ML20101G772

Corrected Amend 152 to License DPR-46,replacing Pages Issued W/Amend Which Contained Minor Editorial Errors

ML20101G772
Person / Time
Site:	Cooper
Issue date:	06/18/1992
From:	Bevan R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20101G620	List: ML20101G617 ML20101G772
References
NUDOCS 9206260282
Download: ML20101G772 (6)

Text

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LI$81 TING CONDITIONS FOR OPEP_ATION StmNETIDNCE REOCREPN'TS 3.12 (cont'd) 4.12 (cont'd)

B.

Reactor Ecuireent Cooline (REC)

B.

Reactor Eauloment Coolint (REC)

Svstem System 1.

Both Reactor Equipment Cooling 1.

REC System Testing subsystems and their associated Item Frecueqqy pumps shall be operable whenever irradiated fuel is in the vessel or a.

Pump Operability Once/MA h the spent fuel pool, except as b.

Motor operated once/ Month specified in 3.12.B.2 and 3.12.B.3 below.

Valve Operability c.

Pump flow rate once/3 months Each pucp shall and after pu=p deliver 1175 gpm maintenance at 65 psid.

d.

System head tank Daily level shall be monitored.

2.

From and after the date that any 2.

When it is de te rmined that any active co=ponent that affects active co=ponent that affects operability of one REC subsystem operability of an REC subsystem is becomes inoperable, continued inoperable, all active components reactor operation is pe rmissible that affect operability of the during the succeeding thirty days operable REC subsystem shall be !

provided that during such thirty verified operable immediately and days all active components that weekly thereafter.

affect operability of the operable REC subsystem, the active components that affect operability of the engineered safeguards compartment I

cooling systems, and the diesel generator associated with the i

operable subsystem are operable.

The allowable repair time does not apply when the reactor is in the

~

shutdown mode and reactor pressure is less than 75 psig.

l 3.

Both REC subsystems, with one pump i

per subsystem, shall be operable as stated in 3.12.B.1 and 3.12.s.2 above during reactor head-off operations requiring LPC1 or Core Spray system availability or Service Water cooling shall be available.

4.

If the requirements of 3.12.B.1 through 3.12.B.3 cannot be met, the reactor shall be shutdown in an orderly manner and in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or operations requiring LPCI or Core Spray system availability shall be halted.

9206260282 920618 DR ADOCK 05000 8

-215b-Amendment No. 80, IAE, 152 h

LIMITING CONDITIONS MR SPERATION SURVEILIANCE REOUIREMD.'TS 3.5.A (cont'd.)

4.5.A (cont'd.)

2.

From and af ter the date that one of 2.

When it is determined that one Core l

the Core Spray subsystems is made or Spray subsystem is inoperable, the found to be inoperable for any operable Core Spray subsystem and reason, continued reactor operation both LPCI subsystems shall be is permissible during the succeeding verified to be operable im:cediately.

seven days provided that during such The operable Core Spray subsystem l seven days all active components shall be verified to be operable that affect operability of the daily thereafter.

operable Core Spray subsystem and all active components that affect 3.

LPCI subsystem testing shall be as operability of both LPCI subsystems follows:

and the diesel generators are operable.

F-m a.

Simulated Once/ Operating 3.

Both LPCI subsystems shall be Automatic Actuation Cycle operable:

Test (1) prior to reactor startup from b.

Pump Operability Once/ month a Cold Condition, except as specified in 3.22.B.1, or c.

Mt r Operated Once/ month Valve Operability (2) when there is irradiated fuel in the vessel and when the d.

Pump Flow Rate Once/3 months reactor vessel pressure is greater than atmospheric d@ m W.

MM pressure, except as specified pu=p shall deliver at least 7700 CPM in 3.5.A.4 and 3.5.A.5 below.

but no more than 8400 CPM against a system head equivalent to a reactor vessel pressure of 20 psid above drywell pressure with water level below the jet pumps.

At the same conditions, two pump LPCI flow shall I be at least 15,000 CPM.

Recirculation pump discharge valves e.

shall be tested each refueling outage to verify full open to full closed in t $ 26 seconds.

f.

An air test shall be performed on 4.

From and af ter the date that one of the drywell and torus headers and n zzles nee /5 years, the RHR (LPCI) pumps is made or found to be inoperable for any 4.

