ML20041A733

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Fourth Interim Deficiency Rept Re Main Steam Valve Room a Pipe Anchor Support Loads,Initially Reported 810723.Vertical Stiffening Walls Designed to Increase R-line Wall Capacity to Hold Applied Pipe Anchor Loads.Next Rept by 820415
ML20041A733
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 02/09/1982
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 8202220449
Download: ML20041A733 (2)


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TENNESSEE VAUCEYicAtJTycglTY S3hE5-54,0)']

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U.S. Nuclear Regulatory Com:nission

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Region II Attn:

Mr. James P. O'Reilly, Regional Administrator N,s c.

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101 Marietta Street, Suite 3100 Y,,

Atlanta, Georgia 30303 N'N.o

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Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - MAIN STEAM VALVE ROOM A PIPE ANCHOR SUPPORT LOADS - BLRD-50-438/81-50, BLRD-50-439/81 FOURTH INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on July 23, 1981 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8120. This was followed by our interim reports dated August 18, October 6, and November 13, 1981. Enclosed is our fourth interim report. We expect to submit our next report by April 15, 1982.

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

, M. Mills, Manager Nuclear Regulation and Safety Enclosure ec:

Mr. Richard C. DeYoung, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

[f' MAL COgp b 17 O202220449 820209

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PDR ADOCK 05000438 S

PDR An Equal Opportunity Employer

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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 MAIN OTEAM VALVE ROOM A PIPE ANCHOR SUPPORT LOADS BLRD-50-438/81-50, BLRD-50-439/81-52 10 CFR 50.55(e)

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FOURTH INTERIM REPORT

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Description of Condition Two main steam pipe anchors and one feedwater pipe anchor '(6-way restraints) per unit are attached to the R-line wall in the A main steam valve rooms. The original design.of the R-line dall and roof slab was accomplished utilizing preliminary loads and preliminary anchor design concepts. ' The anchor design was completed and the actual anchor embedment loads determined. Although the-actual loads were significantly. higher than the preliminary design loads, the R-line wall and roof slabs were not reevaluated.

Interim Progress Vertical stiffening walls have been designed to increase the R-line wall capacity sufficient to withstand the applied pipe anchor loads.

Drawings detailing these walls have been released to Construction.

Additional checking is required for the A4 and All walls. This should be completed and additional information forwarded by our next report.

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