ML20205P563

Proposed Tech Specs Deleting 1,000 Psig Pressure Permissive from MSIV Closure Scram Trip Setting & Making Miscellaneous Editorial Corrections

ML20205P563
Person / Time
Site:	Cooper
Issue date:	11/01/1988
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20205P507	List: ML20205P563 NLS8800476, Application for Amend to License DPR-46,deleting 1,000 Psig Pressure Permissive from MSIV Closure Scram Trip Setting & Making Miscellaneous Editorial Corrections.Fee Paid
References
NUDOCS 8811080218
Download: ML20205P563 (5)

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SAFETY LIMITS

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LIMITING SATETY' SYSTEM SETTINGS s

2.1.A (Cont'd)-

3.

Turbt,ne Stop Valve Closure Scram Trip Setting 110 percent valve' closure when above 30% turbine first stage pressure.

4.

Turbine Control Va.'va Fast Closure Scram Trip Setting

.q Turbine control fluid pressure 11000 psi when above 30% turbine first stage pressure.

5.

Main Steam Line Isolation Valve closure Scram Trip Setting 110 percent valve closure in 3 out of 4 ma a steam lines, and the Reactor Mode Switch'in the "Run" position.

6.

Main Steam Line Isolation Valve Closure on Low Pressure 1825 psig when mode switch is in "Run".

Relationship of instrument water level indications to core and reactor vessel levels is illu-strated in Figure 2.1-1.

B.

Reactor Water Level Trip Settings Which Initiate Core Standby Cool-ing Systems (CSCS)

Reactor low-low water level ini-clation of CSCS systems setting shall be at or above -145.5 in.

indicated level.-

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COOPER NUCLEAR STATION ~

l TABLE 4.2.B (Page 1)

CORE SPRAY SYSTEM TEST & CALIBRATION FREQUENCIES

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Instrument.

Item Item I.D. No.

Functional Test Freq.

Calibration Freq.

Check Instrument 1.

Reactor Low Water Level NBI-LIS-72 A.B.C. & D Once/ Month (1)

Once/3 Months Once/ Day 2.

Reactor Low Pressure NBI-PS-52 A1,A2,C1, & C2 Once/ Month (1)

Once/3 Months None NBI-PIS-52, B & D 3.

Drywell High Pressure PC-PS-101, A.B.C. & D Once/ Month (1)

Once/3 Months None ;

4.

Core Spray Pump Disch, CS-PS-44, A & B Once/ Month (1)

Once/3 Months None-Press.

CS-PS-37, A & B Once/ Month (1)

Once/3 Months None:

5.

Core Spray Pump Time Delay CS-TDR - Kl6, A & B Once/ Month (1)

Once/Oper.

'None.

Cycle (4) 6.

Emergency Bus Low Volt Relay 27XI - IF & IC Once/Oper. Cycle N.A.

None 27X2 - IF & IC Once/Oper. Cycle N.A.

None 7.

Aux. Bus Low Voltage Relay 27X3 - IA & IB Once/Oper. Cycle N.A.

None 8.

Pump Disch. Line #.ow Press.

CM-PS-73, A & B Once/3 Months Once/3 Months None o

8 Logic (4) (6) i 1.

Logic Power Monitor Once/6 Months N.A.

N.?A. :

i 2.

Core Spray Initiation Once/6 Months N.A.

N.' A. #

3.

Pump & Valve (Signal Override)

Once/6 Months N.A.

N.' A. !

Control

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. s TABLE 4.2.B (Page 6)

RCIC TEST & CALIBRATION FREQUENCIES Instrument l

Item Item I.D. No.

Functional Test Freq.

Calibration Freq.

Check l

Instrument Channels 1.

Reactor High Water Level NBI-LIS-101 A & C, #2 Once/ Month (1)

Once/3 Months Once/ Day 2.

Reactor Lee Eater Level 10A - K79 A & B 10A-Once/ Month (1)

N.A.

_Once/ Day K80 A & B 3.

RCIC liigh Turbine Exhaust RCIC-PS-72, A & B Once/ Month (1)

Once/3 Months None -:

Press.

4.

RCIC Low Pump Suction Press.

RCIC-PS-67-1 Once/ Month (1)

Once/3 Months None 5.

RCIC Steam Line Space Excess RCIC-TS-79, A.B.C. & D Once/ Month (1)

Once/Oper. Cycle None Temp.

RCIC-TS-80, A,B,C, & D Once/ Month (1)

Once/Oper. Cycle None RCIC-TS-81, A B.C. 6 D Once/ Month (1)

Once/Oper. Cycle None RCIC-TS-82, A,B.C. & D Once/ Month (1)

Once/Oper. Cycle None 6.