When it is determined that one of reason, continued reactor operation the RHR (LPCI) pumps is inoperable is permissible only during the at a time when it is required to be succeeding thirty days provided that

operable, the remaining active during such

-thirty days the components that affect operability remaining actiye components that of the LPCI subsystem containing the affect operability of the LPCI inoperable

pump, all active subsystem containing the inoperable components that affect operability pump, and all active components that of the operable LPCI subsystem, and affect operability of the operable both Core Spray subsystems shall be LPCI subsystem, both Core Spray verified to be operable immediately subsystems, and both diesel and the operable LPCI pumps daily generators are operable.

thereafter.

115 Amendment No. 57, 76. E0, 9B. 97. U7.

152

LIMfTING CONDITTONS FOR OPERATION SURVEILIANCE REOUIREwENTc 3.5.A (Cont'd.)

4.5.A. (Cont'd.)

5.

From and after the date that one 5.

When it is determined that a LPCI LPCI subsystem is made or found to subsystem is inoperable, the be inoperable for any

reason, operable LPCI subi..em, both Core continued reactor operation is Spray subsystems, and the RHR permissible only during the Service Vater Subsystem associated succeeding 7 days, unless it is with the operable LPCI subsystem sooner made ;etable, provided that shall be verified to be operable during such 7 days all active immediately and daily thereafter.

co=ponents that affect operability of the operable LPCI subsystem, both Core Spray subsystems, the RHR Service Vater subsystem associated with the operable LPCI subsystem, and both diesel generators shall be operable.

6.

All recirculation pump discharge 6.

All recirculation pump discharge valves shall be tested for valves shall be operable prior to operability during any period of reactor startup (or closed if Reactor cold shutdown exceeding permitted elsewhere in these 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have specifications).

not been performed during the preceding 31 days.

7.

The reactor shall not be started up with the RER system supplying cooling to the fuel pool.

8.

If the requirements of 3.5.A 1,2,3,4,5,6 or 7 cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.

Residual Heat Removal (RHR) Service B.

Residual Heat Removal (RHR) Service Water System tiater System 1.

RHR Service Water System testing l

1.

Except as specified in 3.5.B.2, shall be as follows:

3.5.B.3, and 3.5.F.3 below, both RHR Service Water subsystems shall be Item Frecuenev operable whenever irradiated fuel is in the reactor vessel and reactor a.

Pu=p & Valve Once/3 months coolant temperature is greater tha;.

Operability 212*F, and prior to reactor startup from a Cold Condition.

b.

Pump Capacity Test. After pump Each RHR service maintenance and water booster pump every 3 months shall deliver 4000 epm.

116-Amendment No. 36, 92, 93, III, 152

_. _ _ _ _. _. _ _ _ _.. _. _.. _... _ _. _ _ _ _ _,. ~.. _ _ _

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LIMfTVNG CONDITIONS TOR OPERATION SURVEILIANCE REOUIREMENTS 3.5.B (Cont'd.)-

i 4.5.B (Cont'd.)

2.

From and af ter the date that any RHR 2.

When it is determined that any PJ{R l

Service Water booster pump is made Service Water booster pump is l or found to be inoperable for any inoperable, the remaining active reason, continued reactor operation components that affect operability is permissible only during the of the RHR Service Vater subsystem succeeding thirty days, unless such containing the inoperable pump, and pump is sooner made

operable, all active components that affect provided that during such thirty operability of the operable RHR days the remaining active components Service Water subsystem shall be that affect operability of the RHR Service Water subsystem containing verified to be operable ic: mediately and weekly thereafter.

the inoperable pump, and all active components that affect operability of the operable RHR Service Water subsystem are operable.

3.

Fro = and af ter the date that one RER 3.

When one RHR Service Water subsystem Service Water subsystem is made or becomes inoperable, the operable RHR found to be inoperable for any Service Water subsystem and its reason, continued reactor operation associated LPCI subsystem shall be is permissible only during the verified to be operable immediately succeeding seven days unless such and daily thereafter.

j subsystem is socner made operable, provided that all active components that affect operability of the operable RHR Service Water subsystem, its associated LPCI subsystem, and its associated diesel generator are operable.

4 If the requirements of 3.5.B.1, 3.5.B.2 or 3.5.B.3 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C.

R.C_I Systea l

lC.

HPCI System 1.

HPCI System testing shall be l

l1.

The HPCI System shall be operable performed as follows:

whenever there is irradiated fuel in the reactor vessel, reactor pressure Item is greater than 113 psig, and prior Frecuen.qy to reactor startup from a Cold a.

