
-.m
HQIES FOR TABLE 3.2.B l
l 1.
Whenever any CSCS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted.
If a requirement of the first column is reduced by one, the indicated action shall be taken.
If the same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken.
1 Action:
A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.
B.
Declare the system or component inoperable.
C.
Immediately take action B until power is verified on the trip system.
D.
No action required; indiestors are considered redundant.
E.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition.
2.
In only one trip system.
3.
Not considered in a trip system.
4.
Deleted 5.
With diesel power, each RHRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 sec later.
6.
With normal power, one CSS and one RHRS pump is scheduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 sec. with similar pumps starting after about 14 sec, and 21 sec.,
at which time the full complement of CSS and RHRS pumps would be operating.
7.
The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break.
Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
9.
The head tank is designed to assure that the discharge piping from the CS and RHR pumps are full. The pressure shall be maintained at or above the values listed in 3.5.H, which ensures water in the discharge piping and up to the. head tank.
BFN Unit 1 3.2/4.2-23
TABLE 4.2.B (Continued)
SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS c to Function Functional Test Calibration Instrument Check 5$
rr Instrument Channel -
(1) once/3 months none RHR Pump Discharge Pressure Instrument Channel -
(1) once/3 months none Core Spray Pump Discharge Pressure Core Spray Sparger to RPV d/p (1) once/3 months once/ day Trip System Bus Power Monitor once/ operating Cycle N/A none Instrument Channel -
(1) once/3 months none Condensate Header Low Level (LS-73-56A, B)
Instrument Channel -
(1) once/3 months none Suppression Chamber High Level Instrument Channel -
(1) once/3 months once/ day F
Reactor High Water Level n
)
Instrument Channel -
(1) once/3 months none RCIC Turbine Steam Line High Flow Y
s-Instrument Channel -
once/31 days once/18 months-once/ day RCIC Steam Supply Low Pressure Instrument Channel -
once/31 days once/18 months once/ day RCIC Turbine Exhaust Diaphragm High Pre :ure RCIC Steam Lir.e Space (1) once/3 months none Torus Area High Temperature RCIC Steam Line Space (1) once/3 months none RCIC Pump Room Area High Temperature
l TABLE 4.2.B (Continued) r-SURVEILLANCE REQUIREHENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL.THE CSCS 9
Function Functional Test Calibration Instrument Check c tz 5$
HPCI Steam Line Space (1) once/3 months none Torus Area High Temperature HPCI Steam Line Space (1) once/3 months none HPCI Pump Room Area High Temperature 3
Instrument Channel -
(1) once/3 months none HPCI Turbine Steam Line High Flow 4
Instrument Channel -:
once/31 days once/18 months once/ day HPCI Steam Supply Low Pressure i
Instrument Channel --
once/31 days once/18 months once/ day HPCI Turbine Exhaust Diaphragm High Pressure Core Spray System Logic once/18 months (6)
N/A l
RCIC System (Initiating) Logic-once/18 months N/A N/A 2
RCIC System (Isolation) Logic once/18 months-(6)'
N/A 1
HPCI System' (Initiating) Logic
.once/18 months-
- (6)
N/A
~
HPCI System (Isolation) Logic once/18 months (6)
N/A ADS Logic.
once/18 months (6)
N/A LPCI (Initiating) Logic once/18 months.
(6)
' N/A LPCI (Containment Spray) Logic once/18 months (6)
N/A Core Spray System Auto Initiation
.once/18 months (7)
N/A N/A Inhibit (Core Spray Auto Initiation)
LPCI ' Auto Initiat' ion Inhibit once/18 months (7)
N/A N/A (LPCI Auto Initiation) -
i I
k e,..
-m m
-m m
-- J
Y
(.
3.2 BASES (C$nt'd)-
3 steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Section-14.6.2 FSAR.. An alarm with a nominal setpoint of 1.5 x normal full-power: background is provided also.-
Pressure instrumentation is provided to close the main steam isolation; valves in RUN Mode'when the main steam line pressure drops below.825 psig.
The HPCI high flow and temperature instrumentation are provided to detect.
a break in the HPCI steam piping., Tripping of.this instrumentation
- results in actuation of HPCI isolation' valves. Tripping logic for the i
high flow is-a.1-out-of-2 logic, and all sensors are required to'be.
