ML17286A613
| ML17286A613 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/21/1991 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17286A612 | List: |
| References | |
| NUDOCS 9103050334 | |
| Download: ML17286A613 (9) | |
Text
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I rHSTRUMEHTATION I
. 3/4.3.3 'MERGENCY CORE COOLING SYSTBl ACTUATIOH IHSTRUMEHTATIOH LIMrTIHG CONOITIOH FOR OPERATION
- 3. 3. 3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set cansistent with the values sho~n in the Trip Setpoint column of Table 3.3.3-2 and with EMERG"HCY CORE COOLING SYST""I RESPOHSE TIME as shown in 7able 3.3.3 3.
APPLrCABILITY:
As shcwn in Table 3.3.3-1.
ACTION:
a.
C.
Mith an ECCS ac uation instrumen ation channel trip setpoint less canserva ive than the value shown in the Allowable 'lalues column of Table 3.3.3"2, declare the channel incperable until the channel is restored to OPERABLE status with its trip setpaint ad'usted cansis ent'i h the Trip Setpoint value.
lith one or more ECCS actuaticn instrumentation channels inoperable, ~i"4 take the ACTIOH required by Table 3.3.3-1.
Mi h either AOS trip system "A" or "8" inoperable, restcre the incperable trip system to OPERABLE status:
Mithin 7 days, provided hat the HPCS and RCIC sys ems are OPERABLE; otherwise, 2.
Mithin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Other~ise, be in at least HOT SHUTOOMH ~ithin the next 12 hcurs and reduce reac:ar s
earn dome pressure ta less than or eaual to 128 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SUR'IEILLANCE REOUIREMEHTS
-'..3.3.
'Each ECCS ac uation instrumentation charnel shall be demonstrated OPERABLE by the performance of the CHANHEL CH="K, CHAHHEL FUHCTIOHAL TEST, and CHAHHEL CALrBRATIOH cperatians for the OPERATIONAL COHOETIOHS ard a
the
=",eouencies shown in Table 4.3. 3. 1-1.
- 4. 3. 3. 2 L GIC SYSTEM FUHCTIOHAL 7ESTS and simulated automatic cperaticn cf all channels snail "e perfcrmed at lees once per 18 months.
a.3.3.3 The ECCS RE PGHSE TIME or each ECCS shall be demonstrated ta "e within the limit Each test shall include a-lees cne channel all channels are tested at least ance every H
ta al numcer of reduncant cnannels in a spec; trip func-ion shown in Tab>e 3.3.3-3 at least ance per '8 months.
per rip svstem such that
.ines 13 months where.H is the
'iA H HGTOH 'IUC'AR -
UH 7 2
~
I L
9i03050334 9i0221 PDR ADOCK 05000397 P
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2 C)
C.
n Irn C:
I FUNCTION DIVISION 3 TRIP SYSTEH l.
IIPCS SYSICH HIHIHUH OPERABLE CIIANHELS PER TRIP SYSTEM(ag APPLICABLE OPERAIIONAL COHOITIOHS ACTION a.
b.
C.
d.
e.
f.
g.
2(b) 2(b) 2(c) 2(d) 2(d) 1 1/division MINIHUH TOTAL HO.
CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE Reactor Vessel Mater Level - Low, Low, Level 2
Orywell Pressure
- High Reactor Vessel Mater Level-High, Level 0
Condensate Storage Tanks Level-Low Suppression Pool Mater Level-Iligh flPCS System Flow Rate-Low (Hinimum Flow) manual Initiation 1, 2, 3, 1
2 3
1, 2, 3, 1, 2, 3, 1
2 3
1,2,3, 1
2 3
APPLICABLE OPERATIONAL COHOITIOHS 4
Jc c)*
30 30 4*
5*
4*
5*
36 4)k 5'k 36 4*, 5*
3l 4*
5*
34 ACTION TABLE 3.3 Continued)
EHERGEHCY CORE COOI.IHG SYS ti ACTUATIOH IHSTRUHEHTATIOH LOSS OF POWER 0.
IM CO 2/bus I
3/bus 2/bus 1, 2, 3, 4*", 5**
30 l.
- 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage) 1/bus 2.
- 4. 16 kV Emergency Bus Under-voltage (Oegraded Voltage 2/bus Bivision 1 and 2) 3.
