ML20085A735
| ML20085A735 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/18/1991 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20085A723 | List: |
| References | |
| NUDOCS 9107260212 | |
| Download: ML20085A735 (13) | |
Text
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- 1. Steam Jet Air Ejector Off-Gas System 1. Steam Jet Air Ejector Off-Cas System l a. -Operability of the Steam Jet Instrumentation surveillance Air Ej ector Off-Gas System requirements are given on U monitor is defined in Table 4.2.D.
Table 3.21.A.2. t
- b. The timo delay setting for closure of the steam jet air L ejector isolation valves
! shall not exceed 15 minutes.
, c. Other limiting conditions for
{ operation are given o_n Table 3.2.D -and Specif'. cations
] 3.21.A.2 and 3.21.C.6.
2 .. ' Reactor Building Isolation and 2. Reactor Building Isolation and Standby Gas Treatment Initiation
, Standby Gas Treatment Initiation i
The limiting- conditions for Instrumentation surveillance
. operation are given on Table 3.2.D. requirements are given on l Tabic 4.2.D.
- 3. Liquid Radwasto Discharge Isolation The limiting conditions for 3, Liquid Radwaste Dischargo Isolation operation are given on Table 3.2.D Instrumentation surveillance !
-and-Specification 3.21.B. requirements are given on Table 4.2,D.
.4 Main Control Room Ventilation Isolation 4. Main Control Room Ventilation Isolation The limiting conditions for <
operation are given on Table 3.2.D The instrument surveillance I and the Section entitled " Additional requirements are given on Tabic 4.2.D. f Safety Related Plant Capabilities. ,,
! 5. Mechanical Vacuum Pump Isolation 3
i
- 5. Mechanical vacuum Pump Isolation
[ a. -The mechanical vacuum pump j shall ~be capable of being The instrument survei.llance
-F isolated and requirements -are given on Tables automatically 4.1.1, 4.1.2, and 4.2.D.
!! secured by a signal of high -
j- radiation in the main t. team i line tunnel whenever the main steam isolation- valves are open.
- b. If the limits of-(3.2.D.5.a)
! are not met, the vacuum pump
; -shall be isolated.
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- COOPER NUCLEAR STATION TABLE 3.2.B'(Page 6)- .. ]
REACTOR CORE IS01ATION COOLING SYSTEM - (RCIC)' CIRCUITDY REQUIREMENTS , 1j Minimum Number of-- Action Required When
- -Instrument Operable Components , Component Operability-Is Not Assured ' I l Instrument- I.D. No. Settinst Limit- Per Trio System (1)
- RCIC High Turbine RCIC-PS-72, A & B $25 psig 1(2) A' l f Exhaust Press. '
i 8 ~ RCIC Low Pump Suction RCIC-PS-67-1 515" Hg Vacuum 1(2) j. [; ' Press. ;. e a
!- RCIC Steam Line Space RCIC-TS-79, A,B,C,&D $200*F '2(4) A ,
; Excess Temp. RCIC-TS-80, A,B,C,&D: *
'l RCIC-TS-81, A,B,C,&D * 'I j RCIC-TS-82, A,B,C,&D 1
., RCIC Steam Line High RCIC-dPIS'-83 & 84 370" $Ss620" H 2O 1 A i r AP -370" 2S2-620" H 2O ;
-l-
?o.o ,_ _.
