ML20044F304

Proposed Tech Specs Sections 3.4.3.1 & 3.4.3.2 Re Generic Ltr 88-01,drywell Leak Detection Requirements

ML20044F304
Person / Time
Site:	Nine Mile Point
Issue date:	05/19/1993
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20044F302	List: ML20044F301 ML20044F304
References
GL-88-01, GL-88-1, NUDOCS 9305270308
Download: ML20044F304 (3)

Text

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1 1 i-FEACTOR COOLANT SYSTEM ,

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE  ;

LEAKAGE DETECTION SYSTEMS LIMITING CONDITIONS FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

a. The primary containment airbome particulate radioactivity monitoring system,

b. The primary containment airborne gaseous radioactivity monitoring system,

c. The drywell floor drain tank fill rate monitoring system, and

d. Drywell equipment drain tank fill rate monitoring system.

APPLICABILITY: OPERATIONAL CONDITIONS 1,2, and 3.

ACTION:

a. With the primary containment airborne particulate radioactivity monitoring system or the  :

primary containment airbome gaseous radioactivity monitoring system inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are I obtained and analyzed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; otherwise, be in at least HOT ,

SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With the drywell equipinent drain tank fill rate monitoring system inoperable, operation may continue fer up to 30 days provided that the drywell equipment drain tank fill rate is  ;

determined via attemate methods; otherwise, be in at least HOT SHUTDOWN within the -

next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With the drywell floor drain tank fill rate monitoring system' inoperable, operation may continue for up to 30 days provided that the drywell floor drain tank fill rate is determined via ,

alternate methods; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. With both drywell floor drain and the drywell equipment drain tank fill rate monitoring systems inoperable, restore either system to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the  :

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

i 9305270300 930519 PDR ADDCK 05000410

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NINE MILE POINT - UNIT 2 3/4 4 Amendmont No.

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i' REACTOR COOLANT SYSTEM BASES i RECIRCULATION SYSTEM f 3/4.4.1 (Continued) recirculation pump and recirculation nozzles. Sudden equalization of a temperature difference 2: 145 F between the reactor vessel bottom head coolant and the cootent in the upper region of >

the reactor vessel by increasing core flow rate would cause undue stress in the reactor vessel bottom head.

3/4.4.2 SAFETY / RELIEF VALVES The safety / relief valves operate during a postulated ADVS event to prevent the reactor coolant system from being pressurized above a design allowable value of 1375 psig in accordance with the ASME Code. A total of 16 OPERABLE safety / relief valves is required to limit local pressure at active components to within ASME 111 allowable design values (Service Level A). All other. 1 appropriate ASME Ill limits are also bounded by this requirement. Specified surveillance intervals t have been determined in accordance with GENE 770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected instrumentation Technical Specification," as approved by the NRC and documented in the SER (letter to R. D. Binz IV from C.

E. Rossi dated July 21,1992). .

The safety-relief valve lift settings will be demonstrated only during shutdown in accordance with the provisions of Specification 4.0.5.

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS ,

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These detection systems are consistent with the recommendations of RG 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

Generic Letter 88-01, Supplement 1, allows for alternate methods to determine drywell leakage when the normalleakage monitoring systems are inoperable.~ These afternate methods may be used for up to 30 days. The alternate methods given in the Generic Letter Supplement are to manually pump down the drain tank, or to measure the differences in tank level. Other methods, which meet the requirements of Regulatory Guide 1.45 for accuracy and inspectability, may also be used.

3/4.4.3.2. OPERATIONAL LEAXAGE The allowable leahga rates from the reactor coolant system have been based on the predicted and  ;

experimentally observed behavior of cracks in pipes. The background leakage normally expected to .

result from equipment design and the detection capability of the instrumentation for determining j

system leakage were also considered. The evidence obtained from experiments suggests that for i leakage somewh?: greater than that specified for UNIDENTIFIED LEAKAGE, the probability is small B3/4'4-3 N!NE MILE POINT- UNIT 2 AMENDMENT NO. 41

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REACTOR COOLANT SYSTEff i BASES 3/4.4.3.2 OPERATIONAL LEAKAGE (Continued) that the imperfection or crack associated with such leakage would grow rapidly. An UNIDENTIFIED LEAKAGE increase of > 2 gpm within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period indicates a i potential flaw in the Reactor Coolant Pressure Boundary and must be quickly evaluated to determine the source and extent of the leakage. The increase is measured relative to the steady state value; temporary changes in leakage rate as a result of transient conditions (e.g., startup) are not considered. As such, the 2 gpm increase limit is only applicable in MODE 1 when operating pressures and temperatures are established. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shut down to allow further investigation and corrective action.

The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity, thereby reducing the probability of gross valve failure and consequent intersystem LOCA. .

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NINE MILE POINT - UNIT 2 B3/4 4-3a AMENDMENT NO. 41 )

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