ML20153C810

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Proposed Tech Specs Re Containment Cooling Sys
ML20153C810
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 08/26/1988
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20153C772 List:
References
NUDOCS 8809010302
Download: ML20153C810 (8)
v • d • e


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CIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.A . Core Spray and LPCI 4.5.A Core Spray and LPCI i 3Iibsystem (cont'd) Subsystem (cont'df

6. All recirculation pump discharge 6. All recirculation pump discharge

'l valves shall be operable prior to valves shall be tested for l reactor startup (or closed if operability during any period permitted elsewhere in these of reactor cold shutdown exceeding ,

specifications). -48 hours, if operability tests  ;

have not been performed during r the preceding 31 days.

7. If the requirements of 3.5.A canne' l be met, an orderly shutduwn of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. ,

B. Containment Cooling System B. Containment Cooling System -

ThPSW, Torus Cooling. Drywell Spray. DiPSW, Tcrus Cooling. Drywell Spr m and Torus Spray) and Torus Spray) .,

1. Except as specified in 3.5.B.2, 1. Containment Cooling System components 3.5.B. 3, 3. 5.B.4. 3. 5.B. 5, shall be tested as follows: l 3.5.B.6, and 3.5.f.3 below. .

the containment cooling system item frequency shall be operable whenever .

irradiated fuel is in the reactor (a) Each HPSW Pump Once/ month l '

vessel and reactor coolant Operability.

temperature is greater than 212 i degrees f, and prior to reactor (b) Each HPSW motor operated Once/ month l ,

startup from a Cold Shutdown _ valve operability. .'

Condition. ,

(c) IIPSW Pump Capacity After pump

  • Test. Each HPSW maintenance '

pump shall itnd every  :,

deliver 4500 3 tnonths.

gpm at 233 psig. r (d) Each Torus Cooling Once/ month .

motor operated [

valve operability.

(e) Each Drywell Spray Once/ month -

motor operated valve operability.

I (f) Each Torus Spray Once/ month 4 motor operated l valve operability.  ;

(g) Air test on Once/5 years  ;

! drywell and torus headers ,

I and nozzles.

- 121 - i 8809010302 000026 PDR ADOCK 05000277 p PN'J ,

PBAPS

  • SURVEILLANCE REQUIREMENTS

,. ' LIMITING CONDITIONS FOR OPERATION [

t 3.5.B Containment Cooling 4.5.B Containment Cooling i System (cont'd.) System (contd.) l l

2. From and after the date tnat 2. When it is determined that any  ;

two HPSW pumps ace inoperable, any two HPSW pumps are made or i found to be inoperable for any the remaining HPSW pumps shall reason, continued reactor opera- be demonstrated to be operable tion is permissible only during immediately and weekly ,

the succeeding thirty days, unless thereafter.

- such pump is sooner made operable, [

provided that during such thirty  ;

l days the remaining HPSW pumps are operable, t

3. From and after the date that 3. When it is determined that fi l any three HPSW pumps are made or any three HPSW pumps are in- '

found to be inoperable for operable, the remaining HPSW any reason, continued reactor pump and its associated diesel l operation is permissible only generator aball be t during the succeeding fifteen demonstrated to be l days unless such pumps are operable immediately and  !

the operable HPSW pump S sooner made operable provided l l l the remaining HPSW pump is weekly thereafter.  !

I operable. '

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4a. The torus cooling mode of 4. When it is determined RHR shall be operable with that a torus cooling loop i

two independent loops. is inoperable, the operable i Each loop consists oft torus cooling loop and its associated diesel generators ,

i (1) At least one operable shall be tested immediately.

,' RHR pump.  !

I (2) An operable flow path to l

{'

> pump water from the torus  :

1- through an operable RHR l 1 heat exchanger and back l

). to the torus via the flow ,

j test line. l (3) An operable HPSW flow path l

, through the operable heat j exchanger asscciated with the operable RHR pump.

I b. With one torus cooling loop j inoperable, restore the inoperable j loop to operable status within j seven days.

1 i c. With both torus cooling 1 cops j inoperable,, restore at least one loop to operable status within eight hours.

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Sa. The drywell spray mode of RilR 5. When it is determined shall be operable with that a drywell spray loop is -

two independent loops, inoperable, the components of the Each loop consists oft operable drywell spray loop and their associated diesel (1) At least one operable generators shall be tested RilR pump. immediately.

(2) An operable flow path to pump water from the torus through an operable RHR heat exchanger to the drywell spray sparger.

1 (3) An operable llPSW flow path through the operable heat exchangerassociated with the operable RilR pump.

b. With one drywell spray loop ,

inoperable, restore the inoperable loop to operable status within seven days.

c. With both drywell spray loops inoperable, restore at least one loop to operable status within eight hours.

6a. The torus spray mode of RllR 6. When it is determined that shall be operable with two a torus spray loop is independent loops. Each inoperable, the components of loop consists oft the operable torus spray loop components and their associated diesel (1) At least one operable generators shall be tested RilR pump. immediately.

(2) An operable flow path to pump water from the torus through an operable RllR heat exchanger to the torus spray sparger.

(3) An operable llPSW flow path through the operable heat  ;

exchange associated with the operable RiiR pump.

b. With one torus spray loop inoperable, restore the inoperable loop to operable status within seven days.
c. With both torus spray loops inoperable, restore at least one loop to operable I status within eight hours.  !

