ML18029A538

Safety Evaluation Re Mark I Containment long-term Program Pool Dynamic Loads Review for Plant.Pool Dynamic Loads Meet Acceptance Criteria of NUREG-0661 or Alternative Criteria Acceptable

ML18029A538
Person / Time
Site:	Browns Ferry
Issue date:	05/06/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML18029A537	List: ML18029A536 ML18029A538 ML18029A539 ML18029A540
References
RTR-NUREG-0661, RTR-NUREG-661 NUDOCS 8505160214
Download: ML18029A538 (2)

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0 UNITED STATES 0O NUCLEAR REGULATORY COMMISSION Enclosure 1 I

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO MARK I CONTAINMENT LONG-TERN PROGRAM POOL DYNAMIC LOADS REVIEW TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 and 3 DOCKET NOS. 50-259, 50-260 AND 50-296

1. 0 INTRODUCTION In July 1980, the staff issued a report, NUREG-0661, "Safety Evaluation Report, Mark I Containment Long-Term Program," to address the NRC acceptance criteria for the Mark I containment Long-Term Program, which are intended to establish design basis loads that are appropriate for the anticipated life of each Mark I BWR facility, and to restore the originally intended design safety margins for each Mark I containment system.

Since the issuance of NUREG-0661, the Mark I owners submitted additional reports in which they provided additional justification for the adequacy of: ( 1) the data base for specifying torus wall pressure during condensa-tion oscillations; (2) the consideration given to asymmetric torus loading during condensation oscillations; and (3) the effect of fluid compressibility in the vent system on pool-swell loads. As a result of the staff's and its consultant's (Brookhaven National Laboratory) evaluation of these reports, Supplement 1 to NUREG-0661, dated August 1982, has been issued.

2.0 EVALUATION By letter dated January 3, 1984, as supplemented by submittals dated September 11, 1984 and January 25, 1985, Tennessee Valley Authority (TVA) submitted a Plant Unique Analysis Report (PUAR) on the pool dynamic loads for the Browns Ferry Nuclear Plant Mark I containment. This report provides a description of the specific application of the generic Mark I pool dynamic loads and methods for Browns Ferry Nuclear Plant and the plant unique loads used in assessing the capability of the containment and components to accommodate the pool dynamic loading phenomena. The Brookhaven National Laboratory (BNL) was contracted to review the PUAR for compliance with the staff's acceptance criteria and to evaluate the acceptability of any proposed alternative load specification.

A summary of the BNL review and status for each of the pool dynamic loads is presented in the attached report titled "Technical Evaluation of the Browns Ferry Nuclear Plant-Plant Unique Analysis Report." As indicated in the report, TVA has adopted all but a few of the generic criteria. For those few exceptions alternative criteria were proposed. The BNL evaluation 8505i60214 850506

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of these criteria is included in the attached report. Based on its review, the staff endorses the BNL evaluation and conclusion.

3.0 CONCLUSION

S The staff has completed an assessment of Browns Ferry Nuclear Plant against generic acceptance criteria contained in NUREG-0661 and its supplement, and has also reviewed those few areas where alternative criteria have been proposed. In addition, the staff has completed its review of those areas where additional information was relegated to the plant unique review. In each of these areas the staff has concluded that the pool dynamic loads utilized by TVA are conservative and, therefore, acceptable.

Principal Contributor: F. Eltawila Date: Hay 6, 1985

Attachment:

Technical Evaluation, dated September 1984, prepared by BNL