ML19257C142

Forwards Two Final Deficiency Repts Filed by Util W/Nrc

ML19257C142
Person / Time
Site:	Midland
Issue date:	01/07/1980
From:	Gibbs M ISHAM, LINCOLN & BEALE
To:	Cowan F, Linenberger G, Smith I Atomic Safety and Licensing Board Panel
References
NUDOCS 8001250030
Download: ML19257C142 (1)

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ISHAM, LINCOLN & BEALE COUNSELORS AT LAW l ONC FIRST NATIONAL PLAZA FORTV-SECONO FLOOR CNICAco,lLLINO'S 60603 TELEPHONC 312* SS8=7500 TELEM:2-SL88 WASMINGTON OFFICE j 8080 47L* SYNE ET, M. W.

SEVENTr0 FLOOR WA S M 6NOTON, D. C.2OO3 6 202-833 e730 January 7, 1980 Ivan W. Smith, Esq. Mr. Gustave A. Linenberger Atomic Safety and Licensing Board Atomic Safety and Licensing Bd. Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission t Washington, D.C. 20555 Washington, D.C. 20555 Dr. Frederick P. Cowan Apt. B-125 6152 North Verde Trail Boca Raton, Florida 33433 Re: Consumers Power Company o,L.L-- l hVe/

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(Midland Plant, Units 1 and 2) ,, g\

Docket Nos. 50-329, 50-330 Z c ,g C a ,9g, gy [y')4

-1 cc,e/.f s Gentlemen: CW

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Enclosed are two S 50.55 (e) final reports which %' ' ' ' Y -v $$ e WV 4 .

have recently been submitted by Consumers Power Company to '5; , ?

N 'l M the Nuclear Regulatory Commission.

Very truly yours, h

• IE Martha E. Gibbs MEG:cem cc: Service List w/ Enclosures 1829 331 8001250030

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Generet of fice,: 1M5 West Parnell Moed, Jackson. Michigar. =9201 e (51717884453 December 21, 1979 Hove-312-79

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Mr J G Keppler, Regional Director ',

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US Huclear Regulatory Ccemission - l 2 g.f'# -,

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. o MIDLAND NUCLEAR FIANT UNIT N0 1, DOCKET NG 50-329 hl }

UNIT NO 2, DOCKET NO 'i0-330 DROP-IN ANCHORS

References:

1) S H Hovell letter to J G Keppler; Midland Nuclear Plant; Unit No 1, Pocket No 50-329; Unit No 2, Docket No 50-330; Drop-In Anchors; Serial Hove-2k7-79; dated September 12,19*l9

2) S H Howell letter to J G Keppler; Milland Nucler.r Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; i

Drop-In Anchors; Serial Hove-265-79; dated October 12, 1979 l

The referenced letters were interim 50 55(e) rcports on the status of Hilti Drop-In Anchors which did not meet tension testin6 requirements. This letter in the final report in that the corrective actions to assure that each drop-in anchor is acceptable or replaced has been scheduled. Completion of these actions, which vill place the plant in ecnformance, is scheduled for June 1,1980. The use of drop-in anchors has leen dis ontf nued.

The attachment providcc a detailed discussion of the condition and the resolution.

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Attachnent: IIAR-3h, Drop-In Anchors, Final Report, dated November 30, 1979 f~

CC: Director of Office of Inspection & Enforecment / u /-[

Att: Mr Victor Stello, USNRC (15) c U ' .Qb

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Director, Office of Management @'

y[, \}) J Infor=ation, & Procram Control, USNRC (1)18 2'r $ 3 2

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2 Hove-312-T9 BCC: JLBacon, M-108SA -

RCBauman, Plk,h12 WRBird, JSC-216B JLCorley, Midland LHCurtis, Bechtel AA RBCherba, JSC-236A LADreisbach, Bechtel-Midland DE9ern, Midland GSKeeley, P1h-h08B BWMarguglio, JSC-220A DBMiller, Midland RLRixford, Bechtel AA JARutgers,'Bechtel AA -

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Bechtel Associates ProfessionalCorporation Attachment to Howe-312-79

SUBJECT:

HCAR 34 (issued 8/21/79) Drop-In Anchors  !";

. oso . or sr. .:r FINAL REPORT -

DATE: November 30, 1979 PROJECT: Consumers Power Company

, Midland Plant Units 1 & 2 Bechtel Job 7220 Introduction As requested in MCAR 34, this report summarizes project engineering's evaluation and action regarding the' failure of the drop-in anchors to meet the tension testing criteria furnished by project engineering.

This report completes project engineering's action.

Description of Deficiency Specification 7220-C-305, Section 6.2.2 requires tension testing of drop-in anchors to meet the value's indicated in Table 3.2 of that specification. Inprocess inspection of drop-in anchor installation is also required in Specification 7220-C-305. However, when it was learned, that this inspection at the time of installation was not being done at all times, testing was requested by project engineering on August 21, 1978, and again on May 18, 1979,~ to verify,the adequacy of past install;ttion.

For the testing results to be acceptable, it was necessary that a sample of 60 randomly selected anchors be tested with no failures. According to Specification 7220-C-305, the anchor is considered acceptable if a test load equal to twice the design allowable tensile load is applied and the concrete does not break out; the anchor does not break, distort, or deform; and the anchor does not slip excessively or become loose.

Excessive slippage is evident when the washer between the nut and the concrete can be rotated by hand. However, upon completing tension teste on 32 drop-in anchors involving four different bolt diameters, nine anchors did not pass the test. A nonconfer=ance report (NCR) has been generated to identify them. Approximately 900 drop-in anchors had been installed as of August 17, 1979, when project engineering requested that drop-in anchor installation be suspended until further notice. Subse-quently, the testing was completed and results indicated 13 out of 66 anchors did not meet the specification requirements. ,

~ Investigation To investigate the problem with the met with a representativ.e of Hilti, tha. Hidland site to witness testing the drop-in anchors. The Hilti rep DUPLICATE DOCUMENT procedure used is consistent with H

' Entire document previously entered into system under:g ANO No. of pages:

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