RCIC Steam Line High AP RCIC-dPIS-83 Once/ Month (1)

Once/3 Months None RCIC-dPIS-84 Once/ Month (1)

Once/3 Months None Is 7.

RCIC Steam Supply Press. Low RCIC-PS-87, A,B,C, & D Once/ Month (1)

Once/3 Months Nonc Y'

8.

RCIC Low Pump Disch. Flow RCIC-FIS-57 Once/ Mon:h (1)

Once/3 Months None 9.

Pump Disch. Line Low Pressure CM-PS-269 Once/3 Months Once/3 Months None 10.

RCIC Turbine Conditional RCIC-TDR - K9 Once/ Month (I)

Once/Oper. Cycle None Supv. Alarm Timer II.

RCIC Steam Line liigh AP RCIC-TLR-K-12 Once/ Month Once/Oper. Cycle None l

Actuation Timer RCIC-TDR-K-32 Once/ Month Once/Oper. Cycle None l

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Logic Systems (4)(6)

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1.

Logic Bus Power Monitor Once/6 Months N.A.

2.

RCIC Initiation Once/6 Months N.A.

3.

Turbine Trip Once/6 Months N.A.

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4.

RCIC Automatic Isolation Once/6 Months M.A.

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LIMITIND CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-

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4.I'.A.2.c (Cont'd.)

3.4 pump domineralized water into the reactor vessel from the test tank.

.These tests check the actuation of the explosive charge of the tested loop, proper operation of the valves, and pump operability.

The replacement charges to be

' installed will be selected from l*

the same manufactured batch as a previously tested charge.

d.

Both systems, including both ex-plosive valves, shall be tested in l

the course of two operating cycles.

l B.

-Operation with Inoperable Components:

B.

Surveillance with Inoperable Com-l ponents:

}

1.

From and after the date that a redun-I dant component is made or found to 1.

When a component is found to be inop-l l

be inoperable. Specification 3.4.A.1 erable, its redundant component l

l shall be considered fulfilled and shall be demonstrated to be operable l

cantinued operation permitted pro-immediately and daily thereafter vided that the component is returned until the inoperable component is to an operable condition within repaired.

seven days.

C.

Sodium Pentaborate Solution C.

Sodium Pentaborate Solution I

j At al' times when the Standby Liquid The following tests shall be performed l

Control System is required to be op-to verify the availability of the arable the following conditions shall Liquid Control Solutions be mets i

l 1.

The net volume versus concentration 1.

Volumet Check and record at least once-l of the Liquid Control Solution in per day.

the liquid control tank shall be main-tained as required in Figure 3.4.1.

2.

The temperature of the liquid control 2.

Temperature:

Check and

< cord at least solution shall be maintained above the once per day.

curve shown in Figure 3.4.2.

3.

Concentration:

Check and

'ord at least once per month.

Alu..: heck con-centration anytime water or ooron is

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COOPER NUCLEAR STATION

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TABLE 3.7.1 (Page 1)

PRIMARY CONTAINMENT ISOLATION VALVES Number of Power P.2ximum Action On Operated Valves Operating Normal Initiating Valve & Steam Inboard Outboard Time (Sec) (1)

Position (2)

Signal (3)

Main Steam Isolation Valves MS-AO-80-- A.B.C. 4 D 4

35T55 0

GC f MS-AO A.B.C. & D 4

35T$5 0

GC ;

CC !

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Drywell Floor Drain Iso. Valves 2

15 0

RW-AO-82 RW-AO-83 l

Drywell Equipment Drain 2

15 0

GC +

l Iso. Valves RW-AO-94, RW-AO-95 m

8 Main Steam Line Drain 1

1 20 0

GC Valves MS-MO-74 MS-MO-77 Reactor Vater Sample Valves 1

1 15 0

GC RRV-740AV, RRV-741AV Reactor Water Cleanup System 1

1 60 0

CC Iso. Valves R;'CU-MO-15, RWCU-MO-18 i

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i RilR Suction Cooling Iso.

I 1

40 C

SC l t

Valve RllR-MO-17 RiiR-MO-18 l

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l RIIR Discharge to Radwaste 2

20 C

SC Iso. Valves RIIR-MO-57, R!1R-MO-67 Suppression Chamber Purge &

2 15 C

SC Vent PC-245AV, PC-230MV Suppression Chamber N Supply 2

15 C

SC.

y PC-237AV, PC-233MV I

,