ML20116N429

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Proposed TS 3.3.3, ECCS Actuation Instrumentation
ML20116N429
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/16/1992
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20116N427 List:
References
NUDOCS 9211240010
Download: ML20116N429 (9)
v • d • e


Text

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l' ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REQUEST FOR UCENSE AMENDMENT ECCS ACTUATION INSTRUMEN TATION OPERABILITY PAGE CHANGE INSTRUCTIONS UNIT 1 Removed pace Inserted Pace 3/4334 3/4334 3/4338 3/4338 l

UNIT 2 Removed Pace Inserted Paae i 3/4334 3/4 3-34 3/4338 3/4338 l

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E41 9211240010 DR 921116 l p ADocx 05000324  !

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} ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 i NRC DOCKET NOS. 50 325 & 50-324

OPERATING LICENSE NOS. DPR 71 & DPR 62

{ REQUEST FOR LICENSE AMENDMENT j ECCS ACTUATION INSTRUMENTATION OPERABILITY 5

i TECHNICAL SPECIFICATION PAGES UNIT 1 (MARKUPS) a 1

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TABLE 3.3.3-1 .

Si EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION l IO c"s APPLI CABLE

  • MINIMUM NUMBER

' OPERATIONAL OPERABLE PER TRIP SYSTEM CHANNE{S} CONDITIONS ACTION ,

TRIP FUdCTION E!.

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1. COIE SPRAY SYSTEM Reactor Vessel Water Level - Low, Level 3 2 1, 2, 3, 4, 5 30 a.
b. Reactor Steam Dome Pressure - Low (In' - tion Permissive) 2 (b) 1,2,3,4,5 31 2 1, 2, 3 30 4 c. Drywell Pressure - liigh 1 1, 2, 35 4, 5 31
d. Time Delay Relay Bus Power Monitor (d) 1/ bus 1,2,3,4,5 32 e.

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y 2. LOW PRESSURE COOLANT INJECTION MODE OF R!il SYSTEM

.4 2 1, 2, 3 30

a. Drywell Pressure - liigh
b. Reactor Vessel Water Level - Low, Level 3 2 1, 2, 3, 4(b) , $(b) 39
c. Reacter Vessel Shroud Level (Drywell Spray Permissive) -1 1, 2, 3, 4(b) $(b) 3g

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d. Reactor Steam Dome Pressura - Low (Injection Permissive) ()

RilR Pump Start and LPCI Ir.jection Valve Actuation 2 1, 2, 3, 4(b)tb), $(bb) 31 1.

2. Recirculation Loop Pump Di.:harge Valve Actuation 2(f) 1, 2, 3, 4 $ 3g
e. RilR P..mp Start - Time Delay Relay 1 1, 2, 3, 4(b) $(b) , 3g

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f. Bus Power Monitor (d) 1/ bus 1, 2, 3, 4(b) $(b) , 12

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h TABLE 3.3.3-1 (Continued)

EMERCENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION NOTy c

(a; A channel may be placed in an inoperabic status for up to two hours for i required surveillance without placing the trip system in the tripped condition, provided at least one OPERABLE channel in the same trip system is monitoring the affected parameter.

(b) Not applicable when two core spray system subsystems are OPE 3ABLE per i 4.

Specification 3.5.3.1.

(c) Provides signal to HPCI pump suction valves only.

(d) Alarm only.  ;

(e) Required when ESF equipment is required to be OPERABLE.

PAGE

(f) _ c3E E A~rTACHED 3

BRUNSWICK - UNIT 1 * * *3/4 3-38 Amendment No.130

Proposed Note to Table 3.3.31: s (f) On a one t ne basis, prior to start up from tr.e outage that began on April 21,1992, the Minira Jm Number OPERABLE Channels per Tnp System for one reactor steam dome pressure -

low fnjection permissive) trip function may be reduced, for no longer than 7 days, from two (2) chanaets to one (1) channel without declaring t'- ssociated ECCS inoperable in accordance with ACTION 31. This will be done on one occasion for Unit 1 and two occcsions for Unit 2.

