ML20140B864
| ML20140B864 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 03/10/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8603250006 | |
| Download: ML20140B864 (3) | |
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4 TENNESSEE VALLEY ' AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 151B Lookout Place j [ Q Q d l'Okg f % u50 e
BLRD-50-438/83-07 BLHD-50-439/83-04 U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J. Helson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
BELLEFONTE HUCLEAR PLANT UNITS 1 AND 2 - RELIEF VALVES VIOLATE ASME CODE -
BLRD-4 3 8 / 83-O l, BLHD-50-439/83 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector L. Watson on December 23, 1982 in accordanco with 10 CFR 50.55(e) as UCR BLN BLP 8236.
This was followed by our interim reports dated January 21 July 5, 1983 and Hovember 1, 1984.
Enclosed is our final report.
If you have any questions, please get in touch eith R. H. Shell at FTS 858-2688.
Very truly yours,.
i.
TENNESSEE VALLEY AUTHORITY
. h. } W
- i. L. Gridley Manager of Licensing
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Enclosure cc:
Mr. James Taylor, Director (Enclosure) i Office of Inspection and EnforcetenL U.S. Nuclear Regulatory Commission Washington, D.C.
20S55 Records Center (Enclosure)
Institute of Nuclear Power Operations l
1100 Citcle /5 Parkway, Suite 1500 1
Atlanta, Georgia 30339 i
1 1
8603250006 860310 PDR ADOCK 05000438 i
S-PDR i
l I
An Equal Opportunity Empfoyer.
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 RELIEF VALVES VIOLATE ASME CODE BLRD-50-438/83- 0 7 AND BLHD-SO-439/83-04 NCR BLH BLp 8236 10 CFR 50.55(e)
FINAL REPORT Descrip_tjon of Deficiency Relief valves IKC-and 2KC-VHFC-154, -183, -194, and ~205 violate ASME Section III, Division 1, Section HD-36//.2, which prohibits the use of stop valves between a relief' device and the equip. Tent being protected. The decign drawings on which these valves are depicted also disagree with the process and instrumentation diagraa in the B&W cystem deceription (15-4041000001-04)for the component cooling water (KC) system.
Thece relief valves protect the shell of the ueal area caoler in the reactor pumps.
This condition could have reculted in damage to the seal area coolcrc and KC piping.
The cauce of thic deficiency was a lack of knowledge of the applicable code on the part of the desluner.
Thic deficiency could be generic; therefore, a generie review memorandum was initiated to alert the other TVA plant organizaLions to the concern.
Sa f ety_1;;p lica t ions If the subject reliot valves are inadvertently isolated from the seal area coolers and the cotor operated stop valvec upstream and devnstream of the seal area cooler are closed, the KC system could be overprecuurized due to a tube rupture in the ceal area cooler or by the thermal expansion of the isolated shellside water in conjunction with tubeside flow. Overpressurization could cauce a line break in the isolated portion of the KC piping or could damage the ceal area cooler. Therefore, if this condition had remained uncorrected, the cate operation of the plant could have been adversely affected.
Corrective Action Corrective action for this deficient condition consists of relocating the relief valvos upctreaa of the stop valves, placing them on the appropriate drawingc, and installing the change in the field.
The component cooling water system was reviewed to ensure the rect of the cyctem in in compliance with ASHE Code Section llI, Division 1, ND -J6 /7. 2.
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