ML20108C195
| ML20108C195 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 11/01/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8411160422 | |
| Download: ML20108C195 (2) | |
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' TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II November 1, f9kI/ O Afg ?]
w BLRD-50-438/83-07 BLRD-50-439/83-04 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 - RELIEF VALVES VIOLATE ASME CODE
- BLRD-50-438/83-07, BLRD-50-439/83 THIRD INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector L. Watson on December 23, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8236. This was followed by our interim reports dated January 21 and July 5, 1983 Enclosed is our third interim report.
We expect to submit our next report on or about March 4,1986.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Enclosure cc:
Mr. Hichard C. DeYoung, Director (Enclosure)
Office of Inspectior, and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8411160422 841101 PDR ADOCK 05000 s
OFFICIAL COPY -
An Equal Opportunity Employer
V ENCLOSURE 6
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 RELIEF VALVES VIOLATE ASME CODE BLRD-50-438/83-07, BLRD-50-439/83-04 10 CFR 50.55(e)
NCR BLN BLP 8236 THIRD INTERIM REPORT Description of Deficiency Relief valves 1KC-and 2KC-VRFC-154, -183, -194, and -205 violate ASME Section III, division 1, section ND-3677.2 which prohibits the use of stop valves between a relief device and the equipment being protected. These drawings also disagree with the process and instrumentation diagram in the B&W system description for the component cooling water (CCW) system (15-4041000001-04). These relief valves protect the shell of the seal area cooler in the reactor pumps. This condition could have resulted in damage to the seal area coolers.
Interim Progress TVA has relocated each relief valve inlet line connection to a position between the stop valve and the seal area cooler on the CCW return piping.
The design criteria diagram and the pha sical piping drawings for units 1 and 2 have been issued. Pipe support analysis for the unit 1 revised routing has been completed. TVA will provide a final report upon completion of the analyses and design drawing revisions.
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