- t. ;
; RCIC Steam Supply RCIC-PS-87, A,B,C,6D 250 psig 2(2) A j Press. Low ,
i j RCIC Low Pump. RCIC-FIS-57 240 gpm 1(2) A )i; j
- j. Disch. Flow 1
Pump Discharge Line CM-PS-269 210 psig (3) D I Low Pressure RCIC Turbine Condition- RCIC-TDR-K9 13.5 5 T s 16.5 see (3) E ,I l al Supervisory Alarm j ,
! Timer ;
f Reactor Low Water 10A-K80, A & B 2-37" Indicated Level 2(2) A I
! Level 10A-K79, A & B 5 :
[ (NBI-LIS-72, A,B,C, f I 1
& D) , .]i -; Reactor High Water NBI-LIS-101, A & C #2 s+58.5" Indicated Level 2(2) A [ , j-Level '}x !
jy RCIC Steamline High RCIC-TDR-K12 2.MTs3.3 sec i 1 A ! j0 AP Actuation Timer RCIC-TDR-K32 .l s- , L . - - - . , _ . . ~ _ - - . - _ . . _ , .-._. i
;i t a _ -_ _ _ . - _ _ _ _ . . _ - _ .- _ _._ ____.._ . _ _ - -. . .
- l 4 - COOPER NUCLEAP, STATION '
.L-TABLE 3.2.D~ L. l -
-RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS' . .]
, ;; t. :i
[ Number of Sensor j .;.'
.[' Instrurent Setting Channels Provided" Action t System I. D. No. Limit 'by Desizn (1) *[
- 5
{ Steam Jet Air- Ej ector Off-Gas RMP-RM-150 A & B (3) 2 A
-{
i,
. System 1
{' { 1 i Reactor Building Isolation RMP-RM-452 A, B. < 100 mr/hr 4 B j
! and Standby Cas Treatment C&D '
I Initiation , ,
- r. ,
I Liquid,Radwaste Discharge l' RMP-RM (2) 1 C Isolation Main Control Room Ventilation L(RMV-RM-1). 3 4x10 CPM 1 D .', l Isolation i a'- . i i
- f. ...W
. = .. . . . -.. . ... .... -.. . . . . . , .
Mechanical Vacuum Pump Isolation (4)iRMP-RM-251 A, B, 3 times normal full power 4 E , ;
! C&D background. Alarm at i
- f. 1.5 times normal full- i i
! power background l ! j
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f NOTES FOR TABLE 3.2.D 1~. Action required when component operability is not assured. . A. (1)- If radiation level exceeds 1.0 ci/sec (prior to 30 min. delay line) for a period greater than 15 consecutive minutes,- the off gas isolation valve shall close and reactor shutdown shall be initiated immediately and the reactor placed in a cold ; shutdown condition within 24 hours. A .- (2) Refer to Specification 3.21.A.2. B. A minimum of one instrument channel per trip system shall be ,
. operable when handling irradiated fuel inside secondary containment,. and - when moving loads inside secondary containment which have the potential to damage irradiated fuel. If this requirement cannot be met by a trip system, then that trip system shall be tripped. If this requirement cannot be met by both trip systems, then the following actions '
shall be taken: (1) Cease handling of irradiated fuel'inside secondary containment r and remove the load from over the irradiated fuel via the r.,oot
-direct path, or (2) Isolate secondary containmcat and start SBGT.
C. -I)uring release of radioactive wastes, the effluent control monitor shall be set to alarm and automatically closo- the waste - discharge valve prior to exceeding the limits of Specification 3.21.B,1. D.- Refer to1Section entitled " Additional Safety Related Plant Capabilities". E. Refer to Section 3.2.d.5 and the requirements for Primary Containment Isolation on high main steam line radiation. Table 3.2.A.
- 2. . Trip; settings to correspond to Specification 3.21.B.1.
'3. Trip 1 settings to correspond-to Specification 3.21.C.6.a.
'4.
Minimum number of channels operable shall be one during mechanical vacuum
. pump operation.
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, .3 j.3[ COOPER NUCLEAR STATION ,j.'
' TABLE 4.2.A (Page 1) (; ,1 : ,
. PR"JfARY CONTAINMENT AND REACTOR VESSEL ISOLATION SYSTEM j i
- TEST AND CALIBRATION FREQUENCIES ,
y L 8 k 4
! Instrument l ,* Item Item I.D. No. Function' Test Freo. Calibration Freo. Check" I!
