ML20072N004

Second Interim Deficiency Rept Re Relief Valves Violating ASME Code on Use of Stop Valves Between Relief Device & Equipment Being Protected.Initially Reported on 821223. Analysis & Design Drawing Revs Underway.Next Rept by 841102

ML20072N004
Person / Time
Site:	Bellefonte
Issue date:	07/05/1983
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 8307150166
Download: ML20072N004 (2)

Text

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Street Tower II g3Jtit12 July 5, 1983 BLRD-50-438/83-07 BLRD-50-439/83-04 U.S. Nuclear Regulatory Comission Region II Attn:

Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

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 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector L. Watson on December 23, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8236. This was followed by an interim report on January 21, 1983 Enclosed is our second interim report. We expect to submit our next report by November 2, 1984.

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, thnager Nuclear Licensing Enclosure cc:

Mr. Richard C. DeYoung, Director (Enclosure)

Office of Inspection 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 q

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Atlanta, Georgia 30339 8307150166 830705 PDR ADOCK 05000438

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1983-TVA SOTH ANNIVERSARY

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ENCLOSURE 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 SECOND INTERIM REPORT i

Descriotion 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 l

TVA is relocating the relief valve supply line connection to a location between the stop valves and the seal area coolers on the component cooling water return from the seal area coolers.

The design criteria diagram has been issued with approval obtained from d

TVA's Nuclear Engineering Support Branch. Unit 1 and unit 2 physical piping drawings will be issued by July 1,1983, and September 1,1983, respectively. The support analysis and the hanger designs will be completed by April 1,1984, for unit 1 and September 1,1984, for unit 2.

TVA will provide a final report when the analysis and design drawing revisions are complete.

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