ML20039D898
| ML20039D898 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte |
| Issue date: | 12/22/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8201060322 | |
| Download: ML20039D898 (2) | |
Text
6 TENg'A'ernt:
E VALLEY. AUTHORITY
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400 Chestnut' Street Tower II SI DEC30 0,* $4bember 22, 1981 BLRD-50-438/81-76 BLRD-50-439/81-75 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - VIKING FLOW CONTROL VALVES IN FIRE PROTECTION SYSTEM - BLRD-50-438/81-76, BLRD-50-439/81 FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on November 24, 1981 in accordance with 10 CFR 50.55(e) as i
NCR BLN MEB 8103 Enclosed is our first _ interim report. We expect to submit our next report by March 3, 1982. We consider 10 CFR Part 21 to be applicable to this deficiency.
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 L. M. Mills, ager Nuclear Regulation and Safety Enclosure co ec:
Mr. Richard C. DeYoung, Director (Enclosure)
F Cb Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 VIKING FLOW CONTROL VALVES IN FIRE PROTECTION SYSTEM 10 CFR 50.55(e)
BLRD-50-438/81-76, BLRD-50-439/81-75 FIRST INTERIM REPORT Description of Deficiency The Viking model G-1 and G-2 flow control valves manufactured by Viking Corporation of Hastings, Michigan, are used in the Fire Protection System throughout the plant. The valves will not regulate outlet pressure as required by Preoperational Test RFT-8 acceptance criteria. The valves cause severe system vibrations when attempts are made to operate the valves under the high inlet pressure and low flow conditions established by the Preoperational Test.
Interin Progress TVA is evaluating the deficiency to determine the root cause of the deficiency and the appropriate corrective action. TVA is also investigating the application of Viking valves at all other TVA nuclear plants to determine if a similar problem exists at these plants..
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