ML20083F494

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Final Deficiency Rept NCR 1887 Re Lakeside Bridge & Steel Deficient Steam Generator Support Bolts.Initially Reported on 820723.Field Change Request M-3045 to Require Preload of 50% Ultimate Load Prepared
ML20083F494
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 12/21/1983
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, NCR-1887, NUDOCS 8401030101
Download: ML20083F494 (2)


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" TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374ot 400 Chestnut Street Tower II

-,3 ag: 45 I-December 21, 1983 BLRD-50-438/82-48 BLRD-50-439/82-43 U.S. Nuclear Regulatory Commission Region II Attn:

Mr. James P. O'Reilly, Regional Administrator

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101 Marietta Street, NW Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - DEFICIENT STEAM GENERATOR SUPPORT BOLTS - BLRD-50-438/82-48, BLRD-50-439/82 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on July 23, 1982 in accordance with 10 CFR 50.55(e) as NCR 1887. This was followed by our interim reports dated August 19 and December 21, 1982 and March 29 and August 5, 1983 Enclosed is our final report.

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, Manager Nuclear Licensing Enclosure oc (Enclosure):

Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8401030101 831221 PDR ADOCK 05000 S

M'>,o u

]d2 7 1983-TVA SOTH ANNIVERSARY

- An Equal Opportunity Employer

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ENCLOSURE BELLEFONTS NUCLEAR PLANT UNITS 1 AND 2 DEFICIENT STEAM GENERATOR SUPPORT BOLTS NCR 1887 BLRD-50-438182-48, BLRD-50-439/82-43 10 CFR 50.55(e)

FINAL REPORT Description of Deficiency Several two-inch diameter bolts manufactured from SA 540 GR B24 material by Lakeside Bridge and Steel which are used in the upper steam generator restraints appear to be deficient. The deficiency involves loss of ~ tension in the bolts after they were torqued to 65 percent of their ultimate strength. The bolts are in metal to metal joints. The loss of tension was discovered during reinspection of the bolts. The root cause of the tension loss was improper torquing technique in that TVA's Division of Construction (CONST) was tightening the bolts to 100 percent by a one-pass method.

Safety Implications Failure of the restraint bolts would result in possible movement of the steam generator which could damage safety-related piping that is adjacent to the steam generator. Damage to the reactor coolant or other adjacent piping could adversely affect safe operation of the plant.

Corrective Action To prevent recurrence of this deficiency, field change request No. M-3045 has been prepared to add a note to drawing 1RB0430-X2-01 R1 requiring a preload of 50 percent of ultimate or larger on high strength bolts and a two-pass method for torquing (the first tightening pass at 70 percent of required value and the second tightening pass to be at 100 percent of required value).

To e1sure that all of the upper steam generator restraint bolts are properly torqued CONST is preparing a sequence control chart (SCC) that will show the two-pass method for torquing. Remaining corrective actions including adding the note to drawing 1RB0430-X2-01 R1, preparation of the SCC, and required retorquing of these bolts using the two-pass method will be completed by July 9, 1984.

There are no generic implications for this NCR for other TVA plants due to the differences in bolting procedures, bolting material, and various types of supports used. Other bolting issues are covered under individual NCRs as they are identified. Specifically, no other occurrences of this type of deficiency have been identified at Belle fonte. Both Watts Bar and Sequoyah plants tighten the subject bolts to a snug condition (no torquing is involved). At Yellow Creek (YCN), no bolting material of this specification (SA 54) has been installed.

Instead, the upper steam generator supports at YCN are to be made up of snubbers, levers, links, pins, and embedments.

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