ML20141D968

Forwards Jm Farley Unit Alternate Plugging Criteria Return to Power Rept, Per Telcons Held to Discuss Results of Current SG Insp at Unit 1

ML20141D968
Person / Time
Site:	Farley
Issue date:	05/13/1997
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20141D970	List: ML20141D968 ML20141D972
References
GL-95-05, GL-95-5, NUDOCS 9705200252
Download: ML20141D968 (3)

Text

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• D:v2 Morry Southern Nuclxt Mce Presdent Operating Company  ;

f arley Project P0 Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131

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f May 13,1997 SOUTHERN h 4 COMFANY Docket No.: 50-348 Energy ro Smre YourblP  ;

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i Washington, DC 20555 t

Joseph M. Farley Nuclear Plant - Unit 1 Alterste Repair Criteria (ARC) for ODSCC at Tube Support Plate Intersections i Ladies and Gentlemen:

Two conference calls have been held to discuss the results of the current steam generator inspection at Farley Unit 1. During the last conference call, the NRC Staff (Mr. Ted Sullivan) requested that we provide as-found inspection results and growth rate information for the tube  ;

support plate intersections. That information is provided in Enclosure 1. ,

In the last conference call, a preliminary probability of burst calculation was reported as slightly 4

exceeding the 1 x 10 limit of Technical Speci6 cation 4.4.6.5.d.5. That preliminary calculation was based only on the inspection of tube support plate intersections. Subsequent to that calculation, additional tubes which required repair or plugging as a result of degradation in other locations resulted in removing some tubes with tube support plate degradation from 4

service. Consequently, the latest calculation results in a probability of burst of 9.6 x 10 which is less than the technical speci6 cation limit; therefore, no safety assessment is required.

Ilowever, due to the interest in the results of this steam generator inspection, an assessment is provided with the data of Enclosure 1. The latest calculation should also be considered as preliminary; however, the results of calculations for probability of burst and steam line break leakage would not be expected to increase. Additional decreases are possible if additional tubes are removed from service.

It should be noted that the projected steam line break leakage for the next operating cycle is .

15.6 gpm. This exceeds the current limit of i 1.4 gpm. However, a technical specification amendment to reduce the technical specification dose equivalent iodine limit is currently being reviewed by the NRC Staff and should be issued in the near future. This will result in increasing the steam line break leakage limit to 19 gpm. Consequently, both the steam line break leakage and probability of burst projections will satisfy the technical specification and Generic Letter 95-05 requirements for the upcoming cycle.

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9705200252 970513  :

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U.S. Nuclear Regulatory Commission Page 2 Tube R2C85 has been pulled from steam generator C. This tube contains the 13.7 volt

• indication at the first tube support plate intersection. The pulled tube will be shipped to Westinghouse for additional testing. Assuming the results of the testing are consistent with the current database, the results will be reported in the 90-day report for the alternate repair criteria. If the testing provides unexpected, non-conservative results, the NRC Staff will be notified on completion of the testing.

If you have any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY b ht#W Dave Morey REM / cit:TUBPULL DOC

Enclosure:

1. J. M. Farley Nuclear Plant - Unit 1 Alternate Plugging Criteria Return to Power Report cc: Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector Mr, T. A. Reed, NRR - Materials and Chemical Engineering Branch Dr. D. E. Williamson, State Department of Public Health e

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-l; ENCLOSUREI Joseph M. Farley Nuclear Plant - Unit 1 ,

Alternate Plugging Criteria Return to Power Repoll I

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