LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys

Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys

ML20056F411
Person / Time
Site:	Fort Calhoun
Issue date:	08/20/1993
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20056F402	List: LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20056F401 ML20056F407
References
REF-GTECI-A-02, REF-GTECI-RV, TASK-A-02, TASK-A-2, TASK-OR LIC-93-0228, LIC-93-228, NUDOCS 9308270151
Download: ML20056F411 (3)

Text

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U.S. Nuclear Regulatory Commission LIC-93-0228 ATTACHMENT A I

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9308270252 DR 93082o T p ADocK 05000288 PDR d[? --- __

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j 2.0 LIMITING CONDITIONS FOR OPERATION '

2.1 Reactor Coolant System (Continued)

I 2.1.4 Reactor Coolant System Leakage Limits Acolicability  ;

I Applies to the leakage rates of the reactor coolant system when&EFithbtf6Et5i

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Rbjwtive To specify limiting conditions of the reactor coolant system leakage rates. .

Soecifications l

To assure safe reactor operation, the following limiting conditions of the reactor  :

coolant system leakage rates must be met:

l (1) If the reactor coolant system leakage exceeds 1 gpm and the source of -l leakage is not identified within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the reactor shall be placed in the j hot shutdown condition. If the source leakage exceeds 1 gpm and is not identified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown condition.

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j (2) Ifleakage exceeds 10 gpm, the reactor shall be placed in the hot shutdown l

! condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the leakage exceeds 10 gpm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the '

reactor shall be placed in the cold shutdown condition.

4 (3) Primary-to-secondary leakage through the steam generator tubes shall be limited to I gpm total for both steam generators. When primary-to-secondary leakage has been determined to be in excess of the limit, the leakage rate shall be reduced to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall t be placed in the cold shutdown condition within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

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, (4) To determine leakage to the containment, one of the following must be operable at a!! times:

a. Containment Dew Point Instrument A_thi6_s'p_hsrE_Psiti6uldtE_Rsd_istl6._6

. b. donsinment AihibiphsfelGa55605 Radiation Monitor

c. Containment $id5hEEY5stf3i5hnt d IfTiiEithif76fTths[a66feEi65tidnisiiti"liTbpeisble{th~edTiiiitisfb'li6iiily recording of the CVCS Volume Control Tank Inventory Instrumeatievelland ~ ~

restore one of ths in, sti 2d,i. ens.Tt6Toperabls statds Withiff 30' days.

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2.0 LBffTING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.4 Reactor Coolant System Leakage Limits Aonlicability Applies to the leakage rates of the reactor coolant system whenever the reactor  !

coolant temperature is greater than 210 F.

Obiective To specify limiting conditions of the reactor coolant system leakage rates.

Specifications -

To assure safe reactor operation, the following limiting conditions of the reactor coolant system leakage rates must be met: ,

t (1) If the reactor coolant system leakage exceeds I gpm and the source of leakage is not identified within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the reactor shall be placed in the .

hot shutdown condition. If the source leakage exceeds 1 gpm and is not  !

identified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown  ;

condition.  !

4 (2) If leakage exceeds 10 gpm, the reactor shall be placed in the hot shutdown  !

condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the leakage exceeds 10 gpm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown condition. *

(3) Primary-to-secondary leakage through the steam generator tubes shall be  !

limited to 1 gpm total for both steam generators. When primary-to- l secondary leakage has been determined to be in excess of the limit, the leakage rate shall be reduced to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be placed in the cold shutdown condition within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. i (4) To determine leakage to the containment, one of the following must be l operable: I

a. Containment Atmosphere Particulate Radiation Monitor

b. Containment Atmosphere Gaseous Radiation Monitor If neither of the above instruments is operable, then initiate hourly recording of the CVCS Volume Control Tank level and restore one of the instruments to operable status within 30 days.

2-11 Amendment No. M j i

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