- l.
1 l
High' temperature in.-the; vicinity'of the:HPCI equipmentlik sensed'by-
~
-]
four sets of four.binetallic temperature switches..The 16 temperature.
switches are arranged in two trip systems with'eight temperature switches
~
in.each trip system.. Each trip system consists of two channels. Each' channel contains oneftemperature switch located in the pump room and-j three temperature switches located in the torus area. The RCIC high' flow-
[.
and high area temperature sensing instrument' channels are arranged-in the.
.same manner as the HPCI system.
The HPCI high~ steam flow trip setting of 90 paid and the RCIC high steam flow trip setting of 450" H O have been selected such that the' trip i
2 j
setting is high enough to prevent spurious. tripping during pump startup i
but low enough to prevent core:uncovery and maintain-fission product' releases within 10 CFR 100 limits.
![
The HPCI and RCIC steam line space temperature switch trip settings are
~
high enough to prevent spurious; isolation due to normal temperature j
excursions in the vicinity of=the steam supply piping. Additionally,..
these trip settings ensure that the' primary containment isolation steam.
supply valves isolate a break within an acceptable. time period to prevent j.
core uncovery and maintain fission product releases within 10 CFR 100 limits.
f' High temperature at the Reactor Cleanup System floor drain could indicate a break in the cleanup system. When high temperature occurs, the cleanup system is isolated.
1 The instrumentation which initiates CSCS action is arranged'in a dual bus j'
system. As for other vital instrumentation arranged in this fashion, the specification preserves the effectiveness of the system even during periods when maintenance.or testing is'being performed. An exception to this is when logic functional testing is being performed.
Y I
E BFN 3.2/4.2-67 3
(
Unit 1 i
3 e
++ - -
~ ~. -
w,-
.m.n e
n
,a, e
>-,e a
e
3.2 BASES (C:nt'd)
The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to 1.07.
The trip logic for this function is 1-out-of-n:
e.g., any trip on one of six APRMs, eight IRMs, or four SRMs will result in a rod block.
The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met. The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration. This does not significantly
)
increase the risk of an inadvertent control rod withdrawal, as the other j
channel is available, and the RBM is a backup system to the written sequence for withdrawal of control rods.
The APRM rod block function is flow biased and prevents a significant reduction in MCPR, especially during operation at reduced flow. The APRM provides gross core protection; i.e.,
limits the gross core power increase from withdrawal of control rods in the normal withdrawal sequence. The trips are set so that MCPR is maintained greater than 1.07.
The RBM rod block function provides local protection of the core; i.e.,
the prevention of critical power in a local region of the core, for a single rod withdrawal error from a limiting control rod pattern.
If the IRM channels are in the worst condition of allowed bypass, the sealing arrangement is such that for unbypassed IRM channels, a rod block j
signal is generated before the detected neutrons flux has increased by more than a factor of 10.
A downscale indication is an indication the instrument has failed or the instrument is not sensitive enough.
In either case the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
1 For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapid enough to allow either core spray or LPCI to operate in time. The automatic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not operate. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation. The trip settings given in the specification are adequate to assure the above criteria are met. The specification preserves the effectiveness of the system'during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e.,
only one instrument channel out of service.
Two radiation monitors are provided for each unit which initiate Primary Containment Isolation (Group 6 isolation valves) Reactor Building Isolation and operation of the Standby Gas Treatment System. These instrument channels monitor the radiation in the reactor zone ventilation exhaust ducts and in the refueling zone.
l BFN 3.2/4.2-68 Unit 1
TABLE 3.2.B (Continued) jf Sj Minimum No.
ru sc Operable Per Trio Svs(1)
Function Trio Level Settino Action Remarks u
1 HPCI Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
1 RCIC Trip System bus power N/A C
1.
Monitors availability of monitor power to logic systems.
1(2)
Instrument Channel -
1 El ev. 551 '
A 1.
Below trip setting Will Condensate Header Low open HPCI suction valves tevel (LS-73-56A & B) to the suppression chamber.
2(2)
Instrument Channel -
i 7" above instrument zero A
1.
Above trip setting will open Suppression Cnamber High HPCI suction valves to the Level suppression chamber.
