ML20003D681
| ML20003D681 | |
| Person / Time | |
|---|---|
| Site: | Hartsville, Phipps Bend  |
| Issue date: | 03/20/1981 |
| 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 8103300333 | |
| Download: ML20003D681 (2) | |
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TENNESSEE VALLEY AUTHORITY j
CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II March 20, 1981 9 :'i.g HTRD-50-518
-519, -520, -521/81-02 ps PBRD-50-553, -554/81-02 Q'
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Mr. James P. O'Reilly, Director Office of Inspecticn and Enforcemen:
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101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - REPORTABLE DEFICIENCY -
PRESSURE DROP IN ESSENTIAL SERVICE WATER PIPING - H*RD-50-518,
-519, -520, -521/81 PSRD-50-553, -554/81-02 The subject deficiency was initially reported to NRC-0IE, Region II, Inspector R. W. Wright on December 10, 1980, as NCR's HTAMEE8001, HTEME38001, and PENMEE8001. The first' interim report was submitted on January 12, 1981.
In compliance with paragraph 50.55(e) of 10 CFR Part 50, we are enclosing the second interim report on the subject deficiency. TVA anticipates transmitting the final report on or before June 30, 1981.
If you have any questions, please call Jim Domer at FTS 857-2014.
Very truly yours, TENNESSEE VALLEY AUTHORITY q
L. M. Mills,..anager Nuclear Regulation and Safety Enclesure cc:
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ce o Anspection and Enforcement U.S. Nuclear Regulatory Commission Washington,.DC 20555 l
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bI f81033 00333 An Ecuat Occortunity E-::tover
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ENCLOSURE HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS PRESSURE DROP IN ESSENTIAL SERVICE WATER PIPING
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10CFR50 55(e) REPORT NO. 2 (SUPPLEMENTAL INTERIM)
NCR'S HTAME38001, HTBMEB8001, AND PSNMEB8001 On December 10, 1980, TVA informed NRC-0IE Region II, Inspector R. W.
Wright, of a reportable condition regarding potential excessive pressure drop in Essential Service Water (ESW) System raw water piping at the Hartsville and Phipps Send Nuclear Plants. This is the second report on the-subject reportable condition. The final report will be provided~on or before June 30, 1981.
Interim.P rogress ESW System, Division I and II, have been reanalyzed based on the final pressure drop criteria and have also been found to have deficiencies.
(These deficiencies are-being handled as part of the subject NCR's.)
A study is being conducted to determine the best way to resolve these deficiencies.
In addition to increasing the size of the carbon steel piping,.other alternatives being considered include lining the carbon
. steel with cement mortar and changing the pipe material to stainless steel, concrete pressure, or fiberglass-reinforced plastic. We expect to complete this study.and present our resolution of this '.ssue in the final report which will be submitted on or before June 30, 1981.
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