Simulated Once/ operating Condition, except as specified in Automatic

-3.5.C.2 and 3.5.C.3 belev.

Cycle Actuation Test b.

Pump Operability Once/ month c.

Motor Operated Once/ month Valve Operability

-117-Amendment No. 26,95,1 4,152

i e

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3.5 BASES A.

Core Sorav and LPCI Subsystems This specification assures that adequate emergency cooling capability is available whenever irradiated fuel is in the reactor vessel.

The limiting conditions of operation in Specifications 3.5.A.1 through 3.5 A.8 l

specify the combinations of operable subsystems to assure the availability of the minimum required cooling systems.

During reactor shutdown when the residual heat removal system is realigned from LPCI to the shutdown cooling mode, the LPCI subsystems are considered aperable.

l The Core Spray System is a low pressure cociant system which is comprised of two, distinct subsystems and designed to provide emergency cooling to the core by spraying in the event of a loss of-coolant accident.

This system functions in combination with the LPCI System to prevent excessive fuel clad temperature.

l The 1.PCI System is an operating mode of the RHR System and is comprised of two, distinct LPCI subsystems. The LPCI Syste is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident.

This system functions in combination with the Core Spray System to prevent excessive fuel clad tecperature.

The LPCI and Core Spray systems provide adequate cooling for break areas of approxicately 0.2 square feet up to and including the double-ended recirculation line break without assistance from the high pressare emergency core cooling subsystems.

The allowable repair times are established so that the average risk rate for repair would be no greater than the basic risk rate.

The method and concept are described in reference (1). Using the results developed in this reference, the repair period is found to be slightly greater than 1/2 the test interval. This assumes that the l

(1)

Jacobs, I.M., " Guidelines for Deteinining Safe Test Intervals and Repair Times for Engineered Safeguards", General Electric Co.

A.P.E.D.,

April, 1969 (APED 5736).

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-124-Amendment No. 57, 20, 152

3.5.A BASES (cont'd.)

Core Spray subsystems and LPCI subsystems constitute a 1 out of 4 system; however, the cochined effect of the two systems to limit ex ssive clad temperatures must also be considered. The test interval specified in Specification 4.5 is 1 month.

Should one Core Spray subsystem become inoperable, the remaining Core Spray subsystem and the 1.PCI subsystems are available should the need for core cooling arise.

To assure that the remaining Core Spray and LPCI subsystems are available, they are verified to be operable f.smediately.

Should the loss of one LPCI pump occ~, a nearly full complement of core cooling equip =ent is available.

Three LPCI pumps in conjunction with the Core Spray subsystems will perform the core cooling function.

Because of the availability of the majority of the core cooling equipment, which will be verified to be operable, a thirty day repair period is justified. If one LPCI subsyste= is not available, at least 1 LPCI pump must be available to fulfill the containment cooling function.

The 7 day repair period is set on this basis.

J E.

FER Service Water Svstem j

The P2R Service Water System consists of two, disunct subsystems designed to provide heat removal for the containment cooling function. Each PER Service Watcr subsystem contains two FER Service Water booster pumps serving one side of one of two FRR Heat Exchangers, while two RHR (LPCI) pumps serve the other side. The PER Service Water System operates in conjunction with the PRR System to provide the containment cocling function.

The design of the RHR Service Water System is predicated upon the use of one FER Service Water booster pump and one RHR heat exchanger for heat removal af ter a design basis accident.

Thus, there are anple spares for margin above design conditions.

Loss of margin should be avoided and the equipment maintained in a state of operation.

So a 30 day out-of-service time is chosen for this equipment.

If one loop is out-of-service, reactor operation is permissible for seven days.

The requirements for availability of the RHR System for support of the containment cooling function are reflected in the associated action state =ents for the LPCI System.

With co=ponents or subsystems out-of-service, overall core and containment cooling reliability is maintained by verifying the operability of the remaining cooling equipment.

For routine out-o f-s e rvic e periods caused by preventive maintenance, the operability of other systems and components will be verified as given in etc.,

the Technical Specifications. However, if a failure, design deficiency, etc., caused the out-of-service period, then a demonstration of operability may be needed to assure that a similar problem does not exist on the remaining components.

For 4

example, if an out-of-service period were caused by failure of a pump to deliver rated capacity, the other pumps of this type might be subjected to a capacity test.

The pump capacity test is a comparison of measured pu=p performance parameters i

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-125-Amt'dment No. 22,95,IH,152 i

.,.