ML20028F375

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First Interim Deficiency Rept Re Relief Valves Violating ASME Code Section Iii,Div 1,Section ND-3677.2.Initially Reported on 821223.Condition Could Damage Seal Area Coolers. Condition Under Evaluation.Next Rept Expected by 830705
ML20028F375
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 01/21/1983
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 8302010300
Download: ML20028F375 (2)


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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II January 21, 1983.

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BLRD-50-439/83-04

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U.S. Nuclear Regulatory Commission p

Region II E3 Attn: Mr. James P. O'Reilly, Regional Administrator

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101 Marietta Street, Suite 3100 Atlanta, Oeorgia 30303 6

Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - RELIEF VALVES VIOLATE ASME CODE - BLRD-50-438/83-07, BLRD-50-439/83-04, - FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector L. Watson en December 23, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8236. Enclosed is our first interim report. We expect to submit our next report on or about July 5, 1983 If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.

Very truly yours, TENNESSEE VALLEY AUTHORITY

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s' M. Mills, Manager Nuclear Licensing Enclosure cc:

Mr. Richard C. DeYoung, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

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B302010300 830121 g g A7 PDR ADOCK 05000430 S

PDR An Equal Opportunity Employer

ENCLOSURE 1

BELLEFONTE NUCLEAR PLANT UNITS-1 AND 2 RELIEF VALVES VIOLATE ASME CODE 10 CFR 50.55(E)

BLRD-50-438/83-07, BLRD-50-439/83-04 NCR BLN BLP 8236 FIRST INTERIM REPORT D,escription of Deficiency Relief valves 1-KC-and 2KC-VRFC-15t 8

-1 3, -194, and -205 'TVA drawings 3BWO656-KC-02 and 3BWO656-KC-03) violate ASME Section III, aivision 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 relic' valves protect the shell of the seal area cooler in the reactor coolaat pumps. This condition could have resulted in damage to the seal area coolers.

Interim Progress TVA is evaluating the cited condition to determine the corrective action, root cause, and actions required to prevent recurrence. TVA will provide further input upon conclusion of this evaluation.

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