ML070220220

Issuance of Corrected Technical Specification Pages for Amendment Nos. 147 and 127

ML070220220
Person / Time
Site:	Vogtle
Issue date:	01/11/2007
From:	Martin R NRC/NRR/ADRO/DORL/LPLII-1
To:
Martin R, NRR/DORL, 415-1493
Shared Package
ML070080275	List: ML070080266 ML070220220
References
TAC MD1078, TAC MD1079
Download: ML070220220 (2)

Text

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Containment Leakage Rate Testing Program (continued) by ASME Section XI Code, Subsection IWL, except where relief or alternative has been authorized by the NRC. At the discretion of the licensee, the containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities such as tendon testing, or during a maintenance/refueling outage.

4. A one time exception to NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR 50, Appendix JX:

Section 9.2.3: The next Type A test, after the March 2002 test for Unit 1 and the March 1995 test for Unit 2, shall be performned Within 15-y-r-a-r.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, Pa, is 37 psig.

The maximum allowable containment leakage rate, La, at Pa, is 0.2% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criteria are _ 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are _<0.60 La for the combined Type B and Type C tests, and < 0.75 La for Type A tests;

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is < 0.05 La when tested at >_Pa,

2) For each door, the leakage rate is < 0.01 La when pressurized to

>- Pa.

The provisions of SIR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

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

(continued)

Vogtle Units 1 and 2 5.5-16 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Amendment Nos. 147, 127 Corrected by letter dated January 11, 20017

I I Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Deleted.

5.6.10 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9, Steam Ge-nerato-r-(SG)-Progra-m-.- The report shall -include:.

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing.

Vogtle Units 1 and 2 5.6-6 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Amendment Nos. 147, 127 Corrected by letter dated January 11, 2007