2(2)
Instrument Channel -
1583" above vessel zero A
1.
Above trip setting trips RCIC ga Reactor High Water Level turbine.
I 1
Instrument Channel -
1 450" H O (7)
A 1.
Above trip setting isolates 2
RCIC Turbine Steam Line RCIC system and trips RCIC oa High Flow turbine.
i Eo 3(2)
Instrument Channel -
150 psig A
1.
Below trip setting isolates RCIC Steam Supply RCIC system and trips RCIC Pressure - Low (PS 71-1A-D) turbine.
3(2)
Instrument Channel -
120 psig A
1.
Above trip setting isolates RCIC Turbine Exhaust RCIC system and trips RCIC Diaphragm Pressure - High turbine.
(PS 71-11A-D)
- __s_,
._m 4..m i
TABLE 3.2.B (Continued)
Hinimum No.
c: es
- am Operable Per 77 2 Trio Svs(1)
Function Trio tevel' Settina Action Remarks 2(2)
Instrument Channel -
1583" above vessel zero.
A 1.
Above trip setting trips HPCI Reactor High Water Level turbine.
1 Instrument Channel -
190 psi (7)'
'A 1.
Above trip setting isolates HPCI Turbine Steam Line HPCI system and trips HPCI High Flow turbine.
3(2).
HPCI Steam Supply HPCI system and trips HPCI Instrument Channel -
1100 psig A
1.
Below trip setting isolates Pressure - Low turbine.
(PS 73-1A-D) 3(2)
Instrument Channel --
120 psig A
~1.
Above trip setting isolates HPCI Turbine Exhaust HPCI system and trips HPCI Diaphrage (PS 73-20A-C) turbine.
1-Core Spray System Logic N/A B
1.
Includes testing auto -
initiation inhibit to Core Spray Systems in v,
other units.
3?
1 RCIC System (Initiating)'
N/A B-1.
Includes Group 7 valves.
Logic a
2.
Group 7:- The valves in Group 7
[3 are automatically actuated by.
l only the following condition:
1.
The respective turbine steam supply valve not fully closed.
I 1
RCIC System (Isolation)
N/A' B
1.
Includes Group 5 valves.
Logic 2.
Group 5: The valves'in Group 5 are actuated by any of the-following conditions:
i-a.
RCIC Steamline. Space High Temperature b.
RCIC Steamline High Flow
.c.
.RCIC Steamline Low Pressure d.
RCIC Turbine Exhaust Diaphragm High Pressure l'(16)
ADS Logic-N/A -
A t
'*wc w
e u
,_. -. _=
-2 a
m
I l
f TABLE 3.2.8 (Continued) l C to Minimum No.
2 RE Operable Per n
Trio Svs(1)
Function Trio Level Settina Action Remarks u
2 RCIC Steam Line Space 1155'F E
1.
Above trip setting isolates Torus Area
- RCIC system and trips RCIC j
High Temperature turbine.
i 2
RCIC Steam Line Space 1180*F E
1.
Above trip setting isolates RCIC Pump Room Area RCIC system and trips RCIC -
High Temperature turbine.
2 HPCI Steam Line Space 1180*F E'
l'.
Above' trip setting isolates Torus Area HPCI system and trips HPCI High Temperature turbine.
2 HPCI Steam Line Space 1200*F
'E 1.
Above. trip setting isolates HPCI Pump Room Area HPCI system and trips HPCI High Temperature turbine.
e i
N N
\\
N s
~
N 1
w ts 1
l 4-E 1
I 4
t
+
l 4
1
- e i
I s
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~
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i I
j i
t 1
4 i
THIS PAGE INTENTIONALLY LEET BLANK a
5 l
4 i
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i i
BMi 3.2/4.2-21b Unit 3
NOTES FOR TABLE 3.2.B 1.
Whenever any CSCS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted.
If a' requirement of the first column.is reduced by one, the indicated action shall be taken..
If the same function is inoperable in more than'one trip system or the first column reduced by.more than one, action B shall be taken.
Actions-A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not OPERABLE in 24' hours, take action B.
1 B.
Declare.the system or component: inoperable.
C. 'Immediately'take action'B until power is-verified.on the trip. system'..
D.
