ML020920273

Technical Specification Page for Amends 193 and 185 for Catawba, Units 1 & 2

ML020920273
Person / Time
Site:	Catawba
Issue date:	04/01/2002
From:	NRC/NRR/DLPM
To:
References
Download: ML020920273 (1)

Text

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 14.68 psig. The containment design pressure is 15 psig.

The maximum allowable containment leakage rate, La, at P8 , shall be 0.3% of containment air weight per day.

Leakage Rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is < 1.0 La. During the first plant startup following testing in accordance with this program, the leakage rate acceptance criteria are __0.75 La for Type A tests and < 0.6 La for Type B and Type C tests.

b. Air lock testing acceptance criteria for the overall air lock leakage rate is

< 0.05 La when tested at > Pa. For each door, the leakage rate is < 0.01 La when tested at > 14.68 psig.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

5.5.3 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Containment Spray, Safety Injection, Chemical and Volume Control, and Nuclear Sampling. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.4 DELETED (continued)

Catawba Units 1 and 2 5.5-2 Amendment Nos. 193/185