+
! 3 j Instrument Channels lht i- . t Reactor Low Water Level NBI-LIS-101,.A,B.C,6D Once/ Month (1) Once/3 Months once/ Day. ;
) ;
s Reactor Low Low Water Level' NBI-LIS-57..A & B #2 Once/ Month (1) Once/3 Months once/ Day [ { NBI 7?S '.,5, A 6 B #2 l
! .. i i ~-
i Reactor Iow low Low Water' Level .NBI-LIS-57, A &'B fl Once/ Month (1) Once/3 Months once/ Day f
- i. i NBI-LIS-38 A & B fl -i_-
. j Main Steam Line In'r. 'MS-TS-121, A,B,C,&D Once/ Month (1)' Once/ Operating None+ , j < l:; Detection '122, 123, 124, 143, 144, Cycle _
' 'on 145 -146,-147, 148, 149,-
150. [ l l ; 3 -1 J I) Main Steam'Line High Flow MS-dPIS-116, A,B,C,&D
. Once/ Month (1) Once/3 Months- None? [
- g. ; .117 Once/ Month (1) Once/3 Months- None-
- j 118 Once/ Month (1) Once/3 Months Nonej j l 4
! 119 Once/ Month (1) Once/3 Months None; ,
Main Steam Line Low Press. .MS-PS-134, A,B,C,6D Once/ Month (1) Once/3 Months None;
) ,
{'t ! i High Reactor Pressure RR-PS-128, A 6.B Once/ Month (1) Once/3 Months Nonei i . .
, Condenser Low Vacuum HS-PS-103, A,B,C,&D Once/ Month (1) Once/3 Months Nonei {
! i- i l Reactor Water C.U. High Flow RWCU-dPIS-170, A & B' Once/ Month (1) Once/3 Months 'Nonej i r . t 4 1
- Reactor Water C.U. High Space '.RWCU-TS-150 A-D, 151, 152, Once/ Month (1) Once/ Operating None} ,
l
; Temp. :153,"154, 155, 156, 157, < Cycle t ;
i 158, 159,- RUCU-TS-81, A,B,E,F i ; jk RWCU-TS-Si C,D G,H l ,[ [ iA f' i ! j x j j , . i .: .I ! I f !, . g -me - ye u-- m- m
r
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, COOPER NUCLEAR STATION
{ TABLE 4.2.B (Page 2) J
~l RHR SYSTEM TEST & CALIBRATION FREQUENCIES j-
;- t
! .I t e.
t
}' i +
-i Insta.xment'
! Item Item I.D. No. Functional Test Freo. Calibration Frer. Check 1 4
Instrumentation j; , 1 i . j 1. Drywell High Pressure PC-PS-101 A, B,.C & D . Once/ Month (1) Once/3 Months None,[. ;
- j. 2. Reactor Lov Water Level NBI-LIS-72, A, B, C & D fl . Once/ Month-(l) Once/3 Months Once/ Day l l f 3. Reactor Vessel Shroud Level NBI-LITS-73, A & B fl Once/ Month (1) Once/3 Months Once/ Day?
I
- 4. ' Reactor Low Pressure RR-PS-128 A & BL . . Once/ Month (1) Once/3 Months None ,
- 5. Reactor Low ~ Pressure NBI-PS-52 A1,A2,C1, & C2 Once/ Month (1) Once/3 Months None '
NBI-PIS-52 B & D .
- 6. Drywell Press.-Containment PC-PS-119, A,B,C & D Once/ Month (1) Once/3 Months None i
{
- Spray {
!~ 7. RHR Pump Discharge Press. RHR-PS-120, A,B,C & D Once/ Month (1) Once/3 Months None '
t j .4 8. RHR Pump Discharge Press. RER-PS-105, A,B,C & D None !
