ML20112F671
| ML20112F671 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 12/07/1984 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8501150467 | |
| Download: ML20112F671 (2) | |
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~ TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II 8tj g {g lpoember j7.1984 8
BLRD-50-438/84-57
- c. /
BLRD-50-439/84-53 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - INCORRECT RESPONSE SPECTRA IN ANALYSIS OF REACTOR BUILDING SPRAY PIPING - BLRD-50-438/84-57 AND BLRD-50-439/84 FIRST INTERIM REPORT The. subject deficiency was initially reported to NRC-0IE Inspector S. Weise on November 8,1984 in acoordance with 10 CFR 50.55(e) as NCR BLN CEB 8417. Enclosed is our nest interim report. We expect to submit our next report on e about July 19, 1985.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY
'J W. Hu
, !!anager L:zsensing nd pgulations Enclosure j
cc:
Mr. Richard C. -DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear, Regulatory Commission -
Washington, D.C.,
20555~
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Records Center (Enclosure)
' Institute of Nuclear Power Operations 1100 circle 75 Parkway,-Suite 1500
. Atlanta, Georgia 30339 f
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8501150467 841207 DR ADOCK 05000 e
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' An tEqual Opporcunity Employer 3g
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w ENCLOSURE
.BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 INCORRECT RESPONSE SPECTRA IN ANALYSIS OF REACTOR BUILDING SPRAY PIPING BLRD-50-438/84-57, BLRD-50-439/84-53 10 CFR 50.55(e)
NCR BLN CEB 8417 FIRST INTERIM REPORT Description of Deficiency In 1979, amplification factors to be applied to the seismic maponse spectra for the top (elevation 875 feet) of the cylindrical portion of the primary
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containment building at Bellefonte Nuclear Plant (BLN) were informally provided to TVA piping analysis personnel. These amplification factors wem used to determine the response spectra used in the analysis of the reactor building
' spray (NS). piping system. The maximum elevation for the NS piping is 886 feet.
The' amplification factors provided were used to determine the seismic maponse spectra for elevation 886 feet. However, the pipe supports for NS piping am attached to the containment dome at elevations as high as 890.2 feet. The response spectra at 890.2 feet is higher than the spectra at 886 feet.
Therefore, the incorrect response spectra were used in the analysis of the NS piping. This has msulted in support loads which are too low or which are unconservative. Subsequently, some NS piping support designs or installations could be inadequate.
Interim Progress TVA h'as generated the correct seismic response spectra for _ elevation 890.2 feet t
of the containment structure dome. These spectra have been provided to piping analysis personnel and will be used to manalyze the NS piping system for BLN.
The corrected seismic response spectra will also be included in a revision to the BLN seismic analysis mport.
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