ML19331A946

Forwards Two Deficiency Repts Recently Submitted by Util. Related Correspondence

ML19331A946
Person / Time
Site:	Midland
Issue date:	10/23/1979
From:	Gibbs M ISHAM, LINCOLN & BEALE
To:	Cowan F, Linenberger G, Smith I Atomic Safety and Licensing Board Panel
References
NUDOCS 8007240534
Download: ML19331A946 (1)

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R%rp h7pg ISHAM, LINCOLN & BEALE COUNSELORS AT LAW ONC FIRST HAT NAL P ORTV-SCCONO FLOOR TELEPNONC 332-558-7500 TELEX: 2+S2 88 9 at WASH 4NGTON OFFICE 5

f sOSO 17tr STREET, N. W.

SCVCPe?N FLOOR October 23, 1979

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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 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 (Midland Plan At~ nits 1 and 2)

Docket Nos.-50-329, 5b 330 Gsntlemen:

Enclosed are two S 50.55(e) reports which have recently been submitted by Consumers Power Company to the Nuclear Regulatory Commission.

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Very Trulr yours '

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senior Vice President Generet offices: 1945 West Parnali Road, Jackson, Michigan 49201 * ($171788-0453 i

October 19, 1979 Hove-271-79 g% ?

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Mr J G Keppler, Regional Director

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UNIT NO 1, DOCKET HO 50-329 4.*

. UNIT NO 2, DOCKET NO 50-330 los SMALLBREAK/EEACTORCOOLANTPUMPOPERATIONINTERACTION

Reference:

S H Ecvell letter to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; SmallBreak/ReactorCoolantPumpOperationInteraction; Serial Hove-221-79; dated August 15, 1979 In accordance with the requirements of 10 CFR 50 55(e), this letter constitutes a second interim report concerning a potentially unsafe situation with respect to the tripping of reactor coolant pu=ps during certain primary system high void fraction conditions. This situation was described in reference 1.

After careful study of the BW analysis of this condition, and based upon i

their reco==endation, CPCo has d.ecided to incorporate a safety grade eutcestic reactor coolant pump trip system in the Midland design which vill ensure 10 CFR 50 Appendix K criteria vill be =et during all postulated small break scenarios. On Septe=ber 11+,1979, 29 :ac authorized to develop design criteria and trip logic, and Bechtel was instructed to proceed with design and procure =ent.

The schedule for completion of this effort is under development.

Another report, either interim or final, vill be submitted on or before February 8, 1980.

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Director of Office of Inspection & Enforcement Director, Office of ManaEe=cnt Att: Mr Victor Stello, USNRC (15)

Infor=ation & Program Control, USNRC (1)

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Howe-271-79 BCC: JLBacon, M-1085A RCBau=an, P1h 412 g

WRBird, JSC-216B-JLCorley, Midland LHCurtis, Bechtel AA GSKeeley, P14 kO83 CEMahaney, B&W BWMarguglio, JSC-220A DBMiller, Midland JARutgers, Bechtel AA TJSullivan, P24-624A MEDibbs, II&B File:

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Stephevi H. Howell Sensor Vice President General o ffices: 1945 West Pernell Road, Jackson, M'chigan 49201. (517) 783-0453 October 19, 1979 Howe-272-79 Mr J G Keppler, Regional Director Office of Inspection and Enforcement US Nuclear Regulatory Co= mission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDIAND NUCLEAR PIANT UNIT No 1, DOCK 2I' No 50-329 UNIT No 2, DOCKET No 50-330 REACTOR BUILDING SPRAY PIPING SUPPORPS

References:

1) S H Howell letter to J G Keppler; Midland Nuclear Plant; Unit No 1, Docket No 50-329; Unit No 2, Docket No 50-330; Reactor Building Spray Pipin6 Supports; Serial Howe-131-79; dated May 1, 1979

2) G Fiorelli letter to S H Howell; Docket No 50-329 and Docket No 50-330; dated May 23, 1979 Reference 1 was a final So.55(e) report on the analysis of Reactor Building

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Spray Piping Supports.

Subsequent to the final report, we deter =ined that furthel verifications were required in that there were apparent variances fro:s the design drawings for the six ring girder anchors installed in Unit 2, and we advised ycu of this condition via a telecon on May 18, 1979 Reference 2 is your acknowledgnent that we required further review of this matter.

As identified previously, there are 16 anchors per unit. Ten anchors are located directly on the dome with the remaining six anchors per unit located on the appropriate unit's rin'g girder. As identified in the previous reports, it was believed that the lo do=e anchors in Unit 1 and all Unit 2 anchors had been installed according to design drawings.

Subsecuent to finding the variances in the six ring girder anchors, a review of field inspection reports indicated that the six ring girder anchors had not been inspected c=d that the lo dome anchors, per unit, had been inspected including a valkdown by the Engineering Stress Group.

l As-installed dimensional details of the Unit 2 ring girder anchors were forwarded to IIT Grinnell for analysis on Septe=ber 14, 1979 Additional Ections are as follows:

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1) completed by November 5, 1979.ITT Grinnell analysis of the Unit o be 2) be determined after receipt of the results of the Gri erefore e

analysis.

3) there vill most likely be a need for modification of thF en installed, design, which will be processed through established pr j e original durin6 installation.

o ect procedures Another report vill be pro 71ded on or before December 21

, 1979.

uns/lr CC:

Director of Office of Inspection & Enforcement Att:

Mr Victor Stello, USIEC (15)

Director, Office of Management Information and Program Control, USIEC (1)

BCC: JLBacon, M-1085A RCBauman, P14 h12 h7B12ti, JSC-216B TCCooke, Midland JLCorley, Midlard LHCurtis, Bechtel AA LADreisbach, Bechtel-Midlend kTDickson, Midland G6Keeley, P14 LO8B BMiargu6110, JSC-220A I

DBMiller, Midland

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JARutgers, Bechtel AA t

MEGibbs, II&B File: 0.4 9.17

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