No action < required; indicators are: considered l redundant..
E.
Within:24 hours restore the inoperable channel (s) to OPERABLE. status 1
L or place :he inoperable channel (s):in the tripped condition.
L l
2.
In only one trip system.
3.
Not considered in a trip system.
4.
Deleted.
^-
5.
With diesel. power, each RHRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 seconds later.
6.
With normal power, one CSS'and one RHRS pump is scheduled to. start.
instantaneously, one CSS'and one RHRS. pump is sequenced.to start after about-7 seconds with similar pumps starting after about 14 seconds and 21 seconds, at which time the full complement.of CSS.and RRRS pumps would
[
be operating'.
l
/
7.
The RCIC and HPCI steam line high. low trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percene above maximum steady state steam flow to assure that spurious isolation does not occur while. ensuring the-initiation of' isolation following a postulated steam;1ine break.
Similarly,cthe HPCIS setting of 90 psi corresponds to:at least 150 percent above maximum steady state flow while also' ensuring the L
initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
'9.
The head tank is designed to assure that the_ discharge piping from the CS and RHR pumps are full. The' pressure shall be maintained at or above the-values listed in 3.5.H, which ensures water in the discharge piping and up to the head tank.
i BFN 3.2/4.2-22 Unit 3 e,-
-w-uO +
e m
.-,,.=
a TABLE 4.2.B (Cont'd)
SURVEILLANCE REQUIREHENTS FOR INSTRUHENTATION THAT INITIATE OR CONTROL THE CSCS c: en Function Functional Test Calibration Instrument Check am Instrument Channel -
(1) once/3 months none RHR Pump Discharge Pressure g
Instrument Channel -
(1) once/3 months none Core Spray Pump Discharge Pressure Core Spray Sparger to RPV d/p (1) once/3 monthr.
once/ day Trip System Bus Power Honitor once/ operating Cycle N/A none Instrument Channel -
(1) once/3 months none Condensate Header Level (LS-73-56A, 8)
Instrument Channel -
(1) once/3 months none Suppression Chamber High Level Instrument Channel -
(1) once/3 months once/ day Reactor High Water Level Instrument Channel -
(1) once/3 months none RCIC Turbine Steam Line High Flow Instrument Channel -
cnce/31 days once/18 months once/ day RCIC Steam Supply Low Pressure L
Instrument Channel -
once/31 days once/18 months once/ day RCIC Turbine Exhaust Diaphragn High Pressure RCIC Steam Line Space (1) once/3 months none Torus Area High Temperature RCIC Steam Line Space (1) once/3 months none RCIC Pump Room Area High Temperature-HPCI Steam Line Space (1) once/3 months none Torus Area High Temperature HPCI Steam Line Space (1) once/3 months none HPCI Pump Room Area High Temperature i
. ~. ~... ~...... ~. -..~... _..
S.
TABLE 4.2.B (Cont'd)
SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS.
)
b cw Function Functional Test Calibration Instrument Check
- s m Instrument Channel -
(1) once/3 months none HPCI Turbine Steam Line High Flow Instrucent Channel -
once/31 days once/18 months-once/ day HPCI Steam Supply Low Pressure Instrument Channel -
once/31 days.
once/18 months
.once/ day HPCI Turbine Exhaust Diaphrayn High Pressure Core Spray System Logic once/18 months (6)
N/A '
RCIC System (Initiating) Logic once/18 months N/A N/A RCIC System (Isolation) Logic once/18 months (6)
N/A HPCI System (Initiating) Logic once/18 months.
(6)
N/A HPCI System (Isolation) Logic once/18 months (6)
N/A~
ADS Logic once/!S months s(6)
N/A
.LPCI (Initiating) Logic once/18 months (6)
N/A l
w 1
LPCI (Containment Sp' ray) Logic once/18 months (6)
N/A; l
E
.m.
.. m 2
^
n
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.4
1..
3.2 BASES (Cent'd) steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Section 14.6.2 FSAR. An alarm with a nominal setpoint of 1.5 x normal full-power background is provided also.
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressuie drops below 825 psig.