~
Once/ Month (1) Once/3 Months ;
'>* 9. RHR Pump Low Flow Switch - -RHR-dPIS-125:A,& B- ' Once/ Month (1) .Once 3 Months- .None.#
!* 10. RHR Pump Start Time Delay RHR-TDR-K70, A & B. Once/ Month (1) Once/Oper. Cycle None !-
- 11. RHR Inj ection Valve Close T.D. RHR-TDR-K45 1A & IB Once/ Month (1) Once/Oper. Cycle None l
; 12. RHR Pump Start Time Delay RHR-TDR-K75,.A & B Once/ Month (1) Cnce/Oper. Cycle None !
j 13. RHR Heat Exchanger Bypass T.D. RHR-TDR-K93, 8L & B - Once/ Month (1) Once/Oper. Cycle None ! l i 14. RHR Cross Tie Valve Position RHR-IliS-8 Once/ Month (1) N.A. ! ; l 15. Low Voltage Relays . 27 X 3/lA (7)' None i l
- 16. Low Voltage Relays 27 X 3/1B (7) None !-
l-jl
- 17. Low Voltage Relays .27 x 2/1F, 27 .I 2/lG (7) None .
- 18. Lov Voltage Relays .
27 X 1/lF, 271 1/lG (7) None !
- 19. Pump Disch. Line Press.' Low CM-PS-266, CM-f3-270 Once/3 Months once/3 Months None l l 20. Emergency buses Undervoltage 27/lF-2, 27/lFa 2, 27/lG-2, Once/ Month Once/18 Months once/12 hrs.
} Relays (Degraded Voltage) 27/lGB-2 i l
- 21. Emergency buses loss of 27/lF-1, 27/1.FA - , 27/lG-1, Once/ Month Once/18 Months Once/12 hrN. ,'
j Voltage Relays 27/lGB-1, 27/ET-L, 27/ET-2 l- l t 22. Emergency Buses Undervoltage 27X7/lF, 27X7/lG Once/ Month Once/18 Months None ; . Relays. Timers - 5 k
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1 l (y . - - . . ._ 1* - , ; 3.2 MES (Cont'd) t j Both instunnents are required for trip but the instruments are so acaigned that any ,
; instrument failure gives a downscale trip. The trip setting of 1.0 ci/sec (prior to 30 min, delay) provides an improved capability to detect fuel pin cladding failures t to allow prevention of nerious degradation of fuel pin cladding integrity which might ,
result from plant operation with a misoriented or utsloaded fuel assembly. This ! If mit is more restrictive than 0.39 ci/sec noble gas release rate at the air ejectors . (after 30 min. delay) which was used as the source term for an accident analysis of l l the aug.nented off gas system. Using the .39 ci/see source term, the maximum off site ; i total body dose would be less than the .5 rem limit. ; I
- 2. Reactor Building Isolation and Standby Gas Treatment Initiation Reactor 11uilding Isolation and Standby Gas Treatinnut initiation is provided in a 1 out of 2 taken twice logic design via four radiation sensors located on the Reactor l Butiding ventilation exhaust plenum.
Each trip system (division) consists of two r channels with a 1 out of 2 logic for upscale trips, and a 2 out of 2 logic for ; I downscale trips.- This trip function is provided to litit the release of radioactivity resulting from a refueling (fuel handling) accident, j Tiip sottings of (100 mr/hr for the rnonitors in the ventilation exhaust ducts- are i
-based upon initiating normal ventilation isolation and standby gas treatment system i operation so that none of the activity rolcased during the refueling accident 1 caves
) the Reactor Building via the normal ventilation path but rather all the activity is ,
} processed by the standby gas treatment system, i
- 3. Liquid Radwaste Discharge Isolation
-The liquid radwaste monitor assures that all liquid discharged to the discharge canal i i
does not e:.cced the limits of Specification 3.21.B. Upon ensing a high discharge ! level, an isolation .41gnal le generated which closes the adwaste discharge valve. 4 The set point is adjustable to comper. sate for variable isotopic discharges and :
+
dilution flow-rates.
