ML030980820

Issuance of Amendment, Technical Specification Page

ML030980820
Person / Time
Site:	Perry
Issue date:	04/08/2003
From:	Sands S NRC/NRR/DLPM/LPD3
To:	FirstEnergy Nuclear Operating Co
Sands S, 415-3154, NRR/DLPM
Shared Package
ML030980732	List: ML030980820
References
TAC MB4695
Download: ML030980820 (1)

Text

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

- BN-TOP-1 methodology may be used for Type A tests.

- The corrections to NEI 94-01 which are identified on the Errata Sheet attached to the NEI letter. "Appendix J Workshop Questions and Answers." dated March 19. 1996 are considered an integral part of NEI 94-01.

- The containment isolation check valves in the Feedwater penetrations are tested per the Inservice Testing Program (Technical Specification 5.5.6).

- The provisions of NEI 94-01. Section 9.2.3 are revised to include the following exception: The first Type A test performed after the Type A test completed on July 1. 1994 shall be completed no later than June 29, 2009.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident is 6.40 psig. For conservatism Pa is defined as 7.80 psig.

The maximum allowable primary containment leakage rate, La, shall be 0.20% of primary containment air weight per day at the peak containment pressure (P.).

Leakage rate acceptance criteria are:

a. Primary containment leakage rate acceptance criterion is

< 1.0 L,. However, during the first unit startup following testing performed in accordance with this Program, the leakage rate acceptance criteria are < 0.6 La for the Type B and Type C tests, and s 0.75 La for the Type A tests:

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is

• 2.5 scfh when tested at Ž Pa.

2) For each door, leakage rate is s 2.5 scfh when the gap between the door seals is pressurized to 2 Pa.

The provisions of SR 3.0.3 are applicable to the Primary.

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.

(continued)

PERRY - UNIT 1 5.0-15a Amendment No. 126