ML20008F853

Part 21 Rept Re C-E Failure to Implement Design Criteria for Seal Welding to Anchor Bolt,Initially Reported 810401. Channel Will Be Machined Between Bolt Locations & Liner Seal Weld.Next Rept by 810804

ML20008F853
Person / Time
Site:	Yellow Creek
Issue date:	05/01/1981
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-81-417-000 10CFR-050.55E, 10CFR-50.55E, PT21-81-417, PT21-81-417-000, YCRD-50-566-81, YCRD-50-567-81, NUDOCS 8105120177
Download: ML20008F853 (4)

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400 t'..a tnut Street Tower II May 1, 1981 YCRD-50-566/81-12 YCRD-50-567/81-10 Mr. Jane P. O'Reilly, Director Office of napection and Enforcement U.S. Nuclea Regulatory Constission Region II - -ite 3100 101 Marietta t

Atlanta, Georgia 30303

Dear Mr. O'Reilly:

YELLOW CREEK NUCLEAR PLANT UNITS 1 AND 2 - COMBUSTION ENGINEERING FAILURE TO IMPI2ME!E DESIGN CRITERIA - YCRD-50-566/81-12, YCRD-50-567/81 FIRST INTERIM REPORT Tha subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on April 1, 1981, in accordance with 10 CFR 50.55(e) as NCR YCN YCP 8103 Enclosed is our first interim report.

We expect to submit our next report by August 4,1981. We consider 10 CFR Part 21 to be applicabla to this deficiency.

If you have any questions concerning this mtter, ple.ase get in touch with D. L. Lambert at ETS 857-2581.

Very trulv yours, TENNESSEE VALLEY AUTHORITY i

L. M. Mills, Manager Nuclear Regulation and Safety l

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Mr. Victor Stello, Jr., Director (Enclosure) l Office of Inspection t.nd Enforcement U.S. Nuclear Regulatory Commission i

Washington, DC 20555 1

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An Equal Opportunity Em.p' oyer

ENCLOSURE YELLOW CREEK NUCLEAR PLANT UNITS 1 AND 2 COMBUSTION ENGINEERING: FAILURE TO IMPLEMENT

' DESIGN CRITERIA YCRP-50-566/81-12, YCED-50-567/81-10 10 CFR 50.55(e)

FIRST INTERIM REPORT Description of Deficiency While construction employees at the site were preparing to install the spent fuel rack embedment anchor bolts, they discovered that Combustion Engineering's (CE's) design would not adequately prevent leakage of spent fuel pool water past the embedment ancher bolt nut and washer because the design does not allow seal welding to the anchor bolt (see figure 1).

The potential leakage path presented by the embedment design violates the NRC Regulatory Guide (RG) 1.13 recommendations, of which CE is cognizant. TVA design criteria are also violated in that if leakage were to occur, no means are available for early detection and quantification of the leakage other than by a lowering in the pool level. TVA's review should have determined the violation of TVA design criteria since CE is not cognizant of requirements specific to TVA design criteria. The spent fuel pool embedments were designed and cupplied by CE.

Interim Progress CE and TVA have jointly developed a recommended design to alleviate the deficiency in design of the spent fuel rack embedments. The proposed design calls for countersinking the embedment bolt and nut into the embedded plate and machining the top of the bolt to be flush with or lower than the top surface of the embedded plate, so that the liner plate can be lapped over the bolts and seal welded to the embedded plate (see figure 2). To meet TVA's design criteria for leakage detection, a channel will be

=achined between the bolt locations and the liner seal weld around the entire embeddec plate. This channel will be routed off the side of the plate into the leakage channel system beneath the pool liner.

CE is now in the process of revising the design drawings to incorporate the design. The modification to the embedded plates will be completed before installation o'r the plates.

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