- 4. Main Control Room Ventilation The main control room ventilation isolation is provided by a detector. monitoring the intake of the control room ventilation system. Automatic isolation of the normal j supply and exhaust and the activation of the emergency filter system is provided by-the radiation detector trip function at the predetermined trip level.
! 5. = Mechanical Vacuum pump 3 The mechanical vacuum pump isolation prevents the exhausting of radioactive gas thru g- the.1 minute holdup line upon receipt of a main steam line high radiation signal.
1. l ,E._ Drywell Leak DeteltJED
! 1 l- l Flow transmitters are used to record the flow of liquid from the drywell sumps, An j
~
air sampling system is also provided to detect leakage insido the primary containment. I i
! -87n msm, L _ . . _ _ _ _ _ _ _ _ - _
EMfTINGCONDITIONSlhROpFRATION SURVE11,1ANCE REOUIREMENTS r
)3.7.C(cont'd.) 4.7.0 (cont'd.)
t I a. The reactor is suberitical and a. A preoperational secondary l Specification 3.3.A is m.t. containment capability test shall be i
! conducted after isolating the l b. The reactor water temperature is reactor building and placing either l below 212*F and the reactor coolant standby Saa treatment systein filter l systorm is vented, train in operation. Such tests l shall demonstrate the capability to
-c. No activity is being performed which maintain 1/4 inch of water vacuum :
! can reduce the shutdown margin below under calm wind (2<3 ( 5 rn p h ) ;
that specified in Specification conditions with a filter train flow
, 3.3.A. rate- of not more than 100% of building volume per day. (E- wind
- d. No irradiated fuel is being handlod speed) ;
in the secondary containment and no
- loads which could potentially damage b. Additional tests shall be performed irradiated fuel are being moved in during the first operating. cycle i the secondary contaitunent. under an adequate number of different environmental wind ,
- e. If secondary containment integrity conditions, to enable _ valid i cannot be innintained, restore extrapolation of the test results. :
! secondary _ containment integrity
{ within 4 hours or; c. Secondary containment capability to r j . rnaintain 1/4 inch of water vacuum
; a. Be . in at least llot Shutdown under calm wind (2<E ( 5 mph) i
_! within-the next 12 hours and conditio m with a filter train flow in cold shutdown within the rate of not more than 100% of following 24 hours, building volume per day, shall be demonstrated at each refueling i
; b. Suspend irradiated fuel outage prior to refueling, ,
handling operations in the secondary containment, d. After a secondary containment ; movemont of loads which could violation is determined, the standby ; potentially_ damage irradiated gas treatment system will be fuel in the secondary operated immediately after the 1 containment, and all core - affected zones are isolated from the i alterations which could remainder of the secondary !
! reduce the shutdown margin, containment to confirm its ability
! The provisions of to maintain the remainder of the '
Specificatica 1.0,J are not secondary containment at 1/4 inch of
-applicablo, water negative pressure under calin wind conditions,
- j. D. Primary Cont ainment i sola t iog Valves
!. 1. The primar/ containment isolation j -.D. Primary Containment Isolation Valves vrilves surveillance shall be I. _ _ _
performed as-follows:
; 1. During reactor power operating At least once- per operating cycle t' ! conditions, all isolation valves the operable isolation valves that listed in Table 3.7.1 and all P"#"'*d ""d ""'**"#I""III instrument line flow check valves "#* P***#
initiated shall- be tested for shall be- operable except as I simulated automatic initiation and specified in 3.7.D.2. closure times. i-i i ['+ 4 g 7 J
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3,7.A & 4.7,A EJJi(cont' d) The primary containment is normally slightly pressurized during periods of reacter operation. Hitrogen used for inerting could leak out of the containroent but air i could not leak in to increase oxygen concentration. Once the containment is filled 4 with nitrogen to the required concentration, no monitoring of oxygen concentration is necessary. However, at least twice a week the oxygen concentration will be determinvd as added assurance. The 500 gallon conservative limit on the nitrogen storage tank assures that adequate - time is cvailable to get the tank refilled assu.ning normal plant operation. The estimated maximurn makeup rate is 1500 ScrD which would require about 160 gallons for
, a 10 day makeup requirement. The normal leak rate should be about 200 SCFD.