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l'OhPS o, ,

s LIMITI!JG CO!1DITIO!JS FOR OPERATION SURVEILLAllCE REQUIREMFNTS 3.S.B Containment Cooling 4.5.B Containment Cooling System (cont'd.) l l System (cont'd.)

l7. If the requirements of 3.5.B 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 />.

IIPCI Subsystem C. IIPCI Subsystem C.

1. The HPCI Subsystem shall be 1. HPCI Subs;' stem testing operable whenever there is shall be pirformed as follows:

irradiated fuel in the reactor 'requency vessel, reactor pressure is Item greater than 105 psig, and Once/ operating prior to reactor startup (a) Simulated from a cold Condition, Automatic cycle except as specified in Actuation 3.5.C.2 and 3.5.C.3 below. Test e

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1 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS , 3.5.F Minimum Low Pressure Cooling 4.5.F Minimum Low Pressure and Diesel Generator Cooling and Diesel  ;

Availability Generator Availability l

1. During any period when one 1. When it is determined that one j diesel generator is inoper- diesel generator is inoperable, able, continued reactor opera- the operable diesel generators l tion is permissible only shall be demonstrated to be i during the suwceeding seven operable immediately and days unless such diesel gene- daily thereafter.

rator is sooner made operable #

provided that-the remaining diesel generators and the i low pressure core and '[

containment cooling systems which are powered by the remaining diesel [

l generators are operable.  !

d If this requirement cannot be met, an orderly shutdown <!

shall be initiated and the reactor shall be placed in

]

the Cold Shutdown Condition ',

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

3. Any combination of inoperable [

l, components in the core and containment

cooling systems shall not defeat [

! the capability of the remaining ,

operable components to fulfill  !

the cooling functions.

),

3. When irradiated fuel is in the j
reactor vessel and the reactor i

is in the Cold Shutdown Condition, ,

j both core spray systems, the LPCI .

and containment cooling systems ~

]

may be inoperable, provided no i j work is being done which has the potential for draining the  !

3 i reactor vessel. ii l

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! 4. During a refueling outage, o i fuel and LPRM removal and replacement may be performed )

i j l provided at least one of the following conditions below is J

, satisfied:

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PDAPS LIMITING CONDITIONS FOR OPERATION SURVCILLANCE REQUIREMENTS l 3.5.F.4 (cont'd) l

a. Both core spray systems and the LPCI system shall be operable except that one core spray system or the LPCI system may be inoperable for a period of thirty days, or
b. The reactor vessel head is removed, the cavity is flooded, the spent fuel 7ool gates are removed, and the water level is maintained at least 21 feet over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks and no work is being performed which has the potential for draining the reactor vessel.

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3.5.B BASES

  • Containment Cooling System l The Peach Bottom Containment Cooling System consists of the liigh Pressure Service Water (IIPSW ) system and the drywell spray, torus spray and torus cooling modes of the Residual llcal Removal System ( RilRS ) .

The torus cooling mode of RilR consists of two independent loops. A loop is defined as a flow path to pump water, with an RilR pump, from the torus through an Ri!R heat exchanger, then back to the torus via the flow test line.

A flow path from an operable llPSW pump through that RilR heat exchanger completes the functional loop.

The drywell spray mode of RilR consists of two independent loops. A loop is defined as a flow path to pump water, with an RilR pump, from the torus through an RilR heat exchanger to the drywell spray sparger. A flow path from an operable llPSW pump through that RilR heat exchanger completes the functional loop.

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( The torus spray mode of RllR consists of two independent loops. A loop is defined as a flow path to pump water from i

the torus, with an RilR pump, through an RilR heat exchanger to the torus spray sparger. A flow path from an operable llPSW pump through that RilR heat exchanger completes the functional loop.

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The design of these systems is predicated upon use of 1 RilR and 1 IIPSW pump for heat removal after a design basis Thus, there are ample spares for margin above the i

l event.

design conditions. Loss of margin should be avoided and the equipment maintained in a state of operability so a 30-day out-of-service time is chosen for this equipment.

With components or subsystems out-of-service, overall core end containment cooling reliability is maintained by demonstrating the operability of the remaining cooling equipment. The degree of operability to be demonstrated depends on the nature of the reason for the out-of-service equipment. Por routine out-of-service periods caused by preventative maintenance, etc., the pump and valve operability checks will be performed to demonstrate operability of the remaining components. Ilowever, if a l

failure, design deficiency, etc., caused the out-of-service period, then the demonstration of operability should be thorough enough to assure that a similar problem does not l exist on the remaining components. Por example, if an out-l of-service period were caused by a failure of a pump to deliver rated capacity, the other pumps of this type might be subjected to a capacity test. In any event, .

surveillance procedures, as required by Section 6 of these l specifications detail the required extent of tes'.ing.

The pump capacity test is a comparisen of measured pump l performance parameters to shop performance tests. Tests during normal operation will be performed by measuring the flow indication and/or the pump uischarge pressure will be measured and its power requirement will be used to establish flow at that pressure. I

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CERTIFICATE OF SIRVICE I hereby certify that copies of the foregoing Application were served on the follwing by deposit in the United States htail, first class postage prepaid, on the 26th day of August, 1988.

William T. Russell, Regional Admir.istrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 T. P. Johnson, Resident Inspector U.S. Nuclear Regulatory Cocaission Peach Bottom Atomic Power Station P.O. 399 Delta, PA 17314 bir. Thomas Gerusky, Director Bureau or Radiological Protection Department of Environmental Resources P.O. Box 2063 llat risburg, PA 17120

% ,4 1tO j liuggne'J. Biad1ey Attorney for Philadelphia Electric Company l

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