During these periods, the fol'owing actions shall be implemented:

(1) The inoperable channel shall be placed in the condition that will satisfy the logic for allov ing in!ection by the associated ECCS with the reactor steam dome pressure helnw 410 psig 15 psig.

(2) Botn channels in the other trip system shall be mainta!ned OPERABLE.

(3) The reactor vessel head vent shall be maintained in the open position.

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. OPR 71 & DPR 62 REOUEST FOR LICENSE AMENDMENT 4

ECCS ACTUATION INSTRUMENTATION OPERABILITY TECHNICAL SPECIFICATION PAGES UNIT 2 (MARK 1]fS1 i

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pAILE 3.3.3-1 E EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION j y i E MINIMUM NUMBER APPLICABLE M

OPERABLE CHANNE OPERATIONAL 8 I CONDITIONS ACTION l TRIP FUNCTION PER TRIP SYSTQ

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a. Reactor Vessel Water Level - Low, Level 3 2 1,2,3,4,5 31
b. Reactor Steam Dome Pressure - Low (Injection Permissive) 2 1,2,3 30
c. Drywell Pressure - High 1 1, 2, 3, 4, 5 31
d. Time Delay Relay 1/ bus 1,2,3,4,5 32
e. Bus Power Monitor (d) 1 y 2. LOW PRESSURE COO 1 ANT INJECTION MODE OF RHR SYSTEM 2 1,2,3 30
a. Drywell Pressure - High 2 1, 2, 3, 4(b) , 3(b) 30
b. Reactor Vessel Water Level - Low, Level 3 Reactor Vessel Shroud Level (Drywell Spray Permissive) 1 1, 2, 3, 4(b), 3(b) 3g c.

Reactor Steam Dome Pressure - Low (Injection Permissive)

d. 2 W) 1, 2, 3, 3, 4.b),

4((b)3(b) 3(b) 3;

1. RHR Pump Start and LPCI Injection Valve Actuation 26) 1, 2, , 33
2. Recirculation Loop Pump Discharge Valve Actuation 1 1, 2, 3, 4(b) $(b) 33
e. RHR bap Start - Time Delay Relay 1/ bus 1, 2, 3, 4(b), 3(b) 32
f. Bus Power Monitor (d)

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TABLE 3.3.3-1 (Continued) i EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION NOTES (a) A channel may be placed in an inoperable status for up to two hours for I required surveillance without placing the trip system in the tripped condition, provided at least one OPERABLE channel in the same trip system is monitoring the affected parameter.

(b) Not applicable when two core spray system subsystems are OPERABLE per [

Specification 3.5.3.1.

! (c) Provices signal to HPCI pump suction valves only. l (d) Alarm only. l (e) Required when ESF equipment is required to be OPERABLE. l (f) -- GEE AT 'i'A C H E D PAGC -

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BAUNSWICK - UNIT 2 3/4 3-28 Amendment No. 160

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Proposed Note to Table 3.3.31:

(f) On a one time basis, prior to start-up from the outage that began on April 21,1992, the Minimum Number OPERABLE Channels per Trip System for one reactor steam dome pressure -

low (injection permissive) trip function may be reduced, for no longer than 7 days, from two (2) chantsels to one (1) channel without declaring the associated ECCS inoperable in accordance with ACTION 31. This will be done on one occasion for Unit 1 and two occasions for Unit 2.

During these periods, the following actions shall be implemented:

(1) The inoperable channel shall be placed in the condition that will Jatisfy the logic for allowing injection by the associated ECCS with the reactor steam dome pressure below 410 psig i 15 psig.

(2) Both channels in the other trip system shall be maintained OPERABLE.

(3) The reactor vessel head vent shall be maintained in the open position.

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