ML20092M049

Proposed Tech Specs Re auto-start Logic of Containment Spray Sys

ML20092M049
Person / Time
Site:	Oyster Creek
Issue date:	02/19/1992
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20092M028	List: ML20092M026 ML20092M040 ML20092M049
References
NUDOCS 9202270136
Download: ML20092M049 (6)

Text

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TABLE 3.1.1 PROTECTIVE IN"TRUMENTATION REQUIREMENTS (CONT'D)

Reactor Modes Min. No. of Min. No. of in which Function Operable or Instrument Must Be Operable Operating Ch>nnels Per Trip [ tripped] Operable Action Shutdown Refuel Startuo. Run Trio Systems Trio Systems Recuired*

Function Settina D. Core Soray Consider the 2 2 respective

1. Low-Low Reactor ** X(t) X(t) X(t) X core spray Water Level loop inoperable, and comply with spec. 3.4

2. High Drywell 5 3.5 psig X(t) X(t) X(t) X 2(k) 2(k)

Pressure.

X(t) 2 2

3. Low Reactor 2 285 psig X(t) X(t) X Pressure (valve permissive)

E. Containment Soray Comply with Technical Specification 3.4 F. Primary Containnent Isolation s 3.5 psig X(u) X 2(k) 2(k) Isolate

1. High Drywell X(u) X(u) containment or Pressure place in X(u) X 2. 2 cold shutdown

2. Low-Low Reactor 1 7'2" above X(u) X(u) condition Water Level top of active fuel 3.1-11 Amendment No.: 44, 79, 112 OYSTER CREEK Change 4 Correction: 5/11/84

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TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS (CONT'D)

Reactor Modes Min. No. of Min. Fo. of in which Function Operable or Instrument Must Be Operable Operating Channels Per Trip [trippedl Operable Action Setting Shutdown Refuel Startup Run Trio Systems Trio Systems Recuired*

Function X 2 3

6. IRM Upscale 5 108/125 fullscale X X(z) I per

7. a) water level 1 14 gallons X(z) X(z) 1 instrum.

high scram volume discharge volume North b) water level s 14 gallons X(z) X(z) X(z) I 1 per high scram instrum.

volume discharge volume South

! L. Condenser Vacuum Pump Isolation .

1. High Radiation 5 10 x' Normal- During Startup and '2 2 Insert background Run when vacuum pump 1 Control Rods

! in Main Steam l Tunnel operating i

M. Diesel Generator Time delay after

load Secuence energization of Timers relay X 2(m) 1(n) Consider the pump

1. CRD pump 60 sec 15% X X X inoperable and comply with Spec. 3.4.D (see l

Note q)

(

3.1-14 Amendment No.: IS, 44, 60, 63 OYSTER CREEK

TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS (CONT'D)

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Reactor Modes Min. No. of Min. No. of in which Function Operable or Instrument Must Be Operable Operating Channels Per Trip [ tripped] Operable Action Function Setting Shutdown Refuel Startuo Run Trio Systems Trio Systems Recuired*

2. Service Water 120 sec. 15% X X X X 2(o) 2(p) Consider the pump Pump (aa) (SKIA) inoperable and 10 sec. 15% comply within (SK2A) 7 days (See (SK7A) Note q)

(SK8A)

3. Closed Cooling 166 Sec. 15% X X X X 2(m) 1(n) Consider the pump Water Pump (bb) inoperable and co= ply within 7 days (See Note q)

N. Loss of Power

a. 4.16KV Emergency ** X(ff) X(ff) X(ff) X(ff) 2 I Bus .Undervoltage (Loss of Voltage)

b. 4.16 KV Emergency ** X(ff) X(ff) X(ff) X(ff) 2 3 See note ee Bus undervoltage (Degraded Voltage)

OYSTER CR.EEK 3.1-15 Amendment No.: 15, 60.

73, 80

The containment spray system is provided to remove heat energy from the containment in the event of a loss of coolant accident. Actuation of the containment spray system in accordance with plant emergency operating procedures ensures that containment and torus pressure and temperature conditions are within the design basis for containment integrity, EQ, and core  ;

spray NPSH requirements. The flow from one pum) in either loop is more than ample to provide the required heat removal capaallity(2). The emergency service water system provides cooling to the containment spray heat exchangers and, therefore, is required to provide the ultimate heat sink for the energy release in the event of a loss of-coolant accident. The emergency service water pumping requirements are those which correspond to containment cooling heat exchanger performance implicit in the containment cooling description.