3,7 A.6 6 4.7.A.6 LOW LOW SET RELIEF PUNCTIOJ ; The low. low set relief logic is an automatic safety relief valvo (SRV) control system designed to mitigate the postulated thrust load concern of subsequent actuations of SRV's durint certain transients (such as inadvertant MSIV closure) and small and intermediate breah '.oss of coolant accident (LOCA) ovents. The setpoints used in Section 3.7.A.u.b are based upon a rninimum blowdown range to provide adequate time between valve actuations to allow the SRV discharge line high water leg to clear, coupled with consideration of instrument inaccuracy and the main steam isolation valve isolation setpoint. The as found setpoint for NBI PS 51A, the pressure switch controlling the opening of . RV 71D, must be $ 1040 psig. The as found closing setpoint for NB1 PS 51B ;nust be at least 90 psig less than 51A, and must be 2 850 psig. The as found setpoint for NB1 PS 51C, pressure switch controlling the opening of RV 71F must be $; 1050 psig. The as found closing setpoint for NBI-PS 51D must be at 1 cast 90 psig below 51C, and must be 2 850 psig. This ensures that the analytical upper limit for the opening setpoint (1050 psig), the analytical _ lower limit on the closing setroint f850 psig) and the analytical limit on the blowdown range (2 90 psig) for the inw Low 5et Relief Function are not exceeded. Although the specified instrument setpoint tolerance is i 20 psig, an instrument drift of 1 25 psig was used in the aralysis to ensure adequate margin in determining the valve opening and closing setpoints. The opening setpoint is set such that, if both the lowest set non LLS S/RV and thn highest set r of the two LLS S/RVs drif t 25 psig in the worst caso directions, the Lt.S S/RVs will still control. subsequent S/RV actuations. Likewise.-the closing setpoltt is set to ensure the LLS S/RV closing cetpoint remains above the MSIV low pressure trip. The 90 psig blowdown provides adequate energy release from the vessel to ensure timo for the water Icg to clear between subsequent S/RV actuations.
'.7.B & 3.7.C STANDBY CAS TREATMENT SYSTEM AND SECONDARY CONTAINMENT The secondary containrmt is designed to minimize any ground level release of radioactive materials which might result f rom a serious accident. The reactor building provides secondary containment during reactor operation when the drywell is [
sealed and in service. The reactor building providos primary containmen. when the reactor is shut down and trm drywell is open, as during refueling. Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required as well as during refueling, and during movement of loads which could potentially damage irradiated fuel in the secondary containment. Secondary containment may be
; broken for short periods of. time ~to allow . access to the renetor building roof-to perform necessary inspections and maintenance.
The standby gas treatment system is designed to filter and exhaust the reactor building atmosphere to the stack during secondary containment isolation condit tons,
- i. Both standby gas treatment system fans are designed to automatically start upon i
containment isolation and to maintain the reactor building pressure to the design l negative pressure so that all leakage shov1d be in-leakage. Should one system fail to start, the redundant system is designed to start automatically. Each of the two fans has 100 percent capacity. 180-
.. _ __ _ _ _ __ .~ _ .__ _._ _. . _ , _ _ . _ _ _ - _._.