- 4. 16 kV Emergency Bus Undervoltage (Oegraded Voltage Division 3) 2/bus 2/bus 2/bus 1, 2, 3, 4**, 5"*.
38
, TABLE HOTATIOHS (a)
A channel may be placed in an inoperable status for up to~hours during periods of required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
'(b)
Also activates the associated division diesel generator.
(c)
Provides signal to close HPCS pump discharge valve only on 2-out-of-2 logic.
(d)
Provides signal to IIPCS pump suction valves only.
When the system is 'required to be OPERABLE per Specification 3.5.2 or 3.5.3.
Required when ESF equipment is required to be OPERABLE.
Hot required to he OPERABLE when reactor steam dome pressure is less than or equal to 120 psig.
Gl CR TRIP FUtlCTIotl TADLE 4. 3. 3. l-l EHERGEHCY COAE COOLING SYSTEH ACTU IHSTIIUHEHI'ATIOH SUAVEILLAHCE ~AE UIAEHEHTS CIIAIIHEL opEAATIotlnL CIIANHEL FUHCTIotlhL cllnHtIEL COHDITIoHS Fon WIIICII CtlECK TEST CALIBRATIOH SURVEILLANCE ABRUIREO n
Tn O
n.
DIVISION I TRIP SYSTEM 11IHR-TOCTTI01l AHO LPCS SYSTEH a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Drywell Pressure
- lligh c.
LPCS Pump Discharge Flow-Low (Hinimum Flow) d.
Aeactor Vessel Pressure-Low (LPCS Permissive) e.
Aeactor Vessel Pressure-Low (LPCI Permissive) f.
LPCI Pump h Start Time Delay Relay g.
LPCI Pump h Flow-Low (Hinimum Flow) h.
Hanual Initiation 2.
AUTOHATIC DEPAESSUAIlhTIOH SYSTEH TRIP SYSTEH "A"8 a.
Reactor Vessel Mater Level-Low Low Low, Level 1
b.
ADS Timer c.
Aeactor Vessel Water Level-Low, Level 3 (Permissive) il.
LPCS Pump Discharge Pressure-lllgh (Pump Running) e.
LPCI Pump h Discharge Pressure-lligh (Pump Aunning) f.
Hanual Initiation g.
Inhibit Switch S
H.n.
tl.h.
tl.A.
H.A.
N.A.
H.A.
N.A.
S H. A.
tt.h.
H.n.
N. A.
H.h.
,tI A
R H
A H.A.
A H. h.
H.n.
1, 2, 3, 4*, 5" 1
2 3
1, 2, 3, YI*, 5*
1, 2, 3, I", 5" 1, 2, 3, 4"', 5" 1, 2, 3, 4*, 5" II*
5YE 1, 2, 3
1, 2, 3
1, 2,.3 1, 2, 3
1,2)3 1, 2, 3
TABLE 4.3.3. 1-1 (Continued)
EMERGEHCY CORE COOLING SYSTEM ACTUATIOH IHSTRUMEHTATION SURVEILLANCE REqffIREHEHTS TRIP FUNCTIOH B.
DIVISION 2 TRIP SYSTEM 1.
RilR 8 AHD C LPCI MODE CffhHNEL OfECK ClfhHNEL OPERATIONAL FUHCTIONAf.
CHANHEL CONDITIOHS fOR MffJCff TEST CALIOftATION SURVEILLANCE AEqffiP;0 a.
b.
C.
d.
e.
Reactor Vessel Mater Level-Low Low Low, Level 1
Drywell Pressure
- High Reactor Vessel Ptessure-Low (LPCI Permissive)
LPCI Pump B Stat't Time Delay Relay LPCI Pump Discharge Flow-Low (Minimum Flow)
Manual Initiation S
H.A.
H.A.
H.A.
N.A.
H.A.
pr Q pt cp P0 R
R H.A.
- 1) 2) 3 4*
5
]
2 3
4* 5*,
- 1) 2) 3 4*
5"
.1,2,3,4*,5*
O 2.
AUTOMATIC DEPRESSURIZATIOH SYSTEM TRIP SYSTEM "O'9
- a. 'eactor Vessel Mater Level.-
Low Low Low, Level 1
b.
AOS Timer c.
Reactor Vessel Mater Level-Low, Level 3 (Permissive) d.
LPCI Pump B and C Discharge Pressure-ifigh (Pump Running) e.
Manual Initiation f.
Inhibit Switch S
N.A.
H.A.
