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Interim Deficiency Rept Giving Status of Corrective Action Re Broken Anchor Bolts in Unit 1 Reactor Vessel Support Skirt Flange.Next Rept Will Be Sent by 800501.Bechtel Interim Rept Encl
	ML19294C267
Person / Time
Site:	Midland
Issue date:	03/03/1980
From:	Howell S; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML19294C268	List: ML19294C267; ML19294C269;
References
	HOWE-51-80, NUDOCS 8003070395
	Download: ML19294C267 (6)
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C011SumerS W fi l POWBf {Q gl Stephen H. Howell Senior Vice PresLient General Offices: 1945 West Parnell Road, Jackson. Michigan 49201 * (517) 788 4 453 March 3, 1980 Hove-51-80 Mr J G Keppler, Regicnal Director Office of Inspection and Enforcement US Nuclear Regulatcry Con =issicn Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND NUCLEAR PLANT UNIT NO 1, DOCKET NO 50-329 UNIT NO 2, DOCKET No 50-330 UNIT No 1, REACTCR VESSEL BROKEN ANCHOR EOLT

References:

Letter, S H McVell to J G Keppler; Midland Nuclear Plant; Unit No 1, Decket No 50-329; Unit No 2, Decket no 50-330; Unit No 1 Reactor Ve::sel Broken Ancher Bolt; s

1) Ecve-311-79; dated Dece=ber ik, 1979

2) Howe-267-79; dated October 12, 1979

           'Jhis letter, as were the referenced letters, is an interi: 50.55(e) re;crt cencerning broken enchor bolts in the Unit 1 reacter vessel support skirt flange. The enc 1csure to this letter prcvides a status of the actions being taken to resolve this conditien.

Another report, either interin or final, vill be sent on er before May 1, 1980.

h a- $ WRB/lr.

Enclosure:

Broken Reactor Vessel Anchor Bolt in Unit 1 Status Report, MCAR-37, Interin Repcrt #1, dated February 20, 1980. CC: Director of Office of Inspecticn & Enforcement Att Mr Victer Stello, USNRC (15)

                                                                                                             $0/f tor, Office of Management                                                         b Infon::atica & Prcgram Centrc1, USNRC (1)
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8003070 39

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Bechtel Assoc.i,a tes ProfessionalCorporation

SUBJECT:

MCAR 37-(issued 12/28/79) Broken Reactor Vessel Anchor Stud in Unit ! II:T.ERIM RIPORT 1-DATE: February 20, 1980 PROJBCT: Consumtrs Power Company Hidland Plant Units 1 & 2 Bechtel Job 7220 Discrepancy . The discrepancies discussed in this report are the failed reactor vessel anchor studs in Unit 1. Status Reports 1 and 2'*o'n the first failed stud are contained as . attach =ent to this report. Ba ck ground The anchor studs in question are 2-1/2 inches in nc=inal diaceter and 7 feet 4 inches long, embedded vertically in the reinforced concrete reactor vessel pedestal (Figure 1). There The is a total of 96 studs per studs extend approximately reactor vessel as shown in Figure 2. 15 inches out of the concrete to bolt the reactor vessel skirt flange All the studs were purchased to a to the foundation structure. The modified version of ASTM A 354-66, Crade BD standards by Bechtel. modification was a vaiver of Each thestud maxicum dia=etertoallowed was preloaded an initialin the 1966 version for Grade BD bolts. nominal stress of 75 ksi in the shank region (A = 4.9 squarc inches effective except where the shank diameter was reduced to the equivalent Design thread area) before relaxation losses are taken into account. calculations indicate that the prestress force should have been co=puted on the basis of effective tensile area (A - 4.0 square inches)., Th4 result was a higher than planned preload (92 ksi versus 75 ksi), but-the resultant stresses remained well under the design allowable stress of the mater'ial.which is 105 ksi. The anchor studs were purchased from Mississippi Valley Structural Steel (HVSS) of St. Louis, Missouri. All material for the Unit 1 failed _ studs was supplied from Bethlehem Steel, fabricated by Southern Bolt and

Fastener (SB&F) of Shreveport, Louisiana, and heat treated by J.W. Rex of Lansdale, Pennsylvania. These studs were received on site by Bechtel in early 1976, embedded in April 1977 by Bechtel, and tensioned in late July 1979 by Babcock & Wilcox Construction Company (B&W CC), subcontractor to Bechtel, as part of its responsibility for installation of the nuclear steam supply 14, 1979. system. The failure of the first stud was discovered on Septemb~er 20, 1979, Failure of the second and third studs was reported on December and February 5,1980, respectively. The locations it of these studs are is presently believed shown in Figure 2. Based on an ultrasonic test,

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1 Bechtel Associates Professional Corporation

MCAR 37 . - - . Interim Report 1 Page 2 the third stud failed in the lower portion of the shank or in the lower threaded area. This stud will not be recoved until the Unit I studs are detensioned. Investigative Action

Records pertinent to the purchase of the reactor vessel anchor Unresolved studs have been reviewed by Eechtel and Consucers Power Co pany. - questions from this review were sent to the vendor for clarification and a meeting subsequently took place on February 14, 1980, Review in Shreveport, of records Louisiana ydth MVSS, SB&F, Bechtel, CPCo, and the NRC. f or other structures on the Midland project utilizing high-strength, low-alloy steel bolting caterial is currently underway pending deter =ination of the root cause of the failures. Bechtel has contracted with Teledyne Engineering Services of Waltha=, Massachusetts to conduct a failure rechaniss investigation. This investi-gation has, to date, included laboratory testing of the broken portions of the first two failed studs and field hardness testing of all re=aining reactor vessel enchor studs. The report from this investigation is attached. The tensioning procedure prepared by E&W CC has been reviewed bylevel, Bechtel and no inconsistency, other than the previously mentioned prestress

has been identified. Preventive Action Preliminary analysis of the test data indicates that theAll studs were the anchor rendered susceptible to failure by excessive hardness. dtuds for the Unit 1 reactor vessel Vill be detensioned to prevent The any further breakage of studs, taking due care for personnel safety. pretension of the studs in Unit 2 will be lowered to the intended design value of 75 ksi on the effective tensile stress area of 4.0 square inches. The actual tension in the studs will be deter =ined by lift-off force

           . during detensioning.                                                                            .

Corrective Action Possible corrective action is currently being evaluated. Safety Implications _ This deficiency, if uncorrected, could adversely affect the safety of operations of the Midland plant at any ti=e throughout the expected life of the plant.

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  . .-       Bechtel Associates Professional Corporation                               . .

.' 11 CAR 37 , Interim Report 1 - Page 3 - - -

Reportability This condition was reported by CPCo to the NRC under 10 CFR 50.55(e) on September 14, 1979. Submitted by: b.d b/ Ak 4 j 4

                     '                               Approved b,.  [I h d,n h @ crts
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Concurrence by: [ ,,,, ,. EH/bjm Attachments: Status Reports 1 and 2(*)

       "CPCO NOTE:

The informaticn in these repcrts was ir cluded in the interim 50 55(e) reporto provided by letters Ecve-267-79 and Hove-311-79 Therefore, they have not been included in thic intex im 50 55(e) report.

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ML19294C267

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