The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping. Tripping of this instrumentation results in actuation of HPCI isolation valves. Tripping logic for the high flow is a 1-out-of-2 logic, and all sensors are required to be OPERABLE.
l High temperature in the vicinity of the HPCI equipment is sensed by four sets of four bimetallic temperature switches.
The 16 temperature switches are arranged in two trip systems with eight temperature switches in each trip system. Each trip system consists of two channels. Each channel contains one temperature switch located in the pump room and three temperature swit,es located in the torus area. The RCIC high flow and high area temperatute sensing instrument channels are arranged in the same manner as the HPCI system.
The HPCI high steam flow trip setting of 90 psid and the RCIC high steam flow trip setting of 450" H O have been selected such that the trip 2
setting is high enough to prevent spurious tripping during pump startup but low enough to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
The HPCI and RCIC steam line space temperature switch trip settings are high enough to prevent spurious isolation due to normal temperature excursions in the vicinity of the steam supply piping. Additionally, these trip settings ensure that the primary containment isolation steam supply valves isolate a break within an acceptable time period to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
High temperature at the Reactor Cleanup System floor drain could indicate a break in the cleanup system. When high temperature occurs, the cleanup system is isolated.
i The instrumentation which initiates CSCS action is arranged in a dual bus system. As for other vital instrumentation arranged in this fashion, the specification preserves the effectiveness of the system even during j
periods when maintenance or testing is being performed. An exception to this is when logic functional testing is being performed.
BFN 3.2/4.2-66 Unit 3
- 6. f a 3.2 BASES (Ctnt'd)
The control rod block functions are provided to prevent-excessive control rod withdrawal'so that MCPR does not decrease to 1.07.
The trip ~ logic for this function is 1-out-of-n:
e.g., any trip. on one of si APRMs, -
eight IBMs, or four SRMs will result in a rod block.
The minimum instrument channel requirements assureisufficient instrumentation'to assure the single failure criteria is' met. The minimum instrument channel requirements for the RBM may be. reduced by one for maintenance, testing, or calibration.- This'does not significantly1 l
increase the risk of an inadvertent control rod withdrawal, as the other
,)
channel;is available,.and the.RBM is a> backup system to.the written
.l t
sequence for withdrawal ofLcontrol rods.
The APRM rod block function is flow biasedTand prevents a.significant reduction in MCPR, especially during operation at reduced flow. The APRM provides gross +. ore protection; i.e.,
limits the gross core power increase from withdrawal of control rods in the normal withdrawal!
sequence. The trips are set so that MCPR.is maintained greater than 1.07.
.I The RBM rod block; function provides lo'a1' protection ~of the core; i.e.,.
j c
the prevention of critical power in1a localiregion of the core,.for a-
-l single rod withdrawal error from a limiting control rod pattern.
If the IRM~ channels are in the vorst condition of allowed bypass,-the-sealing arrangement is such that for unbypassed IRM. channels, a rod block signal is generated before the detected neutrons flux has increased by more than a factor of 10.
A downscale indication is an indication the instrument has failed or the instrument is not sensitive enough.
In either. case the instrument will not respond to changes in control rod motion and'thus, control rod motion is prevented.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the~ refueling position.
For effective emergency core cooling for small-pipe breaks, the HPCI system must function since reactor pressure does not decrease rapid enough to allow either core spray or LPCI to operate in'.. time. The automatic pressure relief function-is provided as a backup to the HPCI in the event the HPCI does not operate. The arrangement of the tripping contacts is such as to. provide this function when necessary and minimize spurious' operation..The trip settings given in'the specification.are adequate to assure the above criteria'are met.. The specification preserves the effectiveness e the system during periods of maintenance, testing, or calibration, and also minimizes the risk'of inadvertent' operation; i.e.,
only one instrument channel out of service.
Two radiation monitors are provided for each unit which initiate Primary Containment Isolation (Group 6 isolation valves) Reactor Building Isolation and operation of the Standby Gas Treatment System.- These
' instrument channels monitor the radiation in the reactor zone ventilation exhaust ducts and in the refueling zone.
BFN 3.2/4.2-67 l Unit 3 u.
l 4.* -
i ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1 and 3 j
PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-319 LIST OF COMMITMENTS The computer modeling techniques for Unit 1 will be confirmed prior to Unit i restart.
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4 1
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i 2
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l 1
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