H.A.
H.A.
MR M Q M'P Rprp R
H.h.
H.A.
1, 2, 3
1, 2, 3
1, 2, 3
1 ~ 2) 3
TABLE 4.3.3. -I (Continued)
EIIEBGEHCY COBE COOLING SYSTEII ACTUATIOH IHSTBIIIIEHTATIOH SIIBI/EILLABCE BEqUIIIEHI:HTS TRIP FUNCTION C.
DIVISION 3 TRIP SYSTEH l.
IIPCS SYSTEH a.
Reactor Vessel Water Level-Low Low, Level 2
b.
Drywell Pressure-High c.
Reactor Vessel Mater Level-High, Level 8 d.
Condensate Storage Tank Level-Low e.
Suppression Pool Mater Level - High f.
HPCS System Flow Rate-Low (Hinimum Flow) g.
Hanual Initiation D.
LOSS OF POWER 1.
- 4. 16 kV Emergency Bus Undervoltage (Loss of Voltage) 2.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage Division 1 and 2) 3.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage Division 3)
CIIANHEL CIIECK CHANHEL FUHCTIONAI TEST S
N.A.
H.A.
N.A.
H.A.
H.A.
.H @
R H.A.
H.A.
H.A H.A.
H.A.
TABLE HOTATIOHS CHANNEL CALIDRRTIOH R
H.A.
OPERATIOHAL CONDITIONS FOR WHICH SURVEILLANCE RFlFIJ I RF0 1, 2) 3, 4", 5*
1, 2, 3, 4", 5*
3 4*
1, 2, 3, 4*, 5" 1, 2, 3, 4*, 5" 3
48*
5IITA 3
4AA 5**
3 4 III*
5*%
A0Z ZJ0 mU A
O "U
NHot required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.
When the system is required to be OPERABLE per Specification 3.5.2.
"""The secondary time delay 3 second relays are exempt from this monthly testing.
The secondary time delay relays associated with this logic will be functionally tested as part of the Logic System Functional Testing (Surveillance Requirement 4.3.3.2)
5 Vl
-I C) n Im A7 FUNCTIONAL UNITS
- a. 'eactor Vessel Mater Level "
(Low Low, Level 2) b.
Reactor Vessel Mater Level - Iligh, Level (8) c.
Condensate Storage Tank Level - Low CHANNEL CtlECK CIIAHHEL FUNCTIONAL TEST C)IANHEL CALIBRATION TABLE 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION IHSTRUHENTATION SURVEILLANCE RE UIREHENTS
'L Hanual Initiation N.A.
~
)
~'
0
E 3.3.5-1 FUHCTIOHAL UHITS REACTOR CORE ISOLATIOH COOLIHA SYSTFH ACTUATIOH IHSTRVHEHTATIOII HiHIIIVII OPEIIMLE CIIIIWIIELj PER TRIP SYSTEI4 ACTIOH a.
Reactor Vessel
'Water Level - Low Low, Level 2
b.
Reactor Vesse'I Mater Level - lligh, l.evel 0
c.
Condensate Storage Tank Mater Level Low Low d.
Iianual Init.iation 2
2(h) 2(c) 1(d) 50 51 52 53 co placinil the trip system in the tripped condition provi O'least one other OPERABLF. channel in the same trip system is monitoring that parameter.
(h)
One trip system wiLh two-out-of-two logic.
(c)
One trip system with one-ont-of-two logic.
Q'si)
One Lrip system with one channel.
ACTION 50-TABLE 3.3.5-1 (Continued)
REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:
a.
b.
For one trip system, place the inoperable channel(s) and/or that trip system in the tripped condition within 4-hour or declare the RCIC system inoperable.
8 f hossrf'S For both trip systems, declare the RCIC system inoperable~
ACTION 51-ACTION 52-ACTION 53-With the number of OPERABLE channels less than required by the minimum 0 BLE channels per Trip System requirement, declare the RCIC em inoperable. w.at'-~
~+ 4~is
~
With the nualfd of OPERABLE channels lass than required by the Minimum OPE hannels per Trip System requirement, place at least one i o rable channel in the tripped condition within~our or lare the RCIC system inoperable.
4~~ft; With the. number of 5 BLE channels one less than required by the Minimum OPERABLE nels per Trip System requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the RCI ystem inoperable.
WASHINGTON NUCLEAR " UNIT 2 3/4 3-49