ML20097D923

Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs

ML20097D923
Person / Time
Site:	Quad Cities
Issue date:	02/08/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20097D919	List: ML20097D913 ML20097D923
References
NUDOCS 9602130232
Download: ML20097D923 (5)

Text

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QUAD-CITIES DPR-29 l

3. Flow Rate Test - During startup HPCI pump shall following a i

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deliver at least refuel outage or 5000 gpa against an outage in a system head which work was i

corresponding to performed that reactor vessel directly affects pressure:

HPCI system

a. when steam operability.

is being supplied to i

the turbine at 150 to l

325 psig, and l

b. when steam l

2 is being s,upplied to i

the turbine at 920 to 2005 psig.

i

4. If the requirements of Specification

4. Simulated Each refueling 3.5.C.1, 3.5.C.2 or 3.5.C.3 cannot be Automatic outage met, an orderly shutdown shall be Actuation Test initiated, and the reactor pressure shall be reduced to <l50 psig within

5. Logic System Each refueling Functional Test outage.

]

j 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Automatic Pressure Relief Subsystems D. Automatic Pressure Relief Subsystems Surveillance of the automatic pressure relief subsystem sha 1 be performed as follows:

q%

1. The automatic pressure relief

1. The following survei' an shall be carried out on ah month j

subsystem shall be operable whenever.

i the reactor pressure is greater than surveillance interval:

90 psig, irradiated fuel is in the 1

reactor vessel and prior to reactor

a. With the reactor at pressure each relief valve shall be j

startup from a cold condition.

manually opened. Relief valve

2. From and after the date that two of opening shall be verified by a i

the five relief valves of the compensating turbine bypass valve or control valve automatic pressure relief subsystem are made or found to be inoperable closure.

when the reactor is pressurized above 90 psig with irradiated fuel in the

2. A logic system functional test reactor vessel, reactor operation is shall be performed each refueling 4

permissible only during the outage.

succeeding 7 days unless repairs are made and provided that during such

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time the HPCI subsystem is operable.

9602130232 960208 PDR ADOCK 05000254

/fA P

PDR 3.5/4.5-6 Amendment No.

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OPA-30 D.

Automette Press $r0 Relief Subsystems 0.

Automatic Pressure taltef Suesystems Surveillance of the automatic pressure r'ellef subsystem shall be eLighhem performed as follows:

1.

The automatic pressure reiter 1.

The following surveill e shall subsystes shall be opersele be carried out on at th whenever the reactor pressure is surveillance interva :

greater than 90 pstg. trradtated fuel is in the reactor vessel a.

With the reactor at pressure and prior to reactor startup each reiter valve shall be from a cold cond1t1on.

manually opened. Re1ief valve opening shall be vertfted by a comoensating turbine bypass valve or control valve closure.

2.

From and af ter the date that two 2.

A logic system functional test of the five reitef valves of the shall be perforimed each autenstic pressure retter refueling outage.

sutsystem is made or founo to be inoperable when the reactor is pressurtred above 90 pstg with trradiated fuel in the reactor vessel, reactor operation is peratss1ble only during the succeeding 7 days unless repairs are made and provided that during such time the NPCI subsystee is operatie.

3.

If the requirements of Specifi-3.

A stenJlated autanette initiation cation 3.5.0 cannet be met, an which opens all ptiot valves creerly shutdoest shall be intti-shall be performed each re-ated and the reactor pressure fueling outage.

shall be reduced to 90 pstg within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.

neen it is determined that two reitef valves of the automatic pressure rettef subsystem are inoperstle, the NPCI shall De demonstrated to be operable tenedtately.

3.5/4.5-5

/WI Amendment No.

ATTACHMENT B Revised Technical Specification Paces

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QUAD CITIES DPR-29

3. Flow Rate Test -

During Startup HPCI pump shall following a deliver at least refuel outage or

.I 5000 gpm against an outage in a system head which work was corresponding to performed that reactor vessel directly affects I

pressure:

HPCI system l

a. when steam operability.

l Is being i

supplied to the turbine at 150 to 325 psig, and

b. when steam

(

is being supplied to the turbine at 920 to 1005 psig.

4. If the requirements of Specification

4. Simulated Each refueling 3.5.C.1,3.5.C.2 or 3.5.C.3 cannot bo Automatic outage met, an orderly shutdown shail be Actuation Test initiated, and the reactor pressure shall be reduced to <150 psig within

5. Logic System Each refueling

,)

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Functional Test outage D. Automatic Pressure Relief Subsystems D.

Automatic Pressure Relief Subsystems Surveillance of the automatic pressure relief subsystem shall be performed as follows:

1. The automatic pressure relief

1. The following surveillance shall l

subsystem shall be operable whenever be carried out on a eighteen-month I

the reactor pressure is greater than surveillance interval:

90 psig, irradiated fuel is in the reactor vessel and prior to reactor

a. With the reactor at pressure startup from a cold condition, each relief valve shall be manually opened. Relief valve

2. From and after the date that two of opening shall be verified by a the five relief valves of the compensating turbine bypass automatic pressure relief subsystem valve or control valve closure, are made or found to be inoperable when the reactor is pressurized above

2. A logic system functional test 90 psig with irradiated fuel in the shall be performed each refueling reactor vessel, reactor operation is outage.

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permissible only during the succeeding 7 days unless repairs are made and provided that during such time the HPCI subsystem is operable.

l 3.5/4.5-6 Amendment No.168

l QUAD CITIES DPR-30 D. Automatic Pressure Relief Subsystems D. AutomItic Pr:ssura Rglitf Subsystams

)

Surveillance of the automatic i

/

pressure relief subsystem shall be j

performed as follows:

l

1. The automatic pressure relief

1. The following surveillance shall subsystem shall be operable be carried out on an eighteen-month l

whenever the reactor pressure is surveillance interval:

I greater than 90 psig, irradiated fuel is in the reactor vessel

a. With the reactor at pressure and prior to reactor startup each relief valve shall be from a cold condition, manually opened. Relief valve opening shall be verified by a compensating

)

l turbine bypass valve or control valve closure.

2. From and after the date that two of the

2. A logic system functional test five relief valves of the automatic pressure shall be performed each relief subsystem is made or found to be refueling outage.

inoperable when the reactor is pressurized l

above 90 psig with irradiated fuel in the j

reactor vessel, reactor operation is permissible only during the succeeding 7

.)

days unless repairs are made and m,..,

provided that during such time the HPCI subsystem is operable.

3. If the requirements of Specifi-cation 3.5.D cannot be met, an orderly shutdown

3. A simulated automatic initiation shall be initi-which opens all pilot valves ated and the reactor pressure shall be shall be performed each re-reduced to 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

fueling outage.

4. When it is determined that two relief valves of the automatic l

pressure relief subsystem are inoperable, the HPCI shall be demonstrated to be operable immediately.

l 1

l 3.5/4.5-5 Amendment No.164

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