ML18033A688

Proposed Tech Specs Re Thermal & Pressurization Limits, Structural Integrity & Design Fatigue Usage Evaluation

ML18033A688
Person / Time
Site:	Browns Ferry
Issue date:	03/24/1989
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18033A687	List: ML18033A686 ML18033A688
References
NUDOCS 8903300239
Download: ML18033A688 (1)

Text

Enc. 2-11 0 OF S G (cont'd)

In addition to the ISI and IST programs, the following BFN Technical Specifications also provide additional requirements for monitoring component aging and the cumulative effects of power operation over the life of the plant.

1. Techn cal S ecification 3 A - Thermal and Pressurization Limits Temperature and pressure changes during heatup, cooldown, and during inservice hydrostatic testing of the reactor pressure vessel are limited to protect against nonductile failure. These limits were established using the methods derived from Appendix G in Section III of the ASME Boiler and Pressure Vessel Code as required by 10 CFR 50 Appendix G. Reactor vessel irradiation specimens are removed and examined at specific intervals to determine changes in material properties. The results of the examinations are used to update the pressure and temperature limits.

2. Technical S ec fication G Structural Inte rit The ISI program for ASME Code Class 1, 2, and 3 components performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.

3. echnical S ecification 10 1 Desi n Fati ue Usa e Evaluation A fatigue usage evaluation is performed for the reactor pressure vessel. The following locations are monitored: the feedwater nozzles, the shell near the water line, and the flange studs.

Transients that occur during plant operation are reviewed and a cumulative fatigue usage factor for each location is determined.

The cumulative fatigue usage factors for each location are reported in the annual operating report. The worst cumulative usage factor experienced at BFNis less than 0.3 as of December 31, 1987. This is well below the technical specification limit of 1.0. When the cumulative usage factor reaches a value of 1.0, an inservice inspection is included for the specific location at the next scheduled inspection (3 and 1/3 year interval) and 3 and 1/3 year intervals thereafter. An evalua'tion is performed in accordance with the ASME Section XI Code if any flaw indications are detected and the results are submitted to NRC in a special report.

8903300239 890324 PDR ADOCK 05000259 P PDC