C1 e
' LIMITING CONDITIONS l'OR OPfRATION SURVf1LINICE RFOUIPrMFNTS
. 3 . 1 0 . 11 (Cort'd) 4.10 (Cont'd) '4. During spiral reload, SRM operability will be verified by using a portable external source every 12 hours until the required amount of fuel is loaded to inaintain 3 cps. As an alternativo to the above, two fuel assemblies will be loaded in dif ferent cells containing control bladas around each SRM to obtain the required 3 cps. Until these two assemblics have been loaded, the 3 cpr requirement is not necessary. C. Ep.tnL_lltel pool Wat er Leyt1
- c. Epntt_11ttLhnl_Writr_Lettl Whenever irradiated fuel is s.t ore d When irradiated fuel is stored in in the spent fuel pool, the pool the spent f uel pool, the wat er level water level shnll be maintained at shall be recorded daily, or above BLi ' above the top of the fuel.
D. limelimliation Irradiated f uel shall not be handled in or above th3 reactor prior to 24 hours after reactor shutdown. E. ELtuny_Sar. Trenu!rttt system E. Ston@x_GltE_Irrnethtji3 Rut from and after the date that one standby gas trentitient system is made When one standby gar t rent ment or found to be inoperable for any system becomes inoperable, the other reason, handling of irra3tated f uel, standby gas treatment system shall and movement of loads which could be demonstrated to be operabic potentially damage irradiated fuel immediately and daily thereafter, in the secondary containment is A demot.stration of diesel generator permicsibic only during the operability is not. required by this succeeding seven days unless such specification, system is sooner made operable, provided that during such seven days all activo components of the other standby gas treatment system, and i its associated diesel generator, j shall be operable. At least one diesel generator shall i be operable during iuel handling
! operations. This one diesel shall be capabic of supplying power to an operable Standby Gas Troatment System.
F. OnEt_Slondby GnnJ111C_SJfilt!Ui During a retueling outage, refueling
; operation may continue with one core spray system or the LPC1 mode of Rilk inoperable for a period of 30 days. Refueling is permitted with the supprension chan.ber drained provided an operable core spray system or subsystem of the LPCI mode of R11R is aligned to take a suction on the condensate storage tank containing at least 150.000 gallons
('t14 ft. Indicated level). l
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- During releases via this pathway.
! ** During augmented offgas treatment syt, tem operat. ion.
l *** During operation of the Steam Jet Air Ejector. Elevated itelease Point (EltP) Monitoring System, Itadwaste Ventilat ion Monitoring System, and Turbine building Ventilation Monitoring System i j(1) The CllANNEL ITNCTIONAL TEST shall also dernonstrate that automatic isolation of this l patnway and control room alarm annunciation occurs if any of the following conditions i exists: l 1. Instrument indicato, measured levels above the alarm / trip setpoint. l
- 2. Circuit failure.
i l 3. Instrument indienten a downr,cale failure.
- 4. Instrument controls not det in operate mode.
^(2) The CllANNEL l'UNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
f 1. lustrument indicaten measured 1cvols above the alarm / trip setpoint.
- 2. Circuit failure.
3, Instrument indicates a downscale failure. l I 4. Instrument controls not set in operate mode. i, (3) The CllANNEL CAL 1BilATION shall be est ablished in accordance with established stat ion
! calibration procedures. ;
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i j(4) The CilANNEL CAtlllitATION shall include tho use of a standard gas sample containing a i percentage of hydrogen to verif y accuracy of the monitoring channel in its operating range. q j(5) Sarno as (2) except Parts 3 and 4 are deleted.
!(6) Itefer to Section 3.2.D.2 for the limit.ing conditions for operation.
i
}Fl!EQUENCYNOTATION:
i ! j S - At least once per 12 hours. D - At least once per 24 hourc. 4 W - At loant ci a per 7 days. M - At least. once per 31 days. Q - At.least once per 92 days. SA - At least once mer 184 days
;l A - At least once per year.
l- ,_ lt - At least once per 18 months. ; l S/U - Prior to each reactor start up. P - Complet(d prior to each release. { NA - Not applicable ! ! -216w- .a, ,,,' i j
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