ML20069F201
| ML20069F201 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 03/16/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8303220354 | |
| Download: ML20069F201 (2) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II y
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U.S. Nuclear Regulatory Commission
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Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 P
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNIT 1 - INCORRECT THERMAL DATA IN PROBLEM N4-1RK-A FROM PROGRAM "EZ" - BLRD-50-438/83 FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Linda Watson on February 16, 1983 in accordance with 10 CFR 50.55(e) as NCR BLN CEB 8303 Enclosed is our first interim report. We expect to submit our next report by April 19, 1984.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY O
l' L. M. Mil "s, nager Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
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l i OFFICIAL COPY A-8303220354 830316 PDR ADOCK 05000438
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PDR An Equal Opportunity Employer
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNIT 1 INCORRECT THERMAL DATA IN PROBLEM N4-1RK-A FROM PROGRAM "EZ" NCR BLN CEB 8303 BLRD-50-438/83-22 10 CFR 50.55(e)
FIRST INTERIM REPORT Description of Deficiency Analysis problem N4-1RK nas not been qualified for the thermal loading condition on essential air compressor system piping supports. In reviewing the issued analysis problem for Design Change Request (DCR) 2372, the results were found to be wrong due to the input of incorrect thermal data. This was a result of using an unverified program "EZ" and a lack of verification procedures for the "EZ" program in generating the input data.
Interim Progress An in-depth study has been made into the deficiency. The thermal data which was input through the use of the "EZ" computer program has been hypothesized as being a thermal condition that could occur, but has not been documented.
Because of the reviewer's unfamiliarity with the "EZ" computer program and lack of specific verification procedures for this program, the condition was not identified by the reviewer. If the hypothesized thermal condition can be documented as correct and the analysis rerun using the TPIPE computer program, it is believed that the resulting support design loads will be in reasonable agreement with the previously issued support design loads.
It is also believed that the pipe stress will be acceptable after the new resulting thermal range load case has been analyzed. The load case documentation and analysis rerun on TPIPE (which will include the thermal range evaluation) will be done to verify the "EZ" program. The "EZ" computer program is not known to be used on any other Bellefonte problem or problems for other TVA nuclear plant and will not be used for future analysis and therefore, no verification procedures development is needed.
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