ML17264A257
| ML17264A257 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/20/1995 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17264A256 | List: |
| References | |
| NUDOCS 9511300076 | |
| Download: ML17264A257 (5) | |
Text
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FUNCTIONAL UNIT TOTAL NO. of CHANHE I.S NO. of CHAHNEI.S TO TRIP MlH.
OPERABI.E CHAHHF.I.S PERMISSIBI.E BYPASS COHDITIOHS 5
OPFRATOR ACTION IF CONDITIONS OF COI.UMH I
OR 3
CANNOT BE MET TABI.F. 3.5-2 (Continued)
EHGIHEERFD SAFETY FEATURE ACTUATION INSTRUMENTATION CHAHHEL OPF.RABLE ABOVE 3.
AUXILIARYFEEDWATFR Motor and Turbine Driven J
~
Ma>>>>a I I/pumf>
Gun.
Wat.cr I.>>vc I - I ow-low I/ f>u>l>p I/l>ump T CS
= 350 F
i.
St.>> rl Motor f)r i vcn I'>m>ps i i. Start Turbine Driven Pump 3/stm.gcn.
2/stm.gcn.
2/stm.gc n.
either gcn.
I>oth gcn.
3/stm.gen.
2/stm.gen.
2/stm.gcn.
both gc>>.
either gcn.
rRS
= 350 F
TRCS
= >>o F
Loss of 4 KV Volt.age Start Turbine Driven Pump Safety Injection Start. Motor Driven Pumps
~ Trip of both Feed-water Pumps starts Motor Driven 1>umf1>s 2/bus 2/pump 1/bus, 2/bus (bot.l> buses)
(citl>cr bus)
(scc It.cm I)
I/pump 2/pump bot.h pumps either pump t3 Q~
T
= 350o RCS 5'/
f>>>wc r Standby Motor Driven Ma>>>>a I
>cdnlWbu P~s I/f>ump I/f>ump I/pump
~fl
~
I">Oof
=3~ P
>> t.g
TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKSI CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel 1.
Nuclear Power Range Check S
M*(3)
Calibrate Test D(l)
(2)(4) 1)
O*(3)
P(2)(5~.
2)
(CC~)
3) 4)
5)
<)
Remarks Heat balance calculation**
Signal to WT; bistable action (permissivei rod stop> trips)
Upper and lower chambers for axial offset**
High setpoint
(<109% of rated power)
Low setpoint
(<25% ot rated power) 2.
Nuclear Intermediate S(1)
Range N.A.
P(2) 1)
- 2) Once/shift when in service Log level; bistable action (permissive>
rod stop> trip) 3.
Nuclear Source Range S(1) 4.
Reactor Coolant Temperature 5.
Reactor Coolant Flow S
N.A.
~~@.
R P(2) 441)
(2) 1)
2) 1)
2)
Once/shift when in service Bistable action (alarmi trip)
Overtemperature-Delta T
Overpower Delta T
6.
Pressurizer Hater Level 8.
4 Kv Voltage Frequency 9.
Rod Position Indica tion N.A.
S(1,2) 7.
Pressurizer Pressure S
~i6 R c~a~~
N.A.
g~ ~Q. SK cL~~&
c or Protection circuits only.
pvv ~,i~~~ A=iS,~
A-~<~i'~~
- 1) With step counters 2)
Log rod position indications each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when rod deviation monitor is out, of service Dy means of the movable in-core uetector system.
Not required during hot> cold, or refueling shutdown.but as soon as possible af ter return to power.
TABLE 4.1-1 (Continued)
Channel esc i t'o 10.
Rod Position Bank Counters 11.
Steam Generator Level
- 12. Charging Flow
- 13. Residual Heat Removal Pump Flow
~neck S(1,2)
H.A.
N.A.
N.AD
~ho~~
~4 R ~~~lg R
N.A. 1) 2)
N.AD N.A.
Calibrate Test ema ks With rod position indication Log rod position indications each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when rod deviation monitor is out of service lmr <>>, Ac~
~h~v
- 14. Boric Acid Storage Tank Level D
N.A.
Note 4
- 15. Refueling Water Storage Tank Level H.A.
N.A.
16.
Volume Control Tank Level
- 17. Reactor Containment Pressure H.A.
R N.A.
N P~
- 1) Isolation Valve signal
- 18. Radiation Monitoring System
- 19. Boric Acid Control D
N.A.
N.A.
Area Monitors Rl to R9, System Monitor R17 20.
Containment Drain Sump Level H.A.
N.A.
- 21. Valve Temperature Interlocks 24
~ Accumulator Level and Pressure 22.
Pump-Valve Interlock
- 23. Turbine Trip Set-Point H.A.
H.A.
N.A.
N.A.
N.A.
~
~
~
C,ho.~
R C.Qo.~~
P C <') (.ab N.A.
p,-~y ~seals ~~~ ~~i~~~~~
~+P CAw~
+(- SMp Va54Fc ~~~ ~P-
~) ~ ~ ~~~u iw~ Xcu+ 34 Amendment Nc. g 57 4.1-6
Channel Descrgiiin Qhe~k g~li rage
~Te
~em <~rk 42.
43.
RCP Breaker Position Trip N.A.
N.A.
44.
Overtemperature aT Q(1)
- 1) Each channel shall be tested at least once every 92 days on a staggered test basis 45.
Overpower ~T Q(1)
- 1) Each channel shall be tested at least once every 92 days on a staggered test basis 46.
Safety Injection Manual N.A.
Initiation (ESFAS) 47.
Containment Spray Manual N.A.
Initiation (ESFAS) 48.
Containment Isolation Manual Initiation N.A.
49.
Containment Ventilation N.A.
Isolation Manual Initiation N.A.
50.
Steam Line Isolation Manual Initiation N.A.
51.
AuxiliaryFeedwater Manual Initiation N.A.
52.
Feedwater Line Isolation N.A.
Manual Initiation N.A.
TABLE 4.1-2 MXNXMUM FRE UENCXES FOR E UXPHENT AND SAMPLXNG TESTS 1.
Reactor Coolant Chemiatry Samples 2.
Reactor Coolant Boron Tost Chloride and Fluoride Oxygen Boron Concentration Frecru~enc 3 times/week and at least every third day 5 times/week and at least every second day except when below 250'F Weekly 3 ~
Refueling Water Storago Tank Water Sample Boron Concentration Weekly 4.
Boric Acid Storage Boron Concentration Tank TwJ.cc/Weokt'>
5.
Cont:rol Rods 6a. Full Length Control Rod 6b. Full Length Control Rod 7.
Presaurirer Safety Valves 8.
Main Steam Safety Valves en Isolati.on Tri.p
- 10. Rcfuoling System Interlocks C4 (e~~
~ma.~to.
'4,g-i, NS Rod drop times of all full length rods Move any rod not fully inaorted a sufficient number of steps i.n any ono direction to cause a
change of position aa indicated by the rod position i.ndication syat:em Move each rod through i.ta full length to" verify that the rod position indication system transitions occur Set point Set point not iond:n Functioning After vcaacl head removal and at least once per 18 months (1)
Monthly Each Refueling Shut:down Each Refucli.ng Shutdown Each Refueling Shutdown e&ueling-Shutdow Prior to Refueling Operations Amendment No. g, 57 4'-8