Since the loss of-coolant accident while in the cold shutdown condition would not require containment spray, the system may be deactivated to permit integrated leak rate testing of the primary containment while the reactor is in the cold shutdown condition, j l

The control rod drive hydraulic system can provide high pressure coolant injection capability, for break sires up to 0.002 ft , a single control rod ,

drive pump with a flow of 110 gpm is adequate for maintaining the water level nearly five feet abe.e the core, thus alleviating the necessity for ,

auto-relief actuation (3).  :

The core spray main pump com)artments and containment spray pump compartments were provided with water tigit doors (4). Specification 3.4.E ensures that the doors are in place to perform their intended function.

Similarly, since a loss of coolant accident when primary containment integrity is not being maintained would not result in pressure build up in the drywell or torus, the system may be made inoperable under these conditions. This prevents possible personnel injury associated with contact with chromated torus water, ik'h19aC11 7

1. NEDC-31462P, "0yster Creek Nuclear Generating Station SAFER /COREC00L/GESTR-LOCA Loss-of Coolant Accident Analysis,"

August 1987.

2. Licensing Application, Amendment 32, Question 3

3. Licensing Application, Amendment 18, Question 1

4. Licensing Application, Amendment 18, Question 4

5. GPUN Topical Report 053, " Thermal Limits with One Core Spray Sparger" December 1988.

6. NEDE 30010A, " Performance Evaluation of the Oyster Creek Core Spray Sparger", January-1984.

7. Letter and enclosed Safety Evaluation, Walter A. Paulson (NRC) to P. B.

Fiedler(GPUN), July 20, 1984. _

8. APED-5736, " Guidelines for Determining Safe Test Intervals and Repair Times for Engineered Safeguards", April 1969.

0YSTER CREEK 3.4-8 Amendment No.: 153

r TABLE 4.1.2 ti1HJHUM TEST FR[DyfliCIES FOR TRIP SYSTEMS Irlp_S11LeID liinimum Test frequency

1) Dual Channel (Scram) Same as for ressective instru-mentation in Ta)1e 4.1.1 l

2) Rod Block Same as for ressective instru- I mentation in Ta)1e 4.1.1

3) DELETED DELETED

)

4) Automatic _DfEECMutilAl10n, Each refueling outage each trip system, one at a time

5) MSlY Closure, each closure Each refueling outage i logic circuit independently I (1 valve at a time) j

6) Core Spru , 1/3 mo. and each refueling  !

each trip system, one at a time outage.

7) frimary Containment Isolation each Each refueling outage closure circuit independently i

(1 valve at a time)

8) Refuelina Interlocks Prior to each refueling operation

9) Isolation Condenser Actuation Each refueling outage and Isolation, each trip circuit independently (1 valve at a time) ,

10) Reactor Buildina Isolation Same as for respective and SGTS Initiation instrumentation in Table 4.1.1

11) Condenser Vacuum Pump Isolation Prior to each startup

12) Air E.iector Offaas Line Isolation Each refueling outage

13) Containment Vent and Purge Isolation 1/20 mo, i

OfSTER CREEK 4.1-9 Amendment No.: 108, 116, 144

r

, *C. (na111 ment Coniing_1yitem lita fitQUfRC.Y

2. Motor operated valve operability Every 3 months

3. Pum) compartment water. Once/ week and after each entry tigit doors closed D. Emeraency Service Water $_vits

1. Pump Operability Once/ month. Also after major maintenance and prior to startup following a refueling outage.

E. Control Rod Drive Hydraulic

$Ystem

1. Pump Operability Once/ month. Also after mcjor maintenance and prior to startup following a refueling outage,

f. Fire protection Sys.tm

1. Pump and Isolation Once/ month. Also after major valve operability maintenance and prior to startup following a refueling outage, hai:

it is during major maintenance or repair that a system's design intent may be violated accidentally. Therefore, a functional test is required after every major maintenance operation. During an extended outage, such as a refueling outage, major repair and maintenance may be performed on many systems. To be sure that these repairs on other systems do not encroach unintentionally on critical standby cooling systems, they should be given a functional test prior to startup.

Motor o)erated pumps, valves and other active devices that are normally on standby should se exercised periodically to make sure that they are free to operate.

Motors on pumps should operate long enough to approach equilibrium temperature to ensure there is no overheat problem. Whenever practical, valves should be stroked full length to ensure that nothing impedes their motion. Engineering judgment based on experience and availability analyses of the type presented in Appendix L of the FUSAR indicates that testing these components more often than once a month over a long period of time does not significantly improve the system reliability.

Also, at this frequency of testing wearout should not be a problem through the life of the plant.

During tests of the electromatic relief valves, steam from the reactor vessel will be discharged directly to the absorption chamber pool. Scheduling the tests in conjunction with the refueling outage permits tho tests to be run at low power, prior to 5 percent power, enhancing the safety of the plant by assuring EMRV operability before higher power levels are reached.

0YSTER CREEK 4.4-2 Amendment No.: 109