ML17286A613

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Proposed Tech Specs,Deleting Requirements to Incorporate ECCS & RCIC Surveillance Frequencies & Outage Times & Optimize Surveillance Test Intervals for Improved ECCS & RCIC Reliability & Increased Allowable Outage Time
ML17286A613
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 02/21/1991
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17286A612 List:
References
NUDOCS 9103050334
Download: ML17286A613 (9)
v • d • e


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. 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.

C. 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 trip func-ion shown'8 in Tab>e 3.3.3-3 shall be demonstrated ta "e within the limit at least ance per months.

Each test shall include a- lees cne channel per rip svstem such that all channels are tested at least ance every H .ines 13 months where.H is the ta al numcer of reduncant cnannels in a spec;

'iA

~

I H HGTOH 'IUC'AR L - UH 7 2 9i03050334 9i0221 PDR ADOCK 05000397 P PDR I

TABLE 3.3 Continued)

EHERGEHCY CORE COOI.IHG SYS ti ACTUATIOH IHSTRUHEHTATIOH 2

HIH IHUH OPERABLE APPLICABLE CIIANHELS PER OPERAIIONAL FUNCTION TRIP SYSTEM(ag COHOITIOHS ACTION C)

C. DIVISION 3 TRIP SYSTEH n l. IIPCS SYSICH I

rn

a. Reactor Vessel Mater Level - Low, Low, Level 2 2(b) 1, 2, 3, 4 Jc c)* 30
b. Orywell Pressure - High 2(b) 1 2 3 30 C: C. Reactor Vessel Mater Level-High, Level 0 2(c) 1, 2, 3, 4* 5*

I d. Condensate Storage Tanks Level-Low 2(d) 1, 2, 3, 4* 5* 36 4)k 5'k

e. Suppression Pool Mater Level-Iligh 2(d) 1 2 3 36
f. flPCS System Flow Rate-Low (Hinimum Flow) 1 1,2,3, 4*, 5*

4* 5*

3l

g. manual Initiation 1/division 1 2 3 34 MINIHUH APPLICABLE TOTAL HO. - CHANNELS CHANNELS OPERATIONAL OF CHANNELS TO TRIP OPERABLE COHOITIOHS ACTION
0. LOSS OF POWER I

M CO l. 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage) 2/bus 1/bus

2. 4. 16 kV Emergency Bus Under- I voltage (Oegraded Voltage 3/bus 2/bus 2/bus 1, 2, 3, 4*", 5** 30 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.

TADLE 4. 3. 3. l-l EHERGEHCY COAE COOLING SYSTEH ACTU IHSTIIUHEHI'ATIOH SUAVEILLAHCE ~AE UIAEHEHTS Gl CIIAIIHEL opEAATIotlnL CR CIIANHEL FUHCTIotlhL cllnHtIEL COHDITIoHS Fon WIIICII TRIP FUtlCTIotl CtlECK TEST CALIBRATIOH SURVEILLANCE ABRUIREO n n. DIVISION I TRIP SYSTEM Tn 11IHR- TOCTTI01l AHO LPCS SYSTEH

a. Reactor Vessel Water Level-Low Low Low, Level 1 S 1, 2, 3, 4*, 5"
b. Drywell Pressure - lligh H.n. 1 2 3
c. LPCS Pump Discharge Flow-Low (Hinimum Flow) tl.h. 1, 2, 3, YI*, 5*
d. Aeactor Vessel Pressure-Low (LPCS Permissive) tl.A. 1, 2, 3, I", 5"
e. Aeactor Vessel Pressure-Low (LPCI Permissive) H.A. 1, 2, 3, 4"', 5"
f. LPCI Pump h Start Time Delay Relay N.A. 1, 2, 3, 4*, 5"
g. LPCI Pump h Flow-Low (Hinimum Flow) H.A. ,tI A II* 5YE
h. Hanual Initiation N.A. A H.A.
2. AUTOHATIC DEPAESSUAIlhTIOH SYSTEH TRIP SYSTEH "A"8
a. Reactor Vessel Mater Level-Low Low Low, Level 1 S 1, 2, 3
b. ADS Timer H. A. 1, 2, 3
c. Aeactor Vessel Water Level-Low, Level 3 (Permissive) 1, 2,.3 il. LPCS Pump Discharge Pressure-lllgh (Pump Running) tt.h. 1, 2, 3
e. LPCI Pump h Discharge Pressure-lligh (Pump Aunning) H.n. A 1,2)3 O
f. Hanual Initiation N. A. R H. h.
g. Inhibit Switch H.h. H H.n. 1, 2, 3

TABLE 4.3.3. 1-1 (Continued)

EMERGEHCY CORE COOLING SYSTEM ACTUATIOH IHSTRUMEHTATION SURVEILLANCE REqffIREHEHTS ClfhHNEL OPERATIONAL CffhHNEL FUHCTIONAf. CHANHEL CONDITIOHS fOR MffJCff TRIP FUNCTIOH OfECK TEST CALIOftATION SURVEILLANCE AEqffiP;0 B. DIVISION 2 TRIP SYSTEM

1. RilR 8 AHD C LPCI MODE
a. Reactor Vessel Mater Level-Low Low Low, Level 1 S pr Q 1) 2) 3 4* 5
b. Drywell Pressure - High H.A. pt cp C. Reactor Vessel Ptessure-Low (LPCI Permissive) H.A. ] 2 3 4* 5*,
d. LPCI Pump B Stat't Time Delay Relay H.A. 1) 2) 3 4* 5"
e. LPCI Pump Discharge Flow-Low (Minimum Flow)

Manual Initiation N.A. P0 R .1,2,3,4*,5*

H.A. R H.A.

2. AUTOMATIC DEPRESSURIZATIOH SYSTEM TRIP SYSTEM "O'9
a. 'eactor Vessel Mater Level.-

Low Low Low, Level 1 S MR 1, 2, 3

b. AOS Timer N.A. M Q
c. Reactor Vessel Mater Level-Low, Level 3 (Permissive) 1, 2, 3
d. LPCI Pump B and C Discharge Pressure-ifigh (Pump Running) H.A. M'P R 1, 2, 3
e. Manual Initiation H.A. R H.h.
f. Inhibit Switch H.A. prp H.A. 1~ 2) 3 O

TABLE 4.3.3. -I (Continued)

EIIEBGEHCY COBE COOLING SYSTEII ACTUATIOH IHSTBIIIIEHTATIOH SIIBI/EILLABCE BEqUIIIEHI:HTS CHANHEL OPERATIOHAL CIIANHEL FUHCT IONAI CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CIIECK TEST CAL IDRRTIOH SURVEILLANCE RFlFIJ I RF0 C. DIVISION 3 TRIP SYSTEH

l. IIPCS SYSTEH
a. Reactor Vessel Water Level-Low Low, Level 2 S 1, 2) 3, 4", 5*
b. Drywell Pressure-High N.A.
c. Reactor Vessel Mater Level-High, A Level 8 1, 2, 3, 4", 5* 0
d. Condensate Storage Tank Level-Low H.A. 3 4*

Z

e. Suppression Pool Mater ZJ Level - High 1, 2, 3, 4*, 5"
f. HPCS System Flow Rate-Low N.A.

0 (Hinimum Flow) H.A. .H @ R 1, 2, 3, 4*, 5"

g. Hanual Initiation H.A. R H.A.

m D. LOSS OF POWER U

1. 4. 16 kV Emergency Bus Undervoltage (Loss of Voltage) 48* 5IITA A

H.A. H.A. 3 O

"U

2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage Division 1 and 2) H.A 3 4AA 5**
3. 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage Division 3) H.A. H.A. 3 4 III* 5*%

TABLE HOTATIOHS 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.

  • "Required when ESF equipment is required to be OPERABLE.

"""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)

TABLE 4.3.5.1-1 5

Vl REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION IHSTRUHENTATION SURVEILLANCE RE UIREHENTS CIIAHHEL

-I C) CHANNEL FUNCTIONAL C)IANHEL FUNCTIONAL UNITS CtlECK TEST CALIBRATION n

'L I a. 'eactor Vessel Mater Level "

m A7 (Low Low, Level 2)

b. Reactor Vessel Mater Level - Iligh, Level (8)
c. Condensate Storage Tank Level - Low Hanual Initiation N.A.

~ '

~ )

0

E 3.3.5-1 REACTOR CORE ISOLATIOH COOLIHA SYSTFH ACTUATIOH IHSTRVHEHTATIOII Hi HI IIVII OPEIIMLE CIIIIWIIELj FUHCTIOHAL UHITS PER TRIP SYSTEI4 ACTIOH

a. Reactor Vessel 'Water Level - Low Low, Level 2 2 50
b. Reactor Vesse'I Mater Level - lligh, l.evel 0 2(h) 51
c. Storage Tank Mater Level Low Low Condensate 2(c) 52
d. Iianual Init.iation 1(d) 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.

TABLE 3.3.5-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 50- With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. 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
b. For both trip systems, declare the RCIC system inoperable~

ACTION 51- 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 ~

ACTION 52- 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 4~~ft; or lare the RCIC system inoperable